WorldWideScience

Sample records for major plant systems

  1. Major intrinsic proteins (MIPs) in plants: a complex gene family with major impacts on plant phenotype.

    Science.gov (United States)

    Forrest, Kerrie L; Bhave, Mrinal

    2007-10-01

    The ubiquitous cell membrane proteins called aquaporins are now firmly established as channel proteins that control the specific transport of water molecules across cell membranes in all living organisms. The aquaporins are thus likely to be of fundamental significance to all facets of plant growth and development affected by plant-water relations. A majority of plant aquaporins have been found to share essential structural features with the human aquaporin and exhibit water-transporting ability in various functional assays, and some have been shown experimentally to be of critical importance to plant survival. Furthermore, substantial evidence is now available from a number of plant species that shows differential gene expression of aquaporins in response to abiotic stresses such as salinity, drought, or cold and clearly establishes the aquaporins as major players in the response of plants to conditions that affect water availability. This review summarizes the function and regulation of these genes to develop a greater understanding of the response of plants to water insufficiency, and particularly, to identify tolerant genotypes of major crop species including wheat and rice and plants that are important in agroforestry.

  2. Major plant retrofits at Monticello nuclear generating plant

    International Nuclear Information System (INIS)

    Larsen, D.E.; Hogg, C.B.

    1986-01-01

    For the past several years, Northern States Power (NSP) has been making major plant retrofits to Monticello Nuclear generating Station in order to improve plant availability and upgrade the plant components for the potential extension of the operating license (life extension). This paper discusses in detail three major retrofits that have been completed or in the process of completion; recirculation loop piping replacement, reactor pressure vessel (RPV) water level-instrumentation modification, core spray piping replacement, the authors will address the scope of work, design and installation concerns, and life extension considerations during the design and procurement process for these three projects

  3. Impact of major design parameters on the economics of Tokamak power plants

    International Nuclear Information System (INIS)

    Abdou, M.A.; Ehst, D.; Maroni, V.; Stacey, W.M. Jr.

    1977-11-01

    A parametric systems studies program is now in an active stage at Argonne National Laboratory. This paper presents a summary of results from this systems analysis effort. The impact of major design parameters on the economics of tokamak power plants is examined. The major parameters considered are: (1) the plant power rating; (2) toroidal-field strength; (3) plasma β/sub t/; (4) aspect ratio; (5) plasma elongation; (6) inner blanket/shield thickness; and (7) neutron wall load. The performance characteristics and economics of tokamak power plants are also compared for two structural materials

  4. Development of a web-based aging monitoring system for an integrity evaluation of the major components in a nuclear power plant

    International Nuclear Information System (INIS)

    Choi, Jae-Boong; Yeum, Seung-Won; Ko, Han-Ok; Kim, Young-Jin; Kim, Hong-Key; Choi, Young-Hwan; Park, Youn-Won

    2010-01-01

    Structural and mechanical components in a nuclear power plant are designed to operate for its entire service life. Recently, a number of nuclear power plants are being operated beyond their design life to produce more electricity without shutting down. The critical issue in extending a lifetime is to maintain the level of safety during the extended operation period while satisfying the international regulatory standards. However, only a small portion of these components are of great importance for a significant aging degradation which would deeply affect the long-term safety and reliability of the related facilities. Therefore, it is beneficial to build a monitoring system to measure an aging status. While a number of integrity evaluation systems have been developed for NPPs, a real-time aging monitoring system has not been proposed yet . This paper proposes an expert system for the integrity evaluation of nuclear power plants based on a Web-based Reality Environment (WRE). The proposed system provides the integrity assessment for the major mechanical components of a nuclear power plant under concurrent working environments. In the WRE, it is possible for users to understand a mechanical system such as its size, geometry, coupling condition etc. In conclusion, it is anticipated that the proposed system can be used for a more efficient integrity evaluation of the major components subjected to an aging degradation.

  5. Development of a web-based aging monitoring system for an integrity evaluation of the major components in a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jae-Boong, E-mail: boong33@skku.ed [SAFE Research Centre, School of Mechanical Engineering, Sungkyunkwan University, 300 Chunchun-dong, Jangan-gu, Suwon, Kyonggi-do 440-746 (Korea, Republic of); Yeum, Seung-Won; Ko, Han-Ok; Kim, Young-Jin [SAFE Research Centre, School of Mechanical Engineering, Sungkyunkwan University, 300 Chunchun-dong, Jangan-gu, Suwon, Kyonggi-do 440-746 (Korea, Republic of); Kim, Hong-Key; Choi, Young-Hwan; Park, Youn-Won [Korea Institute of Nuclear Safety, 34 Gwahak-ro, Yusong-ku, Teajon 305-338 (Korea, Republic of)

    2010-01-15

    Structural and mechanical components in a nuclear power plant are designed to operate for its entire service life. Recently, a number of nuclear power plants are being operated beyond their design life to produce more electricity without shutting down. The critical issue in extending a lifetime is to maintain the level of safety during the extended operation period while satisfying the international regulatory standards. However, only a small portion of these components are of great importance for a significant aging degradation which would deeply affect the long-term safety and reliability of the related facilities. Therefore, it is beneficial to build a monitoring system to measure an aging status. While a number of integrity evaluation systems have been developed for NPPs, a real-time aging monitoring system has not been proposed yet . This paper proposes an expert system for the integrity evaluation of nuclear power plants based on a Web-based Reality Environment (WRE). The proposed system provides the integrity assessment for the major mechanical components of a nuclear power plant under concurrent working environments. In the WRE, it is possible for users to understand a mechanical system such as its size, geometry, coupling condition etc. In conclusion, it is anticipated that the proposed system can be used for a more efficient integrity evaluation of the major components subjected to an aging degradation.

  6. Design and development of major balance of plant components in solid oxide fuel cell system

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Wen-Tang; Huang, Cheng-Nan; Tan, Hsueh-I; Chao, Yu [Institute of Nuclear Energy Research Atomic Energy Council, Taoyuan County 32546 (Taiwan, Province of China); Yen, Tzu-Hsiang [Green Technology Research Institute, CPC Corporation, Chia-Yi City 60036 (Taiwan, Province of China)

    2013-07-01

    The balance of plant (BOP) of a Solid Oxide Fuel Cell (SOFC) system with a 2 kW stack and an electric efficiency of 40% is optimized using commercial GCTool software. The simulation results provide a detailed understanding of the optimal operating temperature, pressure and mass flow rate in all of the major BOP components, i.e., the gas distributor, the afterburner, the reformer and the heat exchanger. A series of experimental trials are performed to validate the simulation results. Overall, the results presented in this study not only indicate an appropriate set of operating conditions for the SOFC power system, but also suggest potential design improvements for several of the BOP components.

  7. Major factors influencing craft productivity in nuclear power plant construction

    International Nuclear Information System (INIS)

    Borcherding, J.D.; Sebastian, S.J.

    1980-01-01

    This paper reports on a research study whose objective was to determine the most influential factors adversely affecting craft productivity in nuclear power plant construction from the perspective of the tradesmen employed at the sites. Data were collected through the use of a questionnaire survey and group interview sessions, predominantly with workmen, at six nuclear power plant construction projects. Craftsmen were chosen as the major data base because of their awareness of how their time would actually be spent on the project. Topics considered include the factors influencing craft productivity, material availability, redoing work, crew interfacing, overcrowded work areas, instruction time, inspection delays, craft turnover, craft absenteeism, foreman changes, foreman incompetence, engineering design lead time, comprehensive scheduling of the design function, the responsibility of the utility, value engineering, plant standardization, the effective utilization of the planning and scheduling system, and the labor-management committee

  8. Major diseases of ornamental plants and their management

    International Nuclear Information System (INIS)

    Akhtar, M.A.; Zakria, M.; Sohail, F.

    2003-01-01

    Major diseases of ornamental plants are caused by infections agents (biotic) or non-infectious (abiotic) agents. Infectious agents are bacteria, fungi, nematodes and virus. Non infectious agents are nutritional imbalances, environmental stresses and chemical toxicities. Grouping of the diseases has been done on symptomatology basis. Disease management in ornamental plants has been described through cultural practices, chemical and other control strategies. (author)

  9. Engineering Plant Immunity via CRISPR/Cas13a System

    KAUST Repository

    Aljedaani, Fatimah R.

    2018-05-01

    Viral diseases constitute a major threat to the agricultural production and food security throughout the world. Plants cope with the invading viruses by triggering immune responses and small RNA interference (RNAi) systems. In prokaryotes, CRISPR/Cas systems function as an adaptive immune system to provide bacteria with resistance against invading phages and conjugative plasmids. Interestingly, CRISPR/Cas9 system was shown to interfere with eukaryotic DNA viruses and confer resistance against plant DNA viruses. The majority of the plant viruses have RNA genomes. The aim of this study is to test the ability of the newly discovered CRISPR/Cas13a immune system, that targets and cleaves single stranded RNA (ssRNA) in prokaryotes, to provide resistance against RNA viruses in plants. Here, I employ the CRISPR/Cas13a system for molecular interference against Turnip Mosaic Virus (TuMV), a plant RNA virus. The results of this study established the CRISPR/Cas13a as a molecular interference machinery against RNA viruses in plants. Specifically, my data show that the CRISPR/Cas13a machinery is able to interfere with and degrade the TuMV (TuMV-GFP) RNA genome. In conclusion, these data indicate that the CRISPR/Cas13 systems can be employed for engineering interference and durable resistance against RNA viruses in diverse plant species.

  10. Information management systems improve advanced plant design

    International Nuclear Information System (INIS)

    Turk, R.S.; Serafin, S.A.; Leckley, J.B.

    1994-01-01

    Computer-aided engineering tools are proving invaluable in both the design and operation of nuclear power plants. ABB Combustion Engineering's Advanced Light Water Reactor (ALWR) features a computerized Information Management System (IMS) as an integral part of the design. The System 80+IMS represents the most powerful information management tool for Nuclear Power Plants commercially available today. Developed by Duke Power Company specifically for use by nuclear power plant owner operators, the IMS consists of appropriate hardware and software to manage and control information flow for all plant related work or tasks in a systematic, consistent, coordinated and informative manner. A significant feature of this IMS is that it is primarily based on plant data. The principal design tool, PASCE (Plant Application and Systems from Combustion Engineering), is comprised of intelligent databases that describe the design and from which accurate plant drawings are created. Additionally the IMS includes, at its hub, a relational database management system and an associated document management system. The data-based approach and applications associated with the IMS were developed, and have proven highly effective, for plant modifications, configuration management, and operations and maintenance applications at Duke Power Company's operating nuclear plants. This paper presents its major features and benefits. 4 refs

  11. Application of expert system to nuclear power plant operation and guidance system

    International Nuclear Information System (INIS)

    Goto, M.; Takada, Y.

    1990-01-01

    For a nuclear power plant, it is important that an expert system supplies useful information to the operator to meet the increasing demand for high-level plant operation. It is difficult to build a user-friendly expert system that supplies useful information in real time using existing general-purpose expert system shells. Therefore a domain-specific expert system shell with a useful knowledge representation for problem-solving in nuclear power plant operation was selected. The Plant Table (P/T) representation format was developed for description of a production system for nuclear power plant operation knowledge. The P/T consists of plant condition representation designed to process multiple inputs and single output. A large number of operation inputs for several plant conditions are divided into 'timing conditions', 'preconditions' and 'completion conditions' to facilitate knowledge-base build-up. An expert system for a Nuclear Power Plant Operation and Guidance System utilizing the P/T was developed to assist automatic plant operation and surveillance test operation. In these systems, automatic plant operation signals to the plant equipment and operation guidance messages to the operators are both output based on the processing and assessment of plant operation conditions by the P/T. A surveillance test procedure guide for major safety-related systems, such as those for emergency core cooling systems, is displayed on a CRT (Cathode Ray Tube) and test results are printed out. The expert system for a Nuclear Power Plant Operation and Guidance System has already been successfully applied to Japanese BWR plants

  12. Example of an in-plant near-real-time accountancy/process control system

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This session describes an existing computerized in-plant near-real-time accounting and process monitoring system at the Allied-General Nuclear Services (AGNS) Barnwell Nuclear Fuel Plant (BNFP). Details of the system performance, objectives, hardware, plant instrumentation, and system functions are presented. Examples of actual programs for accounting and monitoring are described and system benefits will be discussed. The purpose of this session is to enable participants to: (1) identify the major computer hardware components of functional near-real-time accounting systems; (2) identify the types of process instrumentation necessary to perform near-real-time accounting; (3) describe the major nuclear material control and accounting functions of the AGNS computer system; and (4) assess the benefits to safeguards and plant operations of a computerized near-real-time accounting system

  13. Major controlling factors and predictions for cadmium transfer from the soil into spinach plants.

    Science.gov (United States)

    Liang, Zhenfei; Ding, Qiong; Wei, Dongpu; Li, Jumei; Chen, Shibao; Ma, Yibing

    2013-07-01

    Predicting the mobility, bioavailability and transfer of cadmium (Cd) in the soil-plant system is of great importance with regards to food safety and environmental management. In this study, the transfer characteristics of Cd (exogenous salts) from a wide range of Chinese soils to spinach (Spinacia oleracea L.) were investigated. The major controlling factors and prediction equations for Cd transfer in the soil-plant system were also investigated. The results showed that plant Cd concentration was positively correlated with soil Cd concentration. The maximum transfer factor (ratio of the Cd concentration in the plant to that in the soil) was found in acid soils. The extended Freundlich-type function was able to describe the Cd transfer from soil to spinach plants. Combining soil total Cd, pH and organic carbon (OC) content in the prediction equation greatly improved the correlation performance compared with predictions based on total Cd only. A slight protection effect of OC on Cd uptake was observed at low soil Cd concentrations. The results are a useful tool that can be used to predict Cd transfer from soil to plant. Copyright © 2013 Elsevier Inc. All rights reserved.

  14. The System 80+ standard plant design reduces operations and maintenance costs

    International Nuclear Information System (INIS)

    Chari, D.R.; Robertson, J.E.

    1998-01-01

    To be cost-competitive, nuclear power plants must maximize plant availability and minimize operations and maintenance (O and M) costs. A plant whose design supports these goals will generate more power at less cost and thereby have a lower unit generating cost. The ABB Combustion Engineering Nuclear Systems (ABB-CE) System 80+ Standard Nuclear Power Plant, rated at 1400 megawatts electric (MWe), is designed for high availability at reduced cost. To demonstrate that the duration of refueling outages, the major contributor to plant unavailability, can be shortened, ABB-CE developed a detailed plan that shows a System 80+ plant can safely perform a refueling and maintenance outage in 18 days. This is a significant reduction from the average current U.S. plant outages of 45 days, and is possible due to a two-part outage strategy: use System 80+ advanced system design features and relaxed technical specification (TS) time limits to shift some maintenance from outages to operating periods: and, use System 80+ structural, system, and component features, such as the larger operating floor, permanent pool seal, integral reactor head area cable tray system and missile shield, and longer life reactor coolant pump seals, to reduce the scope and duration of outage maintenance activities. Plant staffing level is the major variable, or controllable contributor to operations costs. ABB-CE worked with the Institute of Nuclear Power Operations (INPO) to perform detailed staffing analyses that show a System 80+ plant can be operated reliably with 30 percent less staff than currently operating nuclear plants of similar size. Safety was not sacrificed when ABB-CE developed the System 80+ refueling outage plan and staffing level. The outage plan was developed utilizing a defense-in-depth concept for shutdown safety. The defense in-depth concept is implemented via systematic control of outage risk evaluation (SCORE) cards. The SCORE cards identify primary and alternate means of

  15. Quality planning for major plant design modifications

    International Nuclear Information System (INIS)

    Dulee, R.J.

    1988-01-01

    This paper reviews the approach and activities undertaken by Public Service Electric and Gas Company's (PSE and G's) nuclear quality assurance (QA) department to support major plant design modifications conducted during refueling outages at Salem Generating Station. It includes the planning and implementation of quality plans developed to provide both QA and quality control (QC) coverage of modification performed by contracted service organizations

  16. Assessment and management of ageing of major nuclear power plant components important to safety: Metal components of BWR containment systems

    International Nuclear Information System (INIS)

    2000-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed toward technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific

  17. Design study of plant system for the fusion experimental reactor (FER)

    International Nuclear Information System (INIS)

    Iida, Hiromasa; Kuroda, Hideo; Yamada, Masao; Suzuki, Tatsushi; Honda, Tsutomu; Ohmura, Hiroshi; Itoh, Shinichi.

    1986-11-01

    This report describes design study results of the FER plant system. The purpose of this study is to have an image of the FER plant system as a whole by designing major auxiliary systems, reactor building and maintenance and radwaste desposal systems. The major auxiliary systems include tritium, cooling, evacuation and fueling systems. For these each systems, flowdiagrams are studied and designs of devices and pipings are conducted. In the reactor building design, layout of the above auxiliary systems in the building is studied with careful zoning concept by the radiation level. Structural integrity of the reactor building is also studied including seismic analysis. In the design of the maintenance and radwaste system flowdiagram of failed reactor components is developed and transfer vehicles and buildings are designed. Finally assuming JAERI Naka site as the reactor site layout of the whole FER plant system is developed. (author)

  18. Dynamic simulation of operating cases and malfunctions of an IGCC power plant system

    Energy Technology Data Exchange (ETDEWEB)

    Koch, I.; Hannemann, F. [Siemens AG, Power Generation (KWU), Erlangen (Germany); Hoffmann, U. [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Chemische Verfahrenstechnik

    1999-07-01

    Fully integrated IGCC plants consist of several units. This novel integration of various plant systems places stiff new requirements on power plant design, as prediction of operating and faulted behavior is made more difficult by many different interactions. This is especially the case for the gas turbine fuel system in an IGCC power plant, as it affects and is affected by all of the other major plant systems. (orig.)

  19. Research on U.S. nuclear power plant major equipment aging

    International Nuclear Information System (INIS)

    Nakos, J.T.; Rosinski, S.T.

    1994-01-01

    The U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), in cooperation with nuclear power plant utilities and the Nuclear Energy Institute, have prepared equipment aging evaluations of nuclear power plant equipment for life extension considerations. Specifically, these evaluations focused on equipment considered important for plant license renewal (U.S. Code of Federal Regulations 10CFR54). open-quotes Industry Reportsclose quotes (IRs), jointly funded by DOE and EPRI, evaluated the aging of major systems, structures, and components (e.g., reactor pressure vessels, Class I structures, PWR and BWR containments, etc.) and contain a mixture of technical and licensing information. open-quotes Aging Management Guidelinesclose quotes (AMGs), funded by DOE, evaluate aging for commodity types of equipment (e.g., pumps, electrical switchgear, heat exchangers, etc.) and concentrate on technical issues only. AMGs are intended for systems engineers and plant maintenance staff. A significant number of technical issues were resolved during IR interactions with the U.S. Nuclear Regulatory Commission (NRC). However, certain technical issues have not been resolved and are considered open-quotes openclose quotes. Examples include certain issues related to fatigue, neutron irradiation embrittlement, intergranular stress corrosion cracking (IGSCC) and electrical cable equipment qualification. Direct NRC interaction did not take place during preparation of individual AMGs due to their purely technical nature. The eventual use of AMGs in a future license renewal application will likely require NRC interaction at that time. With a few noted exceptions, the AMG process indicated that current aging management practices of U.S. utilities were effective in preventing age-related degradation. This paper briefly describes the IR and AMG processes and summarizes the unresolved technical issues identified through preparation of the documents

  20. The plant vascular system: Evolution, development and functions

    Science.gov (United States)

    William J. Lucas; Andrew Groover; Raffael Lichtenberger; Kaori Furuta; Shri-Ram Yadav; Yka Helariutta; Xin-Qiang He; Hiroo Fukuda; Julie Kang; Siobhan M. Brady; John W. Patrick; John Sperry; Akiko Yoshida; Ana-Flor Lopez-Millan; Michael A. Grusak; Pradeep Kachroo

    2013-01-01

    The emergence of the tracheophyte-based vascular system of land plants had major impacts on the evolution of terrestrial biology, in general, through its role in facilitating the development of plants with increased stature, photosynthetic output, and ability to colonize a greatly expanded range of environmental habitats. Recently, considerable progress has been made...

  1. Development of nuclear power plant monitoring system with neutral network using on-line PWR plant simulator

    International Nuclear Information System (INIS)

    Nabeshima Kunihiko; Suzuki Katsuo; Nose, Shoichi; Kudo, Kazuhiko

    1996-01-01

    The purpose of this paper is to demonstrate a nuclear power plant monitoring system using artificial neural network (ANN). The major advantages of the monitoring system are that a multi-output process system can be modelled using measurement information without establishing any mathematical expressions. The dynamics model of reactor plant was constructed by using three layered auto-associative neural network with backpropagation learning algorithm. The basic idea of anomaly detection method is to monitor the deviation between process signals measured from actual plant and corresponding output signals from the ANN plant model. The simulator used is a self contained system designed for training. Four kinds of simulated malfunction caused by equipment failure during steady state operation were used to evaluate the capability of the neural network monitoring system. The results showed that this monitoring system detected the symptom of small anomaly earlier than the prevailing alarm system. (author). 7 refs, 7 figs, 2 tabs

  2. Development of nuclear power plant monitoring system with neutral network using on-line PWR plant simulator

    Energy Technology Data Exchange (ETDEWEB)

    Kunihiko, Nabeshima; Katsuo, Suzuki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan); Nose, Shoichi; Kudo, Kazuhiko [Kyushu Univ., Fukuoka (Japan). Faculty of Engineering

    1997-12-31

    The purpose of this paper is to demonstrate a nuclear power plant monitoring system using artificial neural network (ANN). The major advantages of the monitoring system are that a multi-output process system can be modelled using measurement information without establishing any mathematical expressions. The dynamics model of reactor plant was constructed by using three layered auto-associative neural network with backpropagation learning algorithm. The basic idea of anomaly detection method is to monitor the deviation between process signals measured from actual plant and corresponding output signals from the ANN plant model. The simulator used is a self contained system designed for training. Four kinds of simulated malfunction caused by equipment failure during steady state operation were used to evaluate the capability of the neural network monitoring system. The results showed that this monitoring system detected the symptom of small anomaly earlier than the prevailing alarm system. (author). 7 refs, 7 figs, 2 tabs.

  3. Applications of modern control systems in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Wilhelm, H [Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.). Abt. GK/TE

    1980-10-01

    A new generation of automation and control systems are currently becoming commercially available in the power plant market which, because of their incorporation of microprocessors and bus data transmission systems, represent a major step forward in innovation. The application of these systems meets today's requirements and solutions, for the number of measurements to be performed has increased five or sixfold in the past few years, and the number of drive systems to be controlled has doubled or even tripled. Requirements to be met by process management systems have become vastly more complicated: peak load operation, short startup times, improved communication, and rising safety and reliability requirements, especially in nuclear power plants. Control concepts have been developed for the area relevant to reactor safety and for the whole of the plant, which make full use of the possibilities offered by plant systems. More stringent demands must be met especially in the areas of handling, communication, testing capability, improved function, and flexibility and modular design in the safety sector.

  4. Major gene mutations and domestication of plants

    International Nuclear Information System (INIS)

    Ashri, A.

    1989-01-01

    From the approximately 200,000 species of flowering plants known, only about 200 have been domesticated. The process has taken place in many regions over long periods. At present there is great interest in domesticating new species and developing new uses for existing ones in order to supply needed food, industrial raw materials, etc. It is proposed that major gene mutations were important in domestication; many key characters distinguishing cultivated from related wild species are controlled by one or very few major genes. The deliberate effort to domesticate new species requires at least the following: identification of needs and potential sources, establishment of suitable niches, choice of taxa to be domesticated, specification of the desired traits and key characters to be modified, as well as the potential role of induced mutations. (author). 14 refs

  5. Integration of the ITER diagnostic plant systems with CODAC

    International Nuclear Information System (INIS)

    Simrock, S.; Barnsley, R.; Bertalot, L.; Hansalia, C.; Klotz, W.D.; Makijarvi, P.; Reichle, R.; Vayakis, G.; Yonekawa, I.; Walker, C.; Wallander, A.; Walsh, M.; Winter, A.

    2011-01-01

    ITER requires extensive diagnostic systems in order to meet the requirements for machine operation, protection, plasma control and physics studies. The realization of these systems is a major challenge not only because of the harsh environment and the nuclear requirements but also with respect to Instrumentation and Control (I and C) of all the 59 diagnostics plants. The Plant Systems I and C are mostly 'in-kind', i.e. procured by the seven ITER Domestic Agencies (DAs), while the Central I and C Systems are 'in-fund', i.e. procured by ITER Organization (IO). Standardization of Plant Systems I and C is of primary importance and has been one of the highest priority tasks of CODAC. The standards are published in the Plant Control Design Handbook (PCDH) which will be followed to ensure a homogeneous design, guarantee high availability and simplify maintenance and support future upgrades. Most important for a successful commissioning and operation of the ITER facility are the concepts of interfacing the diagnostics plant systems with CODAC and the standards for instrumentation and control which must be followed all contributing parties. In this paper, we will elaborate on the concepts of interfacing the diagnostics plant systems with CODAC and the standards that must be followed for the design.

  6. Nuclear Plant Aging Research (NPAR) program plan: Components, systems, and structures

    International Nuclear Information System (INIS)

    1987-09-01

    The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems and major components at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechanisms of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring, and maintenance as means of mitigating such effects. Specifically, the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of equipment, a systems, and major components and thereby impair plant safety; (2) to identify methods of inspection, surveillance, and monitoring, or of evaluating residual life of equipment, systems, and major components, which will ensure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair, and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

  7. Beyond Cannabis: Plants and the Endocannabinoid System.

    Science.gov (United States)

    Russo, Ethan B

    2016-07-01

    Plants have been the predominant source of medicines throughout the vast majority of human history, and remain so today outside of industrialized societies. One of the most versatile in terms of its phytochemistry is cannabis, whose investigation has led directly to the discovery of a unique and widespread homeostatic physiological regulator, the endocannabinoid system. While it had been the conventional wisdom until recently that only cannabis harbored active agents affecting the endocannabinoid system, in recent decades the search has widened and identified numerous additional plants whose components stimulate, antagonize, or modulate different aspects of this system. These include common foodstuffs, herbs, spices, and more exotic ingredients: kava, chocolate, black pepper, and many others that are examined in this review. Copyright © 2016 Elsevier Ltd. All rights reserved.

  8. Plant Phenotype Characterization System

    Energy Technology Data Exchange (ETDEWEB)

    Daniel W McDonald; Ronald B Michaels

    2005-09-09

    This report is the final scientific report for the DOE Inventions and Innovations Project: Plant Phenotype Characterization System, DE-FG36-04GO14334. The period of performance was September 30, 2004 through July 15, 2005. The project objective is to demonstrate the viability of a new scientific instrument concept for the study of plant root systems. The root systems of plants are thought to be important in plant yield and thus important to DOE goals in renewable energy sources. The scientific study and understanding of plant root systems is hampered by the difficulty in observing root activity and the inadequacy of existing root study instrumentation options. We have demonstrated a high throughput, non-invasive, high resolution technique for visualizing plant root systems in-situ. Our approach is based upon low-energy x-ray radiography and the use of containers and substrates (artificial soil) which are virtually transparent to x-rays. The system allows us to germinate and grow plant specimens in our containers and substrates and to generate x-ray images of the developing root system over time. The same plant can be imaged at different times in its development. The system can be used for root studies in plant physiology, plant morphology, plant breeding, plant functional genomics and plant genotype screening.

  9. Applications of modern control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Wilhelm, H.

    1980-01-01

    A new generation of automation and control systems are currently becoming commercially available in the power plant market which, because of their incorporation of microprocessors and bus data transmission systems, represent a major step forward in innovation. The application of these systems meets today's requirements and solutions, for the number of measurements to be performed has increased five or sixfold in the past few years, and the number of drive systems to be controlled has doubled or even tripled. Requirements to be met by process management systems have become vastly more complicated: peak load operation, short startup times, improved communication, and rising safety and reliability requirements, especially in nuclear power plants. Control concepts have been developed for the area relevant to reactor safety and for the whole of the plant, which make full use of the possibilities offered by plant systems. More stringent demands must be met especially in the areas of handling, communication, testing capability, improved function, and flexibility and modular design in the safety sector. (orig.) [de

  10. Major trends in nuclear and coal fired plants economics

    International Nuclear Information System (INIS)

    Benson, P.H.; Frank, J.R.; Isacson, H.R.

    1984-01-01

    An in-depth analysis of nuclear plant performance in the United States and elsewhere raises basic questions as to the validity of the present pessimism as a guide for long-range policy. The sad story of the plants in trouble has obscured the good performance of the majority of nuclear power installations. Further, it appears that many of the root causes for the outstanding problems may be indigenous to the existing U.S. utility, regulatory, and financial structure, and not relevant to the long-range intrinsic values of nuclear power either in the United States or in other countries. On the other hand, many of the problems affecting coal fired plants, i.e., fuel supply, economics and pollution control appear to be more critical abroad rather than in the U.S. This paper will review these issues

  11. Development of a majority vote decision module for a self-diagnostic monitoring system for an air-operated valve system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woo Shin [Dept. of Information and Communication Engineering, Sejong University, Seoul (Korea, Republic of); Chai, Jang Bom [Dept. of Mechanical Engineering, Ajou University, Suwon (Korea, Republic of); Kim, In Taek [Dept. of Information and Communication Engineering, Myongji University, Yongin (Korea, Republic of)

    2015-08-15

    A self-diagnostic monitoring system is a system that has the ability to measure various physical quantities such as temperature, pressure, or acceleration from sensors scattered over a mechanical system such as a power plant, in order to monitor its various states, and to make a decision about its health status. We have developed a self-diagnostic monitoring system for an air-operated valve system to be used in a nuclear power plant. In this study, we have tried to improve the self-diagnostic monitoring system to increase its reliability. We have implemented three different machine learning algorithms, i.e., logistic regression, an artificial neural network, and a support vector machine. After each algorithm performs the decision process independently, the decision-making module collects these individual decisions and makes a final decision using a majority vote scheme. With this, we performed some simulations and presented some of its results. The contribution of this study is that, by employing more robust and stable algorithms, each of the algorithms performs the recognition task more accurately. Moreover, by integrating these results and employing the majority vote scheme, we can make a definite decision, which makes the self-diagnostic monitoring system more reliable.

  12. Development of a majority vote decision module for a self-diagnostic monitoring system for an air-operated valve system

    International Nuclear Information System (INIS)

    Kim, Woo Shin; Chai, Jang Bom; Kim, In Taek

    2015-01-01

    A self-diagnostic monitoring system is a system that has the ability to measure various physical quantities such as temperature, pressure, or acceleration from sensors scattered over a mechanical system such as a power plant, in order to monitor its various states, and to make a decision about its health status. We have developed a self-diagnostic monitoring system for an air-operated valve system to be used in a nuclear power plant. In this study, we have tried to improve the self-diagnostic monitoring system to increase its reliability. We have implemented three different machine learning algorithms, i.e., logistic regression, an artificial neural network, and a support vector machine. After each algorithm performs the decision process independently, the decision-making module collects these individual decisions and makes a final decision using a majority vote scheme. With this, we performed some simulations and presented some of its results. The contribution of this study is that, by employing more robust and stable algorithms, each of the algorithms performs the recognition task more accurately. Moreover, by integrating these results and employing the majority vote scheme, we can make a definite decision, which makes the self-diagnostic monitoring system more reliable

  13. Problems of New Plant Variety Protection System in China and Countermeasures

    OpenAIRE

    GUAN, Yuwu

    2013-01-01

    Protection of new plant varieties has been long neglected in China, which has already restricted agricultural technological renovation, and influenced export of Chinese agricultural products. The current scientific and technological management system is not favorable for the output of right of new plant variety, and high cost of protecting new plant varieties directly results in agricultural researchers’ ignorance of right of new plant variety. Major causes were concluded as poor intellectu...

  14. Soil-to-plant transfer factors of trace and major elements in rice plant (Oryza Sativa) at Kalpakkam

    International Nuclear Information System (INIS)

    Sreedevi, K.R.; Rajaram, S.; Thulasi Brindha, J.; Venkataraman, S.; Hegde, A.G.

    2011-01-01

    The objective of this study was to evaluate the distribution of trace and major elements in rice plant (Oryza Sativa) which is the staple diet of the public at Kalpakkam. The transfer factor from soil to various parts of plant was also studied. Trace and major elements such as Fe, Mn, Zn, Co, Cu, Ni, Cr, Cd, Pb , Sr, K, Ca and Mg were selected based on their role in nutrition and also to study the behaviour of their radioactive counterparts. Among the trace elements Fe concentration was observed to be maximum in soil, the mean value of which was 18394 mg/kg dry wt. Cadmium concentration was observed to be minimum with the mean value of 2 mg/kg dry wt. The maximum and minimum concentration observed in the rice grain were due to Zn and Cd and the values were found to be 9 and 0.044 mg/kg dry wt, respectively. In the stem and leaves part the maximum and minimum concentration was due to Fe and Cd and the values were found to be 26.8 and 0.12 mg/kg dry wt. Similarly in the root part Fe and Cd concentrations were found to be maximum and minimum, respectively. Among the different parts of the rice plant, trace elements concentration in root was maximum and in stem and leaves major elements concentration was maximum. Transfer factor from soil to plant parts was computed. In general, the transfer factor was maximum in root, followed by stem and leaves and grain for trace elements. The transfer factor computed for whole rice plant was maximum for Zn and minimum for Sr which is a significant observation from radiological point of view. (author)

  15. Plant Abiotic Stress Proteomics: The Major Factors Determining Alterations in Cellular Proteome

    Science.gov (United States)

    Kosová, Klára; Vítámvás, Pavel; Urban, Milan O.; Prášil, Ilja T.; Renaut, Jenny

    2018-01-01

    HIGHLIGHTS: Major environmental and genetic factors determining stress-related protein abundance are discussed.Major aspects of protein biological function including protein isoforms and PTMs, cellular localization and protein interactions are discussed.Functional diversity of protein isoforms and PTMs is discussed. Abiotic stresses reveal profound impacts on plant proteomes including alterations in protein relative abundance, cellular localization, post-transcriptional and post-translational modifications (PTMs), protein interactions with other protein partners, and, finally, protein biological functions. The main aim of the present review is to discuss the major factors determining stress-related protein accumulation and their final biological functions. A dynamics of stress response including stress acclimation to altered ambient conditions and recovery after the stress treatment is discussed. The results of proteomic studies aimed at a comparison of stress response in plant genotypes differing in stress adaptability reveal constitutively enhanced levels of several stress-related proteins (protective proteins, chaperones, ROS scavenging- and detoxification-related enzymes) in the tolerant genotypes with respect to the susceptible ones. Tolerant genotypes can efficiently adjust energy metabolism to enhanced needs during stress acclimation. Stress tolerance vs. stress susceptibility are relative terms which can reflect different stress-coping strategies depending on the given stress treatment. The role of differential protein isoforms and PTMs with respect to their biological functions in different physiological constraints (cellular compartments and interacting partners) is discussed. The importance of protein functional studies following high-throughput proteome analyses is presented in a broader context of plant biology. In summary, the manuscript tries to provide an overview of the major factors which have to be considered when interpreting data from proteomic

  16. Drought versus heat: What's the major constraint on Mediterranean green roof plants?

    International Nuclear Information System (INIS)

    Savi, Tadeja; Dal Borgo, Anna; Love, Veronica L.; Andri, Sergio; Tretiach, Mauro; Nardini, Andrea

    2016-01-01

    Green roofs are gaining momentum in the arid and semi-arid regions due to their multiple benefits as compared with conventional roofs. One of the most critical steps in green roof installation is the selection of drought and heat tolerant species that can thrive under extreme microclimate conditions. We monitored the water status, growth and survival of 11 drought-adapted shrub species grown on shallow green roof modules (10 and 13 cm deep substrate) and analyzed traits enabling plants to cope with drought (symplastic and apoplastic resistance) and heat stress (root membrane stability). The physiological traits conferring efficiency/safety to the water transport system under severe drought influenced plant water status and represent good predictors of both plant water use and growth rates over green roofs. Moreover, our data suggest that high substrate temperature represents a stress factor affecting plant survival to a larger extent than drought per se. In fact, the major cause influencing seedling survival on shallow substrates was the species-specific root resistance to heat, a single and easy measurable trait that should be integrated into the methodological framework for screening and selection of suitable shrub species for roof greening in the Mediterranean. - Highlights: • The use of hardy shrub species for roof greening should be increased. • We monitored water status of 11 shrub species growing on shallow green roofs. • Species heat and drought tolerance, growth, and survival were studied. • High substrate temperature significantly affected plant survival. • Root resistance to heat could be used as trait for species selection for green roofs.

  17. Systems Modeling For The Laser Fusion-Fission Energy (LIFE) Power Plant

    International Nuclear Information System (INIS)

    Meier, W.R.; Abbott, R.; Beach, R.; Blink, J.; Caird, J.; Erlandson, A.; Farmer, J.; Halsey, W.; Ladran, T.; Latkowski, J.; MacIntyre, A.; Miles, R.; Storm, E.

    2008-01-01

    A systems model has been developed for the Laser Inertial Fusion-Fission Energy (LIFE) power plant. It combines cost-performance scaling models for the major subsystems of the plant including the laser, inertial fusion target factory, engine (i.e., the chamber including the fission and tritium breeding blankets), energy conversion systems and balance of plant. The LIFE plant model is being used to evaluate design trade-offs and to identify high-leverage R and D. At this point, we are focused more on doing self consistent design trades and optimization as opposed to trying to predict a cost of electricity with a high degree of certainty. Key results show the advantage of large scale (>1000 MWe) plants and the importance of minimizing the cost of diodes and balance of plant cost

  18. Commissioning and maintenance experience of in-plant coal handling system of captive power plant at HWP, Manuguru (Paper No. 5.4)

    International Nuclear Information System (INIS)

    Murugappan, K.; Mohan Rao, A.C.; Sastry, M.S.N.

    1992-01-01

    For achieving a non-stop generation of power for a minimum period of one year can be a reality only if due importance is given to inplant coal handling system. The paper highlights the major commissioning and maintenance problem faced and corrective action taken for inplant coal handling system of the captive power plant at Heavy Water Plant, Manuguru. (author)

  19. Supervisory monitoring system in nuclear power plants

    International Nuclear Information System (INIS)

    Ciftcioglu, O.; Turkcan, E.

    1997-01-01

    Monitoring of a power plant is one of the essential tasks during operation and the computer-based implementations are nowadays seemingly quite mature. However, presently these are still not satisfactory enough to meet the high standards to the licensing requirements and they are mostly not truly integrated to the plant's design-based monitoring system. This is basically due to the robustness problem as the majority of the methods are not robust enough for the monitoring of the safety parameter set in a plant or intelligent supervision. Therefore, a supervisory monitoring system (SMS) in a plant is necessary to supervise the monitoring tasks: determining the objectives to be obtained and finding the means to support them. SMS deals with the changing plant status and the coordination of the information flow among the monitoring subunits. By means of these robustness and consistency in monitoring is achieved. The paper will give the guidelines of knowledge and data management techniques in a framework of robust comprehensive and coordinated monitoring which is presented as supervisory monitoring. Such a high level monitoring serves for consistent and immediate actions in fault situations while this particularly has vital importance in preventing imminent severe accidents next to the issues of recognition of the monitoring procedures for licensing and enhanced plant safety. (author). 8 refs, 5 figs

  20. Developing Major Steps for a Feasibility Study for Upgrading I and C Systems in a Large Scale for an Operating Nuclear Power Plant

    International Nuclear Information System (INIS)

    Suh, Yong Suk; Keum, Jong Yong; Kim, Dong Hoon; Kang, Hyeon Tae; Sung, Chan Ho; Lee, Jae Ki; Cho, Chang Hwan

    2009-01-01

    According to the IAEA report as of Jan. 2008, 436 nuclear power reactors are in operation over the world and 368 nuclear power reactors exceed their operating ages by 20 years. The average I and C equipment's life span is 20 years comparing with that the average reactor's life time is 40 to 60 years. This means that a reactor must be faced with I and C equipment obsolescence problems once or twice during its operating years. The I and C equipment is replaced with new equipment only when the obsolescence problem occurs in a nuclear power plant. This is called an equipment basis upgrade in this paper. This replacement is such a general practice that occurs only when needed. We can assume that most of I and C equipment of a plant will meet with the obsolescence problem almost same time since it started operating. Although there must be a little time difference in the occurrence of the problems among I and C equipment, the replacement will be required in consecutive years. With this assumption, it is recommendable to upgrade the equipment, which is to meet with the problem at the same time, with new equipment at the same time. This is called a system basis upgrade in this paper. The system-basis replacement can be achieved in a large scale by coupling systems whose functions are related each other and replacing them together with a new upto- date platform. This paper focuses on the large scale upgrade of I and C systems for existing and operating NPPs. While performing a feasibility study for the large scale upgrade for Korea standard nuclear power plants (KSNPs), six major steps are developed for the study. This paper is to present what to perform in each step

  1. Nanoscale copper in the soil–plant system – toxicity and underlying potential mechanisms

    Energy Technology Data Exchange (ETDEWEB)

    Anjum, Naser A., E-mail: anjum@ua.pt [CESAM-Centre for Environmental and Marine Studies & Department of Chemistry, University of Aveiro, 3810-193 Aveiro (Portugal); Adam, Vojtech [Department of Chemistry and Biochemistry, Faculty of Agronomy, Mendel University in Brno, Zemedelska 1, CZ-613 00 Brno (Czech Republic); Central European Institute of Technology, Brno University of Technology, Technicka 3058/10, CZ-616 00 Brno (Czech Republic); Kizek, Rene [Central European Institute of Technology, Brno University of Technology, Technicka 3058/10, CZ-616 00 Brno (Czech Republic); Duarte, Armando C.; Pereira, Eduarda [CESAM-Centre for Environmental and Marine Studies & Department of Chemistry, University of Aveiro, 3810-193 Aveiro (Portugal); Iqbal, Muhammad [Department of Botany, Faculty of Science, Hamdard University, New Delhi 110062 (India); Lukatkin, Alexander S. [Department of Botany, Plant Physiology and Ecology, N.P. Ogarev Mordovia State University, Bolshevistskaja Str., 68. Saransk 430005 (Russian Federation); Ahmad, Iqbal, E-mail: ahmadr@ua.pt [CESAM-Centre for Environmental and Marine Studies & Department of Chemistry, University of Aveiro, 3810-193 Aveiro (Portugal); CESAM-Centre for Environmental and Marine Studies & Department of Biology, University of Aveiro, 3810-193 Aveiro (Portugal)

    2015-04-15

    Nanoscale copper particles (nano-Cu) are used in many antimicrobial formulations and products for their antimicrobial activity. They may enter deliberately and/or accidentally into terrestrial environments including soils. Being the major ‘eco-receptors’ of nanoscale particles in the terrestrial ecosystem, soil–microbiota and plants (the soil–plant system) have been used as a model to dissect the potential impact of these particles on the environmental and human health. In the soil–plant system, the plant can be an indirect non-target organism of the soil-associated nano-Cu that may in turn affect plant-based products and their consumers. By all accounts, information pertaining to nano-Cu toxicity and the underlying potential mechanisms in the soil–plant system remains scanty, deficient and little discussed. Therefore, based on some recent reports from (bio)chemical, molecular and genetic studies of nano-Cu versus soil–plant system, this article: (i) overviews the status, chemistry and toxicity of nano-Cu in soil and plants, (ii) discusses critically the poorly understood potential mechanisms of nano-Cu toxicity and tolerance both in soil–microbiota and plants, and (iii) proposes future research directions. It appears from studies hitherto made that the uncontrolled generation and inefficient metabolism of reactive oxygen species through different reactions are the major factors underpinning the overall nano-Cu consequences in both the systems. However, it is not clear whether the nano-Cu or the ion released from it is the cause of the toxicity. We advocate to intensify the multi-approach studies focused at a complete characterization of the nano-Cu, its toxicity (during life cycles of the least-explored soil–microbiota and plants), and behavior in an environmentally relevant terrestrial exposure setting. Such studies may help to obtain a deeper insight into nano-Cu actions and address adequately the nano-Cu-associated safety concerns in the ‘soil–plant

  2. Nanoscale copper in the soil–plant system – toxicity and underlying potential mechanisms

    International Nuclear Information System (INIS)

    Anjum, Naser A.; Adam, Vojtech; Kizek, Rene; Duarte, Armando C.; Pereira, Eduarda; Iqbal, Muhammad; Lukatkin, Alexander S.; Ahmad, Iqbal

    2015-01-01

    Nanoscale copper particles (nano-Cu) are used in many antimicrobial formulations and products for their antimicrobial activity. They may enter deliberately and/or accidentally into terrestrial environments including soils. Being the major ‘eco-receptors’ of nanoscale particles in the terrestrial ecosystem, soil–microbiota and plants (the soil–plant system) have been used as a model to dissect the potential impact of these particles on the environmental and human health. In the soil–plant system, the plant can be an indirect non-target organism of the soil-associated nano-Cu that may in turn affect plant-based products and their consumers. By all accounts, information pertaining to nano-Cu toxicity and the underlying potential mechanisms in the soil–plant system remains scanty, deficient and little discussed. Therefore, based on some recent reports from (bio)chemical, molecular and genetic studies of nano-Cu versus soil–plant system, this article: (i) overviews the status, chemistry and toxicity of nano-Cu in soil and plants, (ii) discusses critically the poorly understood potential mechanisms of nano-Cu toxicity and tolerance both in soil–microbiota and plants, and (iii) proposes future research directions. It appears from studies hitherto made that the uncontrolled generation and inefficient metabolism of reactive oxygen species through different reactions are the major factors underpinning the overall nano-Cu consequences in both the systems. However, it is not clear whether the nano-Cu or the ion released from it is the cause of the toxicity. We advocate to intensify the multi-approach studies focused at a complete characterization of the nano-Cu, its toxicity (during life cycles of the least-explored soil–microbiota and plants), and behavior in an environmentally relevant terrestrial exposure setting. Such studies may help to obtain a deeper insight into nano-Cu actions and address adequately the nano-Cu-associated safety concerns in the ‘soil–plant

  3. Study on aging management of fire protection system in nuclear power plant

    International Nuclear Information System (INIS)

    Fang Huasong; Du Yu; Li Jianwen; Shi Haining; Tu Fengsheng

    2010-01-01

    Fire prevention, fire fighting and fire automatic alarms are three aspects which be included in fire protection system in nuclear power plants. The fire protection system can protect personnel, equipment etc in the fire, so their performance will have a direct influence on the safe operation in nuclear power plants. The disabled accidents caused by aging have happened continuously with the extension of time in the fire protection system, which is the major security risk during the running time in nuclear power plants. In view of the importance of fire protection system and the severity of aging problems, the aging are highly valued by the plant operators and related organizations. Though the feedback of operating experience in nuclear power plant, the impact of the fire-fighting equipment aging on system performance and reliability be assessed, the aging sensitive equipment be selected to carry out the aging analysis and to guide the management and maintenance to guarantee the healthy operation in life time of fire protection system in nuclear power plant. (authors)

  4. Integrated operation and management system for a 700MW combined cycle power plant

    Energy Technology Data Exchange (ETDEWEB)

    Shiroumaru, I. (Yanai Power Plant Construction Office, Chugoku Electric Power Co., Inc., 1575-5 Yanai-Miyamoto-Shiohama, Yanai-shi, Yamaguchi-ken (JP)); Iwamiya, T. (Omika Works, Hitachi, Ltd., 5-2-1 Omika-cho, Hitachi-shi, Ibaraki-ken (JP)); Fukai, M. (Hitachi Works, Hitachi, Ltd., 3-1-1 Saiwai-cho, Hitachi-shi, Ibaraki-ken (JP))

    1992-03-01

    Yanai Power Plant of the Chugoku Electric Power Co., Inc. (Yamaguchi Pref., Japan) is in the process of constructing a 1400MW state-of-the-art combined cycle power plant. The first phase, a 350MW power plant, started operation on a commercial basis in November, 1990. This power plant has achieved high efficiency and high operability, major features of a combined cycle power plant. The integrated operation and management system of the power plant takes care of operation, maintenance, control of general business, etc., and was built using the latest computer and digital control and communication technologies. This paper reports that it is expected that this system will enhance efficient operation and management for the power plant.

  5. FPGA-Based Plant Protection System

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yoon Hee; Ha, Jae Hong; Kim, Hang Bae [KEPCO E and C, Daejeon (Korea, Republic of)

    2011-08-15

    This paper relates to a plant protection system which detects non-permissible conditions and determines initiation of protective actions for nuclear power plants (NPPs). Conventional plant protection systems were designed based on analog technologies. It is well known that existing protection systems for NPPs contain many components which are becoming obsolete at an increasing rate. Nowadays maintenance and repair for analog-based plant protection systems may be difficult as analog parts become obsolete or difficult to obtain. Accordingly, as an alternative to the analog technology, the digitalisation of the plant protection system was required. Recently digital plant protection systems which include programmable logic controllers (PLCs) and/or computers have been introduced. However PLC or computer-based plant protection systems use an operating system and application software, and so they may result in a common mode failure when a problem occurs in the operating system or application software. Field Programmable Gate Arrays (FPGAs) are highlighted as an alternative to conventional protection or control systems. The paper presents the design of a four-channel plant protection system whose protection functions are implemented in FPGAs without any central processing unit or operating system.

  6. FPGA-Based Plant Protection System

    International Nuclear Information System (INIS)

    Lee, Yoon Hee; Ha, Jae Hong; Kim, Hang Bae

    2011-01-01

    This paper relates to a plant protection system which detects non-permissible conditions and determines initiation of protective actions for nuclear power plants (NPPs). Conventional plant protection systems were designed based on analog technologies. It is well known that existing protection systems for NPPs contain many components which are becoming obsolete at an increasing rate. Nowadays maintenance and repair for analog-based plant protection systems may be difficult as analog parts become obsolete or difficult to obtain. Accordingly, as an alternative to the analog technology, the digitalisation of the plant protection system was required. Recently digital plant protection systems which include programmable logic controllers (PLCs) and/or computers have been introduced. However PLC or computer-based plant protection systems use an operating system and application software, and so they may result in a common mode failure when a problem occurs in the operating system or application software. Field Programmable Gate Arrays (FPGAs) are highlighted as an alternative to conventional protection or control systems. The paper presents the design of a four-channel plant protection system whose protection functions are implemented in FPGAs without any central processing unit or operating system

  7. Automated control system for the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Labik, V.

    1990-01-01

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

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

    DEFF Research Database (Denmark)

    Yoshikawa, Hidekazu; Lind, Morten; Yang, Ming

    2012-01-01

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

  9. Artificial intelligence expert system for nuclear power plant control and maintenance

    International Nuclear Information System (INIS)

    Westrom, G.B.

    1987-01-01

    A major concern in emergency response in a nuclear power plant is the lack of real experience with a catastrophic condition. Experts do more than just follow a set of rules. They have experience and insight into problems and are able to use their professional judgement. The objectives of this expert system are: Detect subtle off-normal trends in a reactor power plant system. Alert the operator with color graphics and synthesized voice commands. Identify the source of the problem and advise the operator on steps to restore the plant to normal operation. Provide an explanation facility and database to supply detailed information on component history and reasoning process. The RHRS (Residual Heat Removal System) was selected for the initial expert systems development because it is extremely important during refueling and cold shutdown operations

  10. Plant air systems safety study: Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    1982-05-01

    The Portsmouth Gaseous Diffusion Plant Air System facilities and operations are reviewed for potential safety problems not covered by standard industrial safety procedures. Information is presented under the following section headings: facility and process description (general); air plant equipment; air distribution system; safety systems; accident analysis; plant air system safety overview; and conclusion

  11. Analysis on the gamma dose distribution by major corrosion products during preventive maintenance period in nuclear power plant

    International Nuclear Information System (INIS)

    Ha, Wi Ho

    2006-02-01

    The information on dose distribution inside the containment building is an essential requirement to make a reduction of radiation exposure as well as effective operation and design of nuclear power plant. After reactor shutdown, radiation exposure to workers mainly occurs during preventive maintenance period due to inspection or repair works of major components. During that period, gamma doses are induced by major corrosion products in the primary coolant system. The radiation exposure to workers has been assessed by using the measurements. The measurements are, of course, a basic and reliable assessment. But the measurement has defect such as limitation of detecting area. In order to improve the defect of the measurements, system for assessment of gamma dose distribution during preventive maintenance period by using computational code was suggested in this study. First, activity of major corrosion products was calculated by using modified CRUDSIM code. Original CRUDSIM code was modified to add evaluation of other major corrosion products besides cobalt isotopes. Modeling of containment building for YGN Unit 3 was then performed. Gamma dose distribution by major corrosion products inside the containment building was calculated by using MCNPX code. Finally, the calculations were mapped for whole space inside the containment building and were compared with the measurements. As a result of this study, the defect of the measurement are supplemented by using computational calculation system, and it is expected that workers can make an effective work plan through providing dose distribution inside the containment building in advance. In addition, this study can be applied to technology development to make an effective containment shielding design of the next generation reactor as well as an improvement of the safety for workers in nuclear power plant

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  13. Economic consequences of major accidents in the industrial plants: The case of a nuclear power plant

    International Nuclear Information System (INIS)

    Fraix, J.

    1989-09-01

    These last years, newspapers head-lines have reported various accidents (Mexico City, Bhopal, Chernobyl, ...) which have drawn attention to the fact that the major technological risk is now a reality and that, undoubtedly, industrial decision-makers ought to integrate it into their preoccupations. In addition to the sometimes considerable human problems such accidents engender, their economic consequences may be such that they become significant on a national or even international scale. The aim of the present paper is to analyse these economic effects by using the particular context of a nuclear power plant. The author has deliberately limited his subject to the consequences of a major accident, that is to say a sudden event, theoretically unforeseen and beyond man's control. The qualification major means an accident of which the consequences extend far beyond the industrial plant itself. The direct and indirect economic consequences are analysed from the responsibility point of view as well as from the national and international community's point of view. A paragraph explains how the coverage of the costs can rely on the cooperation of a number of parties: responsible company, state, insurers, customers, etc. The study is broadly based on the experience resulting from the two major accidents which happened in the nuclear industry these last years (Three Mile Island in 1979 and Chernobyl in 1986) and makes use of more theoretical considerations, for example in the field of the economic evaluation of human life. (author). 58 refs, 2 figs, 12 tabs

  14. Development of cesium 137 plant uptake predicting model using geographical information systems

    International Nuclear Information System (INIS)

    Lomonos, O.V.

    2002-01-01

    Soil-plant system is a critical component of food chain in processes of Cs 137 migration. In this component it is possible to decrease greatly Cs 137 uptake in food chain. Development of Cs 137 migration model in soil-plant system enable to determine amount of Cs 137 in plant uptake and evaluate agricultural produce accordance with modern ecological requirements. Also this model can help with management of agricultural production. Geographical information systems (GIS) have a wide propagation in radioecology at present time. Models using GIS have several advantages: relative simplicity of evaluation, visualization of evaluated results etc. As a result, plots with possible Cs 137 uptake increasing could be easily discovered. Physical decay, Cs 137 sorption and fixation by soil, Cs 137 vertical migration in soil profile and plant uptake are the main components of the Cs 137 migration model in soil-plant system. Content of biologically available Cs 137 calculated taking into account all of these components. Using GIS with Cs 137 migration model in soil-plant system lets efficiently discover those factors that have major influence on Cs 137 plant uptake increasing. This model improves agricultural production on territories, which polluted by Cs 137

  15. Planning of a Quadgeneration power plant for Jammerbugt energy system

    DEFF Research Database (Denmark)

    Rudra, Souman; Hoffmann, Jessica; Rosendahl, Lasse

    2011-01-01

    Quadgeneration is the simultaneous production of power, heat and cooling and different fuels from flexible feedstocks such as biomass, waste, refinery residue etc. In order to accommodate more renewable energy into the energy system, it is extremely necessary to develop new flexible power plants...... of some equipments in the Quadgeneration power plant. This paper presents two models for the investment planning of a Quadgeneration energy system in Jammerbugt municipality, and uses these models for different case studies addressing the system for production of heat, cooling, liquid fuels...... that can quickly increase or decrease the production of electricity. Such plants should be ultra flexible in terms of production and able to run on many different types of fuels, with one of its major outputs being liquid fuels for the transport sector. The aim of this paper is to integrate district...

  16. An Automated and Continuous Plant Weight Measurement System for Plant Factory.

    Science.gov (United States)

    Chen, Wei-Tai; Yeh, Yu-Hui F; Liu, Ting-Yu; Lin, Ta-Te

    2016-01-01

    In plant factories, plants are usually cultivated in nutrient solution under a controllable environment. Plant quality and growth are closely monitored and precisely controlled. For plant growth evaluation, plant weight is an important and commonly used indicator. Traditional plant weight measurements are destructive and laborious. In order to measure and record the plant weight during plant growth, an automated measurement system was designed and developed herein. The weight measurement system comprises a weight measurement device and an imaging system. The weight measurement device consists of a top disk, a bottom disk, a plant holder and a load cell. The load cell with a resolution of 0.1 g converts the plant weight on the plant holder disk to an analog electrical signal for a precise measurement. The top disk and bottom disk are designed to be durable for different plant sizes, so plant weight can be measured continuously throughout the whole growth period, without hindering plant growth. The results show that plant weights measured by the weight measurement device are highly correlated with the weights estimated by the stereo-vision imaging system; hence, plant weight can be measured by either method. The weight growth of selected vegetables growing in the National Taiwan University plant factory were monitored and measured using our automated plant growth weight measurement system. The experimental results demonstrate the functionality, stability and durability of this system. The information gathered by this weight system can be valuable and beneficial for hydroponic plants monitoring research and agricultural research applications.

  17. An Automated and Continuous Plant Weight Measurement System for Plant Factory

    Directory of Open Access Journals (Sweden)

    Wei-Tai eChen

    2016-03-01

    Full Text Available In plant factories, plants are usually cultivated in nutrient solution under a controllable environment. Plant quality and growth are closely monitored and precisely controlled. For plant growth evaluation, plant weight is an important and commonly used indicator. Traditional plant weight measurements are destructive and laborious. In order to measure and record the plant weight during plant growth, an automated measurement system was designed and developed herein. The weight measurement system comprises a weight measurement device and an imaging system. The weight measurement device consists of a top disk, a bottom disk, a plant holder and a load cell. The load cell with a resolution of 0.1 g converts the plant weight on the plant holder disk to an analogue electrical signal for a precise measurement. The top disk and bottom disk are designed to be durable for different plant sizes, so plant weight can be measured continuously throughout the whole growth period, without hindering plant growth. The results show that plant weights measured by the weight measurement device are highly correlated with the weights estimated by the stereo-vision imaging system; hence, plant weight can be measured by either method. The weight growth of selected vegetables growing in the National Taiwan University plant factory were monitored and measured using our automated plant growth weight measurement system. The experimental results demonstrate the functionality, stability and durability of this system. The information gathered by this weight system can be valuable and beneficial for hydroponic plants monitoring research and agricultural research applications.

  18. Nuclear power plant diagnostic system

    International Nuclear Information System (INIS)

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  19. Conceptual design of small-sized HTGR system (1). Major specifications and system designs

    International Nuclear Information System (INIS)

    Ohashi, Hirofumi; Sato, Hiroyuki; Tazawa, Yujiro; Yan, Xing L.; Tachibana, Yukio

    2011-06-01

    Japan Atomic Energy Agency (JAEA) has started a conceptual design of a 50MWt small-sized high temperature gas cooled reactor (HTGR) for steam supply and electricity generation (HTR50S), which is a first-of-kind of the commercial plant or a demonstration plant of a small-sized HTGR system for steam supply to the industries and district heating and electricity generation by a steam turbine, to deploy in developing countries in the 2030s. The design philosophy is that the HTR50S is a high advanced reactor, which is reducing the R and D risk based on the HTTR design, upgrading the performance and reducing the cost for commercialization by utilizing the knowledge obtained by the HTTR operation and the GTHTR300 design. The major specifications of the HTR50S were determined and targets of the technology demonstration using the HTR50S (e.g., the increasing the power density, reduction of the number of uranium enrichment in the fuel, increasing the burn up, side-by-side arrangement between the reactor pressure vessel and the steam generator) were identified. In addition, the system design of HTR50S, which offers the capability of electricity generation, cogeneration of electricity and steam for a district heating and industries, was performed. Furthermore, a market size of small-sized HTGR systems was investigated. (author)

  20. Assessment and management of ageing of major nuclear power plant components important to safety. Primary piping in PWRs

    International Nuclear Information System (INIS)

    2003-07-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age-related licensing issues. The

  1. Waste receiving and processing plant control system; system design description

    Energy Technology Data Exchange (ETDEWEB)

    LANE, M.P.

    1999-02-24

    The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1.

  2. Waste receiving and processing plant control system; system design description

    International Nuclear Information System (INIS)

    LANE, M.P.

    1999-01-01

    The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1

  3. In vitro and in vivo susceptibility of Leishmania major to some medicinal plants

    Directory of Open Access Journals (Sweden)

    Fatemeh Maleki

    2017-01-01

    Conclusions: Our findings indicate that the tested plant extracts are effective against Leishmania major both during in vitro and in vivo experiments, but further researches are required to recommend a potential plant extract as an alternative drug.

  4. Plant-plant interactions influence developmental phase transitions, grain productivity and root system architecture in Arabidopsis via auxin and PFT1/MED25 signalling.

    Science.gov (United States)

    Muñoz-Parra, Edith; Pelagio-Flores, Ramón; Raya-González, Javier; Salmerón-Barrera, Guadalupe; Ruiz-Herrera, León Francisco; Valencia-Cantero, Eduardo; López-Bucio, José

    2017-09-01

    Transcriptional regulation of gene expression influences plant growth, environmental interactions and plant-plant communication. Here, we report that population density is a key factor for plant productivity and a major root architectural determinant in Arabidopsis thaliana. When grown in soil at varied densities from 1 to 32 plants, high number of individuals decreased stem growth and accelerated senescence, which negatively correlated with total plant biomass and seed production at the completion of the life cycle. Root morphogenesis was also a major trait modulated by plant density, because an increasing number of individuals grown in vitro showed repression of primary root growth, lateral root formation and root hair development while affecting auxin-regulated gene expression and the levels of auxin transporters PIN1 and PIN2. We also found that mutation of the Mediator complex subunit PFT1/MED25 renders plants insensitive to high density-modulated root traits. Our results suggest that plant density is critical for phase transitions, productivity and root system architecture and reveal a role of Mediator in self-plant recognition. © 2017 John Wiley & Sons Ltd.

  5. Seismic design criteria and their application to major hazard plant within the United Kingdom

    International Nuclear Information System (INIS)

    Alderson, M.A.H.G.

    1982-12-01

    The nature of seismic motions and the implications are briefly described and the development of seismic design criteria for nuclear power plants in various countries is described including possible future developments. The seismicity of the United Kingdom is briefly reviewed leading to the present position on seismic design criteria for nuclear power plants within the United Kingdom. Damage from past destructive earthquakes is reviewed and the existing codes of practice and standards are described. Finally the effect of earthquakes on major hazard plant is discussed in general terms including the seismic analysis of a typical plant item. (author)

  6. Plant condition assessments as a requirement before major investment in life extension for a CANDU nuclear power plant

    International Nuclear Information System (INIS)

    Aubray, Marc

    2002-01-01

    Full text: Since, to extend the life of a CANDU-6 reactor beyond its original design life requires the replacement of reactor components (380 pressure and calandria tubes), a major investment will have to be done. After a preliminary technical and economical feasibility study, Hydro- Quebec, owner of the Gentilly-2 NPP, has decided to perform a more detailed assessment to: 1. Get assurance that it is technically and economically viable to extend Gentilly-2 for another 20 years beyond the original design life; 2. Identify the detailed work to be done during the refurbishment period planned in 2008-2009; 3. Define the overall cost and the general schedule of the refurbishment phase; 4. Ensure an adequate licensing strategy to restart after refurbishment; 5. Complete all the Environmental Impact Studies required to obtain the government authorizations. The business case to support the refurbishment of Gentilly-2 has to take in consideration the reactor core components, which will be the major work to be completed during refurbishment. In summary the following main component will have to be changed or refreshed: The pressure and calandria tubes and the feeders (partial replacement only) (ageing mechanisms); The control computers (obsolescence); The condenser tubes (tubes plugging); The turbine control and electric-governor (obsolescence). An extensive campaign is under way to assess the 'health' of the station systems, structures and components (SSC). Two processes have been used for this assessment: Plant Life Management Studies (PLIM) for approximately 10 critical SSC or families of SSC (PLIM Studies); Condition Assessment Studies for other SSC with a lower impact on the Plant production or safety). The PLIM Studies are done on SSC's, which were judged critical because they are not replaceable (Reactor Building, Calandria), or that their failure could have a significant impact on safety or production (electrical motors, majors pumps, heat exchangers and pressure

  7. Drought versus heat: What's the major constraint on Mediterranean green roof plants?

    Energy Technology Data Exchange (ETDEWEB)

    Savi, Tadeja, E-mail: tsavi@units.it [Dipartimento di Scienze della Vita, Università di Trieste, Via L. Giorgieri 10, 34127 Trieste (Italy); Dal Borgo, Anna, E-mail: dalborgo.anna@gmail.com [Dipartimento di Scienze della Vita, Università di Trieste, Via L. Giorgieri 10, 34127 Trieste (Italy); Love, Veronica L., E-mail: vllove1@sheffield.ac.uk [Dipartimento di Scienze della Vita, Università di Trieste, Via L. Giorgieri 10, 34127 Trieste (Italy); Department of Landscape, University of Sheffield, Western Bank, Sheffield, South Yorkshire S10 2TN (United Kingdom); Andri, Sergio, E-mail: s.andri@seic.it [Harpo seic verdepensile, Via Torino 34, 34123 Trieste (Italy); Tretiach, Mauro, E-mail: tretiach@units.it [Dipartimento di Scienze della Vita, Università di Trieste, Via L. Giorgieri 10, 34127 Trieste (Italy); Nardini, Andrea, E-mail: nardini@units.it [Dipartimento di Scienze della Vita, Università di Trieste, Via L. Giorgieri 10, 34127 Trieste (Italy)

    2016-10-01

    Green roofs are gaining momentum in the arid and semi-arid regions due to their multiple benefits as compared with conventional roofs. One of the most critical steps in green roof installation is the selection of drought and heat tolerant species that can thrive under extreme microclimate conditions. We monitored the water status, growth and survival of 11 drought-adapted shrub species grown on shallow green roof modules (10 and 13 cm deep substrate) and analyzed traits enabling plants to cope with drought (symplastic and apoplastic resistance) and heat stress (root membrane stability). The physiological traits conferring efficiency/safety to the water transport system under severe drought influenced plant water status and represent good predictors of both plant water use and growth rates over green roofs. Moreover, our data suggest that high substrate temperature represents a stress factor affecting plant survival to a larger extent than drought per se. In fact, the major cause influencing seedling survival on shallow substrates was the species-specific root resistance to heat, a single and easy measurable trait that should be integrated into the methodological framework for screening and selection of suitable shrub species for roof greening in the Mediterranean. - Highlights: • The use of hardy shrub species for roof greening should be increased. • We monitored water status of 11 shrub species growing on shallow green roofs. • Species heat and drought tolerance, growth, and survival were studied. • High substrate temperature significantly affected plant survival. • Root resistance to heat could be used as trait for species selection for green roofs.

  8. Plant monitor system

    International Nuclear Information System (INIS)

    Scarola, K.; Jamison, D.; Manazir, R.; Rescori, R.; Harmon, D.

    1991-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system which is nuclear qualified for rapid response to changes in plant parameters and a component control system which together provide a discrete monitoring and control capability at a panel in the control room. A separate data processing system, which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs and a large, overhead integrated process status overview board. The discrete indicator and alarm system and the data processing system receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the main machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof. (author)

  9. The application of plant information system on third Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Liu Wangtian

    2005-01-01

    Plant overall control has been applied in Qinshan Nuclear Power Plant, which enhances the security of plant operation, but it is not enough to improve the technical administration level. In order to integrate the overall information and to improve the technical administration level more. Third Qinshan Nuclear Power Plant applies the plant information system. This thesis introduces the application of plant information system in Third Qinshan Nuclear Power Plant and the effect to the plant after the system is carried into execution, in addition, it does more analysis and exceptions for application of plant information system in the future. (authors)

  10. The Species Richness of Vascular Plants and Amphibia in Major Plant Communities in Temperate to Tropical Australia: Relationship with Annual Biomass Production

    International Nuclear Information System (INIS)

    Specht, R. L.; Tyler, M.J.

    2010-01-01

    Aerodynamic fluxes (frictional, thermal, evaporative) in the atmosphere as it flows over and through a plant community determine the Foliage Projective Covers and eco-morphological attributes of new leaves developed annually in overstorey and understorey strata. The number of leaves produced on vertical foliage shoots depends on available soil water and nutrients, also ambient temperature, during this short growth season. Stem density (number of stems per hectare) and species richness (number of species per hectare) in the overstorey of major Floristic Groups are correlated with annual shoot growth (ASG, t ha-1) in that stratum. Species richness in the overstorey increases in the climatic gradient from the arid to the humid zone as well as with increasing air temperatures (about 10 degree C) from temperate to tropical Australia. Species richness in the understorey is highest in plant communities in temperate Australia, decreasing in the temperature gradient towards the tropics. As with other major plant and animal groups within an ecosystem, the species richness of Amphibia is correlated with the amount of solar energy fixed (per annum) by the major plant formation in the regional photosynthetic potential determined by the foliage shoots (ASG, t ha-1) produced annually in the overstorey.

  11. The Species Richness of Vascular Plants and Amphibia in Major Plant Communities in Temperate to Tropical Australia: Relationship with Annual Biomass Production

    Directory of Open Access Journals (Sweden)

    R. L. Specht

    2010-01-01

    Full Text Available Aerodynamic fluxes (frictional, thermal, evaporative in the atmosphere as it flows over and through a plant community determine the Foliage Projective Covers and eco-morphological attributes of new leaves developed annually in overstorey and understorey strata. The number of leaves produced on vertical foliage shoots depends on available soil water and nutrients, also ambient temperature, during this short growth season. Stem density (number of stems per hectare and species richness (number of species per hectare in the overstorey of major Floristic Groups are correlated with annual shoot growth (ASG, t ha−1 in that stratum. Species richness in the overstorey increases in the climatic gradient from the arid to the humid zone as well as with increasing air temperatures (about 10oC from temperate to tropical Australia. Species richness in the understorey is highest in plant communities in temperate Australia, decreasing in the temperature gradient towards the tropics. As with other major plant and animal groups within an ecosystem, the species richness of Amphibia is correlated with the amount of solar energy fixed (per annum by the major plant formation in the region—a photosynthetic potential determined by the foliage shoots (ASG, t ha−1 produced annually in the overstorey.

  12. ITER plant systems

    International Nuclear Information System (INIS)

    Kolbasov, B.; Barnes, C.; Blevins, J.

    1991-01-01

    As part of a series of documents published by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this publication describes the conceptual design of the ITER plant systems, in particular (i) the heat transport system, (ii) the electrical distribution system, (iii) the requirements for radioactive equipment handling, the hot cell, and waste management, (iv) the supply system for fluids and operational chemicals, (v) the qualitative analyses of failure scenarios and methods of burn stability control and emergency shutdown control, (vi) analyses of tokamak building functions and design requirements, (vii) a plant layout, and (viii) site requirements. Refs, figs and tabs

  13. Development of plant maintenance systems

    International Nuclear Information System (INIS)

    Tomita, Jinji; Ike, Masae; Nakayama, Kenji; Kato, Hisatomo

    1989-01-01

    Toshiba is making active efforts for the continuing improvement of reliability and maintainability of operating nuclear power plants. As a part of these efforts, the company has developed new maintenance administration systems, diagnostic monitoring facilities for plant equipments, computer-aided expert systems, and remote-controlled machines for maintenance work. The maintenance administration systems provide efficient work plans and data acquisition capabilities for the management of personnel and equipments involved in nuclear power plant maintenance. The plant diagnostic facilities monitor and diagnose plant conditions for preventive maintenance, as well as enabling rapid countermeasures to be carried out should they be required. Expert systems utilizing artificial intelligence (AI) technology are also employed. The newly developed remote-controlled machines are useful tools for the maintenance inspection of equipment which can not be easily accessed. (author)

  14. Elevated service water temperature systems analysis for a nuclear power plant

    International Nuclear Information System (INIS)

    Lewis, T.; Hurt, W.

    1992-01-01

    This paper describes analyses performed to support the evaluation of the effects of elevated Service Water (SW) temperatures on the operation of a Pressurized Water Reactor. The purpose of the analyses is to provide justification of continued plant operation with SW temperatures up to 5 degrees F (3 degrees C) above the original temperature design limit. The study involved evaluation of the following major components or plant transients: Containment Design Basis Accident (DBA), Emergency Diesel Generator (EDG), Plant Cooldown, Engineered Safety Feature (ESF) Room Coolers, Engineered Safety Feature Pumps, and Assessment for Impact on Normal Operation. The principal objective was related to raising the design maximum temperature of the SW system from 95 degrees F (35 degrees C) to 100 degrees F (38 degrees C). since the Service Water system is safety related, an serves a plant during both normal and design basis conditions, a wide variety of components must be analyzed under various operating modes. The evaluation of systems and components affected by elevated SW temperature is presented, along with conclusions

  15. Found in Translation: Applying Lessons from Model Systems to Strigolactone Signaling in Parasitic Plants.

    Science.gov (United States)

    Lumba, Shelley; Subha, Asrinus; McCourt, Peter

    2017-07-01

    Strigolactones (SLs) are small molecules that act as endogenous hormones to regulate plant development as well as exogenous cues that help parasitic plants to infect their hosts. Given that parasitic plants are experimentally challenging systems, researchers are using two approaches to understand how they respond to host-derived SLs. The first involves extrapolating information on SLs from model genetic systems to dissect their roles in parasitic plants. The second uses chemicals to probe SL signaling directly in the parasite Striga hermonthica. These approaches indicate that parasitic plants have co-opted a family of α/β hydrolases to perceive SLs. The importance of this genetic and chemical information cannot be overstated since parasitic plant infestations are major obstacles to food security in the developing world. Copyright © 2017 Elsevier Ltd. All rights reserved.

  16. Wind power plant system services

    DEFF Research Database (Denmark)

    Basit, Abdul; Altin, Müfit

    Traditionally, conventional power plants have the task to support the power system, by supplying power balancing services. These services are required by the power system operators in order to secure a safe and reliable operation of the power system. However, as in the future the wind power...... is going more and more to replace conventional power plants, the sources of conventional reserve available to the system will be reduced and fewer conventional plants will be available on-line to share the regulation burden. The reliable operation of highly wind power integrated power system might...... then beat risk unless the wind power plants (WPPs) are able to support and participate in power balancing services. The objective of this PhD project is to develop and analyse control strategies which can increase the WPPs capability to provide system services, such as active power balancing control...

  17. The System 80+ Standard Plant Information Management System

    Energy Technology Data Exchange (ETDEWEB)

    Turk, R.S.; Bryan, R.E. [ABB Combuions Engineering Nuclear Systems (United States)

    1998-07-01

    Historically, electric nuclear power plant owners, following the completion of construction and startup, have been left with a mountain of hard-copy documents and drawings. Hundreds of thousands of hours are spent searching for relevant documents and, in most cases, the documents found require many other documents and drawings to fully understand the design basis. All too often the information is incomplete, and eventually becomes obsolete. In the U.S., utilities spend millions of dollars to discover design basis information and update as-built data for each plant. This information must then be stored in an easily accessed usable form to assist satisfy regulatory requirements and to improve plant operating efficiency. ABB Combustion Engineering Nuclear Systems (ABB-CE) has an active program to develop a state-of-the-art Plant Information Management System (IMS) for its advanced light water reactor, the System 80+TM Standard Plant Design. This program is supported by ABB's Product Data Management (PDM) and Computer Aided Engineering (CAE) efforts world wide. This paper describes the System 80+ plant IMS and how it will be used during the entire life cycle of the plant. (author)

  18. The System 80+ Standard Plant Information Management System

    International Nuclear Information System (INIS)

    Turk, R.S.; Bryan, R.E.

    1998-01-01

    Historically, electric nuclear power plant owners, following the completion of construction and startup, have been left with a mountain of hard-copy documents and drawings. Hundreds of thousands of hours are spent searching for relevant documents and, in most cases, the documents found require many other documents and drawings to fully understand the design basis. All too often the information is incomplete, and eventually becomes obsolete. In the U.S., utilities spend millions of dollars to discover design basis information and update as-built data for each plant. This information must then be stored in an easily accessed usable form to assist satisfy regulatory requirements and to improve plant operating efficiency. ABB Combustion Engineering Nuclear Systems (ABB-CE) has an active program to develop a state-of-the-art Plant Information Management System (IMS) for its advanced light water reactor, the System 80+TM Standard Plant Design. This program is supported by ABB's Product Data Management (PDM) and Computer Aided Engineering (CAE) efforts world wide. This paper describes the System 80+ plant IMS and how it will be used during the entire life cycle of the plant. (author)

  19. Demonstration of a Porous Tube Hydroponic System to Control Plant Moisture and Growth

    Science.gov (United States)

    Dreschel, T. W.; Hall, C. R.; Foster, T. E.

    2003-01-01

    Accurate remote detection of plant health indicators such as moisture, plant pigment concentrations, photosynthetic flux, and other biochemicals in canopies is a major goal in plant research. Influencing factors include complex interactions between wavelength dependent absorbing and scattering features from backgrounds as well as canopy biochemical and biophysical constituents. Accurately controlling these factors in outdoor field studies is difficult. Early testing of a porous tube plant culture system has indicated that plant biomass production, biomass partitioning, and leaf moisture of plants can be controlled by precisely managing the root water potential. Managing nutrient solution chemistry can also control plant pigments, biochemical concentrations, plant biomass production, and photosynthetic rates. A test bed was developed which utilized the porous tube technology with the intent of evaluating remote sensing systems, spectral analyses procedures, gas-exchange, and fluorescence measurements for their ability to detect small differences in plant water status. Spectral analysis was able to detect small differences in the mean leaf water content between the treatments. However these small differences were not detectable in the gas-exchange or fluorescence measurements.

  20. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An Kang Il; Hong, Suk Young; Lee, Jeong Soo; Lee, Kwang Yeol; Shin, Sun Hee; Lee, Chun Wha; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2003-03-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following: development of H/W that is necessary to acquire operating real time data of heating and hydraulic power, selection of a safety variable about major system by each type (the fourth unit), communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server, development of connecting database for controlling and storing of heating and hydraulic power operating data, real time monitoring system development based on web using JAVA.

  1. A landscape simulation system for power plants

    International Nuclear Information System (INIS)

    Yoshinaga, Toshiaki; Yoshida, Miki; Usami, Yoshiaki.

    1997-01-01

    As scenes of power plants give many influences to environments, the plants that harmonized with the environments are demanded. We developed a landscape simulation system for the plants by using computer graphics technologies. This system has functions to generate realistic images about plant buildings and environments. Since the system contains information of ridge lines in addition to usual terrain data, the terrain shapes are expressed more precisely. Because the system enables users to visualize plant construction plans, the advance evaluations of plant scenes become possible. We regard this system as useful for environmental assessment of power plants. (author)

  2. Software for computers in safety systems of nuclear power plants

    International Nuclear Information System (INIS)

    Gallagher, J.M.

    1983-01-01

    The application of distributed digital processing techniques to the protection systems of nuclear power plants provides a means to significantly improve the functional capability of the protection system with respect to the operability and availability of the power plant. A major factor in the realization of this improvement is the development and maintenance of essentially error-free software. A joint program for the development of principles for the design, testing and documentation of software to achieve this goal is presented. Results from two separate experiences in the application of these principles in terms of detected software errors are summarized. The low number of errors detected during the verification testing phase demonstrates the effectiveness of the design and documentation principles in the realization of highly reliable software. (author)

  3. Optimization criteria for control and instrumentation systems in nuclear power plants

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    1978-01-01

    The system of dose limitation recently recommended by the International Commission on Radiation Protection includes, as a base for deciding what is reasonably achievable in dose reduction, the optimization of radioprotection systems. This paper, after compiling relevant points in the new system, discusses the application of optimization to control and instrumentation of radioprotection systems in nuclear power plants. Furthermore, an extension of the optimization criterion to nuclear safety systems is also presented and its application to control and instrumentation is discussed; systems including majority logics are particularly scrutinized. Finally, eventual regulatory implications are described. (author)

  4. Plant growth and gas balance in a plant and mushroom cultivation system

    Science.gov (United States)

    Kitaya, Y.; Tani, A.; Kiyota, M.; Aiga, I.

    1994-11-01

    In order to obtain basic data for construction of a plant cultivation system incorporating a mushroom cultivation subsystem in the CELSS, plant growth and atmospheric CO2 balance in the system were investigated. The plant growth was promoted by a high level of CO2 which resulted from the respiration of the mushroom mycelium in the system. The atmospheric CO2 concentration inside the system changed significantly due to the slight change in the net photosynthetic rate of plants and/or the respiration rate of the mushroom when the plant cultivation system combined directly with the mushroom cultivation subsystem.

  5. Plant Systems Biology (editorial)

    Science.gov (United States)

    In June 2003, Plant Physiology published an Arabidopsis special issue devoted to plant systems biology. The intention of Natasha Raikhel and Gloria Coruzzi, the two editors of this first-of-its-kind issue, was ‘‘to help nucleate this new effort within the plant community’’ as they considered that ‘‘...

  6. Guidelines for the application and use of valves in power plant systems

    International Nuclear Information System (INIS)

    Brooks, B.

    1991-01-01

    The improper application, incorrect use, and ineffective maintenance of valves in power plant systems have been determined to be the cause of significant losses in plant availability. Such practices may additionally impact the safe operation of the plant. Numerous programs have been initiated, particularly in the nuclear power generation industry, to address these problems and excellent strides have been taken in that direction. Plant operating data, however, continues to indicate major losses in plant availability attributable to these sources. Although there exists significant knowledge and expertise in valve technology in the valve industry and in the power generation industry, the application of these factors, in preventing and resolving problems, has not been effectively utilized. Detailed information is difficult to glean from numerous sources and may often be restricted by proprietary considerations. Lessons learned in resolving problems have not been broadly disseminated in the industry with the result that individual utilities may be addressing problems unaware that a neighbor utility has already effectively resolved this same problem. To aid the power generation industry in improving upon this condition, EPRI initiated a project to develop 'Guide for the Application and Use of Valves in Power Plant Systems' (RP2233-5). A draft of the document was reviewed by an industry group whose major comment was the need to achieve a more readable text in which information on specific areas of concern is readily accessible. This rewriting has been accomplished along the lines of valve functional requirements. This paper presents an introduction, a summary, and a road map on how to use the guidebook

  7. 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)

  8. Majoring in Information Systems: Reasons Why Students Select (or Not) Information Systems as a Major

    Science.gov (United States)

    Snyder, Johnny; Slauson, Gayla Jo

    2014-01-01

    Filling the pipeline for information systems workers is critical in the information era. Projected growth rates for jobs requiring information systems expertise are significantly higher than the projected growth rates for other jobs. Why then do relatively few students choose to major in information systems? This paper reviews survey results from…

  9. Proceedings: Power Plant Electric Auxiliary Systems Workshop

    International Nuclear Information System (INIS)

    1992-06-01

    The EPRI Power Plant Electric Auxiliary Systems Workshop, held April 24--25, 1991, in Princeton, New Jersey, brought together utilities, architect/engineers, and equipment suppliers to discuss common problems with power plant auxiliary systems. Workshop participants presented papers on monitoring, identifying, and solving problems with auxiliary systems. Panel discussions focused on improving systems and existing and future plants. The solutions presented to common auxiliary system problems focused on practical ideas that can enhance plant availability, reduce maintenance costs, and simplify the engineering process. The 13 papers in these proceedings include: Tutorials on auxiliary electrical systems and motors; descriptions of evaluations, software development, and new technologies used recently by electric utilities; an analysis of historical performance losses caused by power plant auxiliary systems; innovative design concepts for improving auxiliary system performance in future power plants

  10. A development of digital plant protection system architecture

    International Nuclear Information System (INIS)

    Seong, S. H.; Park, H. Y.; Kim, D. H.; Seo, Y. S.; Gu, I. S.

    2000-01-01

    The digital plant protection system (DPPS) which have a large number of advantages compared to current analog protection system has been developed in various field. The major disadvantages of digital system are, however, vulnerable to faults of processor and software. To overcome the disadvantages, the concept of segment and partition in a channel has been developed. Each segment in a channel is divided from sensor to reactor trip and engineered safety features, which is based on the functional diversity of input signals against the various plant transient phenomena. Each partition allocates the function module to an independent processing module in order to process and isolate the faults of each module of a segment. A communication system based on the deterministic protocol with the predictable and hard real-time characteristics has been developed in order to link the various modules within a segment. The self-diagnostics including online test and periodic test procedures are developed in order to increase the safety, reliability and availability of DPPS. The developed DPPS uses the off-the-shelf DSP (digital signal processor) and adopts VME bus architecture, which have sufficient operation experience in the industry. The verification and validation and quality assurance of software has been developed and the architecture and protocol of deterministic communication system has been researched

  11. New design architecture decisions on water chemistry support systems at new VVER plants

    International Nuclear Information System (INIS)

    Kumanina, V.E.; Yurmanova, A.V.

    2010-01-01

    Major goals of nuclear power plant design upgrading are reduction of cost and construction time with unconditional safety assurance. Main ways of further improvement of nuclear power plant design are as follows: review of the results of research engineering and development and of new technologies; harmonization with international codes and standards; justified liberalization of conservatism based on operating experience and use of improved design codes. Operational experience of Russian and foreign NPPs has shown that the designs of new NPPs could be improved by upgrading water chemistry support systems. Some new design solutions for water chemistry support systems are currently implemented at new WWER plants such as Bushehr, Kudankulam, Belene, Balakovo Units 5 and 6, AES-2006 project. The paper highlights the improvements of the following systems and processes: low temperature high pressure primary coolant clean-up system; primary system surface preconditioning during pre-start hot functional testing; steam generator blowdown cleanup system; secondary water chemistry; phosphate water chemistry in intermediate cooling circuits and other auxiliary systems; alternator cooling system water chemistry; steam generator cleanup and decontamination systems. (author)

  12. Promises in intelligent plant control systems

    International Nuclear Information System (INIS)

    Otaduy, P.J.

    1987-01-01

    The control system is the brain of a power plant. The traditional goal of control systems has been productivity. However, in nuclear power plants the potential for disaster requires safety to be the dominant concern, and the worldwide political climate demands trustworthiness for nuclear power plants. To keep nuclear generation as a viable option for power in the future, trust is the essential critical goal which encompasses all others. In most of today's nuclear plants the control system is a hybrid of analog, digital, and human components that focuses on productivity and operates under the protective umbrella of an independent engineered safety system. Operation of the plant is complex, and frequent challenges to the safety system occur which impact on their trustworthiness. Advances in nuclear reactor design, computer sciences, and control theory, and in related technological areas such as electronics and communications as well as in data storage, retrieval, display, and analysis have opened a promise for control systems with more acceptable human brain-like capabilities to pursue the required goals. This paper elaborates on the promise of futuristic nuclear power plants with intelligent control systems and addresses design requirements and implementation approaches

  13. Plant operator performance evaluation system

    International Nuclear Information System (INIS)

    Ujita, Hiroshi; Fukuda, Mitsuko; Kubota, Ryuji.

    1989-01-01

    A plant operator performance evaluation system to analyze plant operation records during accident training and to identify and classify operator errors has been developed for the purpose of supporting realization of a training and education system for plant operators. A knowledge engineering technique was applied to evaluation of operator behavior by both even-based and symptom-based procedures, in various situations including event transition due to multiple failures or operational errors. The system classifies the identified errors as to their single and double types based on Swain's error classification and the error levels reflecting Rasmussen's cognitive level, and it also evaluates the effect of errors on plant state and then classifies error influence, using 'knowledge for phenomena and operations', as represented by frames. It has additional functions for analysis of error statistics and knowledge acquisition support of 'knowledge for operations'. The system was applied to a training analysis for a scram event in a BWR plant, and its error analysis function was confirmed to be effective by operational experts. (author)

  14. Water chemistry data acquisition, processing, evaluation and diagnostic systems in Light Water Reactors: Future improvement of plant reliability and safety

    International Nuclear Information System (INIS)

    Uchida, S.; Takiguchi, H.; Ishigure, K.

    2006-01-01

    Data acquisition, processing and evaluation systems have been applied in major Japanese PWRs and BWRs to provide (1) reliable and quick data acquisition with manpower savings in plant chemical laboratories and (2) smooth and reliable information transfer among chemists, plant operators, and supervisors. Data acquisition systems in plants consist of automatic and semi-automatic instruments for chemical analyses, e. g., X-ray fluorescence analysis and ion chromatography, while data processing systems consist of PC base-sub-systems, e.g., data storage, reliability evaluation, clear display, and document preparation for understanding the plant own water chemistry trends. Precise and reliable evaluations of water chemistry data are required in order to improve plant reliability and safety. For this, quality assurance of the water chemistry data acquisition system is needed. At the same time, theoretical models are being applied to bridge the gaps between measured water chemistry data and the information desired to understand the interaction of materials and cooling water in plants. Major models which have already been applied for plant evaluation are: (1) water radiolysis models for BWRs and PWRs; (2) crevice radiolysis model for SCC in BWRs; and (3) crevice pH model for SG tubing in PWRs. High temperature water chemistry sensors and automatic plant diagnostic systems have been applied in only restricted areas. ECP sensors are gaining popularity as tools to determine the effects of hydrogen injection in BWR systems. Automatic plant diagnostic systems based on artificial intelligence will be more popular after having sufficient experience with off line diagnostic systems. (author)

  15. Evaluation of an ethnopharmacologically selected Bhutanese medicinal plants for their major classes of phytochemicals and biological activities.

    Science.gov (United States)

    Wangchuk, Phurpa; Keller, Paul A; Pyne, Stephen G; Taweechotipatr, Malai; Tonsomboon, Aunchalee; Rattanajak, Roonglawan; Kamchonwongpaisan, Sumalee

    2011-09-01

    As many as 229 medicinal plants have been currently used in the Bhutanese Traditional Medicine (BTM) as a chief ingredient of polyherbal formulations and these plants have been individually indicated for treating various types of infections including malaria, tumor, and microbial. We have focused our study only on seven species of these plants. We aim to evaluate the antiplasmodial, antimicrobial, anti-Trypanosoma brucei rhodesiense and cytotoxicity activities of the seven medicinal plants of Bhutan selected using an ethno-directed bio-rational approach. This study creates a scientific basis for their use in the BTM and gives foundation for further phytochemical and biological evaluations which can result in the discovery of new drug lead compounds. A three stage process was conducted which consisted of: (1) an assessment of a pharmacopoeia and a formulary book of the BTM for their mode of plant uses; (2) selecting 25 anti-infective medicinal plants based on the five established criteria, collecting them, and screening for their major classes of phytochemicals using appropriate test protocols; and (3) finally analyzing the crude extracts of the seven medicinal plants, using the standard test protocols, for their antiplasmodial, antimicrobial, anti-Trypanosoma brucei rhodesiense and cytotoxicity activities as directed by the ethnopharmacological uses of each plant. Out of 25 medicinal plants screened for their major classes of phytochemicals, the majority contained tannins, alkaloids and flavonoids. Out of the seven plant species investigated for their biological activities, all seven of them exhibited mild antimicrobial properties, five plants gave significant in vitro antiplasmodial activities, two plants gave moderate anti-Trypanosoma brucei rhodesiense activity, and one plant showed mild cytotoxicity. Meconopsis simplicifolia showed the highest antiplasmodial activity with IC(50) values of 0.40 μg/ml against TM4/8.2 strain (a wild type chloroquine and

  16. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    International Nuclear Information System (INIS)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee

    2004-02-01

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA

  17. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2004-02-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA.

  18. 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

  19. PLANT BIOPRINTING: NOVEL PERSPECTIVE FOR PLANT BIOTECHNOLOGY

    Directory of Open Access Journals (Sweden)

    Adhityo WICAKSONO

    2015-12-01

    Full Text Available Bioprinting is a technical innovation that has revolutionized tissue engineering. Using conventional printer cartridges filled with cells as well as a suitable scaffold, major advances have been made in the biomedical field, and it is now possible to print skin, bones, blood vessels, and even organs. Unlike animal systems, the application of bioprinting in simple plant tissue cells is still in a nascent phase and has yet to be studied. One major advantage of plants is that all living parts are reprogrammable in the form of totipotent cells. Plant bioprinting may improve scientists’understanding of plant shape and morphogenesis, and could serve for the mass production of desired tissues or plants, or even the production of plant-based biomaterial for industrial uses. This perspectives paper explores these possibilities using knowledge on what is known about bioprinting in other biosystems.

  20. Geography and major host evolutionary transitions shape the resource use of plant parasites.

    Science.gov (United States)

    Calatayud, Joaquín; Hórreo, José Luis; Madrigal-González, Jaime; Migeon, Alain; Rodríguez, Miguel Á; Magalhães, Sara; Hortal, Joaquín

    2016-08-30

    The evolution of resource use in herbivores has been conceptualized as an analog of the theory of island biogeography, assuming that plant species are islands separated by phylogenetic distances. Despite its usefulness, this analogy has paradoxically led to neglecting real biogeographical processes in the study of macroevolutionary patterns of herbivore-plant interactions. Here we show that host use is mostly determined by the geographical cooccurrence of hosts and parasites in spider mites (Tetranychidae), a globally distributed group of plant parasites. Strikingly, geography accounts for most of the phylogenetic signal in host use by these parasites. Beyond geography, only evolutionary transitions among major plant lineages (i.e., gymnosperms, commelinids, and eudicots) shape resource use patterns in these herbivores. Still, even these barriers have been repeatedly overcome in evolutionary time, resulting in phylogenetically diverse parasite communities feeding on similar hosts. Therefore, our results imply that patterns of apparent evolutionary conservatism may largely be a byproduct of the geographic cooccurrence of hosts and parasites.

  1. Cytokinins, A classical multifaceted hormone in plant system

    Directory of Open Access Journals (Sweden)

    Mohd Mazid

    2011-12-01

    Full Text Available Today, owing to the versatile functionality and physiological importance of the phytohormone cytokinin (Ck is a major focus of attention in contemporary wide areas of plant science. Cytokinins (Cks have implicated in diverse essential processes of plant growth and development as well as in regulation of key genes responsible for the metabolism and activities of plants. Cytokinin interact in a complex manner to control a myriad of aspects related to growth, development and differentiation and its deficiency also causes pleiotropic developmental changes such as reduced shoot and increased root growth. Cytokinin signaling involves His Kinase receptors that perceive cytokinin and transmit the signal via a multi-step phosphorelay similar to bacterial two-component signaling system. Also, this review present a scheme for homeostatic regulation of endogenous cytokinins level in terms of the described mechanism of cytokinin action including its receptors and steps involved in regulation of gene expression at the post-transcriptional level and its role in whole plant as well as cell division. In addition, we also demonstrate a wide variety of biological effects including those on gene expression, inhibition of auxin action, stimulation of cell cycle etc.

  2. Chapter 15. Plant pathology and managing wildland plant disease systems

    Science.gov (United States)

    David L. Nelson

    2004-01-01

    Obtaining specific, reliable knowledge on plant diseases is essential in wildland shrub resource management. However, plant disease is one of the most neglected areas of wildland resources experimental research. This section is a discussion of plant pathology and how to use it in managing plant disease systems.

  3. Mapping of a major QTL for salt tolerance of mature field-grown maize plants based on SNP markers.

    Science.gov (United States)

    Luo, Meijie; Zhao, Yanxin; Zhang, Ruyang; Xing, Jinfeng; Duan, Minxiao; Li, Jingna; Wang, Naishun; Wang, Wenguang; Zhang, Shasha; Chen, Zhihui; Zhang, Huasheng; Shi, Zi; Song, Wei; Zhao, Jiuran

    2017-08-15

    Salt stress significantly restricts plant growth and production. Maize is an important food and economic crop but is also a salt sensitive crop. Identification of the genetic architecture controlling salt tolerance facilitates breeders to select salt tolerant lines. However, the critical quantitative trait loci (QTLs) responsible for the salt tolerance of field-grown maize plants are still unknown. To map the main genetic factors contributing to salt tolerance in mature maize, a double haploid population (240 individuals) and 1317 single nucleotide polymorphism (SNP) markers were employed to produce a genetic linkage map covering 1462.05 cM. Plant height of mature maize cultivated in the saline field (SPH) and plant height-based salt tolerance index (ratio of plant height between saline and control fields, PHI) were used to evaluate salt tolerance of mature maize plants. A major QTL for SPH was detected on Chromosome 1 with the LOD score of 22.4, which explained 31.2% of the phenotypic variation. In addition, the major QTL conditioning PHI was also mapped at the same position on Chromosome 1, and two candidate genes involving in ion homeostasis were identified within the confidence interval of this QTL. The detection of the major QTL in adult maize plant establishes the basis for the map-based cloning of genes associated with salt tolerance and provides a potential target for marker assisted selection in developing maize varieties with salt tolerance.

  4. System identification of the Arabidopsis plant circadian system

    Science.gov (United States)

    Foo, Mathias; Somers, David E.; Kim, Pan-Jun

    2015-02-01

    The circadian system generates an endogenous oscillatory rhythm that governs the daily activities of organisms in nature. It offers adaptive advantages to organisms through a coordination of their biological functions with the optimal time of day. In this paper, a model of the circadian system in the plant Arabidopsis (species thaliana) is built by using system identification techniques. Prior knowledge about the physical interactions of the genes and the proteins in the plant circadian system is incorporated in the model building exercise. The model is built by using primarily experimentally-verified direct interactions between the genes and the proteins with the available data on mRNA and protein abundances from the circadian system. Our analysis reveals a great performance of the model in predicting the dynamics of the plant circadian system through the effect of diverse internal and external perturbations (gene knockouts and day-length changes). Furthermore, we found that the circadian oscillatory rhythm is robust and does not vary much with the biochemical parameters except those of a light-sensitive protein P and a transcription factor TOC1. In other words, the circadian rhythmic profile is largely a consequence of the network's architecture rather than its particular parameters. Our work suggests that the current experimental knowledge of the gene-to-protein interactions in the plant Arabidopsis, without considering any additional hypothetical interactions, seems to suffice for system-level modeling of the circadian system of this plant and to present an exemplary platform for the control of network dynamics in complex living organisms.

  5. Developments in power plant cooling systems

    International Nuclear Information System (INIS)

    Agarwal, N.K.

    1993-01-01

    A number of cooling systems are used in the power plants. The condenser cooling water system is one of the most important cooling systems in the plant. The system comprises a number of equipment. Plants using sea water for cooling are designed for the very high corrosion effects due to sea water. Developments are taking place in the design, materials of construction as well as protection philosophies for the various equipment. Power optimisation of the cycle needs to be done in order to design an economical system. Environmental (Protection) Act places certain limitations on the effluents from the plant. An attempt has been made in this paper to outline the developing trends in the various equipment in the condenser cooling water systems used at the inland as well as coastal locations. (author). 5 refs., 6 refs

  6. 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

  7. Monitoring and diagnostic system of fission product transport and release in nuclear power plants

    International Nuclear Information System (INIS)

    Kodaira, H.; Kondo, S.; Togo, Y.

    1983-01-01

    A monitoring and diagnostic system (MADS) of fission product (FP) transport and release in nuclear power plants (NPPs) is proposed and the conceptual design for MADS is studied. A MADS can be described in the most general way as a computer-based information processing system which takes in plant data, processes it and displays the results to the NPP's operating crew. A major concern for MADS is, however, not to evaluate general plant dynamics, but to monitor the distribution of whole radioactive materials such as FP, and to diagnose the plant state in the view of FP transport during the NPP's lifetime. Several functions demanded of MADS are: (a) during normal operation, to certify the fuel integrity and the effectiveness of the purification systems, (b) in an unusual event, to identify the event and to monitor the amount of FP release with accuracy, and (c) in case of a rare occurrence, to estimate the maximum potential release

  8. Analysis of effects on plant performance by major measuring points in the secondary systems of Kori nuclear power plant units 3 and 4

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Park, Jae Chang; Lee, Jung Woon; Kim, Jung Taek; Chang, Soon Heung; Lee, Gwang Gu; Heo, Gyun Young; Lee, Sung Jin; Han, Kyu Hyun; Shin, Byung Soo

    2003-06-01

    In this study, correlation analysis was achieved for the major sensor position and the behavior of secondary system in Kori NPP unit 3, 4. Using the data from simulation model, the correlation between sensor position and electrical output, the correlation between sensor position and heat rate, and the correlation between different sensor positions were analyzed. On the basis of study results, a performance evaluation model was proposed, which can carry out secondary system performance diagnosis

  9. Development of A Plant Navigation System

    International Nuclear Information System (INIS)

    Furuta, Tomihiko; Nakagawa, Tsuneo; Kubota, Ryuji; Ikeda, Kouji

    1998-01-01

    A 'Plant Navigation System (PNS)' is under development to assist nuclear power plant (NPP) operators by automatically displaying the plant situation and plant operational procedures on a CRT screen when abnormalities occur. The operation procedures given in a symptom-oriented manual are expressed in a tree - type flowchart (modified PAD). The optimum operation procedure for an NPP is selected automatically using built-in diagnostic logics based on the current status of the NPP. Concerning the plant situation, the PNS displays important information only on the current status of the NPP. A prototype PNS system is being constructed. (authors)

  10. Design and simulation of a plant control system for a GCFR demonstration plant

    International Nuclear Information System (INIS)

    Estrine, E.A.; Greiner, H.G.

    1980-02-01

    A plant control system is being designed for a 300 MW(e) Gas Cooled Fast Breeder Reactor (GCFR) demonstration plant. Control analysis is being performed as an integral part of the plant design process to ensure that control requirements are satisfied as the plant design evolves. Plant models and simulations are being developed to generate information necessary to further define control system requirements for subsequent plant design iterations

  11. Monitoring support system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashikawa, Yuichi; Kubota, Rhuji; Tanaka, Keiji; Takano, Yoshiyuki

    1996-01-01

    The nuclear power plants in Japan reach to 49 plants and supply 41.19 million kW in their installed capacities, which is equal to about 31% of total electric power generation and has occupied an important situation as a stable energy supplying source. As an aim to keeping safe operation and working rate of the power plants, various monitoring support systems using computer technology, optical information technology and robot technology each advanced rapidly in recent year have been developed to apply to the actual plants for a plant state monitoring system of operators in normal operation. Furthermore, introduction of the emergent support system supposed on accidental formation of abnormal state of the power plants is also investigated. In this paper, as a monitoring system in the recent nuclear power plants, design of control panel of recent central control room, introduction to its actual plant and monitoring support system in development were described in viewpoints of improvement of human interface, upgrade of sensor and signal processing techniques, and promotion of information service technique. And, trend of research and development of portable miniature detector and emergent monitoring support system are also introduced in a viewpoint of labor saving and upgrade of the operating field. (G.K.)

  12. Using a plant health system framework to assess plant clinic performance in Uganda

    DEFF Research Database (Denmark)

    Danielsen, Solveig; Matsiko, Frank B.

    2016-01-01

    and expand, new analytical frameworks and tools are needed to identify factors influencing performance of services and systems in specific contexts, and to guide interventions. In this paper we apply a plant health system framework to assess plant clinic performance, using Uganda as a case study...... factors, influenced by basic operational and financial concerns, inter-institutional relations and public sector policies. Overall, there was a fairly close match between the plant health system attributes and plant clinic performance, suggesting that the framework can help explain system functioning....... A comparative study of plant clinics was carried out between July 2010 and September 2011 in the 12 districts where plant clinics were operating at that time. The framework enabled us to organise multiple issues and identify key features that affected the plant clinics. Clinic performance was, among other...

  13. Plant introduction system applying virtual reality

    International Nuclear Information System (INIS)

    Kasai, Yasusuke; Tanaka, Kazuo; Kimura, Katsumi; Nakakosi, Tetsuhiro

    1995-01-01

    We developed the prototype of the introduction system for nuclear power plant applying 3D-CAD data and the virtual reality (V.R) technologies. For the purpose of the public acceptance (PA), the use of the V.R technologies, such as CG stereographic, will be interesting for the public. Also, it is very important to introduce the components of the plant in detail, which will become easy by using the 3D-CAD data of the nuclear plant. We made a prototype system for introducing the main portion of the nuclear power plant, such as main control room, containment vessel or turbine building, applying CG stereographic by plant 3D data and artificial voice guidance for the explanations. We have exhibited this system in two local festivals at the plant sites. It has been efficient for creating plant scene by using 3D-CAD from the viewpoint of cost, and stereographic has been much attractive to the resident. The detail scenario must be investigated from the viewpoint of PA effect. Also the performance of the graphics workstation should be increased to promote the quality of the CG movie. But we think that this system will have much effective by its novelty and flexibility. (author)

  14. Surveillance system for nuclear power plants

    International Nuclear Information System (INIS)

    Mizeracki, M.T.

    1981-01-01

    This paper describes an integrated surveillance system for nuclear power plant application. The author explores an expanded role for closed circuit television, with remotely located cameras and infrared scanners as the basic elements. The video system, integrated with voice communication, can enhance the safe and efficient operation of the plant, by improving the operator's knowledge of plant conditions. 7 refs

  15. Industrial cost assessment for ITER tritium plant system (water distillation, VPCE and ISS)

    International Nuclear Information System (INIS)

    Sood, S.K.; Kalyanam, K.M.; Fong, C.

    1995-01-01

    The objective of this Industrial Cost Assessment Task for ITER Tritium Plant System consists of providing and order of magnitude cost estimate for the following major subsystems, as outlined in the Scope of Task Agreement and Work Program: water distillation (WD) system, vapour phase catalytic exchange (VPCE) system and the isotope separation system (ISS). The methodology adopted in preparing the order of magnitude cost estimate for the above three subsystems of the ITER tritium plant system is based on building the estimate from the ground up, starting with equipment cost estimates, and adding labour activities separately for engineering, fabrication, assembly, testing installation commissioning, etc. The estimate has been developed assuming that the systems are to be engineered, fabricated and constructed in Canada, (to comply with the Codes, Standards, QA and Seismic Classification applicable in Canada) since information on ITER siting is not currently available. The estimate is based on Ontario Hydro in house cost data on similar systems and equipment, such as the heavy water upgrading plants. The cost estimates are not based on quotations from suppliers for specific ITER components, since this would require completion of detailed design and specifications. 4 refs., 9 tabs., 7 figs

  16. Modernizing and Maintaining Instrumentation and Control Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Naser, Joseph; Torok, Raymond; Shankar, Ramesh

    2003-01-01

    Deregulation of the electric utilities has made a major impact on nuclear power plants. To be competitive, more emphasis is being put on cost-effective production of electricity with a more critical look at whether a system should be modernized due to obsolescence, reliability, or productivity concerns. Instrumentation and control (I and C) systems play an important role in reducing the cost of producing electricity while maintaining or enhancing safety. Systems that are well designed, reliable, enhance productivity, and are cost-effective to operate and maintain can reduce the overall costs. Modern technology with its ability to better provide and use real-time information offers an effective platform for modernizing systems. At the same time, new technology brings new challenges and issues, especially for safety systems in nuclear power plants. To increase competitiveness, it is important to take advantage of the opportunities offered by modern technology and to address the new challenges and issues in a cost-effective manner. The Electric Power Research Institute (EPRI) and its member utilities have been working together with other members of the nuclear industry since 1990 to address I and C modernization and maintenance issues. The EPRI I and C Program has developed a life-cycle management approach for I and C systems that involves the optimization of maintenance, monitoring, and capital resources to sustain safety and performance throughout the plant life. Strategic planning methodologies and implementation guidelines addressing digital I and C issues in nuclear power plants have been developed. Work is ongoing in diverse areas to support the design, implementation, and operation of new digital systems. Technology transfer is an integral part of this I and C program

  17. Advanced safeguards systems development for chemical processing plants. Final report for Fiscal Year 1979

    International Nuclear Information System (INIS)

    Johnson, C.E.

    1980-01-01

    A computer system is being installed by INEL to test and evaluate safeguards monitoring concepts in an operating nuclear fuel processing plant. Safeguards development sensors and instruments installed in the ICPP provide plant information to a computer data acquisition and analysis system. Objective of the system is to collect data from process and safeguards sensors and show how this data can be analyzed to detect diversion operations or improper plant operation, and to test the performance of the monitoring devices. Approximately one-third of the installation designs and one-eighth of the installations were completed in FY 1979. The ICPP processing schedule for FY 1980 permits installation of the remaining monitoring devices before process startup in the fourth quarter of FY 1980. All computer hardware was delivered and checked out in FY 1979. Computer software system designs were completed with the majority of the programming scheduled for FY 1980. Sensor and instrument development in FY 1979 emphasized device testing for ICPP monitoring applications

  18. The impact of major trauma network triage systems on patients with major burns.

    Science.gov (United States)

    Nizamoglu, Metin; O'Connor, Edmund Fitzgerald; Bache, Sarah; Theodorakopoulou, Evgenia; Sen, Sankhya; Sherren, Peter; Barnes, David; Dziewulski, Peter

    2016-12-01

    Trauma is a leading cause of death and disability worldwide. Patients presenting with severe trauma and burns benefit from specifically trained multidisciplinary teams. Regional trauma systems have shown improved outcomes for trauma patients. The aim of this study is to determine whether the development of major trauma systems have improved the management of patients with major burns. A retrospective study was performed over a four-year period reviewing all major burns in adults and children received at a regional burns centre in the UK before and after the implementation of the regional trauma systems and major trauma centres (MTC). Comparisons were drawn between three areas: (1) Patients presenting before the introduction of MTC and after the introduction of MTC. (2) Patients referred from MTC and non-MTC within the region, following the introduction of MTC. (3) Patients referred using the urban trauma protocol and the rural trauma protocol. Following the introduction of regional trauma systems and major trauma centres (MTC), isolated burn patients seen at our regional burns centre did not show any significant improvement in transfer times, admission resuscitation parameters, organ dysfunction or survival when referred from a MTC compared to a non-MTC emergency department. There was also no significant difference in survival when comparing referrals from all hospitals pre and post establishment of the major trauma network. No significant outcome benefit was demonstrated for burns patients referred via MTCs compared to non-MTCs. We suggest further research is needed to ascertain whether burns patients benefit from prolonged transfer times to a MTC compared to those seen at their local hospitals prior to transfer to a regional burns unit for further specialist care. Copyright © 2016 Elsevier Ltd and ISBI. All rights reserved.

  19. Multi-variable systems in nuclear power plant

    International Nuclear Information System (INIS)

    Collins, G.B.; Howell, J.

    1982-01-01

    Nuclear power plant are complex multi-variable dynamically interactive systems which employ many facets of systems and control theory in their analysis and design. Whole plant mathematical models must be developed and validated and in addition to their obvious role in control system synthesis and design, they are also widely used for operational constraint and plant malfunction analysis. The need for and scope of an integrated power plant control system is discussed and, as a specific example, the design of an integrated feedwater regulator is reviewed. The multi-variable frequency response analysis employed in the design is described in detail. (author)

  20. Plant dermatitis-isolation and chemical investigation of the major vesicant principle of Smodingium argutum

    International Nuclear Information System (INIS)

    Gorst-Allman, C.P.; Steyn, P.S.; Wells, M.J.; Fourie, D.M.C.

    1987-01-01

    Dermatitis precipitated by contact with sensitizing or irritating plants can be a persistent and disabling condition. Although presenting a characteristic clinical appearance, its infrequent occurrence oftenresults in difficulty in diagnosis to those unfamiliar with its effects. The most common cause of plant dermatitis in the Southern Transvaal is Smodingium argutum, an indigenous member of the family Anacardiaceae. The major vesicant principle of Smodingium argutum has been isolated for the first time, and its structure determined on the basis of spectroscopic and chemical evidence. 13 C n.m.r. and 1 H n.m.r. data for compounds are given

  1. Plant dermatitis-isolation and chemical investigation of the major vesicant principle of Smodingium argutum

    Energy Technology Data Exchange (ETDEWEB)

    Gorst-Allman, C P; Steyn, P S; Heyl, T; Wells, M J; Fourie, D M.C.

    1987-03-01

    Dermatitis precipitated by contact with sensitizing or irritating plants can be a persistent and disabling condition. Although presenting a characteristic clinical appearance, its infrequent occurrence oftenresults in difficulty in diagnosis to those unfamiliar with its effects. The most common cause of plant dermatitis in the Southern Transvaal is Smodingium argutum, an indigenous member of the family Anacardiaceae. The major vesicant principle of Smodingium argutum has been isolated for the first time, and its structure determined on the basis of spectroscopic and chemical evidence. /sup 13/C n.m.r. and /sup 1/H n.m.r. data for compounds are given.

  2. Plant control system upgrades in the context of industry trends towards plant life-extension

    International Nuclear Information System (INIS)

    De Grosbois, J.; Basso, R.; Hepburn, A.; Kumar, V.

    2002-01-01

    Domestic CANDU nuclear plants were brought online between 1972 and 1986. Over the next decade, most of these stations will be nearing the end of their designed operating life. Effort has traditionally been placed on ensuring that the existing installed plant control system equipment could operate reliably until the end of this design life. Until recently, little attention has been given to plant control system upgrades or replacements to meet the expected requirement for 30+ years of additional plant operation following potential plant refurbishments. Industry developments are changing this thinking. The combination of expected increases in electricity demand (and prices), and the many recent successful turnaround stories of U.S. nuclear power plants has resulted in new interest in plant life improvement and plant life extension programs. Plant control system upgrade decisions are now being driven by the need to replace or upgrade these systems to support plant life extension. This article is the first of several that investigate aspects of plant control system upgrades or replacement, specifically in the context of the CANDU station digital control computers (DCCs). It sets the context for the discussion in the subsequent articles by providing a brief review of industry trends favouring plant refurbishment, by outlining the basic issues of aging and obsolescence of control system equipment, by establishing the need for upgrades and replacements, and by introducing some of the basic challenges to be addressed by the industry as it moves forward. (author)

  3. Plant-wide integrated equipment monitoring and analysis system

    International Nuclear Information System (INIS)

    Morimoto, C.N.; Hunter, T.A.; Chiang, S.C.

    2004-01-01

    A nuclear power plant equipment monitoring system monitors plant equipment and reports deteriorating equipment conditions. The more advanced equipment monitoring systems can also provide information for understanding the symptoms and diagnosing the root cause of a problem. Maximizing the equipment availability and minimizing or eliminating consequential damages are the ultimate goals of equipment monitoring systems. GE Integrated Equipment Monitoring System (GEIEMS) is designed as an integrated intelligent monitoring and analysis system for plant-wide application for BWR plants. This approach reduces system maintenance efforts and equipment monitoring costs and provides information for integrated planning. This paper describes GEIEMS and how the current system is being upgraded to meet General Electric's vision for plant-wide decision support. (author)

  4. Building and application of the plant condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.

    2013-01-01

    To achieve the stable operation of nuclear power plants, we developed the plant condition monitoring system based on the heat and mass balance calculation. This system has adopted the heat balance model based on the actual plant data to find the symptoms of the disorder of the equipment by heat balance changes in the turbine system. (author)

  5. Nuclear plant data systems - some emerging directions

    International Nuclear Information System (INIS)

    Johnson, R.D.; Humphress, G.B.; McCullough, L.D.; Tashjian, B.M.

    1983-01-01

    Significant changes have occurred in recent years in the nuclear power industry to accentuate the need for data systems to support information flow and decision making. Economic conditions resulting in rapid inflation and larger investments in new and existing plants and the need to plan further ahead are primary factors. Government policies concerning environmental control, as well as minimizing risk to the public through increased nuclear safety regulations on operating plants are additional factors. The impact of computer technology on plant data systems, evolution of corporate and plant infrastructures, future plant data, system designs and benefits, and decision making capabilities and data usage support are discussed. (U.K.)

  6. A dependability modeling of software under hardware faults digitized system in nuclear power plants

    International Nuclear Information System (INIS)

    Choi, Jong Gyun

    1996-02-01

    An analytic approach to the dependability evaluation of software in the operational phase is suggested in this work with special attention to the physical fault effects on the software dependability : The physical faults considered are memory faults and the dependability measure in question is the reliability. The model is based on the simple reliability theory and the graph theory with the path decomposition micro model. The model represents an application software with a graph consisting of nodes and arcs that probabilistic ally determine the flow from node to node. Through proper transformation of nodes and arcs, the graph can be reduced to a simple two-node graph and the software failure probability is derived from this graph. This model can be extended to the software system which consists of several complete modules without modification. The derived model is validated by the computer simulation, where the software is transformed to a probabilistic control flow graph. Simulation also shows a different viewpoint of software failure behavior. Using this model, we predict the reliability of an application software and a software system in a digitized system(ILS system) in the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. The derived model is validated by the computer simulation, where the software is transformed to a probabilistic control flow graph. Simulation also shows a different viewpoint of software failure behavior. Using this model, we predict the reliability of an application software and a software system in a digitized system (ILS system) is the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. This modeling method is particularly attractive for medium size programs such as software used in digitized systems of

  7. The general dynamic model of island biogeography revisited on the level of major plant families

    DEFF Research Database (Denmark)

    Lenzner, Bernd; Beierkuhnlein, Carl; Patrick, Weigelt

    2017-01-01

    Aim: The general dynamic model (GDM) proposed by Whittaker et al. (2008) is a widely accepted theoretical framework in island biogeography. In this study, we explore whether GDM predictions hold when overall plant diversity is deconstructed into major plant families. Location: 101 islands from 14...... oceanic archipelagos worldwide. Methods: Occurrence data for all species of nine large, cosmopolitan flowering plant families were used to test predictions derived from the GDM. We analyzed the effects of island area and age on species richness as well as number and percentage of single-island endemic...... species per family using mixed-effect models. Results: Total species and endemic richness as well as the percentage of endemic species showed a hump-shaped relationship with island age. The overall pattern was mainly driven by few species-rich plant families. Varying patterns were found for individual...

  8. Managing modernization of nuclear power plant instrumentation and control systems

    International Nuclear Information System (INIS)

    2004-02-01

    There are many reasons why I and C systems need to be modernized in nuclear power plants, including obsolescence, results of aging technology, failure rates, and the need for additional functionality and improved performance. For many plants, Instrumentation and Control (I and C) modernization will be one of the largest and most important activities over the next decade or longer. Modernization of I and C systems will represent a major capital investment for the plants in the future. Therefore, good and informed management to determine what needs to be modernized, how it should be modernized, and then to do the actual modernization is essential in order to minimize the costs and maximize the benefits. While many reports have discussed I and C modernization topics, one topic that needs more work is how to management I and C modernization projects efficiently. In order to have an efficient modernization project, it is essential that the plant does strategic planning to determine what needs to be done with I and C systems in the context of the overall plant goals, objectives, and commitments. This includes determining what features the the overall I and C, and control room, of the plant should look like at the end of the time period considered by the strategic planning effort, what systems need to be modernized, what systems can be maintained, the priority order of the systems to be modernized, how the systems should be modernized, and so on. To ensure that the individual I and C and control room modernization projects are done consistently with the strategic plan and the overall plant goals, objectives, and commitments, it is important that management establishes a set of plant specific guidelines and generic requirements and processes that the project will need to follow and that can be used as part of the requirements specifications for the new systems. High level management leadership and support is needed for I and C modernization in order to maintain the high

  9. Managing modernization of nuclear power plant instrumentation and control systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-02-01

    There are many reasons why I and C systems need to be modernized in nuclear power plants, including obsolescence, results of aging technology, failure rates, and the need for additional functionality and improved performance. For many plants, Instrumentation and Control (I and C) modernization will be one of the largest and most important activities over the next decade or longer. Modernization of I and C systems will represent a major capital investment for the plants in the future. Therefore, good and informed management to determine what needs to be modernized, how it should be modernized, and then to do the actual modernization is essential in order to minimize the costs and maximize the benefits. While many reports have discussed I and C modernization topics, one topic that needs more work is how to management I and C modernization projects efficiently. In order to have an efficient modernization project, it is essential that the plant does strategic planning to determine what needs to be done with I and C systems in the context of the overall plant goals, objectives, and commitments. This includes determining what features the the overall I and C, and control room, of the plant should look like at the end of the time period considered by the strategic planning effort, what systems need to be modernized, what systems can be maintained, the priority order of the systems to be modernized, how the systems should be modernized, and so on. To ensure that the individual I and C and control room modernization projects are done consistently with the strategic plan and the overall plant goals, objectives, and commitments, it is important that management establishes a set of plant specific guidelines and generic requirements and processes that the project will need to follow and that can be used as part of the requirements specifications for the new systems. High level management leadership and support is needed for I and C modernization in order to maintain the high

  10. A plant virus movement protein forms ringlike complexes with the major nucleolar protein, fibrillarin, in vitro.

    Science.gov (United States)

    Canetta, Elisabetta; Kim, Sang Hyon; Kalinina, Natalia O; Shaw, Jane; Adya, Ashok K; Gillespie, Trudi; Brown, John W S; Taliansky, Michael

    2008-02-29

    Fibrillarin, one of the major proteins of the nucleolus, has methyltransferase activity directing 2'-O-ribose methylation of rRNA and snRNAs and is required for rRNA processing. The ability of the plant umbravirus, groundnut rosette virus, to move long distances through the phloem, the specialized plant vascular system, has been shown to strictly depend on the interaction of one of its proteins, the ORF3 protein (protein encoded by open reading frame 3), with fibrillarin. This interaction is essential for several stages in the groundnut rosette virus life cycle such as nucleolar import of the ORF3 protein via Cajal bodies, relocalization of some fibrillarin from the nucleolus to cytoplasm, and assembly of cytoplasmic umbraviral ribonucleoprotein particles that are themselves required for the long-distance spread of the virus and systemic infection. Here, using atomic force microscopy, we determine the architecture of these complexes as single-layered ringlike structures with a diameter of 18-22 nm and a height of 2.0+/-0.4 nm, which consist of several (n=6-8) distinct protein granules. We also estimate the molar ratio of fibrillarin to ORF3 protein in the complexes as approximately 1:1. Based on these data, we propose a model of the structural organization of fibrillarin-ORF3 protein complexes and discuss potential mechanistic and functional implications that may also apply to other viruses.

  11. Development and application of the plant condition monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.

    2014-01-01

    To achieve the stable operation of nuclear power plants, we developed the plant condition monitoring system based on the heat and mass balance calculation. In this system, it is a significant feature to adopt the sophisticated heat balance model based on the actual plant data to find the symptoms of anomalies in the turbine system from heat balance changes. (author)

  12. High-temperature gas-cooled reactor steam-cycle/cogeneration lead plant. Plant Protection and Instrumentation System design description

    International Nuclear Information System (INIS)

    1983-01-01

    The Plant Protection and Instrumentation System provides plant safety system sense and command features, actuation of plant safety system execute features, preventive features which maintain safety system integrity, and safety-related instrumentation which monitors the plant and its safety systems. The primary function of the Plant Protection and Instrumentation system is to sense plant process variables to detect abnormal plant conditions and to provide input to actuation devices directly controlling equipment required to mitigate the consequences of design basis events to protect the public health and safety. The secondary functions of the Plant Protection and Instrumentation System are to provide plant preventive features, sybsystems that monitor plant safety systems status, subsystems that monitor the plant under normal operating and accident conditions, safety-related controls which allow control of reactor shutdown and cooling from a remote shutdown area

  13. Organelle-localized potassium transport systems in plants.

    Science.gov (United States)

    Hamamoto, Shin; Uozumi, Nobuyuki

    2014-05-15

    Some intracellular organelles found in eukaryotes such as plants have arisen through the endocytotic engulfment of prokaryotic cells. This accounts for the presence of plant membrane intrinsic proteins that have homologs in prokaryotic cells. Other organelles, such as those of the endomembrane system, are thought to have evolved through infolding of the plasma membrane. Acquisition of intracellular components (organelles) in the cells supplied additional functions for survival in various natural environments. The organelles are surrounded by biological membranes, which contain membrane-embedded K(+) transport systems allowing K(+) to move across the membrane. K(+) transport systems in plant organelles act coordinately with the plasma membrane intrinsic K(+) transport systems to maintain cytosolic K(+) concentrations. Since it is sometimes difficult to perform direct studies of organellar membrane proteins in plant cells, heterologous expression in yeast and Escherichia coli has been used to elucidate the function of plant vacuole K(+) channels and other membrane transporters. The vacuole is the largest organelle in plant cells; it has an important task in the K(+) homeostasis of the cytoplasm. The initial electrophysiological measurements of K(+) transport have categorized three classes of plant vacuolar cation channels, and since then molecular cloning approaches have led to the isolation of genes for a number of K(+) transport systems. Plants contain chloroplasts, derived from photoautotrophic cyanobacteria. A novel K(+) transport system has been isolated from cyanobacteria, which may add to our understanding of K(+) flux across the thylakoid membrane and the inner membrane of the chloroplast. This chapter will provide an overview of recent findings regarding plant organellar K(+) transport proteins. Copyright © 2014 Elsevier GmbH. All rights reserved.

  14. 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)

  15. Weed risk assessment for aquatic plants: modification of a New Zealand system for the United States.

    Directory of Open Access Journals (Sweden)

    Doria R Gordon

    Full Text Available We tested the accuracy of an invasive aquatic plant risk assessment system in the United States that we modified from a system originally developed by New Zealand's Biosecurity Program. The US system is comprised of 38 questions that address biological, historical, and environmental tolerance traits. Values associated with each response are summed to produce a total score for each species that indicates its risk of invasion. To calibrate and test this risk assessment, we identified 39 aquatic plant species that are major invaders in the continental US, 31 species that have naturalized but have no documented impacts (minor invaders, and 60 that have been introduced but have not established. These species represent 55 families and span all aquatic plant growth forms. We found sufficient information to assess all but three of these species. When the results are compared to the known invasiveness of the species, major invaders are distinguished from minor and non-invaders with 91% accuracy. Using this approach, the US aquatic weed risk assessment correctly identifies major invaders 85%, and non-invaders 98%, of the time. Model validation using an additional 10 non-invaders and 10 invaders resulted in 100% accuracy for the former, and 80% accuracy for the latter group. Accuracy was further improved to an average of 91% for all groups when the 17% of species with scores of 31-39 required further evaluation prior to risk classification. The high accuracy with which we can distinguish non-invaders from harmful invaders suggests that this tool provides a feasible, pro-active system for pre-import screening of aquatic plants in the US, and may have additional utility for prioritizing management efforts of established species.

  16. Nuclear plants gain integrated information systems

    International Nuclear Information System (INIS)

    Villavicencio-Ramirez, A.; Rodriquez-Alvarez, J.M.

    1994-01-01

    With the objective of simplifying the complex mesh of computing devices employed within nuclear power plants, modern technology and integration techniques are being used to form centralized (but backed up) databases and distributed processing and display networks. Benefits are immediate as a result of the integration and the use of standards. The use of a unique data acquisition and database subsystem optimizes the high costs of engineering, as this task is done only once for the life span of the system. This also contributes towards a uniform user interface and allows for graceful expansion and maintenance. This article features an integrated information system, Sistema Integral de Informacion de Proceso (SIIP). The development of this system enabled the Laguna Verde Nuclear Power plant to fully use the already existing universe of signals and its related engineering during all plant conditions, namely, start up, normal operation, transient analysis, and emergency operation. Integrated systems offer many advantages over segregated systems, and this experience should benefit similar development efforts in other electric power utilities, not only for nuclear but also for other types of generating plants

  17. Expert system for nuclear power plant feedwater system diagnosis

    International Nuclear Information System (INIS)

    Meguro, R.; Kinoshita, Y.; Sato, T.; Yokota, Y.; Yokota, M.

    1987-01-01

    The Expert System for Nuclear Power Plant Feedwater System Diagnosis has been developed to assist maintenance engineers in nuclear power plants. This system adopts the latest process computer TOSBAC G8050 and the expert system developing tool TDES2, and has a large scale knowledge base which consists of the expert knowledge and experience of engineers in many fields. The man-machine system, which has been developed exclusively for diagnosis, improves the man-machine interface and realizes the graphic displays of diagnostic process and path, stores diagnostic results and searches past reference

  18. Microbiota of radish plants, cultivated in closed and open ecological systems

    Science.gov (United States)

    Tirranen, L. S.

    It is common knowledge that microorganisms respond to environmental changes faster than other representatives of the living world. The major aim of this work was to examine and analyze the characteristics of the microbiota of radish culture, cultivated in the closed ecological system of human life-support Bios-3 and in an open system in different experiments. Microbial community of near-root, root zone and phyllosphere of radish were studied at the phases of seedlings, root formation, technical ripeness—by washing-off method—like microbiota of the substrate (expanded clay aggregate) and of the seeds of radish culture. Inoculation on appropriate media was made to count total quantity of anaerobic and aerobic bacteria, bacteria of coliform group, spore-forming, Proteus group, fluorescent, phytopathogenic bacteria, growing on Fermi medium, yeasts, microscopic fungi, Actinomyces. It was revealed that formation of the microbiota of radish plants depends on the age, plant cultivation technology and the specific conditions of the closed system. Composition of microbial conveyor-cultivated in phytotrons varied in quality and in quantity with plant growth phases—in the same manner as cultivation of even-aged soil and hydroponics monocultures which was determined by different qualitative and quantitative composition of root emissions in the course of plant vegetation. The higher plant component formed its own microbial complex different from that formed prior to closure. The microbial complex of vegetable polyculture is more diverse and stable than the monoculture of radish. We registered the changes in the species composition and microorganism quantity during plant cultivation in the closed system on a long-used solution. It was demonstrated that during the short-term (7 days) use of the nutrient solution in the experiments without system closing, the species composition of the microbiota of radish plants was more diverse in a multiple-aged vegetable polyculture (61

  19. Intelligent operation system for nuclear power plants

    International Nuclear Information System (INIS)

    Morioka, Toshihiko; Fukumoto, Akira; Suto, Osamu; Naito, Norio.

    1987-01-01

    Nuclear power plants consist of many systems and are operated by skillful operators with plenty of knowledge and experience of nuclear plants. Recently, plant automation or computerized operator support systems have come to be utilized, but the synthetic judgment of plant operation and management remains as human roles. Toshiba is of the opinion that the activities (planning, operation and maintenance) should be integrated, and man-machine interface should be human-friendly. We have begun to develop the intelligent operation system aiming at reducing the operator's role within the fundamental judgment through the use of artificial intelligence. (author)

  20. Design of comprehensive plant information system considering maintenance indicators in nuclear power plant

    International Nuclear Information System (INIS)

    Takata, Takashi; Yamaguchi, Akira; Yamamoto, Akio

    2013-01-01

    A safety of a nuclear power plant must be ensured and maintained through its entire plant life. For this plant life cycle safety (PLCS), a comprehensive plant information system, in which an each maintenance record of the plant is taken into consideration, is of importance. In this paper, a development of a plant chart, which is a part of the information system, has been developed based on a defense-in-depth concept that is one of the most important concept to ensure the plant safety. In the chart, an updated probability of loss of a component or function is used as a maintenance indicator and a probabilistic risk assessment (PRA) method is applied to quantify the plant status in the chart. (author)

  1. Plant litter dynamics in the forest-stream interface: precipitation is a major control across tropical biomes

    OpenAIRE

    Tonin, Alan M.; Gon?alves, Jos? F.; Bambi, Paulino; Couceiro, Sheyla R. M.; Feitoza, Lorrane A. M.; Fontana, Lucas E.; Hamada, Neusa; Hepp, Luiz U.; Lezan-Kowalczuk, V?nia G.; Leite, Gustavo F. M.; Lemes-Silva, Aurea L.; Lisboa, Leonardo K.; Loureiro, Rafael C.; Martins, Renato T.; Medeiros, Adriana O.

    2017-01-01

    Riparian plant litter is a major energy source for forested streams across the world and its decomposition has repercussions on nutrient cycling, food webs and ecosystem functioning. However, we know little about plant litter dynamics in tropical streams, even?though the tropics occupy 40% of the Earth?s land surface. Here we investigated spatial and temporal (along a year cycle) patterns of litter inputs and storage in multiple streams of three tropical biomes in Brazil (Atlantic forest, Ama...

  2. Diablo Canyon plant information management system and integrated communication system

    International Nuclear Information System (INIS)

    Stanley, J.W.; Groff, C.

    1990-01-01

    The implementation of a comprehensive maintenance system called the plant information management system (PIMS) at the Diablo Canyon plant, together with its associated integrated communication system (ICS), is widely regarded as the most comprehensive undertaking of its kind in the nuclear industry. This paper provides an overview of the program at Diablo Canyon, an evaluation of system benefits, and highlights the future course of PIMS

  3. Diablo Canyon plant information management system and integrated communication system

    Energy Technology Data Exchange (ETDEWEB)

    Stanley, J.W.; Groff, C.

    1990-06-01

    The implementation of a comprehensive maintenance system called the plant information management system (PIMS) at the Diablo Canyon plant, together with its associated integrated communication system (ICS), is widely regarded as the most comprehensive undertaking of its kind in the nuclear industry. This paper provides an overview of the program at Diablo Canyon, an evaluation of system benefits, and highlights the future course of PIMS.

  4. Control system for technological processes in tritium processing plants with process analysis

    International Nuclear Information System (INIS)

    Retevoi, Carmen Maria; Stefan, Iuliana; Balteanu, Ovidiu; Stefan, Liviu; Bucur, Ciprian

    2005-01-01

    Integration of a large variety of installations and equipment into a unitary system for controlling the technological process in tritium processing nuclear facilities appears to be a rather complex approach particularly when experimental or new technologies are developed. Ensuring a high degree of versatility allowing easy modifications in configurations and process parameters is a major requirement imposed on experimental installations. The large amount of data which must be processed, stored and easily accessed for subsequent analyses imposes development of a large information network based on a highly integrated system containing the acquisition, control and technological process analysis data as well as data base system. On such a basis integrated systems of computation and control able to conduct the technological process could be developed as well protection systems for cases of failures or break down. The integrated system responds to the control and security requirements in case of emergency and of the technological processes specific to the industry that processes radioactive or toxic substances with severe consequences in case of technological failure as in the case of tritium processing nuclear plant. In order to lower the risk technological failure of these processes an integrated software, data base and process analysis system are developed, which, based on identification algorithm of the important parameters for protection and security systems, will display the process evolution trend. The system was checked on a existing plant that includes a removal tritium unit, finally used in a nuclear power plant, by simulating the failure events as well as the process. The system will also include a complete data base monitoring all the parameters and a process analysis software for the main modules of the tritium processing plant, namely, isotope separation, catalytic purification and cryogenic distillation

  5. Prototype of an expert system based nuclear power plant information systems

    International Nuclear Information System (INIS)

    Vegh, J.; Bodnar, M.; Buerger, L.; Tanyi, M.; Sefesik, F.

    1994-01-01

    The components and functioning of the GPCS information system applicable for intelligent process monitoring and alarm generation in a WWER-440 type nuclear power plant are described. The prototype system has been developed by using the G2 expert system, plant measurements were simulated by a WWER-440 compact simulator and by archive replay sessions performed by the VERONA-u core monitoring system. The GPCS contains an object oriented description of the basic subsystems of the plant and concentrates on the fast evaluation/displaying of measurements and alarms. The high-level information reflecting actual plant safety status is synthesized from primary measured data, by forming global alarms and by evaluating logical diagrams. (author). 10 refs, 4 figs

  6. Plant dynamics studies towards design of plant protection system for PFBR

    Energy Technology Data Exchange (ETDEWEB)

    Natesan, K., E-mail: natesan@igcar.gov.in [Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India); Kasinathan, N.; Velusamy, K.; Selvaraj, P.; Chellapandi, P. [Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India)

    2012-09-15

    Highlights: Black-Right-Pointing-Pointer Analysis of various design basis events in a fast breeder reactor towards design of plant protection system. Black-Right-Pointing-Pointer Plant dynamic modeling of a sodium cooled fast breeder reactor. Black-Right-Pointing-Pointer Selection of optimum set of plant parameters for considering best plant availability. - Abstract: Prototype fast breeder reactor (PFBR) is a 500 MWe (1250 MWt) liquid sodium cooled pool type reactor currently under construction in India. For a safe and efficient operation of the plant, it is necessary that the reactor is protected from all the transients that may occur in the plant. In order to accomplish this, adequate number of SCRAM parameters is required in the plant protection system with reliable instrumentation. For identifying the SCRAM parameters, the neutronic and thermal hydraulic responses of the plant for various possible events need to be established. Towards this, a one dimensional plant dynamics code DYANA-P has been developed with thermal hydraulic models for reactor core, hot and cold pools, intermediate heat exchangers, pipelines, steam generator, primary sodium circuits and secondary sodium circuits. The code also incorporates neutron kinetics and reactivity feedback models. By a comprehensive plant dynamics study an optimum list of SCRAM parameters and the maximum permissible response time for various instruments used for deriving them have been arrived at.

  7. Developing an economic performance system to enhance nuclear power plant competitiveness

    International Nuclear Information System (INIS)

    2002-01-01

    In 1999 about 16% of the world's electricity was produced by nuclear power, and the total worldwide operating experience of nuclear power plants was over 9200 reactor-years. Some 16 countries are dependent on nuclear power for more than 25% of their electricity generation. In some countries deregulation of the electricity market has either happened or is currently ongoing, while in others it is planned for the future. Nevertheless, many countries are already facing open electricity markets and operating costs are under unprecedented pressure, with competition expected to come soon to the nuclear industry worldwide. To a certain extent, however, the industry has already prepared or is currently preparing to face competition. This report is primarily intended for nuclear power plant and utility managers. It discusses the means and principal issues for the development of the nuclear economic performance international system (NEPIS), which should enhance nuclear power plant competitiveness. The following issues are addressed: The major transformations occurring in the electricity generation industry that require reductions in operations and maintenance costs at nuclear utilities; The methods that nuclear plant management use to identify and justify the economic optimum level of a plant and its use of resources; The value of collecting cost and performance data and the analysis techniques that use that data; The cost data required to be collected; The difficulty of collecting data with existing cost accounting systems; The new cost accounting and collection systems that will be required, The cost effectiveness of the overall process. This report also presents the preliminary results of a pilot project that was established to collect cost data on a few nuclear power plants and was used to verify the adequacy of the definitions and terminology set for NEPIS

  8. An automated, high-throughput plant phenotyping system using machine learning-based plant segmentation and image analysis.

    Science.gov (United States)

    Lee, Unseok; Chang, Sungyul; Putra, Gian Anantrio; Kim, Hyoungseok; Kim, Dong Hwan

    2018-01-01

    A high-throughput plant phenotyping system automatically observes and grows many plant samples. Many plant sample images are acquired by the system to determine the characteristics of the plants (populations). Stable image acquisition and processing is very important to accurately determine the characteristics. However, hardware for acquiring plant images rapidly and stably, while minimizing plant stress, is lacking. Moreover, most software cannot adequately handle large-scale plant imaging. To address these problems, we developed a new, automated, high-throughput plant phenotyping system using simple and robust hardware, and an automated plant-imaging-analysis pipeline consisting of machine-learning-based plant segmentation. Our hardware acquires images reliably and quickly and minimizes plant stress. Furthermore, the images are processed automatically. In particular, large-scale plant-image datasets can be segmented precisely using a classifier developed using a superpixel-based machine-learning algorithm (Random Forest), and variations in plant parameters (such as area) over time can be assessed using the segmented images. We performed comparative evaluations to identify an appropriate learning algorithm for our proposed system, and tested three robust learning algorithms. We developed not only an automatic analysis pipeline but also a convenient means of plant-growth analysis that provides a learning data interface and visualization of plant growth trends. Thus, our system allows end-users such as plant biologists to analyze plant growth via large-scale plant image data easily.

  9. Development of 3D VR plant digital information system

    International Nuclear Information System (INIS)

    Suh, Kune Y.; Ryu, Joong W.; Kang, Myung G.; Kim, H. Y.; Cho, J. G.; Kim, D. H.; Park, J. W.

    2006-07-01

    Currently, there are many ongoing efforts to shorten the plant refueling and maintenance outage durations, and it is expected to become more active as the time goes on. Improved training and education system are required for the personnel to perform efficient inspection on time. This work is focused on establishing virtual Nuclear Power Plant system which will help train the personnel to understand the system characteristics of the plant by creating navigation enabled 3D plant mockups. Furthermore, this project is aimed at constructing information management system over the whole plant area, by integrating safety related data and combining it with web based GUI technology, to make search and management activities easy. This project spans three years. The forst year was spent in 3D mockup modeling of most part of the plant, and prototyping the web based VR plant digital information system. Plant environment, buildings, reactor structure, steam generator, pressurizer, fuel assemblies, pressurizer safety valve, main steamline safety valve, reactor coolant system, main steamline system, auxiliary and main coolant supply system were modeled into 3D mockups. Control functions such as magnification, rotation, movement, transparency, location detection, cross-cut view, full screen toggle and screen capture were implemented to facilitate manipulation of and navigation through the VR mockups. It is expected that the VR plant will serve as an effective support system for power plant regulation and inspection

  10. Safety Evaluation of Full Digital Plant Protection System of Shin-Kori 3 and 4 in Korea

    International Nuclear Information System (INIS)

    Koh, J. S.; Kim, D. I.; Jeong, C. H.; Park, H. S.; Ji, S. H.; Kang, Y. D.; Park, G. Y.

    2009-01-01

    Keeping pace with the emerging trend of digital computer technologies, KHNP has utilized full digital plant protection system into the design of I and C systems at SKN 3 and 4. This paper presents safety review activities and results related to digital plant protection systems during the licensing of construction permit for the Shin-Kori 3 and 4(SKN 3 and 4) in Korea. The major licensing issues regarding the digital systems were software quality and cyber security during planning stage, system integrity with fail-safe design, EMI equipment qualification of digital systems, FPGA qualification and communication independence between safety and non-safety System. This paper addresses our approach to evaluate full digital protection systems with revised safety review guidelines and the resulting discussion to resolve the licensing issues

  11. 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

  12. 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.)

  13. 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.

  14. Chemistry management system for nuclear power plants

    International Nuclear Information System (INIS)

    Nagasawa, Katsumi; Maeda, Katsuji

    1998-01-01

    Recently, the chemistry management in the nuclear power plants has been changing from the problem solution to the predictive diagnosis and maintenance. It is important to maintain the integrity of plant operation by an adequate chemistry control. For these reasons, many plant operation data and chemistry analysis data should be collected and treated effectively to evaluate chemistry condition of the nuclear power plants. When some indications of chemistry anomalies occur, quick and effective root cause evaluation and countermeasures should be required. The chemistry management system has been developed as to provide sophisticate chemistry management in the nuclear power plants. This paper introduces the concept and functions of the chemistry management system for the nuclear power plants. (author)

  15. Ventilation-air conditioner system in nuclear power plant

    International Nuclear Information System (INIS)

    Kubota, Ryuji; Sugisaki, Toshihiko.

    1989-01-01

    This invention concerns a ventilation-air conditioner system which enables, upon occurrence of accidents in a nuclear power plant, continuous operation for other adjacent nuclear power plants with no effect of accidents. Air supply system and exhaust system are operated during usual operaiton. If loss of coolants accidents should occur in an adjacent nuclear power plants, operation is switched from ventilation operaiton to the operation of re-cycling system based on an AND logic of three signals, that is, a pressure HIGH signal for the reactor container, a water level LOW signal for the reactor and a radioactivity signal of the ventilation-air conditioner sytem on the side of air supply in the nuclear power plant. Thus, nuclear reactor buildings of the nuclear power plant are from the external atmosphere. Therefore, the radioactivity HIGH signal for switching to the emergency air conditioner system of the nuclear power plant is not actuated due to the loss of coolant accidents in the adjacent nuclear power plant. In addition, since the atmospheric temperature in the nuclear reactor building can be maintained by a cooling device disposed to the recycling system, reactor shutdown can be prevented. (I.S.)

  16. Advanced liquid metal reactor plant control system

    International Nuclear Information System (INIS)

    Dayal, Y.; Wagner, W.; Zizzo, D.; Carroll, D.

    1993-01-01

    The modular Advanced Liquid Metal Reactor (ALMR) power plant is controlled by an advanced state-of-the-art control system designed to facilitate plant operation, optimize availability, and protect plant investment. The control system features a high degree of automatic control and extensive amount of on-line diagnostics and operator aids. It can be built with today's control technology, and has the flexibility of adding new features that benefit plant operation and reduce O ampersand M costs as the technology matures

  17. A plant control system development approach for IRIS

    International Nuclear Information System (INIS)

    Wood, R.T.; Brittain, C.R.; March-Leuba, J.A.; Conway, L.E.; Oriani, L.

    2003-01-01

    The plant control system concept for the International Reactor Innovative and Secure (IRIS) will make use of integrated control, diagnostic, and decision modules to provide a highly automated intelligent control capability. The plant control system development approach established for IRIS involves determination and verification of control strategies based on whole-plant simulation; identification of measurement, control, and diagnostic needs; development of an architectural framework in which to integrate an intelligent plant control system; and design of the necessary control and diagnostic elements for implementation and validation. This paper describes key elements of the plant control system development approach established for IRIS and presents some of the strategies and methods investigated to support the desired control capabilities. (author)

  18. Towards a systems understanding of plant-microbe interactions

    Directory of Open Access Journals (Sweden)

    Akira eMine

    2014-08-01

    Full Text Available Plants are closely associated with microorganisms including pathogens and mutualists that influence plant fitness. Molecular genetic approaches have uncovered a number of signaling components from both plants and microbes and their mode of actions. However, signaling pathways are highly interconnected and influenced by diverse sets of environmental factors. Therefore, it is important to have systems views in order to understand the true nature of plant-microbe interactions. Indeed, systems biology approaches have revealed previously overlooked or misinterpreted properties of the plant immune signaling network. Experimental reconstruction of biological networks using exhaustive combinatorial mutants is particularly powerful to elucidate network structure and properties and relationships among network components. Recent advances in metagenomics of microbial communities associated with plants further point to the importance of systems approaches and open a research area of microbial community reconstruction. In this review, we highlight the importance of a systems understanding of plant-microbe interactions, with a special emphasis on reconstruction strategies.

  19. Improvement on reliability of control system in power plant

    International Nuclear Information System (INIS)

    Taguchi, S.; Mizumoto, T.; Hirose, Y.; Kashiwai, J.; Takami, I.; Shono, M.; Roji, Y.; Kizaki, S.

    1985-01-01

    Studies made of Japanese PWR operating experiences have revealed that failures in the control system are the primary causes of unscheduled shutdowns. An attempt has, therefore, been made to improve the reliability of the control system in order to raise the plant reliability. The following are the procedures applied to solve the issue; study of operating experiences, fault tree analysis and failure mode and effects analysis. Improvement measures are developed for the control system whose failure threatens to cause the plant trip during the plant life. These systems are the main feedwater control system, rod control system, pressurizer control system and main steam control system in the primary control system. As a result, the plant unavailability is expected to be reduced significantly by applying the improvements. The improvements are applied to the plants under construction and the operating plants in co-operation with utilities and vendors. (author)

  20. Plant-uptake of uranium: Hydroponic and soil system studies

    Science.gov (United States)

    Ramaswami, A.; Carr, P.; Burkhardt, M.

    2001-01-01

    Limited information is available on screening and selection of terrestrial plants for uptake and translocation of uranium from soil. This article evaluates the removal of uranium from water and soil by selected plants, comparing plant performance in hydroponic systems with that in two soil systems (a sandy-loam soil and an organic-rich soil). Plants selected for this study were Sunflower (Helianthus giganteus), Spring Vetch (Vicia sativa), Hairy Vetch (Vicia villosa), Juniper (Juniperus monosperma), Indian Mustard (Brassica juncea), and Bush Bean (Phaseolus nanus). Plant performance was evaluated both in terms of the percent uranium extracted from the three systems, as well as the biological absorption coefficient (BAC) that normalized uranium uptake to plant biomass. Study results indicate that uranium extraction efficiency decreased sharply across hydroponic, sandy and organic soil systems, indicating that soil organic matter sequestered uranium, rendering it largely unavailable for plant uptake. These results indicate that site-specific soils must be used to screen plants for uranium extraction capability; plant behavior in hydroponic systems does not correlate well with that in soil systems. One plant species, Juniper, exhibited consistent uranium extraction efficiencies and BACs in both sandy and organic soils, suggesting unique uranium extraction capabilities.

  1. Transparency and efficiency through plant operations management systems

    International Nuclear Information System (INIS)

    Ladage, L.

    2001-01-01

    Plant operations management systems, being IT application systems, provide integral support of the business processes making up plant operations management. The use of plant operations management systems improves mutually interdependent factors, such as high economic performance, high availability, and maximum safety. Since its commissioning in 1988, the Emsland nuclear power station (KKE) has been run with the IBFS plant operations management system. The work flow management system (WfMS), a module of IBFS, is described as an example of job order processing. IBFS-WfMS is to optimize all processes, thus cutting costs and ensuring that processes are run and documented reliably. Assessing the savings effect achieved through the use of IBFS-WfMS clearly reveals the savings in work/time achieved by the system. These savings are quoted as approx. 4 minutes and DM 10, respectively, per working step, which corresponds to several dozens of manyears or several million DM per annum in the KKE plant under consideration. This result can be extrapolated to other plants. (orig.) [de

  2. The assisting system for uranium enrichment plant operation

    International Nuclear Information System (INIS)

    Nakazawa, Hiroaki; Yamamoto, Fumio

    1990-01-01

    We have been developing an operation assisting system, partially supported by AI system, for uranium enrichment plant. The AI system is a proto-type system aiming a final one which can be applied to any future large uranium enrichment plant and also not only to specific operational area but also to complex and multi-phenomenon operational area. An existing AI system, for example facility diagnostic system that utilizes the result of CCT analysis as knowledge base, has weakness in flexibility and potentiality. To build AI system, we have developed the most suitable knowledge representations using deep knowledge for each facility or operation of uranium enrichment plant. This paper describes our AI proto-type system adopting several knowledge representations that can represent an uranium enrichment plant's operation with deep knowledge. (author)

  3. Membrane Lipid Oscillation: An Emerging System of Molecular Dynamics in the Plant Membrane.

    Science.gov (United States)

    Nakamura, Yuki

    2018-03-01

    Biological rhythm represents a major biological process of living organisms. However, rhythmic oscillation of membrane lipid content is poorly described in plants. The development of lipidomic technology has led to the illustration of precise molecular profiles of membrane lipids under various growth conditions. Compared with conventional lipid signaling, which produces unpredictable lipid changes in response to ever-changing environmental conditions, lipid oscillation generates a fairly predictable lipid profile, adding a new layer of biological function to the membrane system and possible cross-talk with the other chronobiological processes. This mini review covers recent studies elucidating membrane lipid oscillation in plants.

  4. Carrier system for a plant extract or bioactive compound from a plant

    DEFF Research Database (Denmark)

    2018-01-01

    This invention relates to a carrier system for use in producing a beverage with a metered amount of plant extract or bioactive compound.......This invention relates to a carrier system for use in producing a beverage with a metered amount of plant extract or bioactive compound....

  5. Major outage trends in light water reactors. Interim report

    International Nuclear Information System (INIS)

    Burns, E.T.

    1978-04-01

    The report is a summary of the major outages which occurred in light water reactor plants during the period January 1971 through June 1977. Only those outages greater than 100 hours duration (exclusive of refueling outages) are included in the report. The trends in outages related to various reactor systems and components are presented as a function of plant age, and alternatively, calendar year. The principal contributors to major outages are ranked by their effect on the overall outage time for PWRs and BWRs. In addition, the outage history of each operating nuclear plant greater than 150 MWe is presented, along with a brief summary of those outages greater than two months duration

  6. General digitalized system on nuclear power plants

    International Nuclear Information System (INIS)

    Akagi, Katsumi; Kadohara, Hozumi; Taniguchi, Manabu

    2000-01-01

    Hitherto, instrumentation control system in a PWR nuclear power plant has stepwisely adopted digital technology such as application of digital instrumentation control device to ordinary use (primary/secondary system control device, and so on), application of CRT display system to monitoring function, and so forth, to realize load reduction of an operator due to expansion of operation automation range, upgrading of reliability and maintenance due to self-diagnosis function, reduction of mass in cables due to multiple transfer, and upgrading of visual recognition due to information integration. In next term PWR plant instrumentation control system, under consideration of application practice of conventional digital technology, application of general digitalisation system to adopt digitalisation of overall instrumentation control system containing safety protection system, and central instrumentation system (new type of instrumentation system) and to intend to further upgrade economics, maintenance, operability/monitoring under security of reliability/safety is planned. And, together with embodiment of construction program of the next-term plant, verification at the general digitalisation proto-system aiming at establishment of basic technology on the system is carried out. Then, here was described on abstract of the general digitalisation system and characteristics of a digital type safety protection apparatus to be adopted in the next-term plant. (G.K.)

  7. Power plant cooling systems: trends and challenges

    International Nuclear Information System (INIS)

    Rittenhouse, R.C.

    1979-01-01

    A novel design for an intake and discharge system at the Belle River plant is described followed by a general discussion of water intake screens and porous dikes for screening fish and zooplankton. The intake system for the San Onofre PWR plant is described and the state regulations controlling the use of water for power plants is discussed. The use of sewage effluent as a source of cooling water is mentioned with reference to the Palo Verde plant. Progress in dry cooling and a new wet/dry tower due to be installed at the San Juan plant towards the end of this year, complete the survey

  8. Ethnomedicinal plants used for digestive system disorders by the Karen of northern Thailand.

    Science.gov (United States)

    Tangjitman, Kornkanok; Wongsawad, Chalobol; Kamwong, Kaweesin; Sukkho, Treetip; Trisonthi, Chusie

    2015-04-09

    Digestive system disorders have a substantial effect on worldwide morbidity and mortality rates, including in Thailand, where the majority of the rural areas have a lack of proper sanitation and awareness about disease prevention. This has led to the prevalence of different types of digestive diseases. Karen people in Thailand still use medicinal plants as first aid remedies in treating these diseases. Therefore, this study aimed at documenting the plants used to cure and prevent different types of digestive system disorders by Karen people of Chiang Mai Province, northern Thailand. Ethnomedicinal data were collected from six key informants and 172 non-specialist informants regarding their traditional knowledge of medicinal plants. Quantitative approaches were used to determine Use Value (UV), Informant Consensus Factor (ICF) and Fidelity Level (FL) values. The study revealed that 36 medicinal plant species belonging to 31 genera and 24 families were used to treat digestive system disorders. The most prevalent plant families were Zingiberaceae (6 species), Euphorbiaceae (4 species) and Fabaceae (4 species). Leaves were the most commonly used plant part accounting for 32.6% of the plants, followed by the bark (18.6%). About 60% of the administrations were given orally by potion (60%) and consumption as food was also indicated (14%). The highest ICF values were recorded for carminative disorders, stomachaches, geographic tongue, constipation, appetite stimulants and food poisoning (1.00 each) indicating the best agreement among the informants knowledge of medicinal plants that were used to treat aliments in these categories. The highest fidelity level values were recorded for Punica granatum (100.00), Psidium guajava (95.45), and Gymnopetalum integrifolium (90.91) showing conformity of knowledge on species with the best healing potential. Medicinal plants still play an important role among Karen culture. The present information on these medicinal plants, which have

  9. Technical evaluation of major candidate blanket systems for fusion power reactor

    International Nuclear Information System (INIS)

    Tone, Tatsuzo; Seki, Masahiro; Minato, Akio

    1987-03-01

    The key functions required for tritium breeding blankets for a fusion power reactor are: (1) self-sufficient tritium breeding, (2) in-situ tritium recovery and low tritium inventory, (3) high temperature cooling giving a high efficiency of electricity generation and (4) thermo-mechanical reliability and simplified remote maintenance to obtain high plant availability. Blanket performance is substantially governed by materials selection. Major options of structure/breeder/coolant/neutron multiplier materials considered for the present design study are PCA/Li 2 O/H 2 O/Be, Mo-alloy/Li 2 O/He/Be, Mo-alloy/LiAlO 2 /He/Be, V-alloy/Li/Li/none, and Mo-alloy/Li/He/none. In addition, remote maintenance of blankets, tritium recovery system, heat transport and energy conversion have been investigated. In this report, technological problems and critical R and D issues for power reactor blanket development are identified and a comparison of major candidate blanket concepts is discussed in terms of the present materials data base, economic performance, prospects for future improvements, and engineering feasibility and difficulties based on the results obtained from individual design studies. (author)

  10. Chlorination for biofouling control in power plant cooling water system - a review

    International Nuclear Information System (INIS)

    Satpathy, K.K.; Ruth Nithila, S.D.

    2008-01-01

    Fresh water is becoming a rare commodity day by day and thus power plant authorities are turning into sea to make use of the copious amount of seawater available at an economical rate for condenser cooling. Unfortunately, biofouling; the growth and colonization of marine organisms affect the smooth operation of power plant cooling water systems. This is more so, if the plant is located in tropical climate having clean environment, which enhances the variety and density of organisms. Thus, biofouling needs to be controlled for efficient operation of the power plant. Biocide used for biofouling control is decided based on three major criteria viz: it should be economically, operationally and environmentally acceptable to the power plant authorities. Chlorine among others stands out on the top and meets all the above requirements in spite of a few shortcomings. Therefore it is no wonder that still chlorine rules the roost and chlorination remains the most common method of biofouling control in power plant cooling water system all over the world. Although, it is easier said than done, a good amount of R and D work is essential before a precise chlorination regime is put into pragmatic use. This paper discusses in details the chemistry of chlorination such as chlorine demand, chlorine decay, break point chlorination, speciation of chlorine residual and role of temperature and ammonia on chlorination in biofouling control. Moreover, targeted and pulse chlorination are also discussed briefly. (author)

  11. Advanced chemistry management system for nuclear power plants

    International Nuclear Information System (INIS)

    Maeda, Katsuji; Kobayashi, Yasuhiro; Nagasawa, Katsumi

    2000-01-01

    Chemistry control in a boiling water reactor (BWR) plant has a close relationship with radiation field buildup, fuel reliability, integrity of plant components and materials, performance of the water treatment systems and radioactive waste generation. Chemistry management in BWR plants has become more important in order to maintain and enhance plant reliability. Adequate chemistry control and management are also essential to establish, maintain, and enhance plant availability. For these reasons, we have developed the advanced chemistry management system for nuclear power plants in order to effectively collect and evaluate a large number of plant operating and chemistry data. (author)

  12. Human factors: A major issue in plant aging

    International Nuclear Information System (INIS)

    Widrig, R.D.

    1985-01-01

    Humans play a significant role in the effects of aging on safe and reliable operation of nuclear power plants. These human issues may be more important than the issues of materials and component degradation with age. Human actions can accelerate or decelerate physical aging of a plant. And an aging plant can have a significant negative impact on staff quality and performance. The purpose of this paper is to provide some insights into the nature of these human factors issues and their relationship to plant aging. An early awareness of these issues facilitates timely action to at least mitigate these problems before they become insurmountable

  13. Economics of hybrid photovoltaic power plants

    Energy Technology Data Exchange (ETDEWEB)

    Breyer, Christian

    2012-08-16

    The global power supply stability is faced to several severe and fundamental threats, in particular steadily increasing power demand, diminishing and degrading fossil and nuclear energy resources, very harmful greenhouse gas emissions, significant energy injustice and a structurally misbalanced ecological footprint. Photovoltaic (PV) power systems are analysed in various aspects focusing on economic and technical considerations of supplemental and substitutional power supply to the constraint conventional power system. To infer the most relevant system approach for PV power plants several solar resources available for PV systems are compared. By combining the different solar resources and respective economics, two major PV systems are identified to be very competitive in almost all regions in the world. The experience curve concept is used as a key technique for the development of scenario assumptions on economic projections for the decade of the 2010s. Main drivers for cost reductions in PV systems are learning and production growth rate, thus several relevant aspects are discussed such as research and development investments, technical PV market potential, different PV technologies and the energetic sustainability of PV. Three major market segments for PV systems are identified: off-grid PV solutions, decentralised small scale on-grid PV systems (several kWp) and large scale PV power plants (tens of MWp). Mainly by application of 'grid-parity' and 'fuel-parity' concepts per country, local market and conventional power plant basis, the global economic market potential for all major PV system segments is derived. PV power plant hybridization potential of all relevant power technologies and the global power plant structure are analyzed regarding technical, economical and geographical feasibility. Key success criteria for hybrid PV power plants are discussed and comprehensively analysed for all adequate power plant technologies, i.e. oil, gas and coal fired power

  14. Economics of hybrid photovoltaic power plants

    Energy Technology Data Exchange (ETDEWEB)

    Breyer, Christian

    2012-08-16

    The global power supply stability is faced to several severe and fundamental threats, in particular steadily increasing power demand, diminishing and degrading fossil and nuclear energy resources, very harmful greenhouse gas emissions, significant energy injustice and a structurally misbalanced ecological footprint. Photovoltaic (PV) power systems are analysed in various aspects focusing on economic and technical considerations of supplemental and substitutional power supply to the constraint conventional power system. To infer the most relevant system approach for PV power plants several solar resources available for PV systems are compared. By combining the different solar resources and respective economics, two major PV systems are identified to be very competitive in almost all regions in the world. The experience curve concept is used as a key technique for the development of scenario assumptions on economic projections for the decade of the 2010s. Main drivers for cost reductions in PV systems are learning and production growth rate, thus several relevant aspects are discussed such as research and development investments, technical PV market potential, different PV technologies and the energetic sustainability of PV. Three major market segments for PV systems are identified: off-grid PV solutions, decentralised small scale on-grid PV systems (several kWp) and large scale PV power plants (tens of MWp). Mainly by application of 'grid-parity' and 'fuel-parity' concepts per country, local market and conventional power plant basis, the global economic market potential for all major PV system segments is derived. PV power plant hybridization potential of all relevant power technologies and the global power plant structure are analyzed regarding technical, economical and geographical feasibility. Key success criteria for hybrid PV power plants are discussed and comprehensively analysed for all adequate power plant technologies, i.e. oil, gas and

  15. Finnish experiences on licensing and using of programmable digital systems in nuclear power plants

    International Nuclear Information System (INIS)

    Haapanen, P.; Maskuniitty, M.; Heimburger, H.; Hall, L.E.; Manninen, T.

    1993-01-01

    Finnish utility companies, Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), and the licensing authority, the Finnish Centre for Radiation and Nuclear Safety (STUK), are preparing for a new nuclear power plant in Finland. Plant vendors are proposing programmable digital automation systems for both the safety-related and the operational I and C (instrumentation and control) systems in this new unit. Also in existing plant units the replacement of certain old analog systems with state-of-the-art digital ones will become necessary in the years to come. Licensing of programmable systems for safety critical applications requires a new approach due to the special properties and failure modes of these systems. The major difficulties seem to be in the assessment and quantification of software reliability. The Technical Research Centre of Finland has in co-operation with the authority and the utilities conducted a project (AJA) to develop domestically applicable licensing requirements, guidelines and practices. International standards, guidelines and licensing practices have been analyzed in order to specify national licensing requirements. The paper describes and discusses the findings and experiences of the AJA project so far. The experience in introducing advanced programmable digital control and computer systems in the operating nuclear power plants will be covered briefly. Although these systems are not safety-related but systems of more general interest regarding nuclear safety, some routines regarding the licensing of safety- related systems have been followed. In these backfitting and replacement projects some experience have been gained in how to license safety-related programmable systems. (Author) 31 refs., 2 figs

  16. Preinspection of nuclear power plant systems

    International Nuclear Information System (INIS)

    1975-01-01

    The general plans of the systems affecting the safety of the nuclear power plants are accepted by the Institute of Radiation Protection (IRP) on the basis of the preinspection of the systems. This is the prerequisite of the preinspection of the structures and components belonging to these systems. Exceptionally, when separately agreed, the IRP may perform the preinspection of a separate structure or component, although the preinspection documentation of the whole system, e.g. the nuclear heat generating system, has not been accepted. This guide applies to the nuclear power plant systems that have been defined to be preinspected in the classification document accepted by the IRP

  17. Function and regulation of plant major intrinsic proteins

    DEFF Research Database (Denmark)

    Popovic, Milan

    ;1 in Arabidopsis. That led to the discovery that tip4;1 is gametophytic lethal- gene essential for normal seed set. ICP-MS analyses of the elemental composition of tip4;1 heterozygous T-DNA insert mutant plants and 35S::TIP4;1 over-expression plants indicate that AtTIP4;1 has a role in arsenic distribution...... inorganic forms of arsenic in the environment, can be taken up by plants and thus enter the food chain. Once inside the root cells, As(V) is reduced to As(III) which is then extruded to the soil solution or bound to phytochelatins (PCs) and transported to the vacuole in an effort to accomplish...... detoxification. Plant Noduline 26-like Intrinsic Proteins (NIPs) can channel As(III) and consequently influence the detoxification process. The role of the Tonoplast Intrinsic Proteins (TIPs) in As(III) detoxification remains to be clarified, yet TIPs could have an impact on As(III) accumulation in plant cell...

  18. Coordinated Actions of Glyoxalase and Antioxidant Defense Systems in Conferring Abiotic Stress Tolerance in Plants

    Directory of Open Access Journals (Sweden)

    Mirza Hasanuzzaman

    2017-01-01

    Full Text Available Being sessile organisms, plants are frequently exposed to various environmental stresses that cause several physiological disorders and even death. Oxidative stress is one of the common consequences of abiotic stress in plants, which is caused by excess generation of reactive oxygen species (ROS. Sometimes ROS production exceeds the capacity of antioxidant defense systems, which leads to oxidative stress. In line with ROS, plants also produce a high amount of methylglyoxal (MG, which is an α-oxoaldehyde compound, highly reactive, cytotoxic, and produced via different enzymatic and non-enzymatic reactions. This MG can impair cells or cell components and can even destroy DNA or cause mutation. Under stress conditions, MG concentration in plants can be increased 2- to 6-fold compared with normal conditions depending on the plant species. However, plants have a system developed to detoxify this MG consisting of two major enzymes: glyoxalase I (Gly I and glyoxalase II (Gly II, and hence known as the glyoxalase system. Recently, a novel glyoxalase enzyme, named glyoxalase III (Gly III, has been detected in plants, providing a shorter pathway for MG detoxification, which is also a signpost in the research of abiotic stress tolerance. Glutathione (GSH acts as a co-factor for this system. Therefore, this system not only detoxifies MG but also plays a role in maintaining GSH homeostasis and subsequent ROS detoxification. Upregulation of both Gly I and Gly II as well as their overexpression in plant species showed enhanced tolerance to various abiotic stresses including salinity, drought, metal toxicity, and extreme temperature. In the past few decades, a considerable amount of reports have indicated that both antioxidant defense and glyoxalase systems have strong interactions in conferring abiotic stress tolerance in plants through the detoxification of ROS and MG. In this review, we will focus on the mechanisms of these interactions and the coordinated

  19. Coordinated Actions of Glyoxalase and Antioxidant Defense Systems in Conferring Abiotic Stress Tolerance in Plants

    Science.gov (United States)

    Hasanuzzaman, Mirza; Nahar, Kamrun; Hossain, Md. Shahadat; Mahmud, Jubayer Al; Rahman, Anisur; Inafuku, Masashi; Oku, Hirosuke; Fujita, Masayuki

    2017-01-01

    Being sessile organisms, plants are frequently exposed to various environmental stresses that cause several physiological disorders and even death. Oxidative stress is one of the common consequences of abiotic stress in plants, which is caused by excess generation of reactive oxygen species (ROS). Sometimes ROS production exceeds the capacity of antioxidant defense systems, which leads to oxidative stress. In line with ROS, plants also produce a high amount of methylglyoxal (MG), which is an α-oxoaldehyde compound, highly reactive, cytotoxic, and produced via different enzymatic and non-enzymatic reactions. This MG can impair cells or cell components and can even destroy DNA or cause mutation. Under stress conditions, MG concentration in plants can be increased 2- to 6-fold compared with normal conditions depending on the plant species. However, plants have a system developed to detoxify this MG consisting of two major enzymes: glyoxalase I (Gly I) and glyoxalase II (Gly II), and hence known as the glyoxalase system. Recently, a novel glyoxalase enzyme, named glyoxalase III (Gly III), has been detected in plants, providing a shorter pathway for MG detoxification, which is also a signpost in the research of abiotic stress tolerance. Glutathione (GSH) acts as a co-factor for this system. Therefore, this system not only detoxifies MG but also plays a role in maintaining GSH homeostasis and subsequent ROS detoxification. Upregulation of both Gly I and Gly II as well as their overexpression in plant species showed enhanced tolerance to various abiotic stresses including salinity, drought, metal toxicity, and extreme temperature. In the past few decades, a considerable amount of reports have indicated that both antioxidant defense and glyoxalase systems have strong interactions in conferring abiotic stress tolerance in plants through the detoxification of ROS and MG. In this review, we will focus on the mechanisms of these interactions and the coordinated action of

  20. Expert systems for design, operation and management of industrial plant elctrical systems

    Energy Technology Data Exchange (ETDEWEB)

    Delfino, B.; Forzano, P.; Invernizzi, M.; Massucco, S. (Genoa Univ. (Italy) Pavia Univ. (Italy) Ansaldo Industria, Genoa (Italy))

    1991-02-01

    A discussion is made of modern industrial plant requirements with regard to man-machine interfacing. Indications are then given as to the optimum hardware and software for electrical plant and process control systems. Illustrative examples are provided on the use of expert systems to aid in the design of industrial plant electrical systems and to allow safe and reliable on-line control and monitoring.

  1. Fuel management of mixed reactor type power plant systems

    International Nuclear Information System (INIS)

    Csom, Gyula

    1988-01-01

    Breeding gain in symbiotic nuclear power plant system consisting of both thermal and fast breeder reactors depends on the characteristics and the ratio of thermal and fast reactors. The composition of the symbiotic power plant systems was determined for equilibrium and plutonium deficient systems. According to natural uranium utilization, symbiotic power plant systems are not less efficient than the systems containing only fast breeders. Depleted uranium can be applied in both types of systems. Reprocessing demands of the symbiotic power plant sytems were determined. (V.N.) 23 figs.; 1 tab

  2. System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do

    2015-01-01

    The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability

  3. System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do [KEPCO EnC, Daejeon (Korea, Republic of)

    2015-10-15

    The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability.

  4. Plant Growth Modeling Using L-System Approach and Its Visualization

    Directory of Open Access Journals (Sweden)

    Atris Suyantohadi

    2011-05-01

    Full Text Available The visualizationof plant growth modeling using computer simulation has rarely been conducted with Lindenmayer System (L-System approach. L-System generally has been used as framework for improving and designing realistic modeling on plant growth. It is one kind of tools for representing plant growth based on grammar sintax and mathematic formulation. This research aimed to design modeling and visualizing plant growth structure generated using L-System. The environment on modeling design used three dimension graphic on standart OpenGL format. The visualization on system design has been developed by some of L-System grammar, and the output graphic on three dimension reflected on plant growth as a virtual plant growth system. Using some of samples on grammar L-System rules for describing of the charaterictics of plant growth, the visualization of structure on plant growth has been resulted and demonstrated.

  5. The Remotely Controlled Robot System for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Koh, Kwangill; Lee, Gwangnam; Lim, Kyeyoung

    1993-01-01

    The problem of radioactivity has been our major concern. So, it makes the needs of remotely controlled robot system necessary for maintenance and repair services. Up to now, several foreign companies have been contracted for the maintenance of the steam generators of nuclear power plants in Korea, to acquire its own capability of maintaining the steam generators of it impossible for Korea to acquire its own capability of maintaining the steam generators. In case of emergency, it is difficult to take appropriate steps on its own. In order to resolve the above problems, it seems inevitable to develop the robot system for the inspection and repair of steam generator. This project intends to acquire domestic capabilities of maintaining steam generators, so that this advanced skills could be applied to the related areas. As a result, it will save immense money in the future. the purposes of development of the remotely controlled robot system are : to perform the desired tasks at the polluted area without requiring entry of personnel. to closely inspect the steam generator U-tubes at high speed. to inspect the steam generator intelligently and efficiently under the extreme circumstances where radioactivity problem is very severe. to use for the repair of steam generator tube. Considering from the social and technical standpoint, we can say that the development of the remotely controlled robot system for nuclear power plants resulted in great achievements. From the social standpoint, it should be recognized that domestic robot for nuclear power plant was successfully developed and operator was protected against radioactivity. Also, we advanced our skills in the area of mechanical and control system design for an articulated robot. Using the robot controller in hierarchical structure, it was possible to control the robot remotely. In addition, resolver feedback typed A C servo drive was proven to be sturdy in hazardous environment. Now we are confident that our robot will

  6. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators. 2011 Update

    International Nuclear Information System (INIS)

    2011-11-01

    At present there are over four hundred forty operational nuclear power plants (NPPs) in IAEA Member States. Ageing degradation of the systems, structures of components during their operational life must be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This IAEA-TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuteriumuranium (CANDU) reactor, boiling water reactor (BWR), pressurized water reactor (PWR), and water moderated, water cooled energy reactor (WWER) plants are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life cycle management of the plant components, which involves the integration of ageing management and economic planning. The target audience of the reports consists of technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present publication is the steam

  7. Sophistication and integration of plant engineering CAD-CAE systems

    International Nuclear Information System (INIS)

    Yoshinaga, Toshiaki; Hanyu, Masaharu; Ota, Yoshimi; Kobayashi, Yasuhiro.

    1995-01-01

    In respective departments in charge of basic planning, design, manufacture, inspection and construction of nuclear power plants, by the positive utilization of CAD/CAE system, efficient workings have been advanced. This time, the plant integrated CAE system wich heightens the function of these individual systems, and can make workings efficient and advanced by unifying and integrating them was developed. This system is composed of the newly developed application system and the data base system which enables the unified management of engineering data and high speed data conversion in addition to the CAD system for three-dimensional plant layout planning. On the basis of the rich experience and the proposal of improvement of designers by the application of the CAD system for three-dimensional plant layout planning to actual machines, the automation, speed increase and the visualization of input and output by graphical user interface (GUI) in the processing of respective applications were made feasible. As the advancement of plant CAE system, scenic engineering system, integrated layout CAE system, electric instrumentation design CAE system and construction planning CAE system are described. As for the integration of plant CAE systems, the integrated engineering data base, the combination of plant CAE systems, and the operation management in the dispersed environment of networks are reported. At present, Hitachi Ltd. exerts efforts for the construction of atomic energy product in formation integrated management system as the second stage of integration. (K.I.)

  8. Fitting of power generated by nuclear power plants into the Hungarian electricity system

    International Nuclear Information System (INIS)

    Lengyel, Gyula; Potecz, Bela

    1984-01-01

    The moderate increase of electrical energy demands (3% at present) can only be met by the parallel application of fossil and nuclear power plants and by electric power import via the transmission lines of the CMEA countries. The changes in the electrical energy and fuel demands and the development of the available capacities during the last 35 years are reviewed. The major purpose of Hungarian power economy is to save hydrocarbon fuels by taking advantages of power import opportunities by operating nuclear power plants at maximum capacity and the coal fired power stations at high capacity. The basic principles, the algorithm applied to optimize the load distribution of the electrical power system are discussed in detail with special attention to the role of nuclear power. The planned availability of nuclear power plants and the amount of electricity generated by nuclear plants should also be optimized. (V.N.)

  9. Plant Systems Biology at the Single-Cell Level.

    Science.gov (United States)

    Libault, Marc; Pingault, Lise; Zogli, Prince; Schiefelbein, John

    2017-11-01

    Our understanding of plant biology is increasingly being built upon studies using 'omics and system biology approaches performed at the level of the entire plant, organ, or tissue. Although these approaches open new avenues to better understand plant biology, they suffer from the cellular complexity of the analyzed sample. Recent methodological advances now allow plant scientists to overcome this limitation and enable biological analyses of single-cells or single-cell-types. Coupled with the development of bioinformatics and functional genomics resources, these studies provide opportunities for high-resolution systems analyses of plant phenomena. In this review, we describe the recent advances, current challenges, and future directions in exploring the biology of single-cells and single-cell-types to enhance our understanding of plant biology as a system. Copyright © 2017 Elsevier Ltd. All rights reserved.

  10. Assessment and management of ageing of major nuclear power plant components important to safety: CANDU reactor assemblies

    International Nuclear Information System (INIS)

    2001-02-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wearout of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring, and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs) including the Soviet designed water moderated and water cooled energy reactors (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age-related licensing issues. Since the reports are written from a safety perspective, they do not address life or life-cycle management of the plant components, which

  11. Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessels

    International Nuclear Information System (INIS)

    2005-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

  12. Regulatory perspective on digital instrumentation and control systems for future advanced nuclear power plants

    International Nuclear Information System (INIS)

    Chiramal, M.

    1993-01-01

    This paper deals with the question of using digital technology in instrumentation and control systems for modern nuclear power reactors. The general opinion in the industry and among NRC staff is that such technology provides the opportunity for enhanced safety and reliable reactor operations. The major concern is the safe application of this technology so as to avoid common mode or common cause failures in systems. There are great differences between digital and analog system components. SECY-91-292 identifies some general regulatory concerns with regard to digital systems. There is clearly a lack of adequate regulatory direction on the application of digital equipment at this time, but the issue is being addressed by the industry, outside experts, and NRC staff. NRC staff presents a position on the issue of defense-in-depth and diversity with regard to insuring plant safety. Independent manual controls and readouts must be available to allow safe shutdown and monitoring of the plant in the event of safety system failures

  13. Optimal planting systems for cut gladiolus and stock production

    Directory of Open Access Journals (Sweden)

    Iftikhar Ahmad

    2017-10-01

    Full Text Available A study was conducted to elucidate the effect of different planting systems, videlicet (viz. flat, ridge, and raised bed system on growth, yield and quality of gladiolus and stock. Corms of ‘Rose Supreme’ and ‘White Prosperity’ gladiolus and seedlings of ‘Cheerful White’, ‘Lucinda Dark Rose Double’ and ‘Lucinda Dark Rose Single’ stock were planted on different planting systems in individual experiments for each species. Gladiolus had similar good quality production irrespective of planting systems with numerical superiority of ridge planting, which produced longer stems with higher stem fresh weight, but delayed corm sprouting by ca. 1 d compared to raised bed or flat planting system. Among cultivars, ‘Rose Supreme’ produced higher number of florets per spike, taller stems with longer spikes, higher fresh weight of stems and higher number of cormels than ‘White Prosperity’. Stock plants grown on flat beds produced stems with greater stem length, leaf area and fresh weight of stems compared to ridge or raised bed planting systems. Plants grown on ridges produced the highest stem diameter, number of leaves per plant, total leaf chlorophyll contents, and number of flowers per spike. ‘Cheerful White’ and ‘Lucinda Dark Rose Double’ performed best by producing good quality stems in shorter period compared to ‘Lucinda Dark Rose Single’. In summary, gladiolus should be grown on ridges, while stock may be planted on flat beds for higher yields of better quality flowers.

  14. Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals

    International Nuclear Information System (INIS)

    1999-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific plant

  15. Maintenance service for major component of PWR plant. Replacement of pressurizer safe end weld

    International Nuclear Information System (INIS)

    Miyoshi, Yoshiyuki; Kobayashi, Yuki; Yamamoto, Kazuhide; Ueda, Takeshi; Suda, Naoki; Shintani, Takashi

    2017-01-01

    In October 2016, MHI completed the replacement of safe end weld of pressurizer (Pz) of Ringhals unit 3, which was the first maintenance work for main component of pressurized water reactor (PWR) plant in Europe. For higher reliability and longer lifetime of PWR plant, MHI has conducted many kinds of maintenance works of main components of PWR plants in Japan against stress corrosion cracking due to aging degradation. Technical process for replacement of Pz safe end weld were established by MHI. MHI has experienced the work for 21 PWR units in Japan. That of Ringhals unit 3 was planned and conducted based on the experiences. In this work, Alloy 600 used for welds of nozzles of Pz was replaced with Alloy 690. Alloy 690 is more corrosive-resistant than Alloy 600. Specially designed equipment and technical process were developed and established by MHI to replace safe end weld of Pz and applied for the Ringhals unit 3 as a first application in Europe. The application had been performed in success and achieved the planned replacement work duration and total radiation dose by using sophisticated machining and welding equipment designed to meet the requirements to be small, lightweight and remote-controlled and operating by well skilled MHI personnel experienced in maintenance activities for major components of PWR plant in Japan. The success shows that the experience, activities and technology developed in Japan for main components of PWR plant shall be applicable to contribute reliable operations of nuclear power plants in Europe and other countries. (author)

  16. Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis

    International Nuclear Information System (INIS)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

    1993-01-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the I nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant , CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

  17. Research on operation support system for nuclear power plants

    International Nuclear Information System (INIS)

    Wakabayashi, Jiro

    1989-01-01

    Nuclear power plants are the typical, complex, large scale engineering system, and at the time of accidents, there is the possibility to extend disasters to wide range beyond borders, therefore, it is the feature that the requirement for their reliability and safety is much severe as compared with other engineering systems. The fact that human errors become the major cause of large accidents is in common in large scale engineering systems, and the development of the operation support system for preventing it has become an important research subject. Also the research on design support system and maintenance support system is in progress to prevent human errors. Operation support system is composed of diagnostic system, operation guide system, man-machine interface and knowledge data base, and throughout these, the research on the human errors arising in the process of human decision making becomes the basis. Rasmussen's model for decision making, the classification of human errors and the reliability analysis for men, the factors affecting human errors, the acquisition of knowledge, the compilation and management of knowledge data base, the diagnostic system, operation guide system and man-machine interface are described. (K.I.)

  18. Tracing the origin of dissolved silicon transferred from various soil-plant systems towards rivers: a review

    Directory of Open Access Journals (Sweden)

    J.-T. Cornelis

    2011-01-01

    Full Text Available Silicon (Si released as H4SiO4 by weathering of Si-containing solid phases is partly recycled through vegetation before its land-to-rivers transfer. By accumulating in terrestrial plants to a similar extent as some major macronutrients (0.1–10% Si dry weight, Si becomes largely mobile in the soil-plant system. Litter-fall leads to a substantial reactive biogenic silica pool in soil, which contributes to the release of dissolved Si (DSi in soil solution. Understanding the biogeochemical cycle of silicon in surface environments and the DSi export from soils into rivers is crucial given that the marine primary bio-productivity depends on the availability of H4SiO4 for phytoplankton that requires Si. Continental fluxes of DSi seem to be deeply influenced by climate (temperature and runoff as well as soil-vegetation systems. Therefore, continental areas can be characterized by various abilities to transfer DSi from soil-plant systems towards rivers. Here we pay special attention to those processes taking place in soil-plant systems and controlling the Si transfer towards rivers. We aim at identifying relevant geochemical tracers of Si pathways within the soil-plant system to obtain a better understanding of the origin of DSi exported towards rivers. In this review, we compare different soil-plant systems (weathering-unlimited and weathering-limited environments and the variations of the geochemical tracers (Ge/Si ratios and δ30Si in DSi outputs. We recommend the use of biogeochemical tracers in combination with Si mass-balances and detailed physico-chemical characterization of soil-plant systems to allow better insight in the sources and fate of Si in these biogeochemical systems.

  19. Photosynthesis and photoprotective systems of plants in response to ...

    African Journals Online (AJOL)

    Aluminum (Al) toxicity is the major factor limiting plant growth in acidic soils, which comprise up to 70% of the world's potentially arable lands. Although, Al toxicity and tolerance in plant roots have been extensively studied during the past decades because inhibition of root growth is one of the earliest symptoms of Al injury ...

  20. The condition monitoring system of turbine system components for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, Shigetoshi

    2013-01-01

    The thermal and nuclear power plants have been imposed a stable supply of electricity. To certainly achieve this, we built the plant condition monitoring system based on the heat and mass balance calculation. If there are some performance changes on the turbine system components of their power plants, the heat and mass balance of the turbine system will change. This system has ability to detect the abnormal signs of their components by finding the changes of the heat and mass balance. Moreover we note that this system is built for steam turbine cycle operating with saturated steam conditions. (author)

  1. Guidelines for multipurpose data systems for nuclear power plants

    International Nuclear Information System (INIS)

    1994-07-01

    This TECDOC is intended to provide guidance on implementing a system to provide the staff and management of a nuclear power plant with data and information specific to the plant, to assist in making decisions concerning plant operation and maintenance. The guidelines do not deal with issues relating to software and hardware for database management owing to the rapid evolution in these technologies. It will be up to individual utilities to select a suitable technology to meet their data system needs. The guidelines are intended to help a utility with operating plants and/or plants under construction to implement a system which best suits its needs for the compilation of plant specific data. The plant specific data will in turn help in generating quantitative and qualitative results and insights to support decision making for optimized plant operation and maintenance. The guidelines are supplemented by examples of the data systems in use at the utilities that contributed to the preparation of the document Figs and tabs

  2. A nuclear power plant system engineering workstation

    International Nuclear Information System (INIS)

    Mason, J.H.; Crosby, J.W.

    1989-01-01

    System engineers offer an approach for effective technical support for operation and maintenance of nuclear power plants. System engineer groups are being set up by most utilities in the United States. Institute of Nuclear Power operations (INPO) and U.S. Nuclear Regulatory Commission (NRC) have endorsed the concept. The INPO Good Practice and a survey of system engineer programs in the southeastern United States provide descriptions of system engineering programs. The purpose of this paper is to describe a process for developing a design for a department-level information network of workstations for system engineering groups. The process includes the following: (1) application of a formal information engineering methodology, (2) analysis of system engineer functions and activities; (3) use of Electric Power Research Institute (EPRI) Plant Information Network (PIN) data; (4) application of the Information Engineering Workbench. The resulting design for this system engineer workstation can provide a reference for design of plant-specific systems

  3. Control of power plants and power systems. Proceedings

    International Nuclear Information System (INIS)

    Canales-Ruiz, R.

    1996-01-01

    The 88 papers in this volume constitute the proceedings of the International Federation of Automatic Control Symposium held in Mexico in 1995. The broad areas which they cover are: self tuning control; power plant operations; dynamic stability; fuzzy logic applications; power plants modelling; artificial intelligence applications; power plants simulation; voltage control; control of hydro electric units; state estimation; fault diagnosis and monitoring systems; system expansion and operation planning; security assessment; economic dispatch and optimal load flow; adaptive control; distribution; transient stability and preventive control; modelling and control of nuclear plant; knowledge data bases for automatic learning methods applied to power system dynamic security assessment; control of combined cycle units; power control centres. Separate abstracts have been prepared for the three papers relating to nuclear power plants. (UK)

  4. Plant risk status information management system

    International Nuclear Information System (INIS)

    Campbell, D.J.; Ellison, B.C.; Glynn, J.C.; Flanagan, G.F.

    1985-01-01

    The Plant Risk Status Information Management System (PRISIMS) is a PC program that presents information about a nuclear power plant's design, its operation, its technical specifications, and the results of the plant's probabilistic risk assessment (PRA) in a logically and easily accessible format. PRISIMS provides its user with unique information for integrating safety concerns into day-to-day operational decisions and/or long-range management planning

  5. Knowledge acquisition for nuclear power plant unit diagnostic system

    International Nuclear Information System (INIS)

    Li Xiaodong; Xi Shuren

    2003-01-01

    The process of acquiring knowledge and building a knowledge base is critical to realize fault diagnostic system at unit level in a nuclear power plant. It directly determines whether the diagnostic system can be applied eventually in a commercial plant. A means to acquire knowledge and its procedures was presented in this paper for fault diagnostic system in a nuclear power plant. The work can be carried out step by step and it is feasible in a commercial nuclear power plant. The knowledge base of the fault diagnostic system for a nuclear power plant can be built after the staff finish the tasks according to the framework presented in this paper

  6. Function analysis of nuclear power plants for developing of man-machine interface system for Korean next generation reactor

    Energy Technology Data Exchange (ETDEWEB)

    Goo, In Soo; Kim, Jang Yyul; Kim, Jung Soo; Kim, Chang Hoi; Na, Nan Joo; Park, Keun Ok; Park, Won Man; Park, Jae Chang; Suh, Sang Moon; Oh, In Suk; Lee, Dong Young; Lee, Yong Hee; Cha, Kyung Ho; Chun, Se Woo; Hur, Sup [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Jung, Kyung Hoon [Korea Electric Power Co., Seoul (Korea, Republic of); Park, Yeon Sik; Lee, Bum Joo [Korea Power Engineering Company, Inc., Seoul (Korea, Republic of)

    1995-02-01

    In this study, we developed the methodology and implementation plant of function analysis and performed function analysis, which is one of the major activities for the development of Man-Machine Interface System of the KNGR. Identifying the functions of existing plants followed by structuring the functions, we established functions structured at the conceptual and middle levels. This structure was further checked if it would satisfy regulatory requirements and developed to include the aspects of plant performance and other plant features to emphasize its practicality for the application to the design. (Author) 13 refs., 8 figs., 4 tabs.

  7. Function analysis of nuclear power plants for developing of man-machine interface system for Korean next generation reactor

    International Nuclear Information System (INIS)

    Goo, In Soo; Kim, Jang Yyul; Kim, Jung Soo; Kim, Chang Hoi; Na, Nan Joo; Park, Keun Ok; Park, Won Man; Park, Jae Chang; Suh, Sang Moon; Oh, In Suk; Lee, Dong Young; Lee, Yong Hee; Cha, Kyung Ho; Chun, Se Woo; Hur, Sup; Jung, Kyung Hoon; Park, Yeon Sik; Lee, Bum Joo

    1995-02-01

    In this study, we developed the methodology and implementation plant of function analysis and performed function analysis, which is one of the major activities for the development of Man-Machine Interface System of the KNGR. Identifying the functions of existing plants followed by structuring the functions, we established functions structured at the conceptual and middle levels. This structure was further checked if it would satisfy regulatory requirements and developed to include the aspects of plant performance and other plant features to emphasize its practicality for the application to the design. (Author) 13 refs., 8 figs., 4 tabs

  8. Development of plant status display system for on-site educational training system

    International Nuclear Information System (INIS)

    Yoshimura, Seiichi; Fujimoto, Junzo; Okamoto, Hisatake; Tsunoda, Ryohei; Watanabe, Takao; Masuko, Jiro.

    1986-01-01

    The purpose of this system is to make easy the comprehension of the facility and dynamics of nuclear power plants. This report describes the tendency and future position of how the educational training system should be, and furthermore describes the experiment. Main results are as follows. 1. The present status and the future tendency of educational training system for nuclear power plant operators. CAI (Computer Assisted Instruction) system has following characteristics. (1) It is easy to introduce plant specific characteristics to the educational training. (2) It is easy to execute the detailed training for the compensation of the full-scale simulator. 2. Plant status display system for on-site educational training system. The fundamental function of the system is as follows. (1) It has 2 CRT displays and voice output devices. (2) It has easy manupulation type of man-machine interface. (3) It has the function for the evaluation of the training results. 3. The effectiveness of this system. The effectiveness evaluation test has been carried out by using this system actually. (1) This system has been proved to be essentially effective and some improvements for the future utilization has been pointed out. (2) It should be faster when the CRT displayes are changed, and it should have the explanation function when the plant transients are displayed. (author)

  9. Computerized information system of the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Holik, V.

    1986-01-01

    The computer-based information system for the Mochovce nuclear power plant has a hierarchic structure which incorporates SM 1804 microcomputers and SM 1420 minicomputers. With regard to operation it is divided into two levels: the information system at the level of power plant units and the information system t the level of the whole power plant. The information system of a unit provides the collection of information on the technological equipment of each unit for the operative control of the unit and documentation on unit operation. Each unit has its own independent computer information system. The actual nucleus of each unit information system consists of two computer complexes based on SM 1420 twin computers, mutually substitutional. The power plant level information system provides the processing and output of information for personnel in the central control room of the power plant and for other managerial staff. It uses preprocessed information from the unit information systems and direct information from non-unit installations and from dosimetric control rooms of the power plant units. This information system is also based on a computer complex with two SM 1420 computers. (Z.M.)

  10. Individual plant care in cropping systems

    OpenAIRE

    Griepentrog, Hans W.; Nørremark, Michael; Nielsen, Henning; Blackmore, Simon

    2003-01-01

    Individual plant care cropping systems, embodied in precision farming, may lead to new opportunities in agricultural crop management. The objective of the project was to provide high accuracy seed position mapping of a field of sugar beet. An RTK GPS was retrofitted on to a precision seeder to map the seeds as they were planted. The average error between the seed map and the actual plant map was about 32 mm to 59 mm. The results showed that the overall accuracy of the estimated plant position...

  11. Decision support systems for power plants impact on the living standard

    International Nuclear Information System (INIS)

    Chatzimouratidis, Athanasios I.; Pilavachi, Petros A.

    2012-01-01

    Highlights: ► Ten major types of power plant are evaluated as to their impact on living standard. ► Uncertainty in both criteria performance and criteria weighting is considered. ► PROMETHEE II method, 12 criteria and 13 scenarios are used. ► Results are presented per scenario and per type of power plant. ► Optimal solution depends on scenario assumptions of the decision maker. - Abstract: In developed countries, the quality of life is of first priority and an overall assessment of power plant impact on the living standard requires a multicriteria analysis of both positive and negative factors incorporating uncertainty in criteria performance and probability assessment of weighting factors. This study incorporates PROMETHEE II to assess 10 major types of power plant under 12 criteria, 13 fixed and infinite customized probability assessed weight set scenarios. The power plants considered are coal/lignite, oil, natural gas turbine, natural gas combined cycle, nuclear, hydro, wind, photovoltaic, biomass and geothermal. Geothermal, wind and photovoltaic power plants are excellent choices in most of the cases and biomass and hydro should also be preferred to nuclear and fossil fuel. Among nuclear and fossil fuel the choice is based on the specific parameters of each case examined while natural gas technologies have specific advantages. The motivation of this study was to provide a tool for the decision-maker to evaluate all major types of power plant incorporating multicriteria and customized probability assessment of weighting factors.

  12. Ways to integrate document management systems with industrial plant configuration management systems

    International Nuclear Information System (INIS)

    Munoz, M.

    1995-01-01

    Based on experience gained from tasks carried out for Almaraz Nuclear Power Plant, this paper describes computer platforms used both at the power plant and in the main offices of the engineering company. Subsequently, a description is given of the procedure followed for the continuous up-dating of plant documentation, in order to maintain consistency with other information stored in data bases in the Operation Management System, Maintenance System, Modification Management System, etc. The work method used for the unitary updating of all information (document images and attributes corresponding to the different data bases), following refuelling procedures is also described. Lastly, the paper describes the functions and the user interface of the system used in the power plant for document management. (Author)

  13. Expert system for maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Ito, Tetsuo; Kasahara, Takayasu; Watanabe, Takao; Matsuki, Tsutomu.

    1989-01-01

    The basic function of the expert system which supports the maintenance works such as the diagnosis of nuclear power plants and the planning of maintenance works was developed. For the maintenance of large scale plants like nuclear power plants, much manpower is required. Consequently, it has been desired to develop the system for improving the maintainability by utilizing the expertise and empirical knowledge of skilled engineers. This system comprises the subsystems for aiding plant diagnosis and maintenance work planning. The former diagnoses the contents of out of order based on the knowledge base, and thereafter, guides the method of taking measures using simulator. The latter establishes the plan by using the method of limiting branching together so that the maintenance works do not interfere mutually or do not affect the operation. Hereafter, it is intended to improve the man-machine condition and expand knowledge aiming at the practical use. The outline of the system, the constitution of subsystems, the example of plant diagnosis, the support of plant maintenance work planning and so on are reported. (K.I.)

  14. Assessment and Management of ageing of major nuclear power plant components important to safety: PWR pressure vessels

    International Nuclear Information System (INIS)

    1999-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g., caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs; and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life-cycle management of the plant components, which involves the integration of

  15. Operator support system for nuclear power plants

    International Nuclear Information System (INIS)

    Mori, Nobuyuki; Tai, Ichiro; Sudo, Osamu; Naito, Norio.

    1987-01-01

    The nuclear power generation in Japan maintains the high capacity factor, and its proportion taken in the total generated electric power exceeded 1/4, thus it has become the indispensable energy source. Recently moreover, the nuclear power plants which are harmonious with operators and easy to operate are demanded. For realizing this, the technical development such as the heightening of operation watching performance, the adoption of automation, and the improvement of various man-machine systems for reducing the burden of operators has been advanced by utilizing electronic techniques. In this paper, the trend of the man-machine systems in nuclear power plants, the positioning of operation support system, the support in the aspects of information, action and knowledge, the example of a new central control board, the operation support system using a computer, an operation support expert system and the problems hereafter are described. As the development of the man-machine system in nuclear power plants, the upgrading from a present new central control board system PODIA through A-PODIA, in which the operational function to deal with various phenomena arising in plants and safety control function are added, to 1-PODIA, in which knowledge engineering technology is adopted, is expected. (Kako, I.)

  16. Trichoderma harzianum T-78 supplementation of compost stimulates the antioxidant defence system in melon plants.

    Science.gov (United States)

    Bernal-Vicente, Agustina; Pascual, José A; Tittarelli, Fabio; Hernández, José A; Diaz-Vivancos, Pedro

    2015-08-30

    Compost is emerging as an alternative plant growing medium in efforts to achieve more sustainable agriculture. The addition of specific microorganisms such as Trichoderma harzianum to plant growth substrates increases yields and reduces plant diseases, but the mechanisms of such biostimulants and the biocontrol effects are not yet fully understood. In this work we investigated how the addition of citrus and vineyard composts, either alone or in combination with T. harzianum T-78, affects the antioxidant defence system in melon plants under nursery conditions. Compost application and/or Trichoderma inoculation modulated the antioxidant defence system in melon plants. The combination of citrus compost and Trichoderma showed a biostimulant effect that correlated with an increase in ascorbate recycling enzymes (monodehydroascorbate reductase, dehydroascorbate reductase) and peroxidase. Moreover, the inoculation of both composts with Trichoderma increased the activity of antioxidant enzymes, especially those involved in ascorbate recycling. Based on the long-established relationship between ascorbic acid and plant defence responses as well as plant growth and development, it can be suggested that ascorbate recycling activities play a major role in the protection provided by Trichoderma and its biostimulant effect and that these outcomes are linked to increases in antioxidant enzymes. We can conclude that the combination of citrus compost and T. harzianum T-78 constitutes a viable, environmentally friendly strategy for improving melon plant production. © 2014 Society of Chemical Industry.

  17. Imaging corn plants with PhytoPET, a modular PET system for plant biology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.; Kross, B.; McKisson, J.; McKisson, J. E.; Weisenberger, A. G.; Xi, W.; Zorn, C.; Bonito, G.; Howell, C. R.; Reid, C. D.; Crowell, A.; Cumberbatch, L. C.; Topp, C.; Smith, M. F.

    2013-11-01

    PhytoPET is a modular positron emission tomography (PET) system designed specifically for plant imaging. The PhytoPET design allows flexible arrangements of PET detectors based on individual standalone detector modules built from single Hamamatsu H8500 position sensitive photomultiplier tubes and pixelated LYSO arrays. We have used the PhytoPET system to perform preliminary corn plant imaging studies at the Duke University Biology Department Phytotron. Initial evaluation of the PhytoPET system to image the biodistribution of the positron emitting tracer {sup 11}C in corn plants is presented. {sup 11}CO{sub 2} is loaded into corn seedlings by a leaf-labeling cuvette and translocation of {sup 11}C-sugars is imaged by a flexible arrangement of PhytoPET modules on each side. The PhytoPET system successfully images {sup 11}C within corn plants and allows for the dynamic measurement of {sup 11}C-sugar translocation from the leaf to the roots.

  18. Hybrid intelligent monironing systems for thermal power plant trips

    Science.gov (United States)

    Barsoum, Nader; Ismail, Firas Basim

    2012-11-01

    Steam boiler is one of the main equipment in thermal power plants. If the steam boiler trips it may lead to entire shutdown of the plant, which is economically burdensome. Early boiler trips monitoring is crucial to maintain normal and safe operational conditions. In the present work two artificial intelligent monitoring systems specialized in boiler trips have been proposed and coded within the MATLAB environment. The training and validation of the two systems has been performed using real operational data captured from the plant control system of selected power plant. An integrated plant data preparation framework for seven boiler trips with related operational variables has been proposed for IMSs data analysis. The first IMS represents the use of pure Artificial Neural Network system for boiler trip detection. All seven boiler trips under consideration have been detected by IMSs before or at the same time of the plant control system. The second IMS represents the use of Genetic Algorithms and Artificial Neural Networks as a hybrid intelligent system. A slightly lower root mean square error was observed in the second system which reveals that the hybrid intelligent system performed better than the pure neural network system. Also, the optimal selection of the most influencing variables performed successfully by the hybrid intelligent system.

  19. Plant litter dynamics in the forest-stream interface: precipitation is a major control across tropical biomes.

    Science.gov (United States)

    Tonin, Alan M; Gonçalves, José F; Bambi, Paulino; Couceiro, Sheyla R M; Feitoza, Lorrane A M; Fontana, Lucas E; Hamada, Neusa; Hepp, Luiz U; Lezan-Kowalczuk, Vânia G; Leite, Gustavo F M; Lemes-Silva, Aurea L; Lisboa, Leonardo K; Loureiro, Rafael C; Martins, Renato T; Medeiros, Adriana O; Morais, Paula B; Moretto, Yara; Oliveria, Patrícia C A; Pereira, Evelyn B; Ferreira, Lidiane P; Pérez, Javier; Petrucio, Mauricio M; Reis, Deusiano F; S Rezende, Renan; Roque, Nadia; Santos, Luiz E P; Siegloch, Ana E; Tonello, Gabriela; Boyero, Luz

    2017-09-07

    Riparian plant litter is a major energy source for forested streams across the world and its decomposition has repercussions on nutrient cycling, food webs and ecosystem functioning. However, we know little about plant litter dynamics in tropical streams, even though the tropics occupy 40% of the Earth's land surface. Here we investigated spatial and temporal (along a year cycle) patterns of litter inputs and storage in multiple streams of three tropical biomes in Brazil (Atlantic forest, Amazon forest and Cerrado savanna), predicting major differences among biomes in relation to temperature and precipitation regimes. Precipitation explained most of litter inputs and storage, which were generally higher in more humid biomes (litterfall: 384, 422 and 308 g m -2 y -1 , storage: 55, 113 and 38 g m -2 , on average in Atlantic forest, Amazon and Cerrado, respectively). Temporal dynamics varied across biomes in relation to precipitation and temperature, with uniform litter inputs but seasonal storage in Atlantic forest streams, seasonal inputs in Amazon and Cerrado streams, and aseasonal storage in Amazon streams. Our findings suggest that litter dynamics vary greatly within the tropics, but point to the major role of precipitation, which contrasts with the main influence of temperature in temperate areas.

  20. The physical environment and major plant communities of the Karoo National Park, South Africa

    OpenAIRE

    Francine Rubin; A.R. Palmer

    1996-01-01

    The major plant communities of the Karoo National Park are described using the methods of the Zurich-Montpellier school of phytosociology, to assist with the formulation of a management strategy for the park. The vegetation physiognomy consists of Montane Karoo grassy shrublands. Karoo grassy dwarf shrublands. Karoo succulent dwarf shrublands and riparian thicket. Steep elevation and precipitation gradients within the study area have a direct impact on gradients in the vegetation. High elevat...

  1. Fault tolerant, multiplexed control rod position detection and indication system for nuclear power plants

    International Nuclear Information System (INIS)

    Dufek, W.L.; Jelovich, J.J.; Neuner, J.A.

    1977-01-01

    The majority of Westinghouse nuclear plants placed in service thus far have incorporated a Rod Position Indication system based upon an analog design philosophy. This system, while meeting all functional and accuracy requirements, has proven somewhat cumbersome, particularly in the area of initial field calibration and maintenance. This paper describes a new Digital Rod Position Indication system (DRPI) developed for use with pressurized water reactors. The system is based upon a digital design philosophy and meets all previous design constraints and environmental requirements. Further, fault tolerance, improved accuracy, interference from adjacent rods and the elimination of adjustments and calibration has been provided

  2. 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

  3. Plant functional modelling as a basis for assessing the impact of management on plant safety

    International Nuclear Information System (INIS)

    Rasmussen, Birgitte; Petersen, Kurt E.

    1999-01-01

    A major objective of the present work is to provide means for representing a chemical process plant as a socio-technical system, so as to allow hazard identification at a high level in order to identify major targets for safety development. The main phases of the methodology are: (1) preparation of a plant functional model where a set of plant functions describes coherently hardware, software, operations, work organization and other safety related aspects. The basic principle is that any aspect of the plant can be represented by an object based upon an Intent and associated with each Intent are Methods, by which the Intent is realized, and Constraints, which limit the Intent. (2) Plant level hazard identification based on keywords/checklists and the functional model. (3) Development of incident scenarios and selection of hazardous situation with different safety characteristics. (4) Evaluation of the impact of management on plant safety through interviews. (5) Identification of safety critical ways of action in the management system, i.e. identification of possible error- and violation-producing conditions

  4. Development of tritium plant system for fusion reactors. Achievements in the 14-year US-Japan collaboration

    International Nuclear Information System (INIS)

    Nishi, Masataka; Yamanishi, Toshihiko; Shu, Wataru

    2003-01-01

    Fuel processing technology and tritium safe-handling technology have been developed through US/DOE-JAERI collaboration from 1987 till 2001, and the technologies to construct the tritium plant system of ITER have been made currently available. This paper overviews the major achievements of this collaborative researches over fourteen years, which were performed mainly at the Tritium Systems Test Assembly (TSTA) of the Los Alamos National Laboratory (LANL). The tritium plant system consists mainly of a fuel processing system, which includes a fuel cycle system and a blanket tritium recovery system, and a tritium confinement/removal system. The fuel cycle system recovers fuel from plasma exhaust gas and recycles it. In the collaboration, major key components and subsystems were developed, and the performance of the integrated system was successfully demonstrated over its one-month operation in which plasma exhaust model gas was processed at a processing rate of up to 1/6 level of the ITER. The technological basis of the fuel cycle system was thus established. Blanket tritium recovery technology was also successfully demonstrated using the TSTA system. Through the successful safe-operation of the TSTA, reliability of tritium confinement/removal system was verified basically. In addition, much data to confirm or enhance safety were accumulated by experiments such as intentional tritium release in a large room. Furthermore, distribution of tritium contamination in the vacuum vessel of the TFTR, a large tokamak of the Princeton Plasma Physics Laboratory (PPPL), was investigated in this work. (author)

  5. Development of Tritium Plant System for Fusion Reactors - Achievements in the 14-year US-Japan Collaboration -

    Science.gov (United States)

    Nishi, Masataka; Yamanishi, Toshihiko; Shu, Wataru

    Fuel processing technology and tritium safe-handling technology have been developed through US/DOE-JAERI collaboration from 1987 till 2001, and the technologies to construct the tritium plant system of ITER have been made currently available. This paper overviews the major achievements of this collaborative researches over fourteen years, which were performed mainly at the Tritium Systems Test Assembly (TSTA) of the Los Alamos National Laboratory (LANL). The tritium plant system consists mainly of a fuel processing system, which includes a fuel cycle system and a blanket tritium recovery system, and a tritium confinement/removal system. The fuel cycle system recovers fuel from plasma exhaust gas and recycles it. In the collaboration, major key components and subsystems were developed, and the performance of the integrated system was successfully demonstrated over its one-month operation in which plasma exhaust model gas was processed at a processing rate of up to 1/6 level of the ITER. The technological basis of the fuel cycle system was thus established. Blanket tritium recovery technology was also successfully demonstrated using the TSTA system. Through the successful safeoperation of the TSTA, reliability of tritium confinement/removal system was verified basically. In addition, much data to confirm or enhance safety were accumulated by experiments such as intentional tritium release in a large room. Furthermore,distribution of tritium contamination in the vacuum vessel of the TFTR, a large tokamak of the Princeton Plasma Physics Laboratory (PPPL), was investigated in this work.

  6. Proteomics and plant disease: advances in combating a major threat to the global food supply.

    Science.gov (United States)

    Rampitsch, Christof; Bykova, Natalia V

    2012-02-01

    The study of plant disease and immunity is benefiting tremendously from proteomics. Parallel streams of research from model systems, from pathogens in vitro and from the relevant pathogen-crop interactions themselves have begun to reveal a model of how plants succumb to invading pathogens and how they defend themselves without the benefit of a circulating immune system. In this review, we discuss the contribution of proteomics to these advances, drawing mainly on examples from crop-fungus interactions, from Arabidopsis-bacteria interactions, from elicitor-based model systems and from pathogen studies, to highlight also the important contribution of non-crop systems to advancing crop protection. Copyright © 2012 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  7. An integrated reliability management system for nuclear power plants

    International Nuclear Information System (INIS)

    Kimura, T.; Shimokawa, H.; Matsushima, H.

    1998-01-01

    The responsibility in the nuclear field of the Government, utilities and manufactures has increased in the past years due to the need of stable operation and great reliability of nuclear power plants. The need to improve the reliability is not only for the new plants but also for those now running. So, several measures have been taken to improve reliability. In particular, the plant manufactures have developed a reliability management system for each phase (planning, construction, maintenance and operation) and these have been integrated as a unified system. This integrated reliability management system for nuclear power plants contains information about plant performance, failures and incidents which have occurred in the plants. (author)

  8. Use of a plant level logic model for quantitative assessment of systems interactions

    International Nuclear Information System (INIS)

    Chu, B.B.; Rees, D.C.; Kripps, L.P.; Hunt, R.N.; Bradley, M.

    1985-01-01

    The Electric Power Research Institute (EPRI) has sponsored a research program to investigate methods for identifying systems interactions (SIs) and for the evaluation of their importance. Phase 1 of the EPRI research project focused on the evaluation of methods for identification of SIs. Major results of the Phase 1 activities are the documentation of four different methodologies for identification of potential SIs and development of guidelines for performing an effective plant walkdown in support of an SI analysis. Phase II of the project, currently being performed, is utilizing a plant level logic model of a pressurized water reactor (PWR) to determine the quantitative importance of identified SIs. In Phase II, previously reported events involving interactions between systems were screened and selected on the basis of their relevance to the Baltimore Gas and Electric (BGandE) Calvert Cliffs Nuclear Power Plant design and perceived potential safety significance. Selected events were then incorporated into the BGandE plant level GO logic model. The model is being exercised to calculate the relative importance of these events. Five previously identified event scenarios, extracted from licensee event reports (LERs) are being evaluated during the course of the study. A key feature of the approach being used in Phase II is the use of a logic model in a manner to effectively evaluate the impact of events on the system level and the plant level for the mitigation of transients. Preliminary study results indicate that the developed methodology can be a viable and effective means for determining the quantitative significance of SIs

  9. Diffuse-Illumination Systems for Growing Plants

    Science.gov (United States)

    May, George; Ryan, Robert

    2010-01-01

    Agriculture in both terrestrial and space-controlled environments relies heavily on artificial illumination for efficient photosynthesis. Plant-growth illumination systems require high photon flux in the spectral range corresponding with plant photosynthetic active radiation (PAR) (400 700 nm), high spatial uniformity to promote uniform growth, and high energy efficiency to minimize electricity usage. The proposed plant-growth system takes advantage of the highly diffuse reflective surfaces on the interior of a sphere, hemisphere, or other nearly enclosed structure that is coated with highly reflective materials. This type of surface and structure uniformly mixes discrete light sources to produce highly uniform illumination. Multiple reflections from within the domelike structures are exploited to obtain diffuse illumination, which promotes the efficient reuse of photons that have not yet been absorbed by plants. The highly reflective surfaces encourage only the plant tissue (placed inside the sphere or enclosure) to absorb the light. Discrete light sources, such as light emitting diodes (LEDs), are typically used because of their high efficiency, wavelength selection, and electronically dimmable properties. The light sources are arranged to minimize shadowing and to improve uniformity. Different wavelengths of LEDs (typically blue, green, and red) are used for photosynthesis. Wavelengths outside the PAR range can be added for plant diagnostics or for growth regulation

  10. Plant operation state monitoring system

    International Nuclear Information System (INIS)

    Sakai, Masanori; Babuchi, Katsumi; Arato, Toshiaki

    1994-01-01

    The system of the present invention accurately monitors a plant operation state of a plant, such as a nuclear power plant and a thermal power plant by using high temperature water, based on water quality informations. That is, water quality informations for the objective portion by using an electrochemical water quality sensor disposed in the objective portion to be monitored in the plant are continuously extracted for a predetermined period of time. Water quality is evaluated based on the extracted information. Obtained results for water quality evaluation and predetermined reference values of the plant operation handling are compared. Necessary part among the results of the measurement is displayed or recorded. The predetermined period of time described above is a period that the water quality information reaches at least a predetermined value or a period that the predetermined value is estimated by the water quality information, and it is defined as a period capable of measuring the information for three months continuously. The measurement is preferably conducted continuously in a period up to each periodical inspection on about every one year. (I.S.)

  11. Increase net plant output through selective operation of the heat-rejection system

    International Nuclear Information System (INIS)

    Ostrowski, E.T.; Queenan, P.T.

    1987-01-01

    Depending on unit load and ambient meteorological conditions, a net increase of 800 to 5500 kW in plant output is possible for many generating units through optimized operation of the major motor-driven equipment in the heat-rejection system - the circulating water pumps and mechanical-draft cooling tower fans. This can be realised when the resulting decrease in auxiliary-power demand is greater than the decrease in gross electric generation caused by operating fewer pumps and/or fans. No capital expenditures are incurred and only operating procedures are involved so that the performance gains are achieved at no cost. The paper considers the application of this technique to nuclear power plants, pump optimization and the superimposition of fan and cooling tower performance curves

  12. Technical Challenges in the Application and Licensing of Digital Instrumentation and Control Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2015-01-01

    With the modernization of existing analogue instrumentation and control (I&C) systems in nuclear power plants through digital I&C technology, and the implementation of digital I&C systems in new plants, the industry is faced with significant challenges. These challenges appear in the form of difficulties in managing the necessarily incremental transition, highly integrated (and interdependent) architectures, the flexible configurability enabled by digital technology, and uncertainty and inconsistency in licensing digital I&C systems and equipment in the different Member States. This publication discusses 17 major issues that utilities, developers, suppliers and regulatory stakeholders need to consider, so that the industry can capture and benefit from shared experience, recent technological developments, and emerging best practices

  13. Evaluation of safety implications of control systems in LWR nuclear power plants

    International Nuclear Information System (INIS)

    Szukiewicz, A.J.

    1989-06-01

    An in-depth evaluation was performed on non-safety-related control systems (see Section 1) that are typically used during normal plant operation on four nuclear steam supply system plants: a General Electric Company boiling-water reactor, a Westinghouse 3-loop pressurized-water reactor (PWR), a Babcock ampersand Wilcox Co. (B ampersand W) once-through steam generator PWR, and a Combustion Engineering PWR design. A study was also conducted to determine the generic applicability of the results to the class of plants represented by the specific plants analyzed. Generic conclusions were then developed. Steam generator and reactor vessel overfill events and reactor vessel overcooling events were identified as major classes of events having the potential to be more severe than previously analyzed. Specific substasks of this issue were to study these events to determine the need for preventive and/or mitigating design measures. This report describes the technical studies performed by the laboratories, the NRC staff assessment of the results, the generic applicability of the evaluations, and the technical findings resulting from these studies. This final report contains the staff's responses to, and resolution of, the public comments that were solicited and received before September 16,1988, in response to the draft reports issued for public comment on May 27, 1988. 39 refs, 1 fig., 7 tabs

  14. Protocol: optimising hydroponic growth systems for nutritional and physiological analysis of Arabidopsis thaliana and other plants

    Science.gov (United States)

    2013-01-01

    Background Hydroponic growth systems are a convenient platform for studying whole plant physiology. However, we found through trialling systems as they are described in the literature that our experiments were frequently confounded by factors that affected plant growth, including algal contamination and hypoxia. We also found the way in which the plants were grown made them poorly amenable to a number of common physiological assays. Results The drivers for the development of this hydroponic system were: 1) the exclusion of light from the growth solution; 2) to simplify the handling of individual plants, and 3) the growth of the plant to allow easy implementation of multiple assays. These aims were all met by the use of pierced lids of black microcentrifuge tubes. Seed was germinated on a lid filled with an agar-containing germination media immersed in the same solution. Following germination, the liquid growth media was exchanged with the experimental solution, and after 14-21 days seedlings were transferred to larger tanks with aerated solution where they remained until experimentation. We provide details of the protocol including composition of the basal growth solution, and separate solutions with altered calcium, magnesium, potassium or sodium supply whilst maintaining the activity of the majority of other ions. We demonstrate the adaptability of this system for: gas exchange measurement on single leaves and whole plants; qRT-PCR to probe the transcriptional response of roots or shoots to altered nutrient composition in the growth solution (we demonstrate this using high and low calcium supply); producing highly competent mesophyll protoplasts; and, accelerating the screening of Arabidopsis transformants. This system is also ideal for manipulating plants for micropipette techniques such as electrophysiology or SiCSA. Conclusions We present an optimised plant hydroponic culture system that can be quickly and cheaply constructed, and produces plants with similar

  15. Coupling technology for dual-purpose nuclear-desalting plants

    International Nuclear Information System (INIS)

    Jones, J.E. Jr.; Anderson, T.D.; Reed, S.A.

    1976-11-01

    Although the basic technology for the various components of nuclear dual-purpose plants is reasonably well developed, the techniques of coupling the elements together to form a reliable, economical system that will satisfy the diverse operating requirements are not well established. The purpose of the study reported is to examine the technical, economic, and safety considerations in coupling nuclear power plants with distillation units to form a dual-purpose power and water distillation plant. The basic coupling arrangement required to provide a large-scale dual-purpose water plant is to supply steam to the water plant from the exhaust of a back-pressure turbine. The principal component at the interface that may require major research and development is the back-pressure turbine. To satisfy the operational requirements, two major auxiliary systems will be needed. These are: (1) a prime-steam bypass system, and (2) auxiliary condensers. These systems will provide a degree of independence between water and power production and can be justified economically

  16. Nutrient supply of plants in aquaponic systems

    OpenAIRE

    Bittsánszky, András; Uzinger, Nikolett; Gyulai, Gábor; Mathis, Alex; Junge, Ranka; Villarroel, Morris; Kotzen, Benzion; Komives, Tamas

    2016-01-01

    In this preliminary article we present data on plant nutrient concentrations in aquaponic systems, and compare them to nutrient concentrations in “standard” hydroponic solutions. Our data shows that the nutrient concentrations supplied by the fish in aquaponic system are significantly lower for most nutrients, compared to hydroponic systems. Nevertheless, plants do thrive in solutions that have lower nutrient levels than “standard” hydroponic solutions. This is especially true for green leafy...

  17. Human factors: a major issue in plant aging

    International Nuclear Information System (INIS)

    Widrig, R.D.

    1985-07-01

    Human factors issues will be of great significance in the safe and reliable operation of aging nuclear power plants, and they may be more important than materials/component-type issues. Human actions can accelerate or decelerate te physical aging process. And an aging plant can have significant negative implications on staff performance and actions. Some examples include difficulties in attracting and retaining good managers, financial decisions based on a short and uncertain remaining plant life, difficulties in replacing retiring staff, increased maintenance complexity, and increased burden on training. These problems can be dealt with more effectively by early recognition and a well conceived mitigation effort

  18. Influence of in-plant air pollution control measures on power plant and system operation

    International Nuclear Information System (INIS)

    Kurten, H.

    1990-01-01

    The burning of fossil fuels causes the emission of air pollutants which have harmful environmental impact. Consequently many nations have in the last few years established regulations for air pollution control and have initiated the development and deployment of air pollution control systems in power plants. The paper describes the methods used for reducing particulate, SO 2 and NO x emissions, their application as backfit systems and in new plants, the power plant capacity equipped with such systems in the Federal Republic of Germany and abroad and the additional investment and operating costs incurred. It is to be anticipated that advanced power plant designs will produce lower pollutant emissions and less waste at enhanced efficiency levels. A comparison with power generation in nuclear power plants completes the first part of the paper. This paper covers the impact of the above-mentioned air pollution control measures on unit commitment in daily operation

  19. Use of expert systems in nuclear power plants

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1989-01-01

    The application of technologies, particularly expert systems, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, there are a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) in which expert systems can increase the efficiency and effectiveness of overall plant and corporate operations. This document presents a number of potential applications of expert systems in the nuclear power field. 36 refs., 2 tabs

  20. Fuel management of mixed reactor type power plant systems

    International Nuclear Information System (INIS)

    Csom, Gyula

    1988-01-01

    In equilibrium symbiotic power plant system containing both thermal reactors and fast breeders, excess plutonium produced by the fast breeders is used to enrich the fuel of the thermal reactors. In plutonium deficient symbiotic power plant system plutonium is supplied both by thermal plants and fast breeders. Mathematical models were constructed and different equations solved to characterize the fuel utilization of both systems if they contain only a single thermal type and a single fast type reactor. The more plutonium is produced in the system, the higher output ratio of thermal to fast reactors is achieved in equilibrium symbiotic power plant system. Mathematical equations were derived to calculate the doubling time and the breeding gain of the equilibrium symbiotic system. (V.N.) 2 figs.; 2 tabs

  1. System Definition and Analysis: Power Plant Design and Layout

    International Nuclear Information System (INIS)

    1996-01-01

    This is the Topical report for Task 6.0, Phase 2 of the Advanced Turbine Systems (ATS) Program. The report describes work by Westinghouse and the subcontractor, Gilbert/Commonwealth, in the fulfillment of completing Task 6.0. A conceptual design for critical and noncritical components of the gas fired combustion turbine system was completed. The conceptual design included specifications for the flange to flange gas turbine, power plant components, and balance of plant equipment. The ATS engine used in the conceptual design is an advanced 300 MW class combustion turbine incorporating many design features and technologies required to achieve ATS Program goals. Design features of power plant equipment and balance of plant equipment are described. Performance parameters for these components are explained. A site arrangement and electrical single line diagrams were drafted for the conceptual plant. ATS advanced features include design refinements in the compressor, inlet casing and scroll, combustion system, airfoil cooling, secondary flow systems, rotor and exhaust diffuser. These improved features, integrated with prudent selection of power plant and balance of plant equipment, have provided the conceptual design of a system that meets or exceeds ATS program emissions, performance, reliability-availability-maintainability, and cost goals

  2. Soil-to-Plant Transfer Factors of {sup 99}Tc for Korean Major Upland Crops

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong Ho; Lim, Kwang Muk; Jun, In; Keum, Dong Kwon [Korea Atomic Energy Reserach Institute, Daejeon (Korea, Republic of)

    2011-12-15

    In order to investigate the soil-to-plant transfer factor (TF) of {sup 99}Tc for Korean major upland crops (soybean, radish and Chinese cabbage), pot experiments were performed in a greenhouse. Soils were collected from four upland fields (two for soybean and two for radish and Chinese cabbage) around Gyeongju radioactive-waste disposal site. Three to four weeks before sowing, dried soils were mixed with a {sup 99}Tc solution and the mixtures were put into pots and irrigated. TF values were expressed as the ratios of the {sup 99}Tc concentrations in plants (Bq kg{sup -1}-dry or fresh) to those in soils (Bq kg{sup -1}-dry). There was no great difference in the TF value between soils. The TF values for soybean seeds were extremely lower than those for the straws, indicating a very low mobility of {sup 99}Tc to seeds. As representative TF values of{sup 99}Tc,1.8 X 10{sup -1}, 1.2 X 10{sup 1}, 3.2 X 10{sup 2} and 1.3 X 10{sup 2} (for dry plants), arithmetic means for two soils, were proposed for soybean seeds, radish roots, radish leaves and Chinese cabbage leaves, respectively. In the case of the vegetables, proposals for fresh plants were also made. The proposed values are not sufficiently representative so successive updates are needed.

  3. Investigation of human system interface design in nuclear power plant

    International Nuclear Information System (INIS)

    Feng Yan; Zhang Yunbo; Wang Zhongqiu

    2012-01-01

    The paper introduces the importance of HFE in designing nuclear power plant, and introduces briefly the content and scope of HFE, discusses human system interface design of new built nuclear power plants. This paper also describes human system interface design of foreign nuclear power plant, and describes in detail human system interface design of domestic nuclear power plant. (authors)

  4. Alternative majority-voting methods for real-time computing systems

    Science.gov (United States)

    Shin, Kang G.; Dolter, James W.

    1989-01-01

    Two techniques that provide a compromise between the high time overhead in maintaining synchronous voting and the difficulty of combining results in asynchronous voting are proposed. These techniques are specifically suited for real-time applications with a single-source/single-sink structure that need instantaneous error masking. They provide a compromise between a tightly synchronized system in which the synchronization overhead can be quite high, and an asynchronous system which lacks suitable algorithms for combining the output data. Both quorum-majority voting (QMV) and compare-majority voting (CMV) are most applicable to distributed real-time systems with single-source/single-sink tasks. All real-time systems eventually have to resolve their outputs into a single action at some stage. The development of the advanced information processing system (AIPS) and other similar systems serve to emphasize the importance of these techniques. Time bounds suggest that it is possible to reduce the overhead for quorum-majority voting to below that for synchronous voting. All the bounds assume that the computation phase is nonpreemptive and that there is no multitasking.

  5. Safety regulation KTA 3901: Communication systems for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    The regulation applies to communication systems in stationary nuclear power plants with at least one power plant unit, i.e. alarm systems, staff locator systems, communicators, and systems for external communication. The regulation determines the type and extent of staff communication systems as well as the demands to be made on layout, installation, operating systems, and testing of communication systems for nuclear power plants. (orig./HP) [de

  6. Logic verification system for power plant sequence diagrams

    International Nuclear Information System (INIS)

    Fukuda, Mitsuko; Yamada, Naoyuki; Teshima, Toshiaki; Kan, Ken-ichi; Utsunomiya, Mitsugu.

    1994-01-01

    A logic verification system for sequence diagrams of power plants has been developed. The system's main function is to verify correctness of the logic realized by sequence diagrams for power plant control systems. The verification is based on a symbolic comparison of the logic of the sequence diagrams with the logic of the corresponding IBDs (interlock Block Diagrams) in combination with reference to design knowledge. The developed system points out the sub-circuit which is responsible for any existing mismatches between the IBD logic and the logic realized by the sequence diagrams. Applications to the verification of actual sequence diagrams of power plants confirmed that the developed system is practical and effective. (author)

  7. Plant uptake of radiocaesium from artificially contaminated soil monoliths covering major European soil types

    International Nuclear Information System (INIS)

    Waegeneers, Nadia; Sauras-Yera, Teresa; Thiry, Yves; Vallejo, V. Ramon; Smolders, Erik; Madoz-Escande, Chantal; Brechignac, Francois

    2009-01-01

    Uptake of 137 Cs was measured in different agricultural plant species (beans, lettuce, barley and ryegrass) grown in 5 undisturbed soil monoliths covering major European soil types. The first cultivation was made three years after soil contamination and plants were grown during 3 successive years. The plant-soil 137 Cs transfer factors varied maximally 12-fold among soils and 35-fold among species when grown on the same soil. Single correlations between transfer factors and soil properties were found, but they varied widely with plant type and can hardly be used as a predictive tool because of the few soils used. The variation of 137 Cs concentrations in plants among soils was related to differences in soil solution 137 Cs and K concentrations, consistent with previous observations in hydroponics and pot trials. Absolute values of transfer factors could not be predicted based on a model validated for pot trials. The 137 Cs activity concentration in soil solution decreased significantly (11- to 250-fold) for most soils in the 1997-1999 period and is partly explained by decreasing K in soil solution. Transfer factors of lettuce showed both increasing and decreasing trends between 2 consecutive years depending on soil type. The trends could be explained by the variation in 137 Cs and K concentrations in soil solution. It is concluded that differences in 137 Cs transfer factors among soils and trends in transfer factors as a function of time can be explained from soil solution composition, as shown previously for pot trials, although absolute values of transfer factors could not be predicted.

  8. Methodological aspects of fuel performance system analysis at raw hydrocarbon processing plants

    Science.gov (United States)

    Kulbjakina, A. V.; Dolotovskij, I. V.

    2018-01-01

    The article discusses the methodological aspects of fuel performance system analysis at raw hydrocarbon (RH) processing plants. Modern RH processing facilities are the major consumers of energy resources (ER) for their own needs. To reduce ER, including fuel consumption, and to develop rational fuel system structure are complex and relevant scientific tasks that can only be done using system analysis and complex system synthesis. In accordance with the principles of system analysis, the hierarchical structure of the fuel system, the block scheme for the synthesis of the most efficient alternative of the fuel system using mathematical models and the set of performance criteria have been developed on the main stages of the study. The results from the introduction of specific engineering solutions to develop their own energy supply sources for RH processing facilities have been provided.

  9. RNA trafficking in parasitic plant systems

    Science.gov (United States)

    LeBlanc, Megan; Kim, Gunjune; Westwood, James H.

    2012-01-01

    RNA trafficking in plants contributes to local and long-distance coordination of plant development and response to the environment. However, investigations of mobile RNA identity and function are hindered by the inherent difficulty of tracing a given molecule of RNA from its cell of origin to its destination. Several methods have been used to address this problem, but all are limited to some extent by constraints associated with accurately sampling phloem sap or detecting trafficked RNA. Certain parasitic plant species form symplastic connections to their hosts and thereby provide an additional system for studying RNA trafficking. The haustorial connections of Cuscuta and Phelipanche species are similar to graft junctions in that they are able to transmit mRNAs, viral RNAs, siRNAs, and proteins from the host plants to the parasite. In contrast to other graft systems, these parasites form connections with host species that span a wide phylogenetic range, such that a high degree of nucleotide sequence divergence may exist between host and parasites and allow confident identification of most host RNAs in the parasite system. The ability to identify host RNAs in parasites, and vice versa, will facilitate genomics approaches to understanding RNA trafficking. This review discusses the nature of host–parasite connections and the potential significance of host RNAs for the parasite. Additional research on host–parasite interactions is needed to interpret results of RNA trafficking studies, but parasitic plants may provide a fascinating new perspective on RNA trafficking. PMID:22936942

  10. RNA trafficking in parasitic plant systems

    Directory of Open Access Journals (Sweden)

    Megan L LeBlanc

    2012-08-01

    Full Text Available RNA trafficking in plants contributes to local and long-distance coordination of plant development and response to the environment. However, investigations of mobile RNA identity and function are hindered by the inherent difficulty of tracing a given molecule of RNA from its cell of origin to its destination. Several methods have been used to address this problem, but all are limited to some extent by constraints associated with accurately sampling phloem sap or detecting trafficked RNA. Certain parasitic plant species form symplastic connections to their hosts and thereby provide an additional system for studying RNA trafficking. The haustorial connections of Cuscuta and Phelipanche species are similar to graft junctions in that they are able to transmit mRNAs, viral RNAs, siRNAs and proteins from the host plants to the parasite. In contrast to other graft systems, these parasites form connections with host species that span a wide phylogenetic range, such that a high degree of nucleotide sequence divergence may exist between host and parasites and allow confident identification of most host RNAs in the parasite system. The ability to identify host RNAs in parasites, and vice versa, will facilitate genomics approaches to understanding RNA trafficking. This review discusses the nature of host parasite connections and the potential significance of host RNAs for the parasite. Additional research on host-parasite interactions is needed to interpret results of RNA trafficking studies, but parasitic plants may provide a fascinating new perspective on RNA trafficking.

  11. Nuclear plant-aging research on reactor protection systems

    International Nuclear Information System (INIS)

    Meyer, L.C.

    1988-01-01

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed

  12. L-Py: an L-System simulation framework for modeling plant development based on a dynamic language

    Directory of Open Access Journals (Sweden)

    Frederic eBoudon

    2012-05-01

    Full Text Available The study of plant development requires increasingly powerful modeling tools to help understand and simulate the growth and functioning of plants. In the last decade, the formalism of L-systems has emerged as a major paradigm for modeling plant development. Previous implementations of this formalism were made based on static languages, i.e. languages that require explicit definition of variable types before using them. These languages are often efficient but involve quite a lot of syntactic overhead, thus restricting the flexibility of use for modelers. In this work, we present an adaptation of L-systems to the Python language, a popular and powerful open-license dynamic language. We show that the use of dynamic language properties makes it possible to enhance the development of plant growth models: i by keeping a simple syntax while allowing for high-level programming constructs, ii by making code execution easy and avoiding compilation overhead iii allowing a high level of model reusability and the building of complex modular models iv and by providing powerful solutions to integrate MTG data-structures (that are a common way to represent plants at several scales into L-systems and thus enabling to use a wide spectrum of computer tools based on MTGs developed for plant architecture. We then illustrate the use of L-Py in real applications to build complex models or to teach plant modeling in the classroom.

  13. A study on the efficiency improvement of the plant secondary System in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chun Ho; Song Jong Sun [Chosun Univ., Kwangju (Korea, Republic of)

    2012-10-15

    The ultimate objective of the diagnostic test for thermal performance of generation facilities is to assist in making an economic decision on operation optimization of power plants by understanding the degree of heat aging due to operation of relevant facilities and planning on this basis the maintenance and repair. In this thesis, the trend in performance change was analyzed against the acceptance performance test conducted after the replacement of the high pressure turbine in 2007, through thermal performance diagnosis conducted at 100 % reactor thermal output after the 19th planned preventive maintenance of Yonggwang Nuclear Units 1 and 2, and the power plant operation was optimized by acquiring base line data for management of performance record for each major facility of the secondary system and by improving efficiency of unit instruments and peripheral instruments of the secondary system. As a result derived from the thermal performance analysis, the increase in electric output of the power plants was achieved through such operation optimizations of efficiency affecting instruments as optimization of the continuous exhaust flow rate for water supply heaters, vacuum improvement of condensers due to opening the upper/lower screens of heat transfer pipe washing system for condensers during summer, and flow rate optimization of the water vapor supplied to MSR (Moisture Separator Re heater) high pressure re heaters. This improves operation of the existing power plants without additional expense and so requires expert review by responsible personnel for practical application.

  14. A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

    International Nuclear Information System (INIS)

    Yang, Y. K.; Jung, Y. D.; Kim, S. Y.

    1991-12-01

    The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system

  15. A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Y K; Jung, Y D; Kim, S Y [Korea Institute of Science and Technology, Seoul (Korea, Republic of)

    1991-12-15

    The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system.

  16. System 80+ integrated design of a complete plant

    International Nuclear Information System (INIS)

    Turk, R.S.; Stamm, S.L.; Fox, W.A.

    1992-01-01

    In 1985, ABB-Combustion Engineering Nuclear Power (ABB-CENP) and elements of Duke Power Company [now Duke Engineering ampersand Services (DE ampersand S)] joined forces under the aegis of the Electric Power Research Institute (EPRI) Advanced Light Water Reactor (ALWR) Program to develop, with the sponsoring utilities, the design requirements for the next generation of nuclear power plants. With support from the US Department of Energy, ABB-CENP and DE ampersand S again teamed up the following year to initiate a project to design and license the System 80+ standard plant design, an advanced pressurized water reactor that meets these utility requirements. A distinguishing feature of the System 80+ standard design is that it is an essentially complete plant, predesigned and prelicensed to ensure rapid and economical construction. This is in stark contrast to typical prior conduct, where the reactor vendor offered only the nuclear steam supply system and the plant was built on a design-as-you-go basis with constant pressure to release individual elements of the plant design for construction or procurement as soon as possible. Now, however, the design process can be integrated over the total plant, ensuring that the goals set for ALWRs can be met. This integrated design process is manifested in several ways: (1) broad-based participation during the design process by involving designers, analysts, suppliers, constructors, and operators; (2) use of probabilistic risk assessment (PRA) as a design tool to aid in evaluating design features on a total-plant basis; (3) application of human factors engineering methods to a total plant distributed control system to improve the human-machine interface in the design; and (4) use of computer-aided design to enhance assessment of interactions and impacts of all aspects of the total plant. Each of these aspects of integrated plant design is discussed in this paper

  17. State-of-art report on digital I and C system reliability issues for nuclear power plants

    International Nuclear Information System (INIS)

    Hwang, In Koo; Lee, Dong Gyoung; Cha, Kyung Ho; Kwon, Kee Choon; Wood, Richard T.

    2000-01-01

    As the instrumentation and control (Iand C) equipment suppliers tend to provide digital components rather than conventional analog type components for instrument and control systems of nuclear power plants(NPPs), it is unavoidable to adopt digital equipment for safety I and C systems as well as non-safety systems. However, the full introduction of digital equipment to I and C systems of nuclear power plants raises several concerns which have not been considered for conventional analog I and C systems. The two major examples of the issues of digital systems are electromagnetic compatibility (EMC) and software reliability. KAERI invited a technical expert, Dr. Richard T. Wood, from Oak Ridge National Laboratory (ORNL) in Unites States and held seminars to recognize the state-of-art of the above issues and to share the information on techniques dealing with the problems. Dr. Wood has been working on the development of EMC guidelines and technical basis in using digital equipment for safety systems in nuclear power plants on the sponsorship of US Nuclear Regulatory Commission (NRC). Being based on his statements and discussions during his visit, this report describes technical considerations and issues on digital safety I and C system application in NPPs, EMC methods, environmental effects vulnerable to digital components, reliability assurance methods, etc. (author)

  18. 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)

  19. A knowledge based system for plant diagnosis

    International Nuclear Information System (INIS)

    Motoda, H.; Yamada, N.; Yoshida, K.

    1984-01-01

    A knowledge based system for plant diagnosis is proposed in which both event-oriented and function-oriented knowledge are used. For the proposed system to be of practical use, these two types of knowledge are represented by mutually nested four frames, i.e. the component, causality, criteriality, and simulator frames, and production rules. The system provides fast inference capability for use as both a production system and a formal reasoning system, with uncertainty of knowledge taken into account in the former. Event-oriented knowledge is used in both diagnosis and guidance and function-oriented knowledge, in diagnosis only. The inference capability required is forward chaining in the former and resolution in the latter. The causality frame guides in the use of event-oriented knowledge, whereas the criteriality frame does so for function-oriented knowledge. Feedback nature of the plant requires the best first search algorithm that uses histories in the resolution process. The inference program is written in Lisp and the plant simulator and the process I/O control programs in Fortran. Fast data transfer between these two languages is realized by enhancing the memory management capability of Lisp to control the numerical data in the global memory. Simulation applications to a BWR plant demonstrated its diagnostic capability

  20. Estimation of reliability on digital plant protection system in nuclear power plants using fault simulation with self-checking

    International Nuclear Information System (INIS)

    Lee, Jun Seok; Kim, Suk Joon; Seong, Poong Hyun

    2004-01-01

    Safety-critical digital systems in nuclear power plants require high design reliability. Reliable software design and accurate prediction methods for the system reliability are important problems. In the reliability analysis, the error detection coverage of the system is one of the crucial factors, however, it is difficult to evaluate the error detection coverage of digital instrumentation and control system in nuclear power plants due to complexity of the system. To evaluate the error detection coverage for high efficiency and low cost, the simulation based fault injections with self checking are needed for digital instrumentation and control system in nuclear power plants. The target system is local coincidence logic in digital plant protection system and a simplified software modeling for this target system is used in this work. C++ based hardware description of micro computer simulator system is used to evaluate the error detection coverage of the system. From the simulation result, it is possible to estimate the error detection coverage of digital plant protection system in nuclear power plants using simulation based fault injection method with self checking. (author)

  1. Activities at the electric power research institute to support the modernization of instrumentation and control systems in nuclear power plants in the United States of America

    International Nuclear Information System (INIS)

    Naser, J.

    1998-01-01

    Most nuclear power plants in the United States are operating with a vast majority of their original analog instrumentation and control (I and C) equipment. Many of the I and C systems in the plants need to be modernized in a reliable and cost-effective manner to replace obsolete equipment, to reduce operating and maintenance (O and M) costs, to improve plant performance, and to maintain safety. The major drivers for the replacement of the safety, control, and information systems in nuclear power plants are the obsolescence of the existing hardware and the need for more cost-effective power production. Competition between power producers is dictating the need for more cost-effective power production. The increasing O and M costs to maintain systems experiencing obsolescence problems is counter to the needs for more cost-effective power production and improved competitiveness. Modern technology, especially digital systems, offers improved functionality, performance, and reliability; solutions to obsolescence of equipment; reduction in O and M costs, and the potential to enhance safety. Digital I and C systems with their inherent advantages will be implemented only if reliable and cost-effective implementation and licensing acceptance is achieved and if the modernized system supports reduced power production costs. Increasing competition will continue to be a major factor in the operation of nuclear power plants. I will continue to dictate the need for improved productivity and cost-effectiveness. EPRI and its members utilities are working together on an industry-wide Instrumentation and Control Program to address I and C issues and to develop cost-effective solutions. (author)

  2. EDGAR, a new plant radiation monitoring system

    International Nuclear Information System (INIS)

    Vuong, Q.M.; Da Costa Vieira, D.

    2004-01-01

    The EDGAR system is a new radiation monitoring system for nuclear power plant, reprocessing plant and nuclear research reactor for radioactive contamination, gamma and neutron field monitoring. Developed by French Atomic Energy Agency, this system provides not only complete functions of standard RMS, also allows spectroscopy level detection of alpha and beta particles based on a patented collimator unit. A complete computerized approach has been taken allowing full installation control in a single PC based display and communication unit. (author)

  3. Why Are Students Not Majoring in Information Systems?

    Science.gov (United States)

    Walstrom, Kent A.; Schambach, Thomas P.; Jones, Keith T.; Crampton, William J.

    2008-01-01

    The purpose of this study was to examine some of the factors that influence and impact business students when they select their major and, more particularly, to examine why students are not majoring in information systems. Students in an entry level business class responded that they were more knowledgeable about careers in management, marketing,…

  4. Development of a knowledge-based information management system for plant maintenance

    International Nuclear Information System (INIS)

    Yim, Hyung Sang; Park, Young Jae; Lee, Sang Min; Choi, Jae Boong; Kim, Young Jin; Roh, Eun Chul; Lee, Byung Ine

    2003-01-01

    Recently, the importance of Plant Maintenance(PM) was highly raised to provide efficient plant operation which highly affects the productivity. For this reason, a number of engineering methodologies, such as Risk-Based Inspection(RBI), Fitness For Service guidelines(FFS), Plant Lifecycle Management(PLM), have been applied to improve the plant operation efficiency. Also, a network-based business operation system, which is called ERP(Enterprise Resource Planning), has been introduced in the field of plant maintenance. However, there was no attempt to connect engineering methodologies to the ERP PM system. In this paper, a knowledge-based information system for the plant operation of steel making company has been proposed. This system, which is named as K-VRS(Knowledge-based Virtual Reality System), provides a connection between ERP plant maintenance module and knowledge-based engineering methodologies, and thus, enables network-based highly effective plant maintenance process. The developed system is expected to play a great role for more efficient and safer plant maintenance

  5. Development of a knowledge-based information management system for plant maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Yim, Hyung Sang; Park, Young Jae; Lee, Sang Min; Choi, Jae Boong; Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Roh, Eun Chul; Lee, Byung Ine [Pohang Iron and Steel Company, Pohang (Korea, Republic of)

    2003-07-01

    Recently, the importance of Plant Maintenance(PM) was highly raised to provide efficient plant operation which highly affects the productivity. For this reason, a number of engineering methodologies, such as Risk-Based Inspection(RBI), Fitness For Service guidelines(FFS), Plant Lifecycle Management(PLM), have been applied to improve the plant operation efficiency. Also, a network-based business operation system, which is called ERP(Enterprise Resource Planning), has been introduced in the field of plant maintenance. However, there was no attempt to connect engineering methodologies to the ERP PM system. In this paper, a knowledge-based information system for the plant operation of steel making company has been proposed. This system, which is named as K-VRS(Knowledge-based Virtual Reality System), provides a connection between ERP plant maintenance module and knowledge-based engineering methodologies, and thus, enables network-based highly effective plant maintenance process. The developed system is expected to play a great role for more efficient and safer plant maintenance.

  6. The major importance of 'minor' resources: Women and plant biodiversity

    NARCIS (Netherlands)

    Howard, P.L.

    2003-01-01

    Understanding women’s influence on plant biodiversity is essential to our ability to conserve plant genetic resources, especially those plants that are useful to humans. Contrary to previous thinking, it is becoming clear that women know most about these plants because, throughout history, women’s

  7. Simulated coal gas MCFC power plant system verification. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-30

    The objective of the main project is to identify the current developmental status of MCFC systems and address those technical issues that need to be resolved to move the technology from its current status to the demonstration stage in the shortest possible time. The specific objectives are separated into five major tasks as follows: Stack research; Power plant development; Test facilities development; Manufacturing facilities development; and Commercialization. This Final Report discusses the M-C power Corporation effort which is part of a general program for the development of commercial MCFC systems. This final report covers the entire subject of the Unocal 250-cell stack. Certain project activities have been funded by organizations other than DOE and are included in this report to provide a comprehensive overview of the work accomplished.

  8. CANDU 9 operator plant display system

    International Nuclear Information System (INIS)

    Trueman, R.; Webster, A.; MacBeth, M.J.

    1997-01-01

    To meet evolving client and regulatory needs, AECL has adopted an evolutionary approach to the design of the CANDU 9 control centre. That is, the design incorporates feedback from existing stations, reflects the growing diversity in the roles and responsibilities of the operating staff, and reduces costs associated with plant capital and operations, maintenance and administration (OM and A), through the appropriate introduction of new technologies. Underlying this approach is a refined engineering design process that cost-effectively integrates operational feedback and human factors engineering to define the operating staff information and information presentation requirements. Based on this approach, the CANDU 9 control centre will provide utility operating staff with the means to achieve improved operations and reduced OM and A costs. One of the design features that will contribute to the improved operational capabilities of the control centre is a new Plant Display System (PDS) that is separate from the digital control system. The PDS will be used to implement non-safety panel, and console video display systems within the CANDU 9 main control room (MCR). This paper presents a detailed description of the CANDU 9 Plant Display System and features that provide increased operational capabilities. (author)

  9. Integrated monitoring of wind plant systems

    Science.gov (United States)

    Whelan, Matthew J.; Janoyan, Kerop D.; Qiu, Tong

    2008-03-01

    Wind power is a renewable source of energy that is quickly gaining acceptance by many. Advanced sensor technologies have currently focused solely on improving wind turbine rotor aerodynamics and increasing of the efficiency of the blade design and concentration. Alternatively, potential improvements in wind plant efficiency may be realized through reduction of reactionary losses of kinetic energy to the structural and substructural systems supporting the turbine mechanics. Investigation of the complete dynamic structural response of the wind plant is proposed using a large-scale, high-rate wireless sensor network. The wireless network enables sensors to be placed across the sizable structure, including the rotating blades, without consideration of cabling issues and the economic burden associated with large spools of measurement cables. A large array of multi-axis accelerometers is utilized to evaluate the modal properties of the system as well as individual members and would enable long-term structural condition monitoring of the wind turbine as well. Additionally, environmental parameters, including wind speed, temperature, and humidity, are wirelessly collected for correlation. Such a wireless system could be integrated with electrical monitoring sensors and actuators and incorporated into a remote multi-turbine centralized plant monitoring and control system.

  10. Chitosan Effects on Plant Systems

    Directory of Open Access Journals (Sweden)

    Massimo Malerba

    2016-06-01

    Full Text Available Chitosan (CHT is a natural, safe, and cheap product of chitin deacetylation, widely used by several industries because of its interesting features. The availability of industrial quantities of CHT in the late 1980s enabled it to be tested in agriculture. CHT has been proven to stimulate plant growth, to protect the safety of edible products, and to induce abiotic and biotic stress tolerance in various horticultural commodities. The stimulating effect of different enzyme activities to detoxify reactive oxygen species suggests the involvement of hydrogen peroxide and nitric oxide in CHT signaling. CHT could also interact with chromatin and directly affect gene expression. Recent innovative uses of CHT include synthesis of CHT nanoparticles as a valuable delivery system for fertilizers, herbicides, pesticides, and micronutrients for crop growth promotion by a balanced and sustained nutrition. In addition, CHT nanoparticles can safely deliver genetic material for plant transformation. This review presents an overview on the status of the use of CHT in plant systems. Attention was given to the research that suggested the use of CHT for sustainable crop productivity.

  11. Guiding rules for development of intelligent monitoring system of nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, M.; Furukawa, H.; Kozma, R.; Washio, T.

    1996-01-01

    General frameworks and major component techniques for intelligent monitoring of nuclear power plants are presented. The key concept, diversity-based design, is to provide advisory information through consensus of multiple agents, each performing operational decision-making by focusing on mutually different information obtained from the plant. The multi-agent design scheme allows to attain high credibility and tolerance against sensor failure in fault detection and causal reasoning. The advantage of the proposed scheme realized by multiple neural networks was clearly demonstrated through numerical experiments with anomalies in a pressurized water reactor. Relevant techniques are also introduced for diagnostic information evaluation in specified symptoms, and for remedial procedure synthesis. A new architecture for future implementation of the proposed scheme, worm-type multi-agent system, is also proposed as a promising candidate. (author)

  12. Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessel internals

    International Nuclear Information System (INIS)

    2005-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and ware out of components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of heavy water moderated reactors (HWRs), boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

  13. Virtual medical plant modeling based on L-system | Ding | African ...

    African Journals Online (AJOL)

    ... aid of graphics and PlantVR, we implemented the plant shape and 3-D structure's reconstruction. Conclusion: Three-dimensional structure virtual plant growth model based on time- controlled L-system has been successfully established. Keywords: Drug R&D, toxicity, medical plants, fractals; L-system; quasi binary-trees.

  14. Qualification of safety-critical software for digital reactor safety system in nuclear power plants

    International Nuclear Information System (INIS)

    Kwon, Kee-Choon; Park, Gee-Yong; Kim, Jang-Yeol; Lee, Jang-Soo

    2013-01-01

    This paper describes the software qualification activities for the safety-critical software of the digital reactor safety system in nuclear power plants. The main activities of the software qualification processes are the preparation of software planning documentations, verification and validation (V and V) of the software requirements specifications (SRS), software design specifications (SDS) and codes, and the testing of the integrated software and integrated system. Moreover, the software safety analysis and software configuration management are involved in the software qualification processes. The V and V procedure for SRS and SDS contains a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and an evaluation of the software configuration management. The V and V processes for the code are a traceability analysis, source code inspection, test case and test procedure generation. Testing is the major V and V activity of the software integration and system integration phases. The software safety analysis employs a hazard operability method and software fault tree analysis. The software configuration management in each software life cycle is performed by the use of a nuclear software configuration management tool. Through these activities, we can achieve the functionality, performance, reliability, and safety that are the major V and V objectives of the safety-critical software in nuclear power plants. (author)

  15. Systems and synthetic biology approaches to alter plant cell walls and reduce biomass recalcitrance.

    Science.gov (United States)

    Kalluri, Udaya C; Yin, Hengfu; Yang, Xiaohan; Davison, Brian H

    2014-12-01

    Fine-tuning plant cell wall properties to render plant biomass more amenable to biofuel conversion is a colossal challenge. A deep knowledge of the biosynthesis and regulation of plant cell wall and a high-precision genome engineering toolset are the two essential pillars of efforts to alter plant cell walls and reduce biomass recalcitrance. The past decade has seen a meteoric rise in use of transcriptomics and high-resolution imaging methods resulting in fresh insights into composition, structure, formation and deconstruction of plant cell walls. Subsequent gene manipulation approaches, however, commonly include ubiquitous mis-expression of a single candidate gene in a host that carries an intact copy of the native gene. The challenges posed by pleiotropic and unintended changes resulting from such an approach are moving the field towards synthetic biology approaches. Synthetic biology builds on a systems biology knowledge base and leverages high-precision tools for high-throughput assembly of multigene constructs and pathways, precision genome editing and site-specific gene stacking, silencing and/or removal. Here, we summarize the recent breakthroughs in biosynthesis and remodelling of major secondary cell wall components, assess the impediments in obtaining a systems-level understanding and explore the potential opportunities in leveraging synthetic biology approaches to reduce biomass recalcitrance. Published 2014. This article is a U.S. Government work and is in the public domain in the USA. Plant Biotechnology Journal published by Society for Experimental Biology and The Association of Applied Biologists and John Wiley & Sons Ltd.

  16. Optimization of operation for combined heat and power plants - CHP plants - with heat accumulators using a MILP formulation

    Energy Technology Data Exchange (ETDEWEB)

    Grue, Jeppe; Bach, Inger [Aalborg Univ. (Denmark). Inst. of Energy Technology]. E-mails: jeg@iet.auc.dk; ib@iet.auc.dk

    2000-07-01

    The power generation system in Denmark is extensively based on small combined heat and power plants (CHP plants), producing both electricity and district heating. This project deals with smaller plants spread throughout the country. Often a heat accumulator is used to enable electricity production, even when the heat demand is low. This system forms a very complex problem, both for sizing, designing and operation of CHP plants. The objective of the work is the development of a tool for optimisation of the operation of CHP plants, and to even considering the design of the plant. The problem is formulated as a MILP-problem. An actual case is being tested, involving CHP producing units to cover the demand. The results from this project show that it is of major importance to consider the operation of the plant in detail already in the design phase. It is of major importance to consider the optimisation of the plant operation, even at the design stage, as it may cause the contribution margin to rise significantly, if the plant is designed on the basis of a de-tailed knowledge of the expected operation. (author)

  17. Salmonella enterica Induces And Subverts The Plant Immune System

    Directory of Open Access Journals (Sweden)

    Ana Victoria Garcia

    2014-04-01

    Full Text Available Infections with Salmonella enterica belong to the most prominent causes of food poisoning and infected fruits and vegetables represent important vectors for salmonellosis. Whereas it was shown that plants raise defense responses against Salmonella, these bacteria persist and proliferate in various plant tissues. Recent reports shed light into the molecular interaction between plants and Salmonella, highlighting the defense pathways induced and the means used by the bacteria to escape the plant immune system and accomplish colonization. It was recently shown that plants detect Salmonella pathogen-associated molecular patterns (PAMPs, such as the flagellin peptide flg22, and activate hallmarks of the defense program known as PAMP-triggered immunity (PTI. Interestingly, certain Salmonella strains carry mutations in the flg22 domain triggering PTI, suggesting that a strategy of Salmonella is to escape plant detection by mutating PAMP motifs. Another strategy may rely on the type III secretion system (T3SS as T3SS mutants were found to induce stronger plant defense responses than wild type bacteria. Although Salmonella effector delivery into plant cells has not been shown, expression of Salmonella effectors in plant tissues shows that these bacteria also possess powerful means to manipulate the plant immune system. Altogether, the data gathered suggest that Salmonella triggers PTI in plants and evolved strategies to avoid or subvert plant immunity.

  18. Salmonella enterica induces and subverts the plant immune system

    KAUST Repository

    García, Ana V.

    2014-04-04

    Infections with Salmonella enterica belong to the most prominent causes of food poisoning and infected fruits and vegetables represent important vectors for salmonellosis. Although it was shown that plants raise defense responses against Salmonella, these bacteria persist and proliferate in various plant tissues. Recent reports shed light into the molecular interaction between plants and Salmonella, highlighting the defense pathways induced and the means used by the bacteria to escape the plant immune system and accomplish colonization. It was recently shown that plants detect Salmonella pathogen-associated molecular patterns (PAMPs), such as the flagellin peptide flg22, and activate hallmarks of the defense program known as PAMP-triggered immunity (PTI). Interestingly, certain Salmonella strains carry mutations in the flg22 domain triggering PTI, suggesting that a strategy of Salmonella is to escape plant detection by mutating PAMP motifs. Another strategy may rely on the type III secretion system (T3SS) as T3SS mutants were found to induce stronger plant defense responses than wild type bacteria. Although Salmonella effector delivery into plant cells has not been shown, expression of Salmonella effectors in plant tissues shows that these bacteria also possess powerful means to manipulate the plant immune system. Altogether, these data suggest that Salmonella triggers PTI in plants and evolved strategies to avoid or subvert plant immunity. 2014 Garca and Hirt.

  19. Nuclear plant engineering work and integrated management system

    International Nuclear Information System (INIS)

    Ohkubo, Y.; Obata, T.; Tanaka, K.

    1992-01-01

    The Application of computers to the design, engineering, manufacturing and construction works of nuclear power plants has greatly contributed to improvement of productivity and reliability in the nuclear power plants constructed by Mitsubishi Nuclear Group for more than ten years. However, in most cases, those systems have been developed separately and utilized independently in different computer software and hardware environments and have not been fully utilized to achieve high efficiency and reliability. In order to drastically increase the productivity and efficiency, development of NUclear power plant engineering Work and INtegrated manaGement System (NUWINGS) started in 1987 to unify and integrate various conventional and developing systems using the state-of-the-art computer technology. The NUWINGS is almost completed and is now applied to actual plant construction. (author)

  20. Dynamic modelling of balance of plant systems for a pulsed DEMO power plant

    Energy Technology Data Exchange (ETDEWEB)

    Harrington, C., E-mail: Chris.Harrington@ccfe.ac.uk

    2015-10-15

    Highlights: • A fully dynamic model of the balance of plant systems for pulsed DEMO is presented. • An operating strategy for handling pulse/dwell transitions has been devised. • Operation of a water-cooled system without energy storage appears feasible. • Steam turbine cycling can be minimised if rotation speed is maintained. - Abstract: The current baseline concept for a European DEMO defines a pulsed reactor producing power for periods of 2–4 h at a time, interrupted by dwell periods of approximately half an hour, potentially leading to cyclic fatigue of the heat transfer system and power generation equipment. Thermal energy storage systems could mitigate pulsing issues; however, the requirements for such a system cannot be defined without first understanding the challenges for pulsed operation, while any system will simultaneously increase the cost and complexity of the balance of plant. This work therefore presents a dynamic model of the primary heat transfer system and associated steam plant for a water-cooled DEMO, without energy storage, capable of simulating pulsed plant operation. An operating regime is defined such that the primary coolant flows continuously throughout the dwell period while the secondary steam flow is reduced. Simulation results show minimised thermal and pressure transients in the primary circuit, and small thermally induced stresses on the steam turbine rotor. If the turbine can be kept spinning to also minimise mechanical cycling, pulsed operation of a water-cooled DEMO without thermal energy storage may be feasible.

  1. Diagnostic system for combine cycle power plant

    International Nuclear Information System (INIS)

    Shimizu, Yujiro; Nomura, Masumi; Tanaka, Satoshi; Ito, Ryoji; Kita, Yoshiyuki

    2000-01-01

    We developed the Diagnostic System for Combined Cycle Power Plant which enables inexperienced operators as well as experienced operators to cope with abnormal conditions of Combined Cycle Power Plant. The features of this system are the Estimate of Emergency Level for Operation and the Prediction of Subsequent Abnormality, adding to the Diagnosis of Cause and the Operation Guidance. Moreover in this system, Diagnosis of Cause was improved by using our original method and support screens can be displayed for educational means in normal condition as well. (Authors)

  2. The Development of Plant Maintenance Scheduling Via lnventory System for Sustainable Plant Operation

    Directory of Open Access Journals (Sweden)

    Masripan Roslizan

    2016-01-01

    Full Text Available Industrial sector becomes the main concern for developing country. By the time, it was increased rapidly. However, there are many problems observed such as maintenance scheduling, stock inventory and supply chain. Therefore, this research develops new inventory system to develop sustainable plant operation with a high capability to plant operation especially to stock inventory of machine component. In also required green application with minimised used on paper. This system is developed using Radio Frequency Identification (RFID for inventory control which integrated with web-based system. This system consists of several modules such as station module, item module and item request module and report of critical stock in the store. This system can be controlled from a hand-phone with internet connection or automatic alert such as Short Massage Send (SMS and email. The developed system is very effective in monitoring the stock material through the barcode, supply chain and worker performance as well as to reduce the lead time for maintenance activities of the company through sustainable plant operation.

  3. Increased light-use efficiency sustains net primary productivity of shaded coffee plants in agroforestry system.

    Science.gov (United States)

    Charbonnier, Fabien; Roupsard, Olivier; le Maire, Guerric; Guillemot, Joannès; Casanoves, Fernando; Lacointe, André; Vaast, Philippe; Allinne, Clémentine; Audebert, Louise; Cambou, Aurélie; Clément-Vidal, Anne; Defrenet, Elsa; Duursma, Remko A; Jarri, Laura; Jourdan, Christophe; Khac, Emmanuelle; Leandro, Patricia; Medlyn, Belinda E; Saint-André, Laurent; Thaler, Philippe; Van Den Meersche, Karel; Barquero Aguilar, Alejandra; Lehner, Peter; Dreyer, Erwin

    2017-08-01

    In agroforestry systems, shade trees strongly affect the physiology of the undergrown crop. However, a major paradigm is that the reduction in absorbed photosynthetically active radiation is, to a certain extent, compensated by an increase in light-use efficiency, thereby reducing the difference in net primary productivity between shaded and non-shaded plants. Due to the large spatial heterogeneity in agroforestry systems and the lack of appropriate tools, the combined effects of such variables have seldom been analysed, even though they may help understand physiological processes underlying yield dynamics. In this study, we monitored net primary productivity, during two years, on scales ranging from individual coffee plants to the entire plot. Absorbed radiation was mapped with a 3D model (MAESPA). Light-use efficiency and net assimilation rate were derived for each coffee plant individually. We found that although irradiance was reduced by 60% below crowns of shade trees, coffee light-use efficiency increased by 50%, leaving net primary productivity fairly stable across all shade levels. Variability of aboveground net primary productivity of coffee plants was caused primarily by the age of the plants and by intraspecific competition among them (drivers usually overlooked in the agroforestry literature) rather than by the presence of shade trees. © 2017 John Wiley & Sons Ltd.

  4. Plant uptake of radiocaesium from artificially contaminated soil monoliths covering major European soil types

    Energy Technology Data Exchange (ETDEWEB)

    Waegeneers, Nadia [Laboratory for Soil and Water Management, Katholieke Universiteit Leuven, Kasteelpark Arenberg 20, B-3001 Heverlee (Belgium)], E-mail: nadia.waegeneers@agr.kuleuven.ac.be; Sauras-Yera, Teresa [Departament de Biologia Vegetal, Universitat de Barcelona, Av. Diagonal 645, 08028 Barcelona (Spain); Thiry, Yves [SCK.CEN, Radioecology Laboratory, Boeretang 200, B-2400 Mol (Belgium); Vallejo, V. Ramon [Departament de Biologia Vegetal, Universitat de Barcelona, Av. Diagonal 645, 08028 Barcelona (Spain); CEAM, Parque Tecnologico, Charles Darwin 14, 46980 Parterna (Spain); Smolders, Erik [Laboratory for Soil and Water Management, Katholieke Universiteit Leuven, Kasteelpark Arenberg 20, B-3001 Heverlee (Belgium); Madoz-Escande, Chantal; Brechignac, Francois [SERLAB, ISPN, Department for Environmental Protection, CE-Cadarache Batiment 159, Saint-Paul-lez-Durance Cedex 13108 (France)

    2009-06-15

    Uptake of {sup 137}Cs was measured in different agricultural plant species (beans, lettuce, barley and ryegrass) grown in 5 undisturbed soil monoliths covering major European soil types. The first cultivation was made three years after soil contamination and plants were grown during 3 successive years. The plant-soil {sup 137}Cs transfer factors varied maximally 12-fold among soils and 35-fold among species when grown on the same soil. Single correlations between transfer factors and soil properties were found, but they varied widely with plant type and can hardly be used as a predictive tool because of the few soils used. The variation of {sup 137}Cs concentrations in plants among soils was related to differences in soil solution {sup 137}Cs and K concentrations, consistent with previous observations in hydroponics and pot trials. Absolute values of transfer factors could not be predicted based on a model validated for pot trials. The {sup 137}Cs activity concentration in soil solution decreased significantly (11- to 250-fold) for most soils in the 1997-1999 period and is partly explained by decreasing K in soil solution. Transfer factors of lettuce showed both increasing and decreasing trends between 2 consecutive years depending on soil type. The trends could be explained by the variation in {sup 137}Cs and K concentrations in soil solution. It is concluded that differences in {sup 137}Cs transfer factors among soils and trends in transfer factors as a function of time can be explained from soil solution composition, as shown previously for pot trials, although absolute values of transfer factors could not be predicted.

  5. 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

  6. Plant inspection tours with mobile data logging system

    International Nuclear Information System (INIS)

    Roesser, U.

    2006-01-01

    The MDE Mobile Data Logging System has been introduced in a number of German power plants for efficient logging, evaluation, and quality-assured documentation of data recorded on plant inspection tours by means of pocket PCs instead of slips of paper. It will be installed in other nuclear power plants in the near future. The MDE system is composed of the pocket PCs for logging data during plant inspection tours, the associated docking stations installed in the respective areas of application, one PC or, if necessary, several PCs with the appropriate user software, and the associated network links. To install the software in the power plant, lists of rooms and measurement stations as well as other positions on an inspection course are transmitted to the MDE system. When the system has been commissioned, inspection tours are planned in accordance with past experience and optimized in the computer. User experience is taken into account in program updates. New functions improve user comfort and ease of evaluation. Additions to the MDE software, and applications in other areas, are tentatively planned and will be implemented as the need arises. (orig.)

  7. Biofouling of power-plant service systems by Corbicula

    International Nuclear Information System (INIS)

    Page, T.L.; Neitzel, D.A.; Simmons, M.A.; Hayes, P.F.

    1983-08-01

    Corbicula sp. foul the service water systems at nuclear power plants because the environment within these systems is compatible with the ecological requirements of the species. To reduce Corbicula fouling, components of service water systems and operating procedures that enhance the potential for fouling need to be identified. Factors important in mediating biofouling of service water systems appear to be screening potential, minimum and maximum velocities and the operational procedures employed during power plant biofoulant control and downtime. These conclusions are based on the results of a categorical model we used to correlate information from power plants with that on Corbicula life history. Power plant parameters in the model include temperature, dissolved oxygen concentration, screen and strainer size, maximum and minimum velocities, and elements of the biofouling control procedures. Parameters for Corbicula include tolerances to temperature, dissolved oxygen, biofouling control chemicals, velocity preferences, and optimal temperatures for each life stage and behavior. 13 references, 5 figures

  8. Plant water status relationships among major floodplain sites of the Flathead River, Montana

    Science.gov (United States)

    Lee, L.C.; Hinckley, T.M.; Scott, M.L.

    1985-01-01

    Water status measurements of dominant species from major floodplain plant community types of the North Fork Flathead River, Montana were used to test the accuracy of site moisture gradient relationships postulated from floristic ordinations and site water balance estimates. Analysis of variance tests showed significant differences among the average predawn xylem pressure potential (ψp) of species in several community types. However, additional analyses failed to indicate a significant degree of association between averaged predawn Yp measurements and either floristic ordination or site water balance results. Sixty eight percent of 22 trials comparing the diurnal average ψp of the same species in different community types on the same day were less negative for a species in the wetter community types as predicted by floristic ordinations. Similarly, 64% of the trials indicated that the diurnal average stomatal conductance was higher for a species in the wetter type. These results suggest that although a floodplain moisture gradient exists, it alone does not limit the distribution of floodplain plant communities in the North Fork.

  9. Review of nuclear power plant systems

    International Nuclear Information System (INIS)

    Doehler

    1980-01-01

    This presentation starts with a brief description of the Technischer Ueberwachungs-Verein (TUeV) and its main activities in the field of technical assessments. The TUeV-organisation is in general the assessor who performs the review if nuclear power plant systems, structures and equipment. All aspects relating to the safe operation of nuclear power plants are assessed by the TUeV. This paper stresses the review of the design of nuclear power plant systems and structures. It gives an outline on the procedure of an assessment, starting with the regulatory requirements, going into the papers of the applicant and finally ending with the TUeV-appraisal. This procedure is shown using settlement measuring requirements as an example. The review of the design of mechanical structures such as pipes, valves, pump and vessels is shown in detail. (RW)

  10. Experiences Gained from Independent Assessment in Licensing of Advanced I and C Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lindner, Arndt B.; Wach, Dieter H.

    2003-01-01

    Operational benefits and enlarged functionality of modern technology, but also the physical and the technological aging of conventional instrumentation and control (I and C) systems, are motivations for modernization of I and C systems in nuclear power plants (NPPs). In case of safety-relevant I and C systems, the licensing authorities require the demonstration of sufficient safety of the systems.In several countries ongoing research and development projects are directed to provide a scientific basis and engineering solutions for cost-effective assessment of software-based I and C systems important to safety in NPPs. International initiatives have been started to develop a harmonized safety assessment methodology. The Institute for Safety Technology (ISTec) has been engaged in national and international programs as well as in establishing a two-phase qualification approach, which comprises a generic plant-independent qualification of hardware and software components and a plant-specific system qualification phase.In both generic qualification and plant-specific system qualification, ISTec has been involved as an independent third-party assessor for the relevant state authority. This paper reports experiences from the ISTec involvement in the assessment projects, e.g., in the assessment of the I and C important to safety in the new German High-Flux Research Reactor (FRM-2) in Munich and in the assessments of I and C modernization in NPPs of foreign countries (Bohunice, Slovak Republic; Paks, Hungary; and others). Conclusions are drawn from the experiences with respect to the practicability of the two-phase qualification concept and from the major findings in the plant-specific I and C assessments

  11. Nutrient supply of plants in aquaponic systems

    Directory of Open Access Journals (Sweden)

    Andras Bittsanszky

    2016-10-01

    Full Text Available In this preliminary article we present data on plant nutrient concentrations in aquaponics systems, and we compare them to nutrient concentrations in “standard” hydroponic solutions. Our data shows that the nutrient concentrations supplied by the fish in the aquaponics system are significantly lower for most nutrients compared to hydroponic systems. Nevertheless, plants do thrive in solutions that have lower nutrient levels compared to “standard” hydroponic solutions. This is especially true for green leafy vegetables that rarely need additional nutritional supplementation. It is concluded that in the highly complex system of aquaponics, special care has to be taken, via continuous monitoring of the chemical composition of the circulating water, to provide adequate concentrations and ratios of nutrients, and especially for the potentially toxic component, ammonium. If certain plants require nutrient supplementation, we consider that one based on organic substances would be most beneficial. However, protocols for the application of such nutrient amendments still need to be developed.

  12. Insights from a reliability review of digital plant protection system

    International Nuclear Information System (INIS)

    Kim, I.S.; Hwang, S.W.; Kim, B.S.; Jeong, C.H.; Oh, S.H.

    2001-01-01

    The full text follows: As part of the design efforts for Ulchin nuclear power plant units 5 and 6 of Korea, a reliability analysis of digital plant protection system (DPPS) was performed by ABB-CE. An independent review of the DPPS reliability analysis was undertaken by Hanyang University to assist Korea Institute of Nuclear Safety (KINS), the nuclear regulatory body of Korea, in evaluating the design acceptability of the digital system. The DPPS is designed to encompass both reactor trip function and ESFAS (engineered safety feature actuation system) initiation function. The major methods used by the ABB-CE to assess the Ulchin 5-6 DPPS reliability are failure mode and effect analysis (FMEA) and fault tree analysis. Hence, our independent review was conducted focusing on: -) the establishment of review criteria based on various sources, such as the standard review plan of KINS, 10CFR50 Appendix A, IEEE standards 279, 577, and 603; -) the suitability of the FMEA and fault tree analysis for the Ulchin 5-6 DPPS, including the specific methods used (e.g., for human reliability analysis and common-cause failure analysis), the assumptions made (e.g., with respect to test frequency and watchdog timer coverage), and the data employed (e.g., CCF parameter, human error probability, and processor failure rate); and -) the design acceptability of the DPPS especially as compared to the analog plant protection system from a reliability and safety perspective. The paper shall also discuss key issues requiring further in-depth investigation, such as reliability of programmable logic controllers (PLCs), coverage factor of watchdog timers, and susceptibility of redundant digital units to common cause failure. Sensitivity analyses were carried out to investigate the impact of several parameters of special interest, like the coverage factor of watchdog timer and human error probability (e.g. an operator error to manually trip the reactor, or to mis-calibrate the trip parameters) on

  13. A knowledge based operator support system for emergency conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Venkatesh Babu, C.; Subramanium, K.

    1992-01-01

    The control centres of the operating Indian nuclear power plants contain a large number of indicators and controls spread over many panels. In the event of onset of an emergency condition, there results a profusion of information, both numeric and symbolic. The operator may succumb to an information and cognitive overload that may be compounded by a lack of knowledge. The failure to apply knowledge and reasoning to solve an operational problem can lead to human error, which has been a major contributing factor in nuclear accidents. From the viewpoint of Artificial Intelligence, human error occurs if the operational problem requires computing resources that exceed human capabilities. The application of Artificial Intelligence, particularly expert systems, to nuclear power plant control room activities has considerable potential to reduce operator error and improve safety and reliability. The purpose of this paper is to discuss an investigative study of the feasibility of developing an operator support system incorporating Artificial Intelligence techniques. An information processing model of such a system, herein designated as Knowledge Based Operator Support System - KBOSS, employing expert systems technology, has been developed. The features of this system are described, and issues involved in its development are discussed. (author). 2 refs., 5 figs., 1 tab

  14. Improving CANDU plant operation and maintenance through retrofit information technology systems

    International Nuclear Information System (INIS)

    Lupton, L.R.; Judd, R.A.; MacBeth, M.J.

    1998-01-01

    CANDU plant owners are facing an increasingly competitive environment for the generation of electricity. To meet this challenge, all owners have identified that information technology offers opportunities for significant improvements in CANDU operation, maintenance and administration (OM and A) costs. Targeted information technology application areas include instrumentation and control, engineering, construction, operations and plant information management. These opportunities also pose challenges and issues that must be addressed if the full benefits of the advances in information technology are to be achieved. Key among these are system hardware and software maintenance, and obsolescence protection; AECL has been supporting CANDU stations with the initial development and evaluation of systems to improve plant performance and cost. Key initiatives that have been implemented or are in the process of being implemented in some CANDU plants to achieve operational benefits include: critical safety parameter monitor system; advanced computerized annunciation system; plant historical data system; and plant display system. Each system will be described in terms of its role in enhancing current CANDU plant performance and how they will contribute to future CANDU plant performance

  15. Improving CANDU plant operation and maintenance through retrofit information technology systems

    International Nuclear Information System (INIS)

    Lupton, L. R.; Judd, R. A.

    1998-01-01

    CANDU plant owners are facing an increasingly competitive environment for the generation of electricity. To meet this challenge, all owners have identified that information technology offers opportunities for significant improvements in CANDU operation, maintenance and administration (OM and A) costs. Targeted information technology application areas include instrumentation and control, engineering, construction, operations and plant information management. These opportunities also pose challenges and issues that must be addressed if the full benefits of the advances in information technology are to be achieved. Key among these are system hardware and software maintenance, and obsolescence protection. AECL has been supporting CANDU stations with the initial development and evaluation of systems to improve plant performance and cost. Five key initiatives that have been implemented or are in the process of being implemented in some CANDU plants to achieve cooperational benefits include: critical safety parameter monitor system; advanced computerized annunciation system; plant historical data system; plant display system; and digital protection system. Each system will be described in terms of its role in enhancing current CANDU plant performance and how they will contribute to future CANDU plant performance. (author). 8 refs., 3 figs

  16. Basis of plant accounting system

    International Nuclear Information System (INIS)

    Schneider, R.A.

    1984-01-01

    This presentation describes in an introductory manner the accountability design approach which is used for the Model Plant in order to meet US safeguards requirements. The general requirements for the US national system are first presented. Next, the approach taken to meet each general requirement is described. This presentation introduces the general concepts and principles of the accountability system

  17. Monitoring Systems for Hydropower Plants

    Directory of Open Access Journals (Sweden)

    Damaschin Pepa

    2015-07-01

    Full Text Available One of the most important issue in hydro power industry is to determine the necessary degree of automation in order to improve the operation security. Depending upon the complexity of the system (the power plant equipment the automation specialist will build a philosophy of control following some general principals of security and operation. Helped by the modern digital equipment, today is relative easy to design a complete monitoring and supervising system including all the subparts of a hydro aggregate. A series of sensors and transducers specific for each auxiliary installation of the turbine and generator will be provided, together with a PLC or an industrial PC that will run an application software for implementing the security and control algorithms. The purpose of this paper is to offer a general view of these issues, providing a view of designing an automation & control and security system for hydro power plants of small, medium and big power.

  18. Audit of the Reporting Requirements for Major Automated Information System Programs

    National Research Council Canada - National Science Library

    2000-01-01

    .... There are 71 Major Automated Information System programs with total program costs of $26 billion. To qualify as a Major Automated Information System, the program must meet the following critena...

  19. Assessing nuclear power plant safety and recovery from earthquakes using a system-of-systems approach

    International Nuclear Information System (INIS)

    Ferrario, E.; Zio, E.

    2014-01-01

    We adopt a ‘system-of-systems’ framework of analysis, previously presented by the authors, to include the interdependent infrastructures which support a critical plant in the study of its safety with respect to the occurrence of an earthquake. We extend the framework to consider the recovery of the system of systems in which the plant is embedded. As a test system, we consider the impacts produced on a nuclear power plant (the critical plant) embedded in the connected power and water distribution, and transportation networks which support its operation. The Seismic Probabilistic Risk Assessment of such system of systems is carried out by Hierarchical modeling and Monte Carlo simulation. First, we perform a top-down analysis through a hierarchical model to identify the elements that at each level have most influence in restoring safety, adopting the criticality importance measure as a quantitative indicator. Then, we evaluate by Monte Carlo simulation the probability that the nuclear power plant enters in an unsafe state and the time needed to recover its safety. The results obtained allow the identification of those elements most critical for the safety and recovery of the nuclear power plant; this is relevant for determining improvements of their structural/functional responses and supporting the decision-making process on safety critical-issues. On the test system considered, under the given assumptions, the components of the external and internal water systems (i.e., pumps and pool) turn out to be the most critical for the safety and recovery of the plant. - Highlights: • We adopt a system-of-system framework to analyze the safety of a critical plant exposed to risk from external events, considering also the interdependent infrastructures that support the plant. • We develop a hierarchical modeling framework to represent the system of systems, accounting also for its recovery. • Monte Carlo simulation is used for the quantitative evaluation of the

  20. L-py: an L-system simulation framework for modeling plant architecture development based on a dynamic language.

    Science.gov (United States)

    Boudon, Frédéric; Pradal, Christophe; Cokelaer, Thomas; Prusinkiewicz, Przemyslaw; Godin, Christophe

    2012-01-01

    The study of plant development requires increasingly powerful modeling tools to help understand and simulate the growth and functioning of plants. In the last decade, the formalism of L-systems has emerged as a major paradigm for modeling plant development. Previous implementations of this formalism were made based on static languages, i.e., languages that require explicit definition of variable types before using them. These languages are often efficient but involve quite a lot of syntactic overhead, thus restricting the flexibility of use for modelers. In this work, we present an adaptation of L-systems to the Python language, a popular and powerful open-license dynamic language. We show that the use of dynamic language properties makes it possible to enhance the development of plant growth models: (i) by keeping a simple syntax while allowing for high-level programming constructs, (ii) by making code execution easy and avoiding compilation overhead, (iii) by allowing a high-level of model reusability and the building of complex modular models, and (iv) by providing powerful solutions to integrate MTG data-structures (that are a common way to represent plants at several scales) into L-systems and thus enabling to use a wide spectrum of computer tools based on MTGs developed for plant architecture. We then illustrate the use of L-Py in real applications to build complex models or to teach plant modeling in the classroom.

  1. Canadian CANDU plant data systems for technical surveillance and analysis

    International Nuclear Information System (INIS)

    Deverno, M.; Pothier, H.; Xian, C.; Grosbois, J. De; Bosnich, M.

    1996-01-01

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs

  2. Canadian CANDU plant data systems for technical surveillance and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Deverno, M; Pothier, H; Xian, C [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Fredericton, NB (Canada); Grosbois, J De; Bosnich, M [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Chalk River, ON (Canada). Chalk River Labs.

    1997-12-31

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs.

  3. Control system security in nuclear power plant

    International Nuclear Information System (INIS)

    Li Jianghai; Huang Xiaojin

    2012-01-01

    The digitalization and networking of control systems in nuclear power plants has brought significant improvements in system control, operation and maintenance. However, the highly digitalized control system also introduces additional security vulnerabilities. Moreover, the replacement of conventional proprietary systems with common protocols, software and devices makes these vulnerabilities easy to be exploited. Through the interaction between control systems and the physical world, security issues in control systems impose high risks on health, safety and environment. These security issues may even cause damages of critical infrastructures and threaten national security. The importance of control system security by reviewing several control system security incidents that happened in nuclear power plants was showed in recent years. Several key difficulties in addressing these security issues were described. Finally, existing researches on control system security and propose several promising research directions were reviewed. (authors)

  4. A study on expert system applications for nuclear power plant

    International Nuclear Information System (INIS)

    Huh, Young Hwan; Kim, Yeong Jin; Park, Nam Seog; Dong, In Sook; Choi, In Seon

    1987-12-01

    The application of artificial intelligence techniques to nuclear power plants such as expert systems is rapidly emerging. expert systems can contribute significantly to the availability and the improved operation and safety of nuclear power plants. The objective of the project is to develop an expert system in a selected application area in the nuclear power plants. This project will last for 3 years. The first year's tasks are: - Information collection and literature survey on expert systems. - Analysis of several applicable areas for applying AI technologies to the nuclear power plants. - Conceptual design of a few selected domains. - Selection of hardware and software tools for the development of the expert system

  5. Communications interface for plant monitoring system

    International Nuclear Information System (INIS)

    Lee, K.L.; Morgan, F.A.

    1988-01-01

    This paper presents the communications interface for an intelligent color graphic system which PSE and G developed as part of a plant monitoring system. The intelligent graphic system is designed to off-load traditional host functions such as dynamic graphic updates, keyboard handling and alarm display. The distributed system's data and synchronization problems and their solutions are discussed

  6. TQC works in newly-built nuclear power plant and main electric power system plannings

    International Nuclear Information System (INIS)

    Akiyama, Yoshihisa; Kawakatsu, Tadashi; Hashimoto, Yasuo

    1985-01-01

    In the Kansai Electric Power Co., Inc., TQC has been introduced to solve such major problems in nuclear power generation as the securing of nuclear power reliability, the suppression of rises in the costs, the reduction in long periods of power failure and the promotion in siting of nuclear power plants. It is thus employed as a means of the ''creation of a slim and tough business constitution''. The state of activities in Kansai Electric are described in quality assurance of a newly-built nuclear power plant and in raising the reliability of the main electric power system to distribute the generated nuclear power and further the future prospects are explained. (Mori, K.)

  7. Structured Light-Based 3D Reconstruction System for Plants

    Directory of Open Access Journals (Sweden)

    Thuy Tuong Nguyen

    2015-07-01

    Full Text Available Camera-based 3D reconstruction of physical objects is one of the most popular computer vision trends in recent years. Many systems have been built to model different real-world subjects, but there is lack of a completely robust system for plants. This paper presents a full 3D reconstruction system that incorporates both hardware structures (including the proposed structured light system to enhance textures on object surfaces and software algorithms (including the proposed 3D point cloud registration and plant feature measurement. This paper demonstrates the ability to produce 3D models of whole plants created from multiple pairs of stereo images taken at different viewing angles, without the need to destructively cut away any parts of a plant. The ability to accurately predict phenotyping features, such as the number of leaves, plant height, leaf size and internode distances, is also demonstrated. Experimental results show that, for plants having a range of leaf sizes and a distance between leaves appropriate for the hardware design, the algorithms successfully predict phenotyping features in the target crops, with a recall of 0.97 and a precision of 0.89 for leaf detection and less than a 13-mm error for plant size, leaf size and internode distance.

  8. Tele-maintenance 'intelligent' system for technical plants result management

    International Nuclear Information System (INIS)

    Concetti, Massimo; Cuccioletta, Roberto; Fedele, Lorenzo; Mercuri, Giampiero

    2009-01-01

    The management of technical plant for productivity and safety is generally a complex activity, particularly when many plants distributed in the territory are considered (i.e. the more and more frequent case of outsourced plants maintenance by specialized companies), granted quality and cost results are required (i.e. the case of some rather innovative contract solutions) and the technology involved is heterogeneous and innovative (i.e. electro-mechanical plants). In order to efficiently achieve the above aims an 'intelligent' maintenance-management system for the distant monitoring and controlling by a remote control center has been developed. The so-called GrAMS (granted availability management system) system is conceived to give to organizations involved in technical-industrial plants management the possibility to tend to a 'well-known availability' and 'zero-failures' management. In particular, this study deals with the diagnostic aspects and safety level of technical plants (such as elevators, thermo-technical plants, etc.), and with the involvement of ad hoc designed software analysis tools based on neural networks and reliability indicators. Part of the research dealing with the tele-maintenance intelligent system has been financed by the Italian High Institute for Safety (ISPESL) and led to the development of a pre-industrial prototype whose realization and testing is here described

  9. Structured Light-Based 3D Reconstruction System for Plants.

    Science.gov (United States)

    Nguyen, Thuy Tuong; Slaughter, David C; Max, Nelson; Maloof, Julin N; Sinha, Neelima

    2015-07-29

    Camera-based 3D reconstruction of physical objects is one of the most popular computer vision trends in recent years. Many systems have been built to model different real-world subjects, but there is lack of a completely robust system for plants. This paper presents a full 3D reconstruction system that incorporates both hardware structures (including the proposed structured light system to enhance textures on object surfaces) and software algorithms (including the proposed 3D point cloud registration and plant feature measurement). This paper demonstrates the ability to produce 3D models of whole plants created from multiple pairs of stereo images taken at different viewing angles, without the need to destructively cut away any parts of a plant. The ability to accurately predict phenotyping features, such as the number of leaves, plant height, leaf size and internode distances, is also demonstrated. Experimental results show that, for plants having a range of leaf sizes and a distance between leaves appropriate for the hardware design, the algorithms successfully predict phenotyping features in the target crops, with a recall of 0.97 and a precision of 0.89 for leaf detection and less than a 13-mm error for plant size, leaf size and internode distance.

  10. ChemAND - a system health monitor for plant chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Turner, C.W.; Mitchel, G.R.; Tosello, G.; Balakrishnan, P.V.; McKay, G.; Thompson, M. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Dundar, Y.; Bergeron, M.; Laporte, R. [Hydro-Quebec, Groupe Chimie, Centrale Nucleaire Gentilly-2, Gentilly, Quebec (Canada)

    2001-03-01

    Effective management of plant systems throughout their lifetime requires much more than data acquisition and display - it requires that the plant's system health be continually monitored and managed. AECL has developed a System Health Monitor called ChemAND for CANDU plant chemistry. ChemAND, a Chemistry ANalysis and Diagnostic system, monitors key chemistry parameters in the heat transport system, moderator-cover gas, annulus gas, and the steam cycle during full-power operation. These parameters can be used as inputs to models that calculate the effect of current plant operating conditions on the present and future health of the system. Chemistry data from each of the systems are extracted on a regular basis from the plant's Historical Data Server and are sorted according to function, e.g., indicators for condenser in-leakage, air in-leakage, heavy water leakage into the annulus gas, fuel failure, etc. Each parameter is conveniently displayed and is trended along with its alarm limits. ChemAND currently includes two analytical models developed for the balance-of-plant. The first model, ChemSolv, calculates crevice chemistry conditions in the steam generator (SG) from either the SG blowdown chemistry conditions or from a simulated condenser leak. This information can be used by plant staff to evaluate the susceptibility of the SG tubes to crevice corrosion. ChemSolv also calculates chemistry conditions throughout the steam-cycle system as determined by the transport of volatile species such as ammonia, hydrazine, morpholine, and oxygen. The second model, SLUDGE, calculates the deposit loading and distribution in the SG as a function of time, based on concentrations of corrosion product in the final feedwater for both normal and start-up conditions. Operations personnel can use this information to predict where to inspect and when to clean. (author)

  11. ChemAND - a system health monitor for plant chemistry

    International Nuclear Information System (INIS)

    Turner, C.W.; Mitchell, G.R.; Tosello, G.; Balakrishnan, P.V.; McKay, G.; Thompson, M.; Dundar, Y.; Bergeron, M.; Laporte, R.

    2001-01-01

    Effective management of plant systems throughout their lifetime requires much more than data acquisition and display-it requires that the plant's system health be continually monitored and managed. AECL has developed a System Health Monitor called ChemAND for CANDU plant chemistry. ChemAND, a Chemistry ANalysis and Diagnostic system, monitors key chemistry parameters in the heat transport system, moderator-cover gas, annulus gas, and the steam cycle during full-power operation. These parameters can be used as inputs to models that calculate the effect of current plant operating conditions on the present and future health of the system. Chemistry data from each of the systems are extracted on a regular basis from the plant's Historical Data Server and are sorted according to function, e.g., indicators for condenser in-leakage, air in-leakage, heavy water leakage into the annulus gas, fuel failure, etc. Each parameter is conveniently displayed and is trended along with its alarm limits. ChemAND currently includes two analytical models developed for the balance-of-plant. The first model, ChemSolv, calculates crevice chemistry conditions in the steam generator (SG) from either the SG blowdown chemistry conditions or from a simulated condenser leak. This information can be used by plant staff to evaluate the susceptibility of the SG tubes to crevice corrosion. ChemSolv also calculates chemistry conditions throughout the steam cycle system, as determined by the transport of volatile species such as ammonia, hydrazine, morpholine, and oxygen. The second model, SLUDGE, calculates the deposit loading and distribution in the SG as a function of time, based on concentrations of corrosion product in the final feedwater for both normal and start-up conditions. Operations personnel can use this information to predict where to inspect and when to clean. (author)

  12. ChemAND - a system health monitor for plant chemistry

    International Nuclear Information System (INIS)

    Turner, C.W.; Mitchel, G.R.; Tosello, G.; Balakrishnan, P.V.; McKay, G.; Thompson, M.; Dundar, Y.; Bergeron, M.; Laporte, R.

    2001-03-01

    Effective management of plant systems throughout their lifetime requires much more than data acquisition and display - it requires that the plant's system health be continually monitored and managed. AECL has developed a System Health Monitor called ChemAND for CANDU plant chemistry. ChemAND, a Chemistry ANalysis and Diagnostic system, monitors key chemistry parameters in the heat transport system, moderator-cover gas, annulus gas, and the steam cycle during full-power operation. These parameters can be used as inputs to models that calculate the effect of current plant operating conditions on the present and future health of the system. Chemistry data from each of the systems are extracted on a regular basis from the plant's Historical Data Server and are sorted according to function, e.g., indicators for condenser in-leakage, air in-leakage, heavy water leakage into the annulus gas, fuel failure, etc. Each parameter is conveniently displayed and is trended along with its alarm limits. ChemAND currently includes two analytical models developed for the balance-of-plant. The first model, ChemSolv, calculates crevice chemistry conditions in the steam generator (SG) from either the SG blowdown chemistry conditions or from a simulated condenser leak. This information can be used by plant staff to evaluate the susceptibility of the SG tubes to crevice corrosion. ChemSolv also calculates chemistry conditions throughout the steam-cycle system as determined by the transport of volatile species such as ammonia, hydrazine, morpholine, and oxygen. The second model, SLUDGE, calculates the deposit loading and distribution in the SG as a function of time, based on concentrations of corrosion product in the final feedwater for both normal and start-up conditions. Operations personnel can use this information to predict where to inspect and when to clean. (author)

  13. IAEA activity on operator support systems in nuclear power plants

    International Nuclear Information System (INIS)

    Dounaev, V.; Fujita, Y.; Juslin, K.; Haugset, K.; Lux, I.; Naser, J.

    1994-01-01

    Various operator support systems for nuclear power plants are already operational or under development in the IAEA Member States. Operator support systems are based on intelligent data processing and, in addition to plant operation, they are also becoming more important for safety. A key feature of operator support systems is their availability to restructure data to increase its relevance for a given situation. This can improve the user's ability to identify plant mode, system state, and component state and to identify and diagnose faults. Operator support systems can also assist the user in planning and implementing corrective actions to improve the nuclear power plant's availability and safety. In September 1991, the IAEA Committee for Contractual Scientific Services approved the Co-ordinated Research Programme (CRP) on ''Operator Support Systems in Nuclear Power Plants'' in the framework of the Project ''Man-Machine Interface Studies''. The main objective of this programme is to provide guidance and technology transfer for the development and implementation of operator support systems. This includes the experience with human-machine interfaces and closely related issues such as instrumentation and control, the use of computers in nuclear power plants, and operator qualification. (author)

  14. Development of nuclear power plants database system, (2)

    International Nuclear Information System (INIS)

    Izumi, Fumio; Ichikawa, Michio

    1984-06-01

    A nuclear power plant data base system has been developed. The data base involves a large amount of safety design informations for nuclear power plants on operating and planning stage in Japan. The informations, if necessary, can be searched for at high speed by use of this system. The present report is an user's guide for access to the informations utilizing display unit of the JAERI computer network system. (author)

  15. Adapting a reactor safety assessment system for specific plants

    International Nuclear Information System (INIS)

    Ballard, T.L.; Cordes, G.A.

    1991-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system being developed by the Idaho National Engineering Laboratory, the University of Maryland (UofM) and US Nuclear Regulatory Commission (NRC) for use in the NRC Operations center. RSAS is designed to help the Reactor Safety Team monitor and project core status during an emergency at a licensed nuclear power plant. Analysis uses a hierarchical plant model based on equipment availability and automatically input parametric plant information. There are 3 families of designs of pressurized water reactors and 75 plants using modified versions of the basic design. In order to make an RSAS model for each power plant, a generic model for a given plant type is used with differences being specified by plant specific files. Graphical displays of this knowledge are flexible enough to handle any plant configuration. A variety of tools have been implemented to make it easy to modify a design to fit a given plant while minimizing chance for error. 3 refs., 4 figs

  16. Monoterpenes released from fruit, plant, and vegetable systems.

    Science.gov (United States)

    Iqbal, Mohammad Asif; Kim, Ki-Hyun; Ahn, Jeong Hyeon

    2014-09-29

    To quantify the emission rate of monoterpenes (MTs) from diverse natural sources, the sorbent tube (ST)-thermal desorption (TD) method was employed to conduct the collection and subsequent detection of MTs by gas chromatography. The calibration of MTs, when made by both mass spectrometric (MS) and flame ionization detector (FID), consistently exhibited high coefficient of determination values (R2 > 0.99). This approach was employed to measure their emission rate from different fruit/plant/vegetable (F/P/V) samples with the aid of an impinger-based dynamic headspace sampling system. The results obtained from 10 samples (consisting of carrot, pine needle (P. sylvestris), tangerine, tangerine peel, strawberry, sepals of strawberry, plum, apple, apple peel, and orange juice) marked α-pinene, β-pinene, myrcene, α-terpinene, R-limonene, γ-terpinene, and p-cymene as the most common MTs. R-limonene was the major species emitted from citrus fruits and beverages with its abundance exceeding 90%. In contrast, α-pinene was the most abundant MT (37%) for carrot, while it was myrcene (31%) for pine needle. The overall results for F/P/V samples confirmed α-pinene, β-pinene, myrcene, α-terpinene, and γ-terpinene as common MTs. Nonetheless, the types and magnitude of MTs released from fruits were distinguished from those of vegetables and plants.

  17. The effect of plant water storage on water fluxes within the coupled soil-plant system.

    Science.gov (United States)

    Huang, Cheng-Wei; Domec, Jean-Christophe; Ward, Eric J; Duman, Tomer; Manoli, Gabriele; Parolari, Anthony J; Katul, Gabriel G

    2017-02-01

    In addition to buffering plants from water stress during severe droughts, plant water storage (PWS) alters many features of the spatio-temporal dynamics of water movement in the soil-plant system. How PWS impacts water dynamics and drought resilience is explored using a multi-layer porous media model. The model numerically resolves soil-plant hydrodynamics by coupling them to leaf-level gas exchange and soil-root interfacial layers. Novel features of the model are the considerations of a coordinated relationship between stomatal aperture variation and whole-system hydraulics and of the effects of PWS and nocturnal transpiration (Fe,night) on hydraulic redistribution (HR) in the soil. The model results suggest that daytime PWS usage and Fe,night generate a residual water potential gradient (Δψp,night) along the plant vascular system overnight. This Δψp,night represents a non-negligible competing sink strength that diminishes the significance of HR. Considering the co-occurrence of PWS usage and HR during a single extended dry-down, a wide range of plant attributes and environmental/soil conditions selected to enhance or suppress plant drought resilience is discussed. When compared with HR, model calculations suggest that increased root water influx into plant conducting-tissues overnight maintains a more favorable water status at the leaf, thereby delaying the onset of drought stress. © 2016 The Authors. New Phytologist © 2016 New Phytologist Trust.

  18. Distributed control system for CANDU 9 nuclear power plant

    International Nuclear Information System (INIS)

    Harber, J.E.; Kattan, M.K.; Macbeth, M.J.

    1996-01-01

    Canadian designed CANDU pressurized heavy water nuclear reactors have been world leaders in electrical power generation. The CANDU 9 project is AECL's next reactor design. The CANDU 9 plant monitoring, annunciation, and control functions are implemented in two evolutionary systems; the distributed control system (DCS) and the plant display system (PDS). The CDS implements most of the plant control functions in a single hardware platform. The DCS communicates with the PDS to provide the main operator interface and annunciation capabilities of the previous control computer designs along with human interface enhancements required in a modern control system. (author)

  19. Analysis and Design of the Logistics System for Rope Manufacturing Plant

    Directory of Open Access Journals (Sweden)

    Sun Xue

    2017-01-01

    Full Text Available In order to promote logistics system for manufacturing plant, this paper proposed a new design for the logistics system of a rope manufacturing plant. Through the analysis in the aspects of workshop facility layout, material handling and inventory management, the original logistics system of the plant is optimized. According to the comparison of the simulation results between original and optimized design, the optimized model has the higher productive efficiency. This can provide the references for the other manufacturing plant in analysis and design of the logistics system to improve plant efficiency.

  20. Distributed and hierarchical control techniques for large-scale power plant systems

    International Nuclear Information System (INIS)

    Raju, G.V.S.; Kisner, R.A.

    1985-08-01

    In large-scale systems, integrated and coordinated control functions are required to maximize plant availability, to allow maneuverability through various power levels, and to meet externally imposed regulatory limitations. Nuclear power plants are large-scale systems. Prime subsystems are those that contribute directly to the behavior of the plant's ultimate output. The prime subsystems in a nuclear power plant include reactor, primary and intermediate heat transport, steam generator, turbine generator, and feedwater system. This paper describes and discusses the continuous-variable control system developed to supervise prime plant subsystems for optimal control and coordination

  1. Replacement of the control and instrumentation system with the microprocessor based systems in Japanese PWR plants

    International Nuclear Information System (INIS)

    Hayashi, N.

    1998-01-01

    In Ohi Units 3 and 4, Ikata Unit 3, and Genkai Units 3 and 4, the latest of PWR plants now under operation in Japan, the reactor control system and turbine control system employ the microprocessor base digital control systems with a view to improving reliability, operability and maintainability. In the next stage plants, another application of such digital system is also planned for the instrumentation rack for the reactor protection system for further improvement. On the other hand, in Mihama Unit 1, the first of domestic PWR plants, and later plants except for the latest 5 plants, analog control systems are employed for the instrumentation racks. For the analog control systems of these plants, FOXBORO H-Line instruments, equivalent domestic box type instruments or WH7300 Series card type instruments were initially employed, and later replaced with domestic card type control systems after 10-15 year operation. However, 8-12 years have passed since these replacements, so the 15th year generally quoted as an interval for replacing C and I systems is near at hand. This is the time to consider next replacement. This replacement will be based on the latest digital technology. However, it is not practical way for the existing plants to apply the same integrated digital C and I system configuration for the next stage plants, because it requires the drastic change of the C and I system configuration and significant cost-up. Therefore, we must investigate the optimum digital C and I system configuration for the existing system. (author)

  2. Radiation exposure control by estimation of multiplication factors for online remote radiation monitoring systems at vitrification plant

    International Nuclear Information System (INIS)

    Deokar, U.V.; Kulkarni, V.V.; Khot, A.R.; Mathew, P.; Kamlesh; Purohit, R.G.; Sarkar, P.K.

    2012-01-01

    Vitrification Plant is commissioned for vitrification of high level liquid waste (HLW) generated in nuclear fuel cycle operations by using Joule Heated Ceramic Melter first time in India. Exposure control is a major concern in operating plant. Therefore in addition to installed monitors, we have developed online remote radiation monitoring system to minimize number of entries in amber areas and to reduce the exposure to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed with actual measurements and by theoretical shielding calculations. The multiplication factors were estimated for remote on line monitoring of Melter Off Gas (MOG) filter, Hood filter, three exhaust filter banks, and over-pack monitoring. This paper summarizes - how the online remote monitoring system helped in saving of 128.52 person-mSv collective dose (14.28% of budgeted dose). The system also helped in the reduction of 2.6 m 3 of Cat-I waste. Our online remote monitoring system has helped the plant management to plan in advance for replacement of these filters, which resulted in considerable saving in collective dose and secondary waste

  3. Analysis of reactor trips involving balance-of-plant failures

    International Nuclear Information System (INIS)

    Seth, S.; Skinner, L.; Ettlinger, L.; Lay, R.

    1986-01-01

    The relatively high frequency of plant transients leading to reactor trips at nuclear power plants in the US is of economic and safety concern to the industry. A majority of such transients is due to failures in the balance-of-plant (BOP) systems. As a part of a study conducted for the US Nuclear Regulatory Commission, Mitre has carried out a further analysis of the BOP failures associated with reactor trips. The major objectives of the analysis were to examine plant-to-plant variations in BOP-related trips, to understand the causes of failures, and to determine the extent of any associated safety system challenges. The analysis was based on the Licensee Event Reports submitted on all commercial light water reactors during the 2-yr period, 1984-1985

  4. Plant traits correlated with generation time directly affect inbreeding depression and mating system and indirectly genetic structure

    Directory of Open Access Journals (Sweden)

    Hardy Olivier J

    2009-07-01

    Full Text Available Abstract Background Understanding the mechanisms that control species genetic structure has always been a major objective in evolutionary studies. The association between genetic structure and species attributes has received special attention. As species attributes are highly taxonomically constrained, phylogenetically controlled methods are necessary to infer causal relationships. In plants, a previous study controlling for phylogenetic signal has demonstrated that Wright's FST, a measure of genetic differentiation among populations, is best predicted by the mating system (outcrossing, mixed-mating or selfing and that plant traits such as perenniality and growth form have only an indirect influence on FST via their association with the mating system. The objective of this study is to further outline the determinants of plant genetic structure by distinguishing the effects of mating system on gene flow and on genetic drift. The association of biparental inbreeding and inbreeding depression with population genetic structure, mating system and plant traits are also investigated. Results Based on data from 263 plant species for which estimates of FST, inbreeding (FIS and outcrossing rate (tm are available, we confirm that mating system is the main influencing factor of FST. Moreover, using an alternative measure of FST unaffected by the impact of inbreeding on effective population size, we show that the influence of tm on FST is due to its impact on gene flow (reduced pollen flow under selfing and on genetic drift (higher drift under selfing due to inbreeding. Plant traits, in particular perenniality, influence FST mostly via their effect on the mating system but also via their association with the magnitude of selection against inbred individuals: the mean inbreeding depression increases from short-lived herbaceous to long-lived herbaceous and then to woody species. The influence of perenniality on mating system does not seem to be related to

  5. Nuclear power plant alarm systems: Problems and issues

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Brown, W.S.

    1991-01-01

    Despite the incorporation of advanced technology into nuclear power plant alarm systems, human factors problems remain. This paper identifies to be addressed in order to allow advanced technology to be used effectively in the design of nuclear power plant alarm systems. The operator's use and processing of alarm system information will be considered. Based upon a review of alarm system research, issues related to general system design, alarm processing, display and control are discussed. It is concluded that the design of effective alarm systems depends on an understanding of the information processing capabilities and limitations of the operator. 39 refs

  6. Nuclear power plant alarm systems: Problems and issues

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.M.; Brown, W.S.

    1991-01-01

    Despite the incorporation of advanced technology into nuclear power plant alarm systems, human factors problems remain. This paper identifies to be addressed in order to allow advanced technology to be used effectively in the design of nuclear power plant alarm systems. The operator's use and processing of alarm system information will be considered. Based upon a review of alarm system research, issues related to general system design, alarm processing, display and control are discussed. It is concluded that the design of effective alarm systems depends on an understanding of the information processing capabilities and limitations of the operator. 39 refs.

  7. Environmental stress is the major cause of transcriptomic and proteomic changes in GM and non-GM plants

    KAUST Repository

    Batista, Rita

    2017-08-31

    The approval of genetically modified (GM) crops is preceded by years of intensive research to demonstrate safety to humans and environment. We recently showed that in vitro culture stress is the major factor influencing proteomic differences of GM vs. non-GM plants. This made us question the number of generations needed to erase such

  8. Environmental stress is the major cause of transcriptomic and proteomic changes in GM and non-GM plants

    KAUST Repository

    Batista, Rita; Fonseca, Cá tia; Planchon, Sé bastien; Negrã o, Só nia; Renaut, Jenny; Oliveira, M. Margarida

    2017-01-01

    The approval of genetically modified (GM) crops is preceded by years of intensive research to demonstrate safety to humans and environment. We recently showed that in vitro culture stress is the major factor influencing proteomic differences of GM vs. non-GM plants. This made us question the number of generations needed to erase such

  9. Prediction of arsenic and antimony transporter major intrinsic proteins from the genomes of crop plants.

    Science.gov (United States)

    Azad, Abul Kalam; Ahmed, Jahed; Alum, Md Asraful; Hasan, Md Mahbub; Ishikawa, Takahiro; Sawa, Yoshihiro

    2018-02-01

    Major intrinsic proteins (MIPs), commonly known as aquaporins, transport water and non-polar small solutes. Comparing the 3D models and the primary selectivity-related motifs (two Asn-Pro-Ala (NPA) regions, the aromatic/arginine (ar/R) selectivity filter, and Froger's positions (FPs)) of all plant MIPs that have been experimentally proven to transport arsenic (As) and antimony (Sb), some substrate-specific signature sequences (SSSS) or specificity determining sites (SDPs) have been predicted. These SSSS or SDPs were determined in 543 MIPs found in the genomes of 12 crop plants; the As and Sb transporters were predicted to be distributed in noduline-26 like intrinsic proteins (NIPs), and every plant had one or several As and Sb transporter NIPs. Phylogenetic grouping of the NIP subfamily based on the ar/R selectivity filter and FPs were linked to As and Sb transport. We further determined the group-wise substrate selectivity profiles of the NIPs in the 12 crop plants. In addition to two NPA regions, the ar/R filter, and FPs, certain amino acids especially in the pore line, loop D, and termini contribute to the functional distinctiveness of the NIP groups. Expression analysis of transcripts in different organs indicated that most of the As and Sb transporter NIPs were expressed in roots. Copyright © 2017 Elsevier B.V. All rights reserved.

  10. The plant expert system (PLEXSYS) development environment

    International Nuclear Information System (INIS)

    Hashemi, S.; Patterson, L.; Jeffery, M.; Delashmutt, L.

    1989-06-01

    The PLEXSYS software engineering tool provides an environment with which utility engineers can build and use expert systems for power plant applications. PLEXSYS provides the engineer with access to many powerful Artificial Intelligence methodologies, while retaining an engineering frame of reference and minimizing the need for a formal background in computer science. The principle concept is that the description and understanding of power plant systems centers on graphical forms such as piping and instrumentation diagrams and electrical line diagrams, which define a graphics-based model of plant knowledge that is common to many applications. PLEXSYS provides a model editor that allows the user to construct and modify models of hydraulic, electrical, and information systems in terms of elementary components and their interconnections. Analysis of the resulting schematic models is provided by several functions that perform network analysis, schematic browsing, mathematical modeling and customization of the user interface. 41 figs., 1 tab

  11. Silicon Regulates Potential Genes Involved in Major Physiological Processes in Plants to Combat Stress

    Directory of Open Access Journals (Sweden)

    Abinaya Manivannan

    2017-08-01

    Full Text Available Silicon (Si, the quasi-essential element occurs as the second most abundant element in the earth's crust. Biological importance of Si in plant kingdom has become inevitable particularly under stressed environment. In general, plants are classified as high, medium, and low silicon accumulators based on the ability of roots to absorb Si. The uptake of Si directly influence the positive effects attributed to the plant but Si supplementation proves to mitigate stress and recover plant growth even in low accumulating plants like tomato. The application of Si in soil as well as soil-less cultivation systems have resulted in the enhancement of quantitative and qualitative traits of plants even under stressed environment. Silicon possesses several mechanisms to regulate the physiological, biochemical, and antioxidant metabolism in plants to combat abiotic and biotic stresses. Nevertheless, very few reports are available on the aspect of Si-mediated molecular regulation of genes with potential role in stress tolerance. The recent advancements in the era of genomics and transcriptomics have opened an avenue for the determination of molecular rationale associated with the Si amendment to the stress alleviation in plants. Therefore, the present endeavor has attempted to describe the recent discoveries related to the regulation of vital genes involved in photosynthesis, transcription regulation, defense, water transport, polyamine synthesis, and housekeeping genes during abiotic and biotic stress alleviation by Si. Furthermore, an overview of Si-mediated modulation of multiple genes involved in stress response pathways such as phenylpropanoid pathway, jasmonic acid pathway, ABA-dependent or independent regulatory pathway have been discussed in this review.

  12. Plant experience with check valves in passive systems

    Energy Technology Data Exchange (ETDEWEB)

    Pahladsingh, R R [GKN Joint Nuclear Power Plant, Dodewaard (Netherlands)

    1996-12-01

    In the design of the advanced nuclear reactors there is a tendency to introduce more passive safety systems. The 25 year old design of the GKN nuclear reactor is different from the present BWR reactors because of some special features, such as the Natural Circulation - and the Passive Isolation Condenser system. When reviewing the design, one can conclude that the plant has 25 years of experience with check valves in passive systems and as passive components in systems. The result of this experience has been modeled in a plant-specific ``living PSA`` for the plant. A data-analysis has been performed on components which are related to the safety systems in the plant. As part of this study also the check valves have been taken in consideration. At GKN, the check valves have shown to be reliable components in the systems and no catastrophic failures have been experienced during the 25 years of operation. Especially the Isolation Condenser with its operation experience can contribute substantially to the insight of check valves in stand-by position at reactor pressure and operating by gravity under different pressure conditions. With the introduction of several passive systems in the SBWR-600 design, such as the Isolation Condensers, Gravity Driven Cooling, and Suppression Pool Cooling System, the issue of reliability of check valves in these systems is actual. Some critical aspects for study in connection with check valves are: What is the reliability of a check valve in a system at reactor pressure, to open on demand; what is the reliability of a check valve in a system at low pressure (gravity), to open on demand; what is the reliability of a check valve to open/close when the stand-by check wave is at zero differential pressure. The plant experience with check valves in a few essential safety systems is described and a brief introduction will be made about the application of check valves in the design of the new generation reactors is given. (author). 6 figs, 1 tab.

  13. Documents for designing the emergency system for the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Machek, J.; Fiser, V.

    1993-12-01

    The organizational structure of the emergency system at the Temelin nuclear power plant is described and the responsibilities, principal assignments and number of personnel and their qualification are outlined; these include the Emergency Staff, emergency organization of the operator shift, Technical Support Center, External Emergency Support Center, and Operating Support Center. The emergency information system to secure personnel activities in emergency situations is also described. This consists of a critical safety function display system, a post-accident monitoring system, and a post-accident sampling system. The performance of the emergency support centers, their equipment with communications and computer hardware, and the number and qualification of personnel are also dealt with. The emergency classification is as follows: anomaly, incident, accident, major accident. The information and warning system is briefly described. A decision flow-chart for the assessment of emergency situations and their classification, including the complete algorithm for classifying accidents in the accident classification system, is given in the annex. (J.B.)

  14. Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2008-01-01

    This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. 1.2. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1981), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1986), which are superseded by this new Safety Guide. 1.3. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1981 and 1986, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2000, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included

  15. Phase I: the pipeline-gas demonstration plant. Demonstration plant engineering and design. Volume 18. Plant Section 2700 - Waste Water Treatment

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-05-01

    Contract No. EF-77-C-01-2542 between Conoco Inc. and the US Department of Energy provides for the design, construction, and operation of a demonstration plant capable of processing bituminous caking coals into clean pipeline quality gas. The project is currently in the design phase (Phase I). This phase is scheduled to be completed in June 1981. One of the major efforts of Phase I is the process and project engineering design of the Demonstration Plant. The design has been completed and is being reported in 24 volumes. This is Volume 18 which reports the design of Plant Section 2700 - Waste Water Treatment. The objective of the Waste Water Treatment system is to collect and treat all plant liquid effluent streams. The system is designed to permit recycle and reuse of the treated waste water. Plant Section 2700 is composed of primary, secondary, and tertiary waste water treatment methods plus an evaporation system which eliminates liquid discharge from the plant. The Waste Water Treatment Section is designed to produce 130 pounds per hour of sludge that is buried in a landfill on the plant site. The evaporated water is condensed and provides a portion of the make-up water to Plant Section 2400 - Cooling Water.

  16. Energy Conversion Alternatives Study (ECAS), Westinghouse phase 1. Volume 10: Liquid-metal MHD systems. [energy conversion efficiency of electric power plants using liquid metal magnetohydrodynamics

    Science.gov (United States)

    Holman, R. R.; Lippert, T. E.

    1976-01-01

    Electric Power Plant costs and efficiencies are presented for two basic liquid-metal cycles corresponding to 922 and 1089 K (1200 and 1500 F) for a commercial applications using direct coal firing. Sixteen plant designs are considered for which major component equipment were sized and costed. The design basis for each major component is discussed. Also described is the overall systems computer model that was developed to analyze the thermodynamics of the various cycle configurations that were considered.

  17. INFORMATION SYSTEM SALES OF INDOOR AND OUTDOOR ORNAMENTAL PLANTS-BASED ONLINE

    Directory of Open Access Journals (Sweden)

    Sutedi Sutedi

    2017-05-01

    Full Text Available Ornamental plants have fairly high commercial value and much sought after by various circles. The prospect is in the business of ornamental plants can be said very brilliant and profitable. Where is in the business of ornamental plants can bring about advantages not the least. The business struggled with ornamental plants can have very favorable prospects for the long term. There are an awful lot of various kinds of ornamental plants that we can choose to use as ornaments to beautify residential home. The ornamental plants can be used as indoor ornamental plants placed in homes or can also be used as outdoor ornamental plants grown in the garden. Ornamental plants while more popular community-wide information system for ornamental plant however is currently designed specifically and not many people who know the information on price and specs or type of indoor and outdoor ornamental plants so that the need for sales information system of indoor and outdoor ornamental plants-based online. With the sales information system of Indoor and Outdoor ornamental plants-based online is expected to facilitate the customers, business processes that occur in the company's units, unit – units that exist within the system a functioning production units as the unit working on/produce ornamental plants. With the utilization of the system marketing media, promoting, finding new customers, the sales process, recapitulation payment of ornamental plants, control the conditions of stock products, development and delivery of products to customers including convincing the product gets to the customer

  18. Off-gas treatment system Process Experimental Pilot Plant (PREPP) k-t evaluation

    International Nuclear Information System (INIS)

    Hedahl, T.G.; Cargo, C.H.; Ayers, A.L.

    1982-06-01

    The scope of work for this task involves a systems' evaluation, using the Kepner-Tregoe (K-T) decision analysis methodology, of off-gas treatment alternatives for a Process Experimental Pilot Plant (PREPP). Two basic systems were evaluated: (1) a wet treatment system using a quencher and scrubber system; and (2) a dry treatment system using a spray dryer and baghouse arrangement. Both systems would neutralize acidic off-gases (HCL and SO 2 ) and remove radioactive particulates prior to release to the environment. The K-T analysis results provided a numerical comparison of the two basic off-gas treatments systems for PREPP. The overall ratings for the two systems differ by only 7%. The closeness of the evaluation indicates that either system is capable of treating the off-gases from PREPP. Based on the analysis, the wet treatment system design is slightly more favorable for PREPP. Technology development, expected operability, total costs, and safety aspects were determined to be more advantageous for the wet system design. Support technology was the only major category that appears less favorable for using the wet off-gas system for PREPP. When considering the two criteria considered most important for PREPP (capital cost and major accident prevention - both rated 10), the wet treatment system received maximum ratings. Space constraints placed on the design by the existing TAN-607 building configuration also are more easily met by the wet system design. Lastly, the level of development for the wet system indicates more applicable experience for nuclear waste processing

  19. Expert System Control of Plant Growth in an Enclosed Space

    Science.gov (United States)

    May, George; Lanoue, Mark; Bathel, Matthew; Ryan, Robert E.

    2008-01-01

    The Expert System is an enclosed, controlled environment for growing plants, which incorporates a computerized, knowledge-based software program that is designed to capture the knowledge, experience, and problem-solving skills of one or more human experts in a particular discipline. The Expert System is trained to analyze crop/plant status, to monitor the condition of the plants and the environment, and to adjust operational parameters to optimize the plant-growth process. This system is intended to provide a way to remotely control plant growth with little or no human intervention. More specifically, the term control implies an autonomous method for detecting plant states such as health (biomass) or stress and then for recommending and implementing cultivation and/or remediation to optimize plant growth and to minimize consumption of energy and nutrients. Because of difficulties associated with delivering energy and nutrients remotely, a key feature of this Expert System is its ability to minimize this effort and to achieve optimum growth while taking into account the diverse range of environmental considerations that exist in an enclosed environment. The plant-growth environment for the Expert System could be made from a variety of structures, including a greenhouse, an underground cavern, or another enclosed chamber. Imaging equipment positioned within or around the chamber provides spatially distributed crop/plant-growth information. Sensors mounted in the chamber provide data and information pertaining to environmental conditions that could affect plant development. Lamps in the growth environment structure supply illumination, and other additional equipment in the chamber supplies essential nutrients and chemicals.

  20. Development of waste water reuse water system for power plants

    Energy Technology Data Exchange (ETDEWEB)

    Park, K K; Kim, D H; Weon, D Y; Yoon, S W; Song, H R [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1998-12-31

    1. Status of waste water discharge at power plants 2. Present status of waste water reuse at power plants 3. Scheme of waste water reuse at power plants 4. Standardization of optimum system for waste water reuse at power plants 5. Establishment of low cost zero discharge system for waste water 6. Waste water treatment technology of chemical cleaning. (author). 132 figs., 72 tabs.

  1. Development of waste water reuse water system for power plants

    Energy Technology Data Exchange (ETDEWEB)

    Park, K.K.; Kim, D.H.; Weon, D.Y.; Yoon, S.W.; Song, H.R. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1997-12-31

    1. Status of waste water discharge at power plants 2. Present status of waste water reuse at power plants 3. Scheme of waste water reuse at power plants 4. Standardization of optimum system for waste water reuse at power plants 5. Establishment of low cost zero discharge system for waste water 6. Waste water treatment technology of chemical cleaning. (author). 132 figs., 72 tabs.

  2. Root Zone Respiration on Hydroponically Grown Wheat Plant Systems

    Science.gov (United States)

    Soler-Crespo, R. A.; Monje, O. A.

    2010-01-01

    Root respiration is a biological phenomenon that controls plant growth and physiological development during a plant's lifespan. This process is dependent on the availability of oxygen in the system where the plant is located. In hydroponic systems, where plants are submerged in a solution containing vital nutrients but no type of soil, the availability of oxygen arises from the dissolved oxygen concentration in the solution. This oxygen concentration is dependent on the , gas-liquid interface formed on the upper surface of the liquid, as given by Henry's Law, depending on pressure and temperature conditions. Respiration rates of the plants rise as biomass and root zone increase with age. The respiration rate of Apogee wheat plants (Triticum aestivum) was measured as a function of light intensity (catalytic for photosynthesis) and CO2 concentration to determine their effect on respiration rates. To determine their effects on respiration rate and plant growth microbial communities were introduced into the system, by Innoculum. Surfactants were introduced, simulating gray-water usage in space, as another factor to determine their effect on chemical oxygen demand of microbials and on respiration rates of the plants. It is expected to see small effects from changes in CO2 concentration or light levels, and to see root respiration decrease in an exponential manner with plant age and microbial activity.

  3. The Use of Grafting to Study Systemic Signaling in Plants.

    Science.gov (United States)

    Tsutsui, Hiroki; Notaguchi, Michitaka

    2017-08-01

    Grafting has long been an important technique in agriculture. Nowadays, grafting is a widely used technique also to study systemic long-distance signaling in plants. Plants respond to their surrounding environment, and at that time many aspects of their physiology are regulated systemically; these start from local input signals and are followed by the transmission of information to the rest of the plant. For example, soil nutrient conditions, light/photoperiod, and biotic and abiotic stresses affect plants heterogeneously, and plants perceive such information in specific plant tissues or organs. Such environmental cues are crucial determinants of plant growth and development, and plants drastically change their morphology and physiology to adapt to various events in their life. Hitherto, intensive studies have been conducted to understand systemic signaling in plants, and grafting techniques have permitted advances in this field. The breakthrough technique of micrografting in Arabidopsis thaliana was established in 2002 and led to the development of molecular genetic tools in this field. Thereafter, various phenomena of systemic signaling have been identified at the molecular level, including nutrient fixation, flowering, circadian clock and defense against pathogens. The significance of grafting is that it can clarify the transmission of the stimulus and molecules. At present, many micro- and macromolecules have been identified as mobile signals, which are transported through plant vascular tissues to co-ordinate their physiology and development. In this review, we introduce the various grafting techniques that have been developed, we report on the recent advances in the field of plant systemic signaling where grafting techniques have been applied and provide insights for the future. © The Author 2017. Published by Oxford University Press on behalf of Japanese Society of Plant Physiologists. All rights reserved. For permissions, please email: journals.permissions@oup.com.

  4. Calcium efflux systems in stress signalling and adaptation in plants

    Directory of Open Access Journals (Sweden)

    Jayakumar eBose

    2011-12-01

    Full Text Available Transient cytosolic calcium ([Ca2+]cyt elevation is an ubiquitous denominator of the signalling network when plants are exposed to literally every known abiotic and biotic stress. These stress-induced [Ca2+]cyt elevations vary in magnitude, frequency and shape, depending on the severity of the stress as well the type of stress experienced. This creates a unique stress-specific calcium signature that is then decoded by signal transduction networks. While most published papers have been focused predominantly on the role of Ca2+ influx mechanisms in shaping [Ca2+]cyt signatures, restoration of the basal [Ca2+]cyt levels is impossible without both cytosolic Ca2+ buffering and efficient Ca2+ efflux mechanisms removing excess Ca2+ from cytosol, to reload Ca2+ stores and to terminate Ca2+ signalling. This is the topic of the current review. The molecular identity of two major types of Ca2+ efflux systems, Ca2+-ATPase pumps and Ca2+/H+ exchangers, is described, and their regulatory modes are analysed in detail. The spatial and temporal organisation of calcium signalling networks is described, and the importance of existence of intracellular calcium microdomains is discussed. Experimental evidence for the role of Ca2+ efflux systems in plant responses to a range of abiotic and biotic factors is summarised. Contribution of Ca2+-ATPase pumps and Ca2+/H+ exchangers in shaping [Ca2+]cyt signatures is then modelled by using a four-component model (plasma- and endo- membrane-based Ca2+-permeable channels and efflux systems taking into account the cytosolic Ca2+ buffering. It is concluded that physiologically relevant variations in the activity of Ca2+-ATPase pumps and Ca2+/H+ exchangers are sufficient to fully describe all the reported experimental evidence and determine the shape of [Ca2+]cyt signatures in response to environmental stimuli, emphasising the crucial role these active efflux systems play in plant adaptive responses to environment.

  5. Distributed Control Systems in New Nuclear Power Plants

    International Nuclear Information System (INIS)

    Doerfler, Joseph

    2008-01-01

    With the growing demand for energy many countries have expressed interest in constructing new plants over the next 15 to 20 years. These expectations have presented a challenge to the nuclear industry to provide a high volume of construction. A key strategy to meet this challenge is developing an advanced nuclear power plant design that allows for a modular construction, a high level of standardization, passive safety features, reduced number of components, and a short bid-to-build time. In addition, the implementation of the plant control system has evolved as new technologies emerge to support these goals. The purpose of this paper is to discuss the ways that the distributed control and information systems in the new generation of nuclear power plants will differ from those currently in service. The new designs provide opportunities to improve overall performance through the use of bus technology, a video display driven Human System Interface, enhanced diagnostics and improved maintenance features. However, the new technologies must fully address requirements for cyber security and high reliability. This paper will give an overview of new technology, improvements, as well as emerging issues in new plant design. (authors)

  6. Distributed Control Systems in New Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Doerfler, Joseph [Westinghouse Electric Company, 4350 Northern Pike, Monroeville, PA 15146 (United States)

    2008-07-01

    With the growing demand for energy many countries have expressed interest in constructing new plants over the next 15 to 20 years. These expectations have presented a challenge to the nuclear industry to provide a high volume of construction. A key strategy to meet this challenge is developing an advanced nuclear power plant design that allows for a modular construction, a high level of standardization, passive safety features, reduced number of components, and a short bid-to-build time. In addition, the implementation of the plant control system has evolved as new technologies emerge to support these goals. The purpose of this paper is to discuss the ways that the distributed control and information systems in the new generation of nuclear power plants will differ from those currently in service. The new designs provide opportunities to improve overall performance through the use of bus technology, a video display driven Human System Interface, enhanced diagnostics and improved maintenance features. However, the new technologies must fully address requirements for cyber security and high reliability. This paper will give an overview of new technology, improvements, as well as emerging issues in new plant design. (authors)

  7. Safety classification of nuclear power plant systems, structures and components

    International Nuclear Information System (INIS)

    1992-01-01

    The Safety Classification principles used for the systems, structures and components of a nuclear power plant are detailed in the guide. For classification, the nuclear power plant is divided into structural and operational units called systems. Every structure and component under control is included into some system. The Safety Classes are 1, 2 and 3 and the Class EYT (non-nuclear). Instructions how to assign each system, structure and component to an appropriate safety class are given in the guide. The guide applies to new nuclear power plants and to the safety classification of systems, structures and components designed for the refitting of old nuclear power plants. The classification principles and procedures applying to the classification document are also given

  8. Computerized reactor protection and safety related systems in nuclear power plants. Proceedings of a specialists' meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Though the majority of existing control and protection systems in nuclear power plants use old analogue technology and design philosophy, the use of computers in safety and safety related systems is becoming a current practice. The Specialists Meeting on ''Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants'' was organized by IAEA (jointly by the Division of Nuclear Power and the Fuel Cycle and the Division of Nuclear Installation Safety), in co-operation with Paks Nuclear Power Plant in Hungary and was held from 27-29 October 1997 in Budapest, Hungary. The meeting focused on computerized safety systems under refurbishment, software reliability issues, licensing experiences and experiences in implemented computerized safety and safety related systems. Within a meeting programme a technical visit to Paks NPP was organized. The objective of the meeting was to provide an international forum for the presentation and discussion on R and D, in-plant experiences in I and C important to safety, backfits and arguments for and reservations against the digital safety systems. The meeting was attended by 70 participants from 16 countries representing NPPs and utility organizations, design/engineering, research and development, and regulatory organizations. In the course of 4 sessions 25 technical presentations were made. The present volume contains the papers presented by national delegates and the conclusions drawn from the final general discussion

  9. Evidence for coherent mixing of excited and charge-transfer states in the major plant light-harvesting antenna, LHCII

    NARCIS (Netherlands)

    Ramanan, Charusheela; Ferretti, Marco; van Roon, Henny; Novoderezhkin, Vladimir I.; van Grondelle, Rienk

    2017-01-01

    LHCII, the major light harvesting antenna from plants, plays a dual role in photosynthesis. In low light it is a light-harvester, while in high light it is a quencher that protects the organism from photodamage. The switching mechanism between these two orthogonal conditions is mediated by protein

  10. Application of fatigue monitoring system in PWR nuclear power plant

    International Nuclear Information System (INIS)

    Piao Lei

    2014-01-01

    Fatigue failure is one form of equipment failure of nuclear power plant, influencing equipment lifetime and lifetime extension. Fatigue monitoring system can track real thermal transient at fatigue sensitive components, establish a basis for fatigue analyses based on realistic operating loads, identify unexpected operational transients, optimize the plant behavior by improved operating modes, provide supporting data for lifetime management, enhance security of plant and reduce economical loss. Fatigue monitoring system has been applied in many plants and is required to be applied in Generation-III nuclear power plant. It is necessary to develop the fatigue monitoring system with independent intellectual property rights and improve the competitiveness of domestic Generation-III nuclear power technology. (author)

  11. ChemANDTM - a system health monitor for plant chemistry

    International Nuclear Information System (INIS)

    Turner, C.W.; Mitchel, G.R.; Balakrishnan, P.V.; Tosello, G.

    1999-07-01

    Effective management of plant systems throughout their lifetime requires much more than data acquisition and display - it requires that the plant's system health be continually monitored and managed. AECL has developed a System Health Monitor called ChemAND for CANDU plant chemistry. ChemAND, a Chemistry ANalysis and Diagnostic system, monitors key chemistry parameters in the heat transport system, moderator-cover gas, annulus gas, and the steam cycle during full-power operation and feeds these parameters to models that calculate the effect of current plant operating conditions on the present and future health of the system. Chemistry data from each of the systems are extracted on a regular basis from the plant's Historical Data Server and are sorted according to function, e.g., indicators for condenser in-leakage, air in-leakage, heavy water leakage into the annulus gas, fuel failure, etc. Each parameter is conveniently displayed and is trended along with its alarm limits. ChemAND currently has two analytical models developed for the balance-of-plant. CHEMSOLV calculates crevice chemistry conditions in the steam generator (SG) from either the SG blowdown chemistry conditions or from a simulated condenser leak. This information will be used by operations personnel to evaluate the potential for SG tube corrosion in the crevice region. CHEMSOLV also calculates chemistry conditions throughout the steam-cycle system, as determined by the transport of volatile species such as ammonia, hydrazine, morpholine, and oxygen. A second model, SLUDGE, calculates the deposit loading in the SG as a function of time, based on concentrations of corrosion product in the final feedwater and plant operating conditions. Operations personnel can use this information to predict where to inspect and when to clean. In a future development, SLUDGE will track deposit loading arising from start-up crud bursts and will be used in conjunction with the thermohydraulics code, THIRST, to predict

  12. Nitrogen-system safety study: Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    1982-07-01

    The Department of Energy has primary responsibility for the safety of operations at DOE-owned nuclear facilities. The guidelines for the analysis of credible accidents are outlined in DOE Order 5481.1. DOE has requested that existing plant facilities and operations be reviewed for potential safety problems not covered by standard industrial safety procedures. This review is being conducted by investigating individual facilities and documenting the results in Safety Study Reports which will be compiled to form the Existing Plant Final Safety Analysis Report which is scheduled for completion in September, 1984. This Safety Study documents the review of the Plant Nitrogen System facilities and operations and consists of Section 4.0, Facility and Process Description, and Section 5.0, Accident Analysis, of the Final Safety Analysis Report format. The existing nitrogen system consists of a Superior Air Products Company Type D Nitrogen Plant, nitrogen storage facilities, vaporization facilities and a distribution system. The system is designed to generate and distribute nitrogen gas used in the cascade for seal feed, buffer systems, and for servicing equipment when exceptionally low dew points are required. Gaseous nitrogen is also distributed to various process auxiliary buildings. The average usage is approximately 130,000 standard cubic feet per day

  13. Backfitting of the nuclear plant V1 power control system

    International Nuclear Information System (INIS)

    Karpeta, C.; Rubek, J.; Stirsky, P.

    1985-01-01

    The paper deals with some aspects of implementation of modifications into the Czechoslovak nuclear plant V1 control system as called for on the basis of experience gained during the first period of the plant operation. Brief description of the plant power control system and its main functions is given. Some deficiencies in the system performance during abnormal conditions are outlined and measures taken to overcome them are presented. (author)

  14. Simulation for transient stability study of the Taiwan power system - a nuclear majority system

    International Nuclear Information System (INIS)

    Huang, J.C.C.

    1984-01-01

    A transient stability program was developed for the Taiwan Power Company, which has a high proportion of nuclear generation in its power system. This program offers a new territory to investigate nuclear plant effects on the power system transient stability. This program also provides a high speed tool for the Taipower system operational planning. A generalized procedure of synchronous machine modeling for a large-scale stability study is presented. The merits and weaknesses of machine modeling can be comprehended through each item of this procedure. Three types of nonlinear synchronous machine modeling implemented into this stability program are derived by following this procedure. A robust subroutine was derived to perform the fourth order Runge-Kutta integration method, making the software programming neat and systematical. For simulating the nuclear plant influence on the system, this program implemented an additional four functions: load-limit operation simulated by a low-value gate in the governor model, bypass valve capacity monitored by sending out a warning message, rotor overspeed protection relay, and generator anti-motoring relay

  15. The System 80+ Standard Plant design control document. Volume 19

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains five technical specification bases that are part of Appendix 16 A of the ADM Design and Analysis. They are: TS B3.3 Instrumentation Bases; TS B3.4 RCS Bases; TS B3.5 ECCS Bases; TS B3.6 Containment Systems Bases; and TS B3.7 Plant Systems Bases

  16. 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.)

  17. The development of an automatic classification system of nuclear power plant states

    International Nuclear Information System (INIS)

    Mitomo, Nobuo; Matsuoka, Takeshi

    2000-01-01

    For the future autonomous plant, automatic control and diagnostics are being incorporated and operators are mainly engaged in the high levels of diagnosis and decision-making in emergencies. Therefore these matters will be performed through the Man-Machine Interface(MMI). Ship Research Institute has been carrying out the research on the MMI system for autonomous power plants. The automatic classification system of plant states is one of the functions of this MMI and the system utilizes COBWEB, which is known as a way of clustering data to acquire concepts. In this paper, many plant states produced by a plant simulator we examined in order to confirm the effectiveness of this system. The system has well classified plant states produced by a plant simulator. (author)

  18. Analysis on Single Point Vulnerabilities of Plant Control System

    International Nuclear Information System (INIS)

    Chi, Moon Goo; Lee, Eun Chan; Bae, Yeon Kyoung

    2011-01-01

    The Plant Control System (PCS) is a system that controls pumps, valves, dampers, etc. in nuclear power plants with an OPR-1000 design. When there is a failure or spurious actuation of the critical components in the PCS, it can result in unexpected plant trips or transients. From this viewpoint, single point vulnerabilities are evaluated in detail using failure mode effect analyses (FMEA) and fault tree analyses (FTA). This evaluation demonstrates that the PCS has many vulnerable components and the analysis results are provided for OPR-1000 plants for reliability improvements that can reduce their vulnerabilities

  19. Analysis on Single Point Vulnerabilities of Plant Control System

    Energy Technology Data Exchange (ETDEWEB)

    Chi, Moon Goo; Lee, Eun Chan; Bae, Yeon Kyoung [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2011-08-15

    The Plant Control System (PCS) is a system that controls pumps, valves, dampers, etc. in nuclear power plants with an OPR-1000 design. When there is a failure or spurious actuation of the critical components in the PCS, it can result in unexpected plant trips or transients. From this viewpoint, single point vulnerabilities are evaluated in detail using failure mode effect analyses (FMEA) and fault tree analyses (FTA). This evaluation demonstrates that the PCS has many vulnerable components and the analysis results are provided for OPR-1000 plants for reliability improvements that can reduce their vulnerabilities.

  20. Retrofitting Trojan Nuclear Plant's spent resin transfer system

    International Nuclear Information System (INIS)

    Pierce, R.E.

    1979-01-01

    The spent resin slurry transport system at the Trojan Nuclear Plant operated by Portland General Electric Company is one of the most advanced systems of its type in the nuclear industry today. The new system affords the plant's operators safe remote sonic indication for spent resin and cover water levels, manual remote dewatering and watering capability to establish desirable resin-to-water volumetric ratios, reliable non-mechanical resin agitation utilizing fixed spargers, and controllable process flow utilizing a variable speed recessed impeller pump

  1. Self-control system in storage unit of PV plants

    Energy Technology Data Exchange (ETDEWEB)

    Al-Shaban, Saad; Mohmoud, Ali [Hadhramout Univ. of Science and Technology, Faculty of Engineering, Mukalla (Yemen)

    2000-04-01

    A new system for self-controlling of storage batteries being charged by PV plants has been developed. This provides enhanced system reliability, lower system cost, and simpler operation for the user. In this system, the only requirement is to design and select PV panels so that their voltage-sensitive region (on the I-V curve) coincides with that required for a simpler remote PV plant and for long periods. (Author)

  2. Arsenic-phosphorus interactions in the soil-plant-microbe system: Dynamics of uptake, suppression and toxicity to plants.

    Science.gov (United States)

    Anawar, Hossain M; Rengel, Zed; Damon, Paul; Tibbett, Mark

    2018-02-01

    High arsenic (As) concentrations in the soil, water and plant systems can pose a direct health risk to humans and ecosystems. Phosphate (Pi) ions strongly influence As availability in soil, its uptake and toxicity to plants. Better understanding of As(V)-Pi interactions in soils and plants will facilitate a potential remediation strategy for As contaminated soils, reducing As uptake by crop plants and toxicity to human populations via manipulation of soil Pi content. However, the As(V)-Pi interactions in soil-plant systems are complex, leading to contradictory findings among different studies. Therefore, this review investigates the role of soil type, soil properties, minerals, Pi levels in soil and plant, Pi transporters, mycorrhizal association and microbial activities on As-Pi interactions in soils and hydroponics, and uptake by plants, elucidate the key mechanisms, identify key knowledge gaps and recommend new research directions. Although Pi suppresses As uptake by plants in hydroponic systems, in soils it could either increase or decrease As availability and toxicity to plants depending on the soil types, properties and charge characteristics. In soil, As(V) availability is typically increased by the addition of Pi. At the root surface, the Pi transport system has high affinity for Pi over As(V). However, Pi concentration in plant influences the As transport from roots to shoots. Mycorrhizal association may reduce As uptake via a physiological shift to the mycorrhizal uptake pathway, which has a greater affinity for Pi over As(V) than the root epidermal uptake pathway. Copyright © 2017 Elsevier Ltd. All rights reserved.

  3. Optimization of control area ventilation systems for Japanese PWR plants

    International Nuclear Information System (INIS)

    Naitoh, T.; Nakahara, Y.

    1987-01-01

    The nuclear power plant has been required to reduce the cost for the purpose of making the low-cost energy since several years ago in Japan. The Heating, Ventilating and Air Conditioning system in the nuclear power plant has been also required to reduce its cost. On the other hand the ventilation system should add the improvable function according to the advanced plant design. In response to these different requirements, the ventilation criteria and the design of the ventilation system have been evaluated and optimized in Japanese PWR Plant design. This paper presents the findings of the authors' study

  4. Retrofit of safety and control systems in nuclear power plants

    International Nuclear Information System (INIS)

    Keiper, J.T.; Fassett, G.B.

    1986-01-01

    The modularity, compactness, compatibility, and licensability of the microcontrol system make it a cost-effective approach to obtain the benefits of digital control technology in the retrofit of nuclear power plants. Retrofit of individual loops or complete systems can be scheduled to meet the operational needs of the plant. The existing racks, panels, and cable systems can be utilized to the maximum extent to minimize the installed cost. Future expansion to total plant control or plant management is supported by the network communication module or gateway. The microcontrol module provides benefits now in improved operation, and future benefits in planned, controlled upgrading

  5. Liposome-Based Delivery Systems in Plant Polysaccharides

    International Nuclear Information System (INIS)

    Meiwan, C.; Yitao, W.; Yanfang, Z.; Xinsheng, P.; Jingjing, H.; Ping, Z.

    2012-01-01

    Plant polysaccharides consist of many monosaccharide by α or β glycosidic bond which can be extracted by the water, alcohol, lipophile liquid from a variety of plants including Cordyceps sinensis, astragalus, and mushrooms. Recently, many evidences illustrate that natural plant polysaccharides possess various biological activities including strengthening immunity, lowering blood sugar, regulating lipid metabolism, anti oxidation, anti aging, and antitumour. Plant polysaccharides have been widely used in the medical field due to their special features and low toxicity. As an important drug delivery system, liposomes can not only encapsulate small-molecule compound but also big-molecule drug; therefore, they present great promise for the application of plant polysaccharides with unique physical and chemical properties and make remarkable successes. This paper summarized the current progress in plant polysaccharides liposomes, gave an overview on their experiment design method, preparation, and formulation, characterization and quality control, as well as in vivo and in vitro studies. Moreover, the potential application of plant polysaccharides liposomes was prospected as well.

  6. Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

    Energy Technology Data Exchange (ETDEWEB)

    Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

    1983-02-01

    This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants.

  7. Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

    International Nuclear Information System (INIS)

    Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

    1983-02-01

    This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants

  8. The fate of arsenic in soil-plant systems.

    Science.gov (United States)

    Moreno-Jiménez, Eduardo; Esteban, Elvira; Peñalosa, Jesús M

    2012-01-01

    Arsenic is a natural trace element found in the environment. In some cases and places, human activities have increased the soil concentration of As to levels that exceed hazard thresholds. Amongst the main contributing sources of As contamination of soil and water are the following: geologic origin, pyriticmining, agriculture, and coal burning. Arsenic speciation in soils occurs and is relatively complex. Soils contain both organic and inorganic arsenic species. Inorganic As species include arsenite and arsenate, which are the most abundant forms found in the environment. The majority of As in aerated soils exists as H₂AsO₄- (acid soils) or HAsO₄²- (neutral species and basic). However, HA₃sO₃ is the predomiant anaerobic soils, where arsenic availability is higher and As(III) is more weakly retained in the soil matrix than is As(V). The availability of As in soils is usually driven by multiple factors. Among these factors is the presence of Fe-oxides and/or phosphorus, (co)precipitation in salts, pH, organic matter, clay content, rainfall amount, etc. The available and most labile As fraction can potentially be taken up by plant roots, although the concentration of this fraction is usually low. Arsenic has no known biological function in plants. Once inside root cells, As(V) is quickly reduced to As(III), and, in many plant species, becomes complexed. Phosphorus nutrition influences As(V) uptake and toxicity in plants, whilst silicon has similar influences on As(III). Plants cope with As contamination in their tissues by possessing detoxification mechanisms. Such mechanisms include complexation and compartmentalization. However, once these mechanisms are saturated, symptoms of phytotoxicity appear. Phytotoxic effects commonly observed from As exposure includes growth inhibition, chlorophyll degradation, nutrient depletion and oxidative stress. Plants vary in their ability to accumulate and tolerate As (from tolerant hyperaccumulators to sensitive

  9. 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

  10. Optimistic Selection Rule Better Than Majority Voting System

    Science.gov (United States)

    Sugiyama, Takuya; Obata, Takuya; Hoki, Kunihito; Ito, Takeshi

    A recently proposed ensemble approach to game-tree search has attracted a great deal of attention. The ensemble system consists of M computer players, where each player uses a different series of pseudo-random numbers. A combination of multiple players under the majority voting system would improve the performance of a Shogi-playing computer. We present a new strategy of move selection based on the search values of a number of players. The move decision is made by selecting one player from all M players. Each move is selected by referring to the evaluation value of the tree search of each player. The performance and mechanism of the strategy are examined. We show that the optimistic selection rule, which selects the player that yields the highest evaluation value, outperforms the majority voting system. By grouping 16 or more computer players straightforwardly, the winning rates of the strongest Shogi programs increase from 50 to 60% or even higher.

  11. AVLIS Production Plant Project Management Plan

    International Nuclear Information System (INIS)

    1984-01-01

    The AVLIS Production Plant is designated as a Major System Acquisition (in accordance with DOE Order 4240.IC) to deploy Atomic Vapor Laser Isotope Separation (AVLIS) technology at the Oak Ridge, Tennessee site, in support of the US Uranium Enrichment Program. The AVLIS Production Plant Project will deploy AVLIS technology by performing the design, construction, and startup of a production plant that will meet capacity production requirements of the Uranium Enrichment Program. The AVLIS Production Plant Project Management Plan has been developed to outline plans, baselines, and control systems to be employed in managing the AVLIS Production Plant Project and to define the roles and responsibilities of project participants. Participants will develop and maintain detailed procedures for implementing the management and control systems in agreement with this plan. This baseline document defines the system that measures work performed and costs incurred. This plan was developed by the AVLIS Production Plant Project staff of Martin Marietta Energy Systems, Inc. and Lawrence Livermore National Laboratory in accordance with applicable DOE directives, orders and notices. 38 figures, 19 tables

  12. Plant experience with an expert system for alarm diagnosis

    International Nuclear Information System (INIS)

    Gimmy, K.L.

    1986-01-01

    An expert system called Diagnosis of Multiple Alarms (DMA) is in routine use at four nuclear reactors operated by the DuPont Company. The system is wired to plant alarm annunciators and does event-tree analysis to see if a pattern exists. Any diagnosis is displayed to the plant operator and the corrective procedure to be followed is also identified. The display is automatically superseded if a higher priority diagnosis is made. The system is integrated with operator training and procedures. Operating results have been positive. DMA has diagnosed several hard-to-locate small leaks. There have been some false diagnosis, and realistic plant environments must be considered in such expert systems. 2 refs., 5 figs

  13. A review of major factors influencing plant responses to recreation impacts

    Science.gov (United States)

    Kuss, Fred R.

    1986-09-01

    This article reviews some of the more important factors found to influence the susceptibility of plants to trampling impacts associated with recreational use of natural areas. A three-way interaction mediates plant responses to impacts: plant x environment x stress level(s). Plant responses vary in part according to the genetic constitution of the plant, life and growth form, the adaptive flexibility of the plant, and anatomical differences inherent to growth habit and morphology. Other factors that influence plant sensitivities to impacts are the habitat environments in which plants grow, since a number of conditions such as moisture excesses or deficiencies, nitrogen or oxygen starvation, late frosts, etc., cause physiological injury and may increase plant sensitivity to impacts. Among the environmental factors that may increase or lessen plant sensitivities to impacts are soil moisture levels, canopy density, elevation, aspect, microclimate, soil drainage, texture, fertility and productivity. Seasonal influences also bear consideration since environmental changes and phonological and physiological events are mediated by time of year. Stresses are caused by both direct and indirect forms of impact and vary according to season of use, frequency and amount of use, and the type of activity. These interactions are further complicated by evidence that inter- and intraspecific competition, antagonism, and commensalism may influence differences in the sensitivity of plant communities to impacts.

  14. U.S. and South Korean Cooperation in the World Nuclear Energy Market: Major Policy Considerations

    Science.gov (United States)

    2010-01-21

    system and other major components. • Samsung C&T Corporation. Plant construction. • Hyundai Engineering and Construction. Plant construction...market. Other countries that have been mentioned in the news media include Vietnam, Malaysia , Thailand, and Middle East neighbors of the UAE.25 A Korean

  15. Mass balance of pent achloroni trobenzene-14c and metabolites in a closed aerated soil plant or soil-system

    International Nuclear Information System (INIS)

    Kamal, M.

    1984-01-01

    Two experiments were carried out with pentachloronitrobenzene- 14 C and soils with and without plants in a closed aerated laboratory system. In both experiments, degradation to 14 CO 2 within 16 or 53 days, respectively, was very low (=0,01% of initially applied 14 C). Volatilization loses were about 15% in the system with plants (16 days) and were negligible in the soil without plants (53 days). The uptake into plants within 16 days was 5.26% of initially applied 14 C(0.86% unchanged parent compound, 3.35% soluble metabolites, and 1.05% unextractable residues); the major portion of soluble metabolites was highly polar conjugates which were not characterized further. The radioactivity left in both soils after 16 or 53 days, respectively, considered of 57 or 37% unchanged parent compound, 10 or 42% soluble metabolites, and 13 or 25% soil-bound residues. In the soil without plants, the following conversion products were identified after 53 days: pentachloroaniline (18.7% of initially applied 14 C), pentachlorthioanisole (17.3%), pentachlorobenzene, and pentachlorophenylmethylsulphoxide (2.6% each). (author)

  16. Major activated corrosion products cobalt, silver and antimony in the primary coolant of PWR power plants

    International Nuclear Information System (INIS)

    Xu Mingxia

    2012-01-01

    The production of the major activated corrosion products such as cobalt, silver and antimony in the primary coolant of PWR power plants and the impacts on the increase of the dose rates caused by these corrosion products during the shutdown are described in the paper. Investigating the corrosion product behavior during the operation and shutdown periods aims at detecting the appearance of these radiological pollutants in the early time and searching relevant solutions that may enable eventually to decrease the dose rate. The solutions may include: Replacing critical material in the primary system's equipment and components, which contact with primary coolant circuit to possibly limit the source term, Elaborating strictly the specific chemical and shutdown procedure to optimize the purification capacity and to minimize the over-contaminations; Improving purification techniques according to the real operation circumstance, and limiting the impacts of these pollutants. It is obvious in the real practices that implementing appropriate solution will be benefit to decrease or limit the pollutants species like cobalt, silver and antimony. (author)

  17. Software V ampersand V methods for digital plant protection system

    International Nuclear Information System (INIS)

    Kim, Hung-Jun; Han, Jai-Bok; Chun, Chong-Son; Kim, Sung; Kim, Kern-Joong.

    1997-01-01

    Careful thought must be given to software design in the development of digital based systems that play a critical role in the successful operation of nuclear power plants. To evaluate the software verification and validation methods as well as to verify its system performance capabilities for the upgrade instrumentation and control system in the Korean future nuclear power plants, the prototype Digital Plant, Protection System (DPPS) based on the Programmable Logic Controller (PLC) has been constructed. The system design description and features are briefly presented, and the software design and software verification and validation methods are focused. 6 refs., 2 figs

  18. Pattern-recognition system application to EBR-II plant-life extension

    International Nuclear Information System (INIS)

    King, R.W.; Radtke, W.H.; Mott, J.E.

    1988-01-01

    A computer-based pattern-recognition system, the System State Analyzer (SSA), is being used as part of the EBR-II plant-life extension program for detection of degradation and other abnormalities in plant systems. The SSA is used for surveillance of the EBR-II primary system instrumentation, primary sodium pumps, and plant heat balances. Early results of this surveillance indicate that the SSA can detect instrumentation degradation and system performance degradation over varying time intervals, and can provide derived signal values to replace signals from failed critical sensors. These results are being used in planning for extended-life operation of EBR-II

  19. The System 80+ Standard Plant design control document. Volume 18

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains the following technical specifications of section 16 (Technical Specifications) of the ADM Design and Analysis: TS 3.3 Instrumentation; TS 3.4 Reactor Coolant System; TS 3.5 Emergency Core Cooling System; TS 3.6 Containment Systems; TS 3.7 Plant Systems; TS 3.8 Electrical Power Systems; TS 3.9 Refueling Operations; TS 4.0 Design Features; TS 5.0 Administrative Controls. Appendix 16 A Tech Spec Bases is also included. It contains the following: TS B2.0 Safety Limits Bases; TS B3.0 LCO Applicability Bases; TS B3.1 Reactivity Control Bases; TS B3.2 Power Distribution Bases

  20. Design and analysis of heat recovery system in bioprocess plant

    International Nuclear Information System (INIS)

    Anastasovski, Aleksandar; Rašković, Predrag; Guzović, Zvonimir

    2015-01-01

    Highlights: • Heat integration of a bioprocess plant is studied. • Bioprocess plant produces yeast and ethyl-alcohol. • The design of a heat recovery system is performed by batch pinch analysis. • Direct and indirect heat integration approaches are used in process design. • The heat recovery system without a heat storage opportunity is more profitable. - Abstract: The paper deals with the heat integration of a bioprocess plant which produces yeast and ethyl-alcohol. The referent plant is considered to be a multiproduct batch plant which operates in a semi-continuous mode. The design of a heat recovery system is performed by batch pinch analysis and by the use of the Time slice model. The results obtained by direct and indirect heat integration approaches are presented in the form of cost-optimal heat exchanger networks and evaluated by different thermodynamic and economic indicators. They signify that the heat recovery system without a heat storage opportunity can be considered to be a more profitable solution for the energy efficiency increase in a plant

  1. Water system integration of a chemical plant

    International Nuclear Information System (INIS)

    Zheng Pingyou; Feng Xiao; Qian Feng; Cao Dianliang

    2006-01-01

    Water system integration can minimize both the freshwater consumption and the wastewater discharge of a plant. In industrial applications, it is the key to determine reasonably the contaminants and the limiting concentrations, which will decide the freshwater consumption and wastewater discharge of the system. In this paper, some rules to determine the contaminants and the limiting concentrations are proposed. As a case study, the water system in a chemical plant that produces sodium hydroxide and PVC (polyvinyl chloride) is integrated. The plant consumes a large amount of freshwater and discharges a large amount of wastewater, so minimization of both the freshwater consumption and the wastewater discharge is very important to it. According to the requirements of each water using process on the water used in it, the contaminants and the limiting concentrations are determined. Then, the optimal water reuse scheme is firstly studied based on the water network with internal water mains. To reduce the freshwater consumption and the wastewater discharge further, decentralized regeneration recycling is considered. The water using network is simplified by mixing some of the used water. After the water system integration, the freshwater consumption is reduced 25.5%, and the wastewater discharge is reduced 48%

  2. 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

  3. 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.

  4. Expert systems to assist plant operation

    International Nuclear Information System (INIS)

    Matsumoto, Yoshihiro; Mori, Nobuyuki; Wada, Norio

    1985-01-01

    Large-scale real-time process control systems, such as those for electric power dispatching, large thermal and nuclear power stations, steel mill plants and manufacturing automation systems, need expert systems to assist operator's decision. The expert systems newly developed to fulfill the requirement are founded on OKBS (object oriented knowledge based system). OKBS provides various object types: fuzzy logic type, production rule type, frame type, state transition type, abstract data type and input/output transformation type. (author)

  5. A modular approach to modeling power plant systems

    International Nuclear Information System (INIS)

    Yee, N.S.

    1990-01-01

    This paper reports on power plants which are large, non-linear systems with numerous interactions between its component parts. In the analysis of such complex systems, dynamic simulation is recognized as a powerful method of keeping track of the myriad of interactions. A simulation can be used to answer the what if questions that are asked when replacing components, changing operational procedures, or training operators. While there are many applications for the simulation of power plant components and systems, its use is often discouraged because it can be difficult and expensive. Power plant engineering is itself a multi-disciplinary field involving fluid mechanics, heat transfer, thermodynamics, chemical engineering, nuclear engineering, and electrical engineering. Simulation requires, in addition, knowledge in model formulation, computer programming and numerical solution of differential equations

  6. High Efficiency Nuclear Power Plants Using Liquid Fluoride Thorium Reactor Technology

    Science.gov (United States)

    Juhasz, Albert J.; Rarick, Richard A.; Rangarajan, Rajmohan

    2009-01-01

    An overall system analysis approach is used to propose potential conceptual designs of advanced terrestrial nuclear power plants based on Oak Ridge National Laboratory (ORNL) Molten Salt Reactor (MSR) experience and utilizing Closed Cycle Gas Turbine (CCGT) thermal-to-electric energy conversion technology. In particular conceptual designs for an advanced 1 GWe power plant with turbine reheat and compressor intercooling at a 950 K turbine inlet temperature (TIT), as well as near term 100 MWe demonstration plants with TITs of 950 and 1200 K are presented. Power plant performance data were obtained for TITs ranging from 650 to 1300 K by use of a Closed Brayton Cycle (CBC) systems code which considered the interaction between major sub-systems, including the Liquid Fluoride Thorium Reactor (LFTR), heat source and heat sink heat exchangers, turbo-generator machinery, and an electric power generation and transmission system. Optional off-shore submarine installation of the power plant is a major consideration.

  7. Plant operator selection system for evaluating employment candidates' potential for success in electric power plant operations positions

    International Nuclear Information System (INIS)

    Dunnette, M.D.

    1982-01-01

    The Plant Operator Selection System is a battery of tests and questionnaires that can be administered to job candidates in less than three hours. Various components of the battery measure what a job candidate has accomplished in previous educational and work situations, how well a candidate compares with others on a number of important aptitudes or abilities, and whether or not a candidate possesses the kind of personal stability required in power plant operations positions. A job candidate's answers to the tests and questionnaires of the Plant Operator Selection System are scored and converted to an OVERALL POTENTIAL INDEX. Values of the OVERALL POTENTIAL INDEX [OPI] range between 0 and 15. Candidates with high OPI values are much more likely to become effective and successful plant operators than candidates with low OPI values. It is possible to estimate the financial advantages to a company of using the Plant Operator Selection System in evaluating candidates for plant operations jobs

  8. Bioelectric potentials in the soil-plant system

    Science.gov (United States)

    Pozdnyakov, A. I.

    2013-07-01

    A detailed study of the electric potentials in the soil-plant system was performed. It was found that the electric potential depends on the plant species and the soil properties. A theoretical interpretation of the obtained data was given. All the plants, independently from their species and their state, always had a negative electric potential relative to the soil. The electric potential of the herbaceous plants largely depended on the leaf area. In some plants, such as burdock ( Arctium lappa) and hogweed ( Heracleum sosnowskyi), the absolute values of the negative electric potential exceeded 100 mV. The electric potential was clearly differentiated by the plant organs: in the flowers, it was lower than in the leaves; in the leaves, it was usually lower than in the leaf rosettes and stems. The electric potentials displayed seasonal dynamics. As a rule, the higher the soil water content, the lower the electric potential of the plants. However, an inverse relationship was observed for dandelions ( Taraxacum officinale). It can be supposed that the electric potential between the soil and the plant characterizes the vital energy of the plant.

  9. Gravisensitivity of various host plant -virus systems in simulated microgravity

    Science.gov (United States)

    Mishchenko, Lidiya; Taran, Oksana; Gordejchyk, Olga

    In spite of considerable achievements in the study of gravity effects on plant development, some issues of gravitropism, like species-specificity and gravitation response remain unclear. The so-lution of such problems is connected with the aspects of life supply, in piloted space expeditions. The role of microgravity remains practically unstudied in the development of relations in the system host plant-virus, which are important for biotechnologies in crop production. It is ev-ident that the conditions of space flight can act as stressors, and the stress inducted by them favors the reactivation of latest herpes viruses in humans (satish et al., 2009) Viral infections of plants, which also can be in a latest state at certain stages of plant organism development, cause great damage to the growth and development of a host plant. Space flight conditions may cause both reactivation of latent viral infection in plants and its elimination, as it has been found by us for the system WSMW -wheat (Mishchenko et al., 2004). Our further research activities were concentrated on the identification of gravisensitivity in the system virus -potato plant to find out whether there was any species -related specificity of the reaction. In our research we used potato plants of Krymska Rosa, Zhuravushka, Agave, Belarosa, Kupalinka, and Zdubytok varieties. Simulated microgravity was ensured by clinostats KG-8 and Cycle -2. Gravisensitiv-ity has been studied the systems including PVX, PVM and PVY. Virus concentrations have been determined by ELISA using LOEWE reagents (placecountry-regionGermany). Virus iden-tification by morphological features were done by electron microscopy. For the system PVX -potato plant, we found the reduction in virus antigens content with prolonged clinostating. On the 18th day of cultivation, the plants showed a high level of X-virus antigen content on both stationary (control) and clinostated variants. On 36th and 47th day, depending plant variety, clinostated

  10. Seismic qualification of PWR plant auxiliary feedwater systems

    International Nuclear Information System (INIS)

    Lu, S.C.; Tsai, N.C.

    1983-08-01

    The NRC Standard Review Plan specifies that the auxiliary feedwater (AFW) system of a pressurized water reactor (PWR) is a safeguard system that functions in the event of a Safe Shutdown Earthquake (SSE) to remove the decay heat via the steam generator. Only recently licensed PWR plants have an AFW system designed to the current Standard Review Plan specifications. The NRC devised the Multiplant Action Plan C-14 in order to make a survey of the seismic capability of the AFW systems of operating PWR plants. The purpose of this survey is to enable the NRC to make decisions regarding the need of requiring the licensees to upgrade the AFW systems to an SSE level of seismic capability. To implement the first phase of the C-14 plan, the NRC issued a Generic Letter (GL) 81-14 to all operating PWR licensees requesting information on the seismic capability of their AFW systems. This report summarizes Lawrence Livermore National Laboratory's efforts to assist the NRC in evaluating the status of seismic qualification of the AFW systems in 40 PWR plants, by reviewing the licensees' responses to GL 81-14

  11. Knowledge based system for fouling assessment of power plant boiler

    International Nuclear Information System (INIS)

    Afgan, N.H.; He, X.; Carvalho, M.G.; Azevedo, J.L.T.

    1999-01-01

    The paper presents the design of an expert system for fouling assessment in power plant boilers. It is an on-line expert system based on selected criteria for the fouling assessment. Using criteria for fouling assessment based on 'clean' and 'not-clean' radiation heat flux measurements, the diagnostic variable are defined for the boiler heat transfer surface. The development of the prototype knowledge-based system for fouling assessment in power plants boiler comprise the integrations of the elements including knowledge base, inference procedure and prototype configuration. Demonstration of the prototype knowledge-based system for fouling assessment was performed on the Sines power plant. It is a 300 MW coal fired power plant. 12 fields are used with 3 on each side of boiler

  12. Operation status display and monitoring system for BWR nuclear power plant

    International Nuclear Information System (INIS)

    Wakabayashi, Yasuo; Hayakawa, Hiroyasu; Kawamura, Atsuo; Kaneda, Mitsunori.

    1982-01-01

    Lately, the development of the system has been made for BWR plants, which monitors the operating status not only in normal operation but also in abnormal state and also for plant safety. Recently, the improvement of man-machine interface has been tried through the practical use of technique which displays data collectively on a CRT screen relating them mutually. As one of those results, the practical use of an electronic computer and color CRT display for No. 1 unit in the Fukushima No. 2 Nuclear Power Station (2F-1), Tokyo Electric Power Co., is described. Also, new centralized control panels containing such systems were used for the 1100 MWe BWR nuclear power plants now under construction, No. 3 unit of the Fukushima No. 2 Power Station and No. 1 unit of Kashiwazaki-Kariwa Nuclear Power Station (2F-3 and K-1, respectively). The display and monitoring system in 2F-1 plant is the first one in which a computer and color CRTs were practically employed for a BWR plant in Japan, and already in commercial operation. The advanced operating status monitoring system, to which the result of evaluation of the above system was added, was incorporated in the new centralized control panels presently under production for 2F-3 and K-1 plants. The outline of the system, the functions of an electronic computer, plant operating status monitor, surveillance test guide, the automation of plant operation and auxiliary operation guide are reported for these advanced monitoring system. It was confirmed that these systems are useful means to improve the man-machine communication for plant operation minitoring. (Wakatsuki, Y.)

  13. The System 80+ Standard Plant design control document. Volume 2

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the following information of the CDM: (2.8) Steam and power conversion; (2.9) Radioactive waste management; (2.10) Tech Support Center; (2.11) Initial test program; (2.12) Human factors; and sections 3, 4, and 5. Also covered in this volume are parts 1--6 of section 1 (General Plant Description) of the ADM Design and Analysis

  14. Nuclear power plant personnel training process management system

    International Nuclear Information System (INIS)

    Arjona Vazquez, Orison; Venegas Bernal, Maria del Carmen; Armeteros Lopez, Ana L.

    1996-01-01

    The system in charge the management of the training process personnel from a nuclear power plant was designed taking into account all the requirements stated in the training guide for nuclear power plant personnel and their evaluation, which were prepared by the IAEA in 1995 in order to implement the SAT in the training programs for nuclear plant personnel. In the preparations of formats and elements that shape the system, account has been taken of the views expressed in such a guide, in some other bibliography that was consulted, and in the authors own opinion mainly with regard to those issues which the guide does not go deeper into

  15. Nuclear plant requirements during power system restoration

    International Nuclear Information System (INIS)

    Adamski, G.; Jenkins, R.; Gill, P.

    1995-01-01

    This paper is one of a series presented on behalf of the System Operation Subcommittee with the intent of focusing industry attention on power system restoration issues. This paper discusses a number of nuclear power plant requirements that require special attention during power system restoration

  16. HVAC systems and nuclear plant safety. Final report, May 1992

    International Nuclear Information System (INIS)

    1992-05-01

    The primary objective of this study was to provide perspective on the overall risk impact of heating, ventilating, and air conditioning (HVAC) system problems. Industry experience with HVAC system problems is documented and analyzed. In addition, the results of 10 plant-specific probabilistic risk assessments (PRA) were reviewed to determine the contribution of HVAC systems to the risk of core damage. The PRAs included in this review cover a broad range of plant types and operating conditions. The review found that the impact of HVAC systems on risk is plant specific. These results exhibit a broad range of frequencies for HVAC contribution to risk, and the percentage of total core damage due to HVAC problems also had a wide variability. Plant-specific differences in design, environment, operation, and maintenance are the primary factors in determining the risk contribution of HVAC systems. (author)

  17. Sea water pumping-up power plant system combined with nuclear power plant

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Tanaka, Masayuki.

    1991-01-01

    It is difficult to find a site suitable to construction for a sea water pumping-up power plant at a place relatively near the electric power consumption area. Then, a nuclear power plant is set at the sea bottom or the land portion of a sea shore near the power consumption area. A cavity is excavated underground or at the bottom of the sea in the vicinity of the power plant to form a lower pond, and the bottom of the sea, as an upper pond and the lower pond are connected by a water pressure pipe and a water discharge pipe. A pump water turbine is disposed therebetween, to which electric power generator is connected. In addition, an ordinary or emergency cooling facility in the nuclear power plant is constituted such that sea water in the cavity is supplied by a sea water pump. Accordingly, the sea water pumping-up plant system in combination with the nuclear power plant is constituted with no injuring from salts to animals and plants on land in the suburbs of a large city. The cost for facilities for supplying power from a remote power plant to large city areas and power loss are decreased and stable electric power can be supplied. (N.H.)

  18. Monoterpenes Released from Fruit, Plant, and Vegetable Systems

    Directory of Open Access Journals (Sweden)

    Mohammad Asif Iqbal

    2014-09-01

    Full Text Available To quantify the emission rate of monoterpenes (MTs from diverse natural sources, the sorbent tube (ST-thermal desorption (TD method was employed to conduct the collection and subsequent detection of MTs by gas chromatography. The calibration of MTs, when made by both mass spectrometric (MS and flame ionization detector (FID, consistently exhibited high coefficient of determination values (R2 > 0.99. This approach was employed to measure their emission rate from different fruit/plant/vegetable (F/P/V samples with the aid of an impinger-based dynamic headspace sampling system. The results obtained from 10 samples (consisting of carrot, pine needle (P. sylvestris, tangerine, tangerine peel, strawberry, sepals of strawberry, plum, apple, apple peel, and orange juice marked α-pinene, β-pinene, myrcene, α-terpinene, R-limonene, γ-terpinene, and p-cymene as the most common MTs. R-limonene was the major species emitted from citrus fruits and beverages with its abundance exceeding 90%. In contrast, α-pinene was the most abundant MT (37% for carrot, while it was myrcene (31% for pine needle. The overall results for F/P/V samples confirmed α-pinene, β-pinene, myrcene, α-terpinene, and γ-terpinene as common MTs. Nonetheless, the types and magnitude of MTs released from fruits were distinguished from those of vegetables and plants.

  19. A fault diagnosis system for nuclear power plant operation

    International Nuclear Information System (INIS)

    Ohga, Yukiharu; Hayashi, Yoshiharu; Yuchi, Hiroyuki; Utena, Shunsuke; Maeda, Akihiko

    2002-01-01

    A fault diagnosis system has been developed to support operators in nuclear power plants. In the system various methods are combined to get a diagnosis result which provides better detection sensitivity and result reliability. The system is composed of an anomaly detection part with diagnosis modules, an integration part which obtains the diagnosis result by combining results from each diagnosis module, and a prediction part with state prediction and estimation modules. For the anomaly detection part, three kinds of modules are prepared: plant signal processing, early fault detection and event identification modules. The plant signal processing module uses wavelet transform and chaos technologies as well as fast Fourier transform (FFT) to analyze vibration sensor signals and to detect signal anomaly. The early fault detection module uses the neural network model of a plant subprocess to estimate the process variable values assuming normal conditions, and to detect an anomaly by comparing the measured and estimated values. The event identification module identifies the kind of occurring event by using the neural network and knowledge processing. In the integration part the diagnosis is performed by using knowledge processing. The knowledge for diagnosis is structured based on the means-ends abstraction hierarchy to simplify knowledge input and maintenance. In the prediction part, the prediction module predicts the future changes of process variables and plant interlock statuses and the estimation module estimates the values of unmeasurable variables. A prototype system has been developed and the system performance was evaluated. The evaluation results show that the developed technologies are effective to improve the human-machine system for plant operation. (author)

  20. Systems for harvesting and handling cotton plant residue

    Energy Technology Data Exchange (ETDEWEB)

    Coates, W. [Univ. of Arizona, Tucson, AZ (United States)

    1993-12-31

    In the warmer regions of the United States, cotton plant residue must be buried to prevent it from serving as an overwintering site for insect pests such as the pink bollworm. Most of the field operations used to bury the residue are high energy consumers and tend to degrade soil structure, thereby increasing the potential for erosion. The residue is of little value as a soil amendment and consequently is considered a negative value biomass. A commercial system to harvest cotton plant residue would be of both economic and environmental benefit to cotton producers. Research has been underway at the University of Arizona since the spring of 1991 to develop a commercially viable system for harvesting cotton plant residue. Equipment durability, degree of densification, energy required, cleanliness of the harvested material, and ease of product handling and transport are some of the performance variables which have been measured. Two systems have proven superior. In both, the plants are pulled from the ground using an implement developed specifically for the purpose. In one system, the stalks are baled using a large round baler, while in the other the stalks are chopped with a forage harvester, and then made into packages using a cotton module maker. Field capacities, energy requirements, package density and durability, and ease of handling with commercially available equipment have been measured for both systems. Selection of an optimum system for a specific operation depends upon end use of the product, and upon equipment availability.

  1. How to design electrical systems with central control capability for industrial plants

    Energy Technology Data Exchange (ETDEWEB)

    Cigolini, S.; Galati, G.; Lionetto, P.F.; Stiz, M. (Siemens, Milan (Italy) Centro Elettrotecnico Sperimentale Italiano, Milan (Italy))

    1991-12-01

    The modern centralized control system, incorporating microprocessors, constitutes an extremely efficacious instrument for the management of an industrial plant's electrical system and provides the performance, reliability, flexibility and safety features required by today's technologically advanced plant processes. The use of intelligent centralized control systems, capable of autonomous operation and dialoguing with industrial plant electrical systems, simplifies the design of the overall plant. This paper reviews the main design criteria for the automated systems and gives examples of some suitable commercially available intelligent systems.

  2. An intelligent tutoring system for a power plant simulator

    Energy Technology Data Exchange (ETDEWEB)

    Seifi, H.; Seifi, A.R. [Tarbiat Modarres University, Tehran (Iran). Faculty of Engineering, Dept. of Electrical Engineers

    2002-07-28

    An intelligent tutoring system (ITS) is proposed for a power plant simulator. With a well designed ITS, the need for an instructor is minimized and the operator may readily and efficiently take, in real-time, the control of simulator with appropriate messages he(she) gets from the tutoring system. Using SIMULINK and based on object oriented programming (OOP) and C programming language, a fossil-fuelled power plant simulator with an ITS is proposed. Promising results are demonstrated for a typical power plant.

  3. Food-Energy Interactive Tradeoff Analysis of Sustainable Urban Plant Factory Production Systems

    Directory of Open Access Journals (Sweden)

    Li-Chun Huang

    2018-02-01

    Full Text Available This research aims to analyze the food–energy interactive nexus of sustainable urban plant factory systems. Plant factory systems grow agricultural products within artificially controlled growing environment and multi-layer vertical growing systems. The system controls the supply of light, temperature, humidity, nutrition, water, and carbon dioxide for growing plants. Plant factories are able to produce consistent and high-quality agricultural products within less production space for urban areas. The production systems use less labor, pesticide, water, and nutrition. However, food production of plant factories has many challenges including higher energy demand, energy costs, and installation costs of artificially controlled technologies. In the research, stochastic optimization model and linear complementarity models are formulated to conduct optimal and equilibrium food–energy analysis of plant factory production. A case study of plant factories in the Taiwanese market is presented.

  4. Development trends for diagnostic systems in nuclear power plants

    International Nuclear Information System (INIS)

    Kunze, U.; Pohl, U.

    1998-01-01

    Monitoring systems used in nuclear power plants have made remarkable progress over the past four or five years. Development has followed the trends and changes in philosophy for the purpose of monitoring systems in nuclear power plants: They are no longer expected to fulfill only safety tasks, the plant personnel require information on which to base condition-oriented maintenance. A new generation of monitoring and diagnostic systems has been developed by Siemens recently. This new generation, called Series '95, is PC-based. An overview is given for the KUeS '95 loose parts diagnostic system, the SUeS '95 vibration monitoring system, the FLUeS leak detection system and the SIPLUG valve diagnostics system. The objectives behind the development of these new systems are both safety-related and economic. The new systems improve the reliability and quality of monitoring techniques and incorporate better detection and diagnostic capabilities. Progress has also been made in automation of the systems so as to reduce routine work, give higher sensitivity for the monitoring task and reduce the scope of maintenance. (author)

  5. An online ID identification system for liquefied-gas cylinder plant

    Science.gov (United States)

    He, Jin; Ding, Zhenwen; Han, Lei; Zhang, Hao

    2017-11-01

    An automatic ID identification system for gas cylinders' online production was developed based on the production conditions and requirements of the Technical Committee for Standardization of Gas Cylinders. A cylinder ID image acquisition system was designed to improve the image contrast of ID regions on gas cylinders against the background. Then the ID digits region was located by the CNN template matching algorithm. Following that, an adaptive threshold method based on the analysis of local average grey value and standard deviation was proposed to overcome defects of non-uniform background in the segmentation results. To improve the single digit identification accuracy, two BP neural networks were trained respectively for the identification of all digits and the easily confusable digits. If the single digit was classified as one of confusable digits by the former BP neural network, it was further tested by the later one, and the later result was taken as the final identification result of this single digit. At last, the majority voting was adopted to decide the final identification result for the 6-digit cylinder ID. The developed system was installed on a production line of a liquefied-petroleum-gas cylinder plant and worked in parallel with the existing weighing step on the line. Through the field test, the correct identification rate for single ID digit was 94.73%, and none of the tested 2000 cylinder ID was misclassified through the majority voting.

  6. Food-Energy Interactive Tradeoff Analysis of Sustainable Urban Plant Factory Production Systems

    OpenAIRE

    Li-Chun Huang; Yu-Hui Chen; Ya-Hui Chen; Chi-Fang Wang; Ming-Che Hu

    2018-01-01

    This research aims to analyze the food–energy interactive nexus of sustainable urban plant factory systems. Plant factory systems grow agricultural products within artificially controlled growing environment and multi-layer vertical growing systems. The system controls the supply of light, temperature, humidity, nutrition, water, and carbon dioxide for growing plants. Plant factories are able to produce consistent and high-quality agricultural products within less production space for urban a...

  7. Directional Selection from Host Plants Is a Major Force Driving Host Specificity in Magnaporthe Species.

    Science.gov (United States)

    Zhong, Zhenhui; Norvienyeku, Justice; Chen, Meilian; Bao, Jiandong; Lin, Lianyu; Chen, Liqiong; Lin, Yahong; Wu, Xiaoxian; Cai, Zena; Zhang, Qi; Lin, Xiaoye; Hong, Yonghe; Huang, Jun; Xu, Linghong; Zhang, Honghong; Chen, Long; Tang, Wei; Zheng, Huakun; Chen, Xiaofeng; Wang, Yanli; Lian, Bi; Zhang, Liangsheng; Tang, Haibao; Lu, Guodong; Ebbole, Daniel J; Wang, Baohua; Wang, Zonghua

    2016-05-06

    One major threat to global food security that requires immediate attention, is the increasing incidence of host shift and host expansion in growing number of pathogenic fungi and emergence of new pathogens. The threat is more alarming because, yield quality and quantity improvement efforts are encouraging the cultivation of uniform plants with low genetic diversity that are increasingly susceptible to emerging pathogens. However, the influence of host genome differentiation on pathogen genome differentiation and its contribution to emergence and adaptability is still obscure. Here, we compared genome sequence of 6 isolates of Magnaporthe species obtained from three different host plants. We demonstrated the evolutionary relationship between Magnaporthe species and the influence of host differentiation on pathogens. Phylogenetic analysis showed that evolution of pathogen directly corresponds with host divergence, suggesting that host-pathogen interaction has led to co-evolution. Furthermore, we identified an asymmetric selection pressure on Magnaporthe species. Oryza sativa-infecting isolates showed higher directional selection from host and subsequently tends to lower the genetic diversity in its genome. We concluded that, frequent gene loss or gain, new transposon acquisition and sequence divergence are host adaptability mechanisms for Magnaporthe species, and this coevolution processes is greatly driven by directional selection from host plants.

  8. Distributing radiation management system of nuclear power plants

    International Nuclear Information System (INIS)

    Mihoya, Eiichi; Akashi, Michio

    1999-01-01

    The importance of radiation management for nuclear facilities including nuclear power plants has increased as the general public understanding has progressed, and necessary information for management must be processed exactly and quickly. In nuclear power plants, radiation management is performed by each individual operation, and collected information is managed by the system of each operation. The distributing radiation management system has been developed aiming to use a general-purpose LAN and make quick and efficient use of information managed by individual operations. This paper describes the system configuration and functions. (author)

  9. National Plant Germplasm System: Critical Role of Customer Service

    Science.gov (United States)

    The National Plant Germplasm System (NPGS) conserves plant genetic resources, not only for use by future generations, but for immediate use by scientists and educators around the world. With a great deal of interaction between genebank curators and users of plant genetic resources, customer service...

  10. Biochar application reduce ammonia volatilization in a soil-plant system: A closed chamber experiment

    Science.gov (United States)

    Mandal, Sanchita; Donner, Erica; Smith, Euan; Lombi, Enzo

    2017-04-01

    Ammonia (NH3) volatilization is considered as one of the major mechanisms responsible for the loss of nitrogen (N) from soil-plant systems worldwide. About 10-30% of N can be lost as NH3 volatilization, which constitutes a significant economic loss. In recent years carbon-based materials such as biochar have created a great research interest because of their ability to increase soil fertility by reducing nutrient loss and pollutants bioavailability in soil. Most of the studies so far have investigated how biochar addition can reduce NH3 volatilization from soils but less information is available for soil-plant systems. In this research, wheat plants (Triticum aestivum, variety: Calingiri) were grown in a calcareous soil (pH 8, calcarosol) inside a closed chamber system to assess both ammonia volatilization and plant N uptake. In this specialized glass chamber air was passed through an inlet where the flow rate was maintained using an air pump (3.5 L min-1). The air outlet was passed through a sulphuric acid trap which was used to capture the volatilized NH3 from the chamber. Plants were watered using the inlet to maintain 50% field capacity throughout the incubation. Two different biochar samples were used in this study: a poultry manure biochar (PM-BC) and a green waste compost biochar (GW-BC) produced at 250 ˚C. Five different application rates were tested (0, 0.5, 1, 1.5, and 2%). The soil was mixed with biochar samples, water, N, P, K, Ca, Mg, and S for one week before sowing. After one week of germination, plants were transferred to the chamber for further three weeks incubation for NH3 volatilization measurement. The study identified that biochar application reduced the NH3 volatilization and increase the plant biomass. Biochar application at 0.5 and 2% decreased the NH3 volatilization by 36 and 48% respectively. The N uptake of the plants also increased from 2.9 to 28% at 0.5 and 2% application rates respectively. The dry biomass of the plant also increased

  11. The development and use of plant models to assist with both the commissioning and performance optimisation of plant control systems

    International Nuclear Information System (INIS)

    Conner, A.S.; Region, S.E.

    1984-01-01

    Successful engagement of cascade control systems used to control complex nuclear plant often present control engineers with difficulties when trying to obtain early automatic operation of these systems. These difficulties often arise because prior to the start of live plant operation, control equipment performance can only be assessed using open loop techniques. By simulating simple models of plant on a computer and linking it to the site control equipment, the performance of the system can be examined and optimised prior to live plant operation. This significantly reduces the plant down time required to correct control equipment performance faults during live plant operation

  12. An evaluation method of fault-tolerance for digital plant protection system in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Jun Seok; Kim, Man Cheol; Seong, Poong Hyun; Kang, Hyun Gook; Jang, Seung Cheol

    2005-01-01

    In recent years, analog based nuclear power plant (NPP) safety related instrumentation and control (I and C) systems have been replaced to modern digital based I and C systems. NPP safety related I and C systems require very high design reliability compare to the conventional digital systems so that reliability assessment is very important. In the reliability assessment of the digital system, fault tolerance evaluation is one of the crucial factors. However, the evaluation is very difficult because the digital system in NPP is very complex. In this paper, the simulation based fault injection technique on simplified processor is used to evaluate the fault-tolerance of the digital plant protection system (DPPS) with high efficiency with low cost

  13. Basic Study on Data-Centric design information integration system framework development for adapting Nuclear Power Plant construction in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Byung Ki [KHNP, Gyeongju (Korea, Republic of)

    2016-05-15

    This study established the concept of data-centric design, which is the latest design technique, by analyzing the existing literature so that the data-centric design would be applied to the nuclear power plant projects in Korea and analyzed the status of data-centric design application by the advanced companies and the domestic design companies participating in the nuclear power plant projects. By analyzing the function of the 3D CAD commercial system and all design drawings used in the nuclear power plant projects in Korea, a data-centric design integrated system model has been developed. This study established the concept of data-centric design technology, analyzed the functions of the plant architect engineering (A/E) software being globally used in the plant field and the design process status of nuclear power plant projects in Korea. A design information integration system building model, which is capable of data-centric design, in the place of the existing document-centric system design such as P and ID and SLD, has been suggested through the investigation on the data-centric design cases of the advanced companies. The major functions of the suggested model required for the application to the domestic industry were drawn. The suggested framework builds the field design, which was performed in the 3D system of the constructor, as an owner's field design system, which can manage all design drawings generated from the field design and the related information in integrated way. An as-built full model integrated of plant architect engineering, supplier design and field design is built. It is handed over to the operation team at the O and M stage and utilized in the maintenance and repair. As a power plant full model of future construction project has been enabled, an improved design process has been suggested, in which only the design change information during the plant architect engineering (A/E) and the design change information during the field design

  14. Reliability of emergency ac power systems at nuclear power plants

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.

    1983-07-01

    Reliability of emergency onsite ac power systems at nuclear power plants has been questioned within the Nuclear Regulatory Commission (NRC) because of the number of diesel generator failures reported by nuclear plant licensees and the reactor core damage that could result from diesel failure during an emergency. This report contains the results of a reliability analysis of the onsite ac power system, and it uses the results of a separate analysis of offsite power systems to calculate the expected frequency of station blackout. Included is a design and operating experience review. Eighteen plants representative of typical onsite ac power systems and ten generic designs were selected to be modeled by fault trees. Operating experience data were collected from the NRC files and from nuclear plant licensee responses to a questionnaire sent out for this project

  15. Application of 3-dimensional CAD modeling system in nuclear plants

    International Nuclear Information System (INIS)

    Suwa, Minoru; Saito, Shunji; Nobuhiro, Minoru

    1990-01-01

    Until now, the preliminary work for mutual components in nuclear plant were readied by using plastic models. Recently with the development of computer graphic techniques, we can display the components on the graphics terminal, better than with use of plastic model and actual plants. The computer model can be handled, both telescopically and microscopically. A computer technique called 3-dimensional CAD modeling system was used as the preliminary work and design system. Through application of this system, database for nuclear plants was completed in arrangement step. The data can be used for piping design, stress analysis, shop production, testing and site construction, in all steps. In addition, the data can be used for various planning works, even after starting operation of plant. This paper describes the outline of the 3-dimensional CAD modeling system. (author)

  16. Localization of equipment for digital plant protection system

    Energy Technology Data Exchange (ETDEWEB)

    Koo, I. S.; Park, H. Y.; Lee, C. K. and others

    2000-10-01

    The objective of this project lies on the development of design requirements, establishment of structure and manufacture procedures, development of the software verification and validation(V and V) techniques of the digital plant protection system. The functional requirements based on the analog protection system and digital design requirements are introduced, the processor and system bus for safety grade equipment are selected and the interface requirements and the design specification have been developed in order to manufacture the quick prototype of the digital plant protection system. The selection guidelines of parts, software development and coding and testing for digital plant protection system have been performed through manufacturing the quick prototype based on the developed design specification. For the software verification and validation, the software review plan and techniques of verification and validation have been researched. The digital validation system is developed in order to verify the quick prototype. The digital design requirements are reviewed by the software safety plan and V and V plans. The formal methods for verifying the safety-grade software are researched, then the methodology of formal analysis and testing have been developed.

  17. Localization of equipment for digital plant protection system

    International Nuclear Information System (INIS)

    Koo, I. S.; Park, H. Y.; Lee, C. K. and others

    2000-10-01

    The objective of this project lies on the development of design requirements, establishment of structure and manufacture procedures, development of the software verification and validation(V and V) techniques of the digital plant protection system. The functional requirements based on the analog protection system and digital design requirements are introduced, the processor and system bus for safety grade equipment are selected and the interface requirements and the design specification have been developed in order to manufacture the quick prototype of the digital plant protection system. The selection guidelines of parts, software development and coding and testing for digital plant protection system have been performed through manufacturing the quick prototype based on the developed design specification. For the software verification and validation, the software review plan and techniques of verification and validation have been researched. The digital validation system is developed in order to verify the quick prototype. The digital design requirements are reviewed by the software safety plan and V and V plans. The formal methods for verifying the safety-grade software are researched, then the methodology of formal analysis and testing have been developed

  18. Design of a Type-1 Diabetes Vaccine Candidate Using Edible Plants Expressing a Major Autoantigen

    Directory of Open Access Journals (Sweden)

    Edoardo Bertini

    2018-05-01

    Full Text Available Type-1 diabetes (T1D is a metabolic disease involving the autoimmune destruction of insulin-producing pancreatic beta cells. It is often diagnosed by the detection of autoantibodies, typically those recognizing insulin itself or the 65-kDa isoform of glutamic acid decarboxylase (GAD65. Oral insulin can be used to induce systemic immunological tolerance and thus prevent or delay the onset of T1D, suggesting that combination treatments with other autoantigens such as GAD65 could be even more successful. GAD65 has induced oral tolerance and prevented T1D in preclinical studies but it is difficult to produce in sufficient quantities for clinical testing. Here we combined edible plant systems, namely spinach (Spinacia oleracea cv Industra and red beet (Beta vulgaris cv Moulin Rouge, with the magnICON® expression system to develop a safe, cost-effective and environmentally sustainable platform for the large-scale production of GAD65. The superior red beet platform was extensively characterized in terms of recombinant protein yields and bioequivalence to wild-type plants, and the product was tested for its ability to resist simulated gastric digestion. Our results indicate that red beet plants are suitable for the production of a candidate oral vaccine based on GAD65 for the future preclinical and clinical testing of T1D immunotherapy approaches.

  19. Process control and monitoring system: Thermal Power Plant Gacko

    International Nuclear Information System (INIS)

    Jeremovic, Dragan; Skoko, Maksim; Gjokanovic, Zdravko

    2004-01-01

    DCS Ovation system, manufactured by Westinghouse, USA, is described in this paper. Emphasize on concept of realization and basic characteristic in Thermal Power Plant Gacko is given in this paper. The most important, noticed by now, comparative effects and performances of new monitoring and control system according to classical monitoring and control system of 300 MW units Thermal Power Plant Gacko in Gacko, are given in the conclusion. (Author)

  20. Reliability of the emergency AC power system at nuclear power plants

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.; Baranowsky, P.W.

    1983-01-01

    The reliability of the emergency ac power systems typical of most nuclear power plants was estimated, and the cost and increase in reliability for several improvements were estimated. Fault trees were constructed based on a detailed design review of the emergency ac power systems of 18 nuclear plants. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports (LERs) and from operating experience information obtained from nuclear plant licensees. No one or two improvements can be made at all plants to significantly increase the industry-average emergency ac power system reliability; rather the most beneficial improvements are varied and plant specific. Improvements in reliability and the associated costs are estimated using plant specific designs and failure probabilities

  1. Development of Tokai reprocessing plant maintenance support system (TORMASS) in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Shimizu, Kazuyuki; Tomita, Tsuneo; Sakai, Katsumi

    2008-01-01

    The maintenance work of many equipments such as mechanical, electrical and instrumentations installed in Tokai reprocessing plant has been performed more then 10,000 times per year and about 90% of maintenances were preventive work. For the maintenance management, optimization of maintenance information is required. Therefore, Tokai Reprocessing Plant Maintenance Support System (TORMASS) was developed from 1985 to 1992 as the aim of construction for suitable maintenance management system. About 24,000 equipments of specifications and about 261,000 maintenance detail were registered in this system. TORMASS has been used for the repair, inspection and replacement of equipment since 1992. (author)

  2. Automated systems for control of technological processes at nuclear power plants and their use in putting the plant into operation

    International Nuclear Information System (INIS)

    Majtan, L.

    1987-01-01

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

  3. Annotation of Selaginella moellendorffii major intrinsic proteins and the evolution of the protein family in terrestrial plants

    Directory of Open Access Journals (Sweden)

    Hanna Isa Anderberg

    2012-02-01

    Full Text Available Major intrinsic proteins (MIPs also called aquaporins form pores in membranes to facilitate the permeation of water and certain small polar solutes across membranes. MIPs are present in virtually every organism but are uniquely abundant in land plants. To elucidate the evolution and function of MIPs in terrestrial plants, the MIPs encoded in the genome of the spikemoss Selaginella moellendorffii were identified and analyzed. In total 19 MIPs were found in S. moellendorffii belonging to six of the seven MIP subfamilies previously identified in the moss Physcomitrella patens. Only three of the MIPs were classified as members of the conserved water specific plasma membrane intrinsic protein (PIP subfamily whereas almost half were found to belong to the diverse NOD26-like intrinsic protein (NIP subfamily permeating various solutes. The small number of PIPs in S. moellendorffii is striking compared to all other land plants and no other species has more NIPs than PIPs. Similar to moss, S. moellendorffii only has one type of tonoplast intrinsic protein (TIP. Based on ESTs from non-angiosperms we conclude that the specialized groups of TIPs present in higher plants are not found in primitive vascular plants but evolved later in a common ancestor of seed plants. We also note that the silicic acid permeable NIP2 group that has been reported from angiosperms appears at the same time. We suggest that the expansion of the number MIP isoforms in higher plants is primarily associated with an increase in the different types of specialized tissues rather than the emergence of vascular tissue per se and that the loss of subfamilies has been possible due to a functional overlap between some subfamilies.

  4. DNA Damage Repair System in Plants: A Worldwide Research Update.

    Science.gov (United States)

    Gimenez, Estela; Manzano-Agugliaro, Francisco

    2017-10-30

    Living organisms are usually exposed to various DNA damaging agents so the mechanisms to detect and repair diverse DNA lesions have developed in all organisms with the result of maintaining genome integrity. Defects in DNA repair machinery contribute to cancer, certain diseases, and aging. Therefore, conserving the genomic sequence in organisms is key for the perpetuation of life. The machinery of DNA damage repair (DDR) in prokaryotes and eukaryotes is similar. Plants also share mechanisms for DNA repair with animals, although they differ in other important details. Plants have, surprisingly, been less investigated than other living organisms in this context, despite the fact that numerous lethal mutations in animals are viable in plants. In this manuscript, a worldwide bibliometric analysis of DDR systems and DDR research in plants was made. A comparison between both subjects was accomplished. The bibliometric analyses prove that the first study about DDR systems in plants (1987) was published thirteen years later than that for other living organisms (1975). Despite the increase in the number of papers about DDR mechanisms in plants in recent decades, nowadays the number of articles published each year about DDR systems in plants only represents 10% of the total number of articles about DDR. The DDR research field was done by 74 countries while the number of countries involved in the DDR & Plant field is 44. This indicates the great influence that DDR research in the plant field currently has, worldwide. As expected, the percentage of studies published about DDR systems in plants has increased in the subject area of agricultural and biological sciences and has diminished in medicine with respect to DDR studies in other living organisms. In short, bibliometric results highlight the current interest in DDR research in plants among DDR studies and can open new perspectives in the research field of DNA damage repair.

  5. Nuclear power plant V-2

    International Nuclear Information System (INIS)

    1998-01-01

    The nuclear power plant Bohunice V -2 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - December 1976; first controlled reactor power - 7 August 1984, 2 August 1985; connection to the grid - 20 August 1984, 9 August 1985; commercial operation - 14 February 1985, 18 December 1985. This leaflet contains: NPP V-2 construction; Major technological equipment [WWER 440 V230 type reactor; Nuclear Power plant operation safety (Safety barriers; Safety systems [Active safety systems, Passive safety systems]); Centralized heat supply system; Scheme of Bohunice V-2 NPP and technical data

  6. SEPI an expert system for plant design

    International Nuclear Information System (INIS)

    Carotenuto, M.; Corleto, P.; Landeyro, P.

    1988-01-01

    The availability and suitability of technological information is of great importance in every kind of design task, especially when safety and reliability considerations are involved. In this paper an ''expert system for plant design'' (SEPI), is presented, together with its first application to nuclear back-end plants. This system is available on ENEA computer network. It is thought to be used both to collect know-how developed in the field and to assist unskilled designers during selection, evaluation and dimensioning tasks. It attemps to reproduce the normal way of ''reasoning'' and acting, and provides some graphic facilities

  7. A recombinase-mediated transcriptional induction system in transgenic plants

    DEFF Research Database (Denmark)

    Hoff, T; Schnorr, K M; Mundy, J

    2001-01-01

    We constructed and tested a Cre-loxP recombination-mediated vector system termed pCrox for use in transgenic plants. In this system, treatment of Arabidopsis under inducing conditions mediates an excision event that removes an intervening piece of DNA between a promoter and the gene to be expressed......-mediated GUS activation. Induction was shown to be possible at essentially any stage of plant growth. This single vector system circumvents the need for genetic crosses required by other, dual recombinase vector systems. The pCrox system may prove particularly useful in instances where transgene over...

  8. System 80+TM standard plant: Design and operations overview

    International Nuclear Information System (INIS)

    Matzie, R.A.; Ritterbusch, S.E.

    1999-01-01

    The System 80+ Standard Plant Design is a 1400 MWe evolutionary Advanced Light Water Reactor (ALWR), designed to meet the Electric Power Research Institute (EPRI) ALWR Utility Requirements Document (URD) and the demands of the international market for nuclear power plants which are not only safer but also more economical to maintain and operate. ABB Combustion Engineering Nuclear Power used a defense-in-depth process that (1) adds design margin to basic components to improve performance during normal operation and to decrease the likelihood of an unanticipated transient or an accident, (2) improves the redundancy and diversity of safety systems in order to mitigate design basis accidents and prevent severe accidents, and (3) improves severe accident mitigation capability. This paper describes the most important improved systems and components with emphasis on severe accident prevention and mitigation capability. The improved design features were implemented in an evolutionary manner using proven components. This approach ensures that the plant operates safely and economically, as demonstrated by operating plants in the US and the Republic of Korea. Detailed studies, summarized in this paper, have shown that the System 80+ plant availability is expected to exceed the ALWR requirement of 87% and that the annual operations and maintenance costs are expected to be reduced by $14 million. (author)

  9. Nuclear power plant operational data compilation system

    International Nuclear Information System (INIS)

    Silberberg, S.

    1980-01-01

    Electricite de France R and D Division has set up a nuclear power plant operational data compilation system. This data bank, created through American documents allows results about plant operation and operational material behaviour to be given. At present, French units at commercial operation are taken into account. Results obtained after five years of data bank operation are given. (author)

  10. Plant systems/components modularization study. Final report

    International Nuclear Information System (INIS)

    1977-07-01

    The final results are summarized of a Plant Systems/Components Modularization Study based on Stone and Webster's Pressurized Water Reactor Reference Design. The program has been modified to include evaluation of the most promising areas for modular consideration based on the level of the Sundesert Project engineering design completion and the feasibility of their incorporation into the plant construction effort

  11. System for the analysis of plant chromosomes

    International Nuclear Information System (INIS)

    Medina Martin, D.; Peraza Gonzalez, L.H.

    1996-01-01

    The paper describes a computer system for the automation workers of recognition analysis and interpretation of plant chromosomes. This system permit to carry out the analysis in a more comfortable and faster way, using the image processing techniques

  12. Development of management system for plant repairing work

    International Nuclear Information System (INIS)

    Terauchi, Makoto

    1999-01-01

    In the fast breeder reactor, ''Monju'', in order to conduct nuclear plant repairing works securely and effectively, development of a computer system to assist management business on plant repairing work was begun on 1993. The system has been applied to about 5,000 times of operational management through past four times of plant inspection and to daily inspections and maintenance, and is daily used at working places of ''Monju'' such as issue/management of about 110,000 times of operational prohibition tag in isolated management. And, by automation of issue/management on working sheets and operational prohibition tag and others conducted hitherto by hand, the management business has been largely rationalized. (G.K.)

  13. Application of disturbance analysis methodology to safety related transients in the electrical systems of a nuclear power plant. Report UCLA-ENG-8056

    International Nuclear Information System (INIS)

    Guarro, S.; Okrent, D.

    1981-08-01

    The present study tries to address the question of whether or not the computerized on-line procedures known under the name of DAS (Disturbance Analysis System) can be usefully and successfully applied to provide timely diagnostics and operational suggestions during the occurrence of a major electrical transient in the auxiliary systems of a nuclear power plant. The perspective of the study is from the plant-safety point of view. A short definition of DAS methodology features and capabilities is presented. A discussion of some of the problems of a general nature that are encountered in DAS safety-oriented applications are also included. The event insufficient power on both emergency buses, with reference to a particular plant dsign (San Onofre 1), is presented. Some transients that have recently occurred in the power supply systems of operating plants are examined. Whether or not a DAS could have successfully dealt with such occurrences is considered

  14. Application of disturbance analysis methodology to safety related transients in the electrical systems of a nuclear power plant. Report UCLA-ENG-8056

    Energy Technology Data Exchange (ETDEWEB)

    Guarro, S.; Okrent, D.

    1981-08-01

    The present study tries to address the question of whether or not the computerized on-line procedures known under the name of DAS (Disturbance Analysis System) can be usefully and successfully applied to provide timely diagnostics and operational suggestions during the occurrence of a major electrical transient in the auxiliary systems of a nuclear power plant. The perspective of the study is from the plant-safety point of view. A short definition of DAS methodology features and capabilities is presented. A discussion of some of the problems of a general nature that are encountered in DAS safety-oriented applications are also included. The event insufficient power on both emergency buses, with reference to a particular plant dsign (San Onofre 1), is presented. Some transients that have recently occurred in the power supply systems of operating plants are examined. Whether or not a DAS could have successfully dealt with such occurrences is considered.

  15. Engineering Design of ITER Prototype Fast Plant System Controller

    Science.gov (United States)

    Goncalves, B.; Sousa, J.; Carvalho, B.; Rodrigues, A. P.; Correia, M.; Batista, A.; Vega, J.; Ruiz, M.; Lopez, J. M.; Rojo, R. Castro; Wallander, A.; Utzel, N.; Neto, A.; Alves, D.; Valcarcel, D.

    2011-08-01

    The ITER control, data access and communication (CODAC) design team identified the need for two types of plant systems. A slow control plant system is based on industrial automation technology with maximum sampling rates below 100 Hz, and a fast control plant system is based on embedded technology with higher sampling rates and more stringent real-time requirements than that required for slow controllers. The latter is applicable to diagnostics and plant systems in closed-control loops whose cycle times are below 1 ms. Fast controllers will be dedicated industrial controllers with the ability to supervise other fast and/or slow controllers, interface to actuators and sensors and, if necessary, high performance networks. Two prototypes of a fast plant system controller specialized for data acquisition and constrained by ITER technological choices are being built using two different form factors. This prototyping activity contributes to the Plant Control Design Handbook effort of standardization, specifically regarding fast controller characteristics. Envisaging a general purpose fast controller design, diagnostic use cases with specific requirements were analyzed and will be presented along with the interface with CODAC and sensors. The requirements and constraints that real-time plasma control imposes on the design were also taken into consideration. Functional specifications and technology neutral architecture, together with its implications on the engineering design, were considered. The detailed engineering design compliant with ITER standards was performed and will be discussed in detail. Emphasis will be given to the integration of the controller in the standard CODAC environment. Requirements for the EPICS IOC providing the interface to the outside world, the prototype decisions on form factor, real-time operating system, and high-performance networks will also be discussed, as well as the requirements for data streaming to CODAC for visualization and

  16. Monitoring ethylene emissions from plants cultured for a controlled ecological life support system

    Science.gov (United States)

    Corey, Kenneth A.

    1995-01-01

    Emission of hydrocarbons and other volatile compounds by materials and organisms in closed environments will be a major concern in the design and management of advanced life support systems with a bioregenerative component. Ethylene, a simple hydrocarbon synthesized by plants, is involved in the elicitation of a wide range of physiological responses. In closed environments, ethylene may build up to levels which become physiologically active. In several growouts of 'Yecora Rojo' wheat in Kennedy Space Center's Biomass Production Chamber (BPC), it was observed that leaf flecking and rolling occurred in the sealed environment and was virtually eliminated when potassium permanganate was used to scrub the atmospheric environment. It was suggested that ethylene, which accumulated to about 60 ppb in the chamber and which was effectively absorbed by potassium permanganate, was responsible for the symptoms. The objectives of this work were to: (1) determine rates of ethylene evolution from lettuce (Lactuca sativa cultivar Waldemann's Green) and wheat (Triticum aestivum cultivar Yecora Rojo) plants during growth and development; (2) determine the effects of exposure of whole, vegetative stage plants to exogenous ethylene concentrations in the range of what would develop in closed environment growth chambers; and (3) develop predictive functions for changes in ethylene concentration that would develop under different cropping and closed environment configurations. Results will lead to the development of management strategies for ethylene in bioregenerative life support systems.

  17. Qualification, certification and training systems of a Japanese nuclear power plant supplier

    International Nuclear Information System (INIS)

    Yoshijima, S.; Tomita, J.; Yoneda, Y.

    1982-01-01

    Training and indoctrination of personnel are very important for performing quality assurance activities in nuclear power plants. The paper presents policies, procedures and practices with regard to a training system for site construction workers, a training system for plant operation personnel at a special facility, and services and activities for operating plants. The training system for site workers and technicians offers basic training for all workers, and special training and qualification for field welders, cable-termination workers and non-destructive examination personnel. In addition to the qualification system for field welders applied by the regulatory body, a privat-company qualification system exists. Also, a training centre for BWR operators has been established. This facility has a simulator duplicating the main control room of an actual plant and a computer-assisted instruction system. Standard training courses, short-term basic courses, re-training courses, group training courses and special training courses are held at the training centre. Finally, the services and activities performed by Toshiba Corporation for operating plants are described. These activities of the plant supplier aim at keeping up and further enhancing the safety and reliability of operating plants and mainly consist of: (1) collection and evaluation of plant operation data, with re-evaluation and improvement of systems and components; (2) development of new maintenance techniques; (3) development of measures for reducing annual outage periods; and (4) plant emergency preparedness. (author)

  18. 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.)

  19. A PC-based signal validation system for nuclear power plants

    International Nuclear Information System (INIS)

    Erbay, A.S.; Upadhyaya, B.R.; Seker, S.

    1998-01-01

    In order to achieve the desired operating configuration in any process, the system conditions must be measured accurately. Examples of measurements are temperature, pressure, flow, level, motor current, vibration, etc. However, in order to operate within desired limits, it is important to know the reliability of plant measurements. Signal validation (SV) deals with this issue, and is defined as the detection, isolation and characterization of faulty signals. Also referred to as fault detection, signal validation checks inconsistencies among redundant measurements and estimates their expected values using other measurements and system models. The benefits of SV are both economic and safety related. Catastrophic signal failure can result in plant shutdown and lost revenue. Pre-catastrophic failure detection would therefore minimize plant downtime and increase plant availability. The control action taken depends primarily upon the information provided by the plant instruments. Thus, increased plant productivity and increased reliability of operator actions, would result from the implementation of such a system. The purpose of this study is to investigate some of the existing signal validation methods by incremental improvements and to develop new modules. Each of the SV modules performs a specific task. The architecture consists of four modules, an information base and a system executive integrated with a graphical user interface (GUI). All the modules are used for validation during both steady-state and transient operating conditions. The entire system was developed in the PC-framework under Microsoft Windows TM . Some improvements were made in the structure of static data-driven models by incorporating one and two-step regression. Kalman filtering is based on the use of a physical model of plant components and was implemented for a steam generator system in a nuclear power plant. This is applicable to both steady-state and transient operations. The system executive

  20. Simulation study of a system for diagnosis of nuclear power plant operation

    International Nuclear Information System (INIS)

    Wakabayashi, J.; Fukumoto, A.

    1981-01-01

    A diagnostic system of the nuclear power plant operation is proposed and the applicability of this system to the actual plant has been verified by computer simulation. A typical pressurized water reactor plant simulator was made by an analog computer and the diagnostic system was made by a digital computer. The observed signals obtained from the actual plant are simulated by superposing the equivalent observation noises generated by the digital computer on the sampled signals obtained from the plant simulator. 8 refs

  1. The System 80+ Standard Plant design control document. Volume 1

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the DCD introduction and contains sections 1 and parts 1--7 of section 2 of the CDM. Parts 1--7 included the following: (2.1) Design of SSC; (2.2) Reactor; (2.3) RCS and connected systems; (2.4) Engineered Safety Features; (2.5) Instrumentation and Control; (2.6) Electric Power; and (2.7) Auxiliary Systems

  2. Poison and diluent system for nuclear power plants

    International Nuclear Information System (INIS)

    Parker, W.G.; Ravets, J.M.; Preble, B.S.

    1978-01-01

    A system to prevent supercriticality in nuclear power plants in the unlikely event of a core destructive accident terminating in the nuclear core meltdown is described. The system dilutes and poisons the molten core to maintain subcriticality, and is useful in mobile nuclear power plants, or in nuclear plants subject to seismic disturbances, where the orientation of the nuclear reactor after the accident is unknown. It is also applicable to alleviate the consequences of loss of coolant flow accidents from any cause. Aside from preventing supercriticality, the system serves the dual purpose of acting as a biological shield and/or structural member that reduces the deleterious effects of accidental core impaction, without compromising power plant weight and size constraints. A borated material, with a melting point greater than the fuel melting point, is inserted in the pressure vessel behind an inner wall. In the unlikely event of a core meltdown, the molten fuel melts through the inner wall and is diluted and poisoned by the borated material. In the event the molten fuel melts through the pressure vessel, additional borated material is provided to continue diluting and poisoning

  3. Development of support system for nuclear power plant piping

    International Nuclear Information System (INIS)

    Horino, Satoshi

    1987-01-01

    Ishikawajima-Harima Heavy Industries Co., Ltd. has advanced the development of Integrated Nuclear Plant Piping System (INUPPS) for nuclear power plants since 1980, and continued its improvement up to now. This time as its component, a piping support system (PISUP) has been developed. The piping support system deals with the structures such as piping supports and the stands for maintenance and inspection, and as for standard supporting structures, it builds up automatically the structures including the selection of optimum members by utilizing the standard patterns in cooperation with the piping design system including piping stress analysis. As for the supporting structures deviating from the standard, by amending a part of the standard patterns in dialogue from, structures can be built up. By using the data produced in this way, this system draws up consistently a design book, production management data and so on. From the viewpoint of safety, particular consideration is given to the aseismatic capability of nuclear power plants, and piping is fundamentally designed regidly to avoid resonance. It is necessary to make piping supports so as to have sufficient strength and rigidity. The features of the design of piping supports for nuclear power plant, the basic concept of piping support system, the constitution of the software and hardware, the standard patterns and the structural patterns of piping support system and so on are described. (Kako, I.)

  4. The Development of a Fault Tree Model for Balance of Plant System

    International Nuclear Information System (INIS)

    Hwang, Mee Jeong; Park, Jin Hee; Lim, Ho Gon

    2011-01-01

    In this paper, we propose a fault tree modeling method for BOP (balance of plant) system to develop a combined risk model and trip model, and the application plans of the developed model. Where, the trip means the reactor trip and turbine and generator trip. We have usually modeled the safety-related systems and their supporting systems to assess the risk analysis of a nuclear power plant. However, the BOP system.s condition change induces the risk change. That is, the BOP system.s condition is relevant to plants. performance and affects to the plant risk. The existing model for BOP systems is a simplified system model or SPV (Single-point vulnerability) evaluation model. However, these models are not effective enough to use for the plant's performance evaluation. Also, lately an integrated decision-making framework is required for risk-informed applications. The methods for monitoring the performance of a nuclear power plant differ from the purpose. For example, MSPI (mitigating system performance index) and MR (maintenance rule) use different methods and indexes to monitor the performance. Therefore, for consistent decision-making, it is necessary to develop a risk assessment model including a systems model inducing reactor trip. The system.s model inducing reactor trip and turbine/generator trip is defined as the 'trip model'

  5. Feasibility Study on The Modulization of Structure and System Facility for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, K.S. [Korea Electric Power Research Institute, Taejon (Korea)

    2002-07-01

    This final report is a results of Study on applicable to SC(Steel Concrete) structure for NPPS and experimentation of SC wall-Support joint carried out by KEPRI from 2001.7.1 to 2000.3.27. The major objectives is to study on application of SC structure and behavior of SC wall-support joint. This result is applicable to plan a main project for ''Development of Modular Construction System in the Nuclear Power Plant''. (author). 45 refs., 19 figs., 23 tabs.

  6. PGSB/MIPS PlantsDB Database Framework for the Integration and Analysis of Plant Genome Data.

    Science.gov (United States)

    Spannagl, Manuel; Nussbaumer, Thomas; Bader, Kai; Gundlach, Heidrun; Mayer, Klaus F X

    2017-01-01

    Plant Genome and Systems Biology (PGSB), formerly Munich Institute for Protein Sequences (MIPS) PlantsDB, is a database framework for the integration and analysis of plant genome data, developed and maintained for more than a decade now. Major components of that framework are genome databases and analysis resources focusing on individual (reference) genomes providing flexible and intuitive access to data. Another main focus is the integration of genomes from both model and crop plants to form a scaffold for comparative genomics, assisted by specialized tools such as the CrowsNest viewer to explore conserved gene order (synteny). Data exchange and integrated search functionality with/over many plant genome databases is provided within the transPLANT project.

  7. Reliability of the emergency ac-power system at nuclear power plants

    International Nuclear Information System (INIS)

    Battle, R.E.; Campbell, D.J.; Baranowsky, P.W.

    1982-01-01

    The reliability of the emergency ac-power systems typical of several nuclear power plants was estimated, the costs of several possible improvements was estimated. Fault trees were constructed based on a detailed design review of the emergency ac-power systems of 18 nuclear plants. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports (LERs) and from operating experience information obtained from nuclear plant licensees. It was found that there are not one or two improvements that can be made at all plants to significantly increase the industry-average emergency ac-power-system reliability, but the improvements are varied and plant-specific. Estimates of the improvements in reliability and the associated cost are estimated using plant-specific designs and failure probabilities

  8. DISPATCHING CONTROL SYSTEM OF THE CONCRETE BATCHING PLANTS

    Directory of Open Access Journals (Sweden)

    Andrey Vladimirovich Ostroukh

    2015-09-01

    Full Text Available This paper proposes an approach to the design of dispatching control system of the concrete batching plant, which is a set of hardware maintenance, information, mathematical and software for control of technological objects. The proposed system is scalable and can include a control subsystem of mobile concrete plant, laboratory, subsystems, access control, and personnel management jobs. The system provides optimum automating the collection and processing of information for generating control signals and transmitting them without loss and distortion to the actuators in order to achieve the most efficient operation of process control object as a whole.

  9. The System 80+ Standard Plant design control document. Volume 11

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers parts 6 and 7 and appendix 7A for section 7 (Instrumentation and Control) of the ADM Design and Analysis. The topics covered by these are: other systems required for safety; control systems not required by safety; and CMF evaluation of limiting faults. Parts 1--3 of section 8 (Electric Power) of the ADM are also included in this volume. Topics covered by these parts are: introduction; offsite power system; and onsite power system

  10. System 80+ Design and Licensing : Improving Plant Reliability

    International Nuclear Information System (INIS)

    Newman, Robert E.

    1989-01-01

    The U. S. nuclear industry is striving to improve plant reliability and availability through improved plant design, component designs and plant maintenance. In an effort to improve safety and to demonstrate that commercial nuclear power is economically competitive with other energy sources, the utilities, nuclear vendors, architect engineers and constructors, and component suppliers are all participating in an industry-wide effort to develop improved Light Water Reactor (LWR) designs that are based upon the many years of successful LWR operation. In an age when the world faces the environmental pressures of the greenhouse effect and acid rain, electricity generated from nuclear energy must play an increasing role in the energy picture of Korea, the United States and the rest of the world. This paper discusses the plant availability requirement that has been established by the industry-wide effort mentioned above. After briefly describing Combustion Engineering's program for development of the System 80 Plus standard design and the participation of the Korea Advanced Energy Research Institute (KAERI) in the program, the paper then describes the design features that are being incorporated into System 80+. The industry ALRR Program has established a very ambitious criterion of 87% for the plant availability of future nuclear units. To satisfy such a requirement, the next generation of nuclear plants will include a great many design improvements that reflect the hundreds of years of operating experience that we have accrued. C-ESA's System 80+ will include a number of design changes that improve operating margins and make the plant easier to operate and maintain. Not surprisingly, there is a great deal of overlap between improved safety and improved reliability. In the end, our design will satisfy the future needs of the utilities, the regulators, and the public. C-E is very pleased that KAERI is working with US to achieve these important goals

  11. 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)

  12. Integration of artificial intelligence systems for nuclear power plant surveillance and diagnostics

    International Nuclear Information System (INIS)

    Uhrig, R.E.; Hines, J.W.; Nelson, W.R.

    1998-01-01

    The objective of this program is to design, construct, operate, test, and evaluate a prototype integrated monitoring and diagnostic system for a nuclear power plant. It is anticipated that this technology will have wide application to other complex systems (e.g., fossil power plants, chemical processing plants, and possibly air traffic control systems). Over the past decade, the University of Tennessee (UT) and others have carried out many projects utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems, and genetic algorithms) to enhance the performance (safety, efficiency, reliability, and availability) of nuclear power plants. Investigations and studies have included a) instrumentation surveillance and calibration validation, b) inferential sensing to calibration of feedwater venturi flow during fouling, c) thermodynamic performance modeling with iterative improvement of plant beat rate, d) diagnosis of nuclear power plant transients, and e) increase in thermal power through monitoring of DNBR (Departure from Nucleate Boiling Regime). To increase the likelihood of these individual systems being used in a nuclear power plant, they must be integrated into a single system that operates virtually autonomously, collecting, interpreting, and providing information to the operators in a simple and understandable format. (author)

  13. Integration of artificial intelligence systems for nuclear power plant surveillance and diagnostics

    Energy Technology Data Exchange (ETDEWEB)

    Uhrig, R.E.; Hines, J.W.; Nelson, W.R.

    1998-07-01

    The objective of this program is to design, construct, operate, test, and evaluate a prototype integrated monitoring and diagnostic system for a nuclear power plant. It is anticipated that this technology will have wide application to other complex systems (e.g., fossil power plants, chemical processing plants, and possibly air traffic control systems). Over the past decade, the University of Tennessee (UT) and others have carried out many projects utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems, and genetic algorithms) to enhance the performance (safety, efficiency, reliability, and availability) of nuclear power plants. Investigations and studies have included a) instrumentation surveillance and calibration validation, b) inferential sensing to calibration of feedwater venturi flow during fouling, c) thermodynamic performance modeling with iterative improvement of plant beat rate, d) diagnosis of nuclear power plant transients, and e) increase in thermal power through monitoring of DNBR (Departure from Nucleate Boiling Regime). To increase the likelihood of these individual systems being used in a nuclear power plant, they must be integrated into a single system that operates virtually autonomously, collecting, interpreting, and providing information to the operators in a simple and understandable format. (author)

  14. Integration of artificial intelligence systems for nuclear power plants surveillance and diagnostics

    International Nuclear Information System (INIS)

    Chetry, Moon K.

    2012-01-01

    The objective of this program is to design, construct operate, test, and evaluate a prototype integrated monitoring and diagnostic system for a nuclear power plant. It is anticipated that this technology will have wide application to other complex systems (e.g., fossil power plants, chemical processing plants, and possibly air traffic control systems). Over the past decade, the University of Tennessee (UT) and others have carried out many projects utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems and genetic algorithms) to enhance the performance (safety, efficiency, reliability, and availability) of nuclear power plants. Investigations and studies have included a) instrumentation surveillance and calibration validation, b) inferential sensing to calibration of feed water venture flow during fouling, c) thermodynamic performance modeling with iterative improvement of plant heat rate, d) diagnosis of nuclear power plant transients

  15. Upgrading instrumentation and control systems for plant safety and operation

    International Nuclear Information System (INIS)

    Martin, M.; Prehler, H.J.; Schramm, W.

    1997-01-01

    Upgrading the electrical systems and instrumentation and control systems has become increasingly more important in the past few years for nuclear power plants currently in operation. As the requirements to be met in terms of plant safety and availability have become more stringent in the past few years, Western plants built in the sixties and seventies have been the subject of manifold backfitting and upgrading measures in the past. In the meantime, however, various nuclear power plants are facing much more thorough upgrading phases because of the difficulties in obtaining spare parts for older equipment systems. As digital technology has become widespread in many areas because of its advantages, and as applications are continuously expanding, conventional equipment and systems are losing more and more ground as a consequence of decreasing demand. Merely because of the pronounced decline in demand for conventional electronic components it is possible for equipment manufacturers to guarantee spare parts deliveries for older systems only for specific future periods of time. In addition, one-off manufacture entails high costs in purchases of spare parts. As a consequence of current thinking more and more focusing on availability and economy, upgrading of electrical systems and instrumentation and control systems is becoming a more and more topical question, for older plants even to ensure completion of full service life. (orig.) [de

  16. Development and testing of an integrated signal validation system for nuclear power plants

    International Nuclear Information System (INIS)

    Upadhyaya, B.R.; Kerlin, T.W.; Gaudio, P.J. Jr.

    1989-09-01

    Since the incident at Three Mile Island unit 2, computerized plant status display, implementation of human factors in control room design, and plant monitoring based on expert system technology have seen a tremendous growth. One such proposed operator assist device is a plant signal validation system. This system is used to check the consistency of redundant measurements (sensors) of selected process variables, estimate their expect values from plant-wide data, and detect, isolate and characterize the type of anomaly in the instrument channel outputs. In large process control systems signals from several hundred instrument channels are routed via data highways to control systems, protection (safety) systems and plant monitoring systems. The need of automated signal validation is necessary because of the large amount of information available, and as a result the operator's inability to validate information from many diverse sources. This is also useful for improved plant control (minimize challenges on control systems), minimizing plant downtime, and for predictive maintenance advising. 107 refs., 56 figs., 6 tabs

  17. DENINT power plant cost benefit analysis code: Analysis of methane fuelled power plant/district heating system

    International Nuclear Information System (INIS)

    Cincotti, V.; D'Andrea, A.

    1989-07-01

    The DENINT power plant cost benefit analysis code takes into consideration, not only power production costs at the generator terminals, but also, in the case of cogeneration, the costs of the fuel supply and heat and power distribution systems which depend greatly on the location of the plant. The code is able to allow comparisons of alternatives with varying annual operation hours, fuel cost increases, and different types of fossil fuels and production systems. For illustrative purposes, this paper examines two methane fired cogeneration plant/district heating alternatives

  18. Introducing WISDEM:An Integrated System Modeling for Wind Turbines and Plant (Presentation)

    Energy Technology Data Exchange (ETDEWEB)

    Dykes, K.; Graf, P.; Scott, G.; Ning, A.; King, R.; Guo, Y.; Parsons, T.; Damiani, R.; Felker, F.; Veers, P.

    2015-01-01

    The National Wind Technology Center wind energy systems engineering initiative has developed an analysis platform to leverage its research capabilities toward integrating wind energy engineering and cost models across wind plants. This Wind-Plant Integrated System Design & Engineering Model (WISDEM) platform captures the important interactions between various subsystems to achieve a better National Wind Technology Center wind energy systems engineering initiative has developed an analysis platform to leverage its research capabilities toward integrating wind energy engineering and cost models across wind plants. This Wind-Plant Integrated System Design & Engineering Model (WISDEM) platform captures the important interactions between various subsystems to achieve a better understanding of how to improve system-level performance and achieve system-level cost reductions. This work illustrates a few case studies with WISDEM that focus on the design and analysis of wind turbines and plants at different system levels.

  19. Thermal coupling system analysis of a nuclear desalination plant

    International Nuclear Information System (INIS)

    Adak, A.K.; Srivastava, V.K.; Tewari, P.K.

    2010-01-01

    When a nuclear reactor is used to supply steam for desalination plant, the method of coupling has a significant technical and economic impact. The exact method of coupling depends upon the type of reactor and type of desalination plant. As a part of Nuclear Desalination Demonstration Project (NDDP), BARC has successfully commissioned a 4500 m 3 /day MSF desalination plant coupled to Madras Atomic Power Station (MAPS) at Kalpakkam. Desalination plant coupled to nuclear power plant of Pressurized Heavy Water Reactor (PHWR) type is a good example of dual-purpose nuclear desalination plant. This paper presents the thermal coupling system analysis of this plant along with technical and safety aspects. (author)

  20. New model concepts for dynamic plant uptake and mass flux estimates in the soil-plant-air system

    DEFF Research Database (Denmark)

    Rein, Arno; Bauer-Gottwein, Peter; Trapp, Stefan

    2010-01-01

    in environmental systems at different scales. Feedback mechanisms between plants and hydrological systems can play an important role. However, they have received little attention to date. Here, a new model concept for dynamic plant uptake models applying analytical matrix solutions is presented, which can...

  1. Evaluation of a triplex real-time PCR system to detect the plant-pathogenic molds Alternaria spp., Fusarium spp. and C. purpurea.

    Science.gov (United States)

    Grube, Sabrina; Schönling, Jutta; Prange, Alexander

    2015-12-01

    This article describes the development of a triplex real-time PCR system for the simultaneous detection of three major plant-pathogenic mold genera (Alternaria spp., Fusarium spp. and the species Claviceps purpurea). The designed genus-specific primer-probe systems were validated for sensitivity, specificity and amplification in the presence of background DNA. Copyright © 2015 Elsevier B.V. All rights reserved.

  2. The System 80+ Standard Plant design control document. Volume 15

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains all five parts of section 12 (Radiation Protection) of the ADM Design and Analysis. Topics covered are: ALARA exposures; radiation sources; radiation protection; dose assessment; and health physics program. All six parts and appendices A and B for section 13 (Conduct of Operations) of the ADM Design and Analysis are also contained in this volume. Topics covered are: organizational structure; training program; emergency planning; review and audit; plant procedures; industrial security; sabotage protection (App 13A); and vital equipment list (App 13B)

  3. Evaluation of air cleaning system concepts for emergency use in LMFBR plants

    International Nuclear Information System (INIS)

    Hilliard, R.K.; McCormack, J.D.; Postma, A.K.

    1976-12-01

    Nineteen different air cleaning concepts are arranged into twenty-four systems and evaluated for use as accident mitigating systems in LMFBR plants. Both single, low-leakage containment plants and once-through operation applicable to containment/confinement plants are considered. Plant characteristics affecting air cleaning requirements are defined for 1000 MW(e) plants and a sodium and radiological release term is postulated. The accident conditions under which the emergency air cleaning system (EACS) must function is established by use of SOFIRE-II and HAA-3B computer codes. Criteria are developed for evaluating the various systems and for assigning comparative ratings. The numerical ratings are combined with information on cost and development potential to arrive at recommendations for the most promising systems. The conclusion is made that reliable and effective systems are feasible for use as engineered safety features for LMFBR plants, but that development effort is required for all the air cleaning concepts evaluated

  4. Safety analysis of an expert reactor protection system in nuclear power plants

    International Nuclear Information System (INIS)

    EL-Kafas, A.E.A.E.

    1996-01-01

    the purpose of the dissertation is to develop a real time expert reactor protection system (ERPS) for operational safety of pressurized water reactor nuclear power plant. The system is developed to diagnose plant failures and for identification of plant transients (with and without scram). for this ERPS. probabilistic safety analysis techniques are used to check the availability and priority of the recommended safety system in case of plant accidents . the real- time information during transients and accidents can be obtained to asses the operator in his decision - making . Also, the ERPS is able to give advice for the reactor operator to take the appropriate corrective action during abnormal situations. The system model consists of the dynamic differential equations for reactor core, pressurizer, steam generator, turbine and generator, piping and plenums. The system of equations can be solved by appropriate codes also displayed directly from sensors of the plant. All scenarios of transients, accidents and fault tress for plant systems are learned to ERPS

  5. Computer aided construction engineering system for nuclear power plants

    International Nuclear Information System (INIS)

    Yoshinaga, Toshiaki; Nakajima, Akira; Miyahara, Ryohei; Miura, Jun

    1990-01-01

    The construction CAE system for nuclear power plants is the tool for the construction work simulator (procedure, processes and management simulation) connected to 3D-CAD (three-dimensional plant layout planning CAD). The data used for construction work simulation are registered in the data base as the installation smallest unit data from the 3D-CAD. This construction work simulator comprises the automatic installation procedure decision system, with which a construction planner decides installation procedure by using a high performance graphic work station, and based on a 3D-CAD model, utilizing empirical procedure logic, the dialogue system for making the installation procedure more optimal by utilizing effectively the graphic function, the evaluation system for synthetically evaluating workability, personnel plan and so on by adding the simulation of human behavior based on these procedures, the schedule system which carries out work process simulation based on the above, the data base system for letting to do these plans effectively and the project management system. By means of these, the plant construction of high quality is expected. (K.I.)

  6. Global biogeography of mating system variation in seed plants.

    Science.gov (United States)

    Moeller, David A; Briscoe Runquist, Ryan D; Moe, Annika M; Geber, Monica A; Goodwillie, Carol; Cheptou, Pierre-Olivier; Eckert, Christopher G; Elle, Elizabeth; Johnston, Mark O; Kalisz, Susan; Ree, Richard H; Sargent, Risa D; Vallejo-Marin, Mario; Winn, Alice A

    2017-03-01

    Latitudinal gradients in biotic interactions have been suggested as causes of global patterns of biodiversity and phenotypic variation. Plant biologists have long speculated that outcrossing mating systems are more common at low than high latitudes owing to a greater predictability of plant-pollinator interactions in the tropics; however, these ideas have not previously been tested. Here, we present the first global biogeographic analysis of plant mating systems based on 624 published studies from 492 taxa. We found a weak decline in outcrossing rate towards higher latitudes and among some biomes, but no biogeographic patterns in the frequency of self-incompatibility. Incorporating life history and growth form into biogeographic analyses reduced or eliminated the importance of latitude and biome in predicting outcrossing or self-incompatibility. Our results suggest that biogeographic patterns in mating system are more likely a reflection of the frequency of life forms across latitudes rather than the strength of plant-pollinator interactions. © 2017 John Wiley & Sons Ltd/CNRS.

  7. Photoprotection in Plants Involves a Change in Lutein 1 Binding Domain in the Major Light-harvesting Complex of Photosystem II

    NARCIS (Netherlands)

    Ilioaia, C.; Johnson, M.P.; Liao, P.N.; Pascal, A.A.; van Grondelle, R.; Walla, P.J.; Ruban, A.V.; Robert, B.

    2011-01-01

    Nonphotochemical quenching (NPQ) is the fundamental process by which plants exposed to high light intensities dissipate the potentially harmful excess energy as heat. Recently, it has been shown that efficient energy dissipation can be induced in the major light-harvesting complexes of photosystem

  8. An expert display system and nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Beltracchi, L.

    1988-01-01

    An expert display system controls automatically the display of segments on a cathode ray tube's screen to form an image of plant operations. The image consists of an icon of: 1) the process (heat engine cycle), 2) plant control systems, and 3) safety systems. A set of data-driven, forward-chaining computer stored rules control the display of segments. As plant operation changes, measured plant data are processed through the rules, and the results control the deletion and addition of segments to the display format. The icon contains information needed by control rooms operators to monitor plant operations. One example of an expert display is illustrated for the operator's task of monitoring leakage from a safety valve in a steam line of a boiling water reactor (BWR). In another example, the use of an expert display to monitor plant operations during pre-trip, trip, and post-trip operations is discussed as a universal display. The viewpoints and opinions expressed herein are the author's personal ones, and they are not to be interpreted as Nuclear Regulatory Commission criteria, requirements, or guidelines

  9. The System 80+ Standard Plant design control document. Volume 10

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains Appendices 6A, 6B, and 6C for section 6 (Engineered Safety Features) of the ADM Design and Analysis. Also, parts 1--5 of section 7 (Instrumentation and Control) of the ADM Design and Analysis are covered. The following information is covered in these parts: introduction; reactor protection system; ESF actuation system; system required for safe shutdown; and safety-related display instrumentation

  10. Behaviour of transuranic radionuclides in soils, plants and soil-plant system

    International Nuclear Information System (INIS)

    Vyas, B.N.; Mistry, K.B.

    1996-01-01

    The present paper reviews the investigations undertaken to elucidate the physicochemical, edaphic and physiological aspects of the behaviour of long-lived transuranic radionuclides 239 Pu and 241 Am in typical Indian soils and soil-plant systems. 23 refs

  11. Report by the scientific secretary on major IAEA activities during 1989-1991

    International Nuclear Information System (INIS)

    Kossilov, A.

    1992-01-01

    Major IAEA activities in the field of nuclear power plant control and instrumentation in 1989-1991 are described: IAEA/OECD/NEA International Symposium on ''Balancing Automation and Human Action in Nuclear Power Plants'', Munich, Germany, 9-13 July 1990; specialists meetings; cooperation with OECD/NEA; a Review Report on ''Control Rooms and Man-Machine Interface in Nuclear Power Plants''; Advisory Group Meeting on ''The Balance Between Automation and Human Actions in NPP Operation''; use of simulators for training and maintaining competence; the guidelines for control room design; operator support systems in NPPs

  12. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Design Requirements Document (DRD)

    Science.gov (United States)

    Rigo, H. S.; Bercaw, R. W.; Burkhart, J. A.; Mroz, T. S.; Bents, D. J.; Hatch, A. M.

    1981-01-01

    A description and the design requirements for the 200 MWe (nominal) net output MHD Engineering Test Facility (ETF) Conceptual Design, are presented. Performance requirements for the plant are identified and process conditions are indicated at interface stations between the major systems comprising the plant. Also included are the description, functions, interfaces and requirements for each of these major systems. The lastest information (1980-1981) from the MHD technology program are integrated with elements of a conventional steam electric power generating plant.

  13. Experience on a BWR plant diagnosis system

    International Nuclear Information System (INIS)

    Tanabe, A.; Kawai, K.; Hashimoto, Y.

    1981-01-01

    It is important to watch plant dynamics and equipment condition for avoiding a big transient or avoiding damage to a system by equipment failure. After the TMI accident the necessity of a diagnosis system has been recognized and such development activities have become of primary importance in many organizations. A diagnosis system has two kinds of function. One is the early detection of an anomaly before detection by a conventional instrumentation system. The other is appropriate instruction after alarm or scram has occurred. The authors have been developing the former system by a noise analysis technique and a feasibility study has been undertaken in recent years as a joint research programme of several electric power companies and the Toshiba Corporation. A prototype diagnosis system has been installed on a BWR plant in Japan. This diagnosis system concerns reactor core, jet pumps and three main control systems. Many data from normal operation have been accumulated using this system and a variation pattern of normal noise data is clarified. On this basis, anomally detection criteria have been determined using statistical decision theory. It is confirmed that this system performance is satisfactory, and that the system will be of great use for surveillance of core and control systems without artificial disturbances. (author)

  14. Application of NASA Kennedy Space Center system assurance analysis methodology to nuclear power plant systems designs

    International Nuclear Information System (INIS)

    Page, D.W.

    1985-01-01

    The Kennedy Space Center (KSC) entered into an agreement with the Nuclear Regulatory Commission (NRC) to conduct a study to demonstrate the feasibility and practicality of applying the KSC System Assurance Analysis (SAA) methodology to nuclear power plant systems designs. In joint meetings of KSC and Duke Power personnel, an agreement was made to select to CATAWBA systems, the Containment Spray System and the Residual Heat Removal System, for the analyses. Duke Power provided KSC with a full set a Final Safety Analysis Reports as well as schematics for the two systems. During Phase I of the study the reliability analyses of the SAA were performed. During Phase II the hazard analyses were performed. The final product of Phase II is a handbook for implementing the SAA methodology into nuclear power plant systems designs. The purpose of this paper is to describe the SAA methodology as it applies to nuclear power plant systems designs and to discuss the feasibility of its application. The conclusion is drawn that nuclear power plant systems and aerospace ground support systems are similar in complexity and design and share common safety and reliability goals. The SAA methodology is readily adaptable to nuclear power plant designs because of it's practical application of existing and well known safety and reliability analytical techniques tied to an effective management information system

  15. YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety

    International Nuclear Information System (INIS)

    Mattila, L.; Vanttola, T.

    1992-01-01

    The major part of nuclear energy research in Finland has been organised as five-year nationally coordinated research programs. The research programme on Systems Behaviour and Operational Aspects of Safety is under