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Sample records for plant-specific pra studies

  1. An overview of insights gained and lessons learned from U.S. plant-specific PRA studies

    International Nuclear Information System (INIS)

    Joksimovich, V.

    1985-01-01

    Probabilistic Risk Assessment (PRA) has been under development for over twenty years, but it has reached the level of widespread use only in the aftermath of the TMI accident. Over thirty PRAs have now been completed in the U.S. PRAs have been in the mainstream of many licensing decisions because the NRC recognizes that they provide independent and comprehensive plant safety audit. Some difficulties have been experienced leading to interpretive and intercomparison studies. Numerous global and plant-specific insights have been derived. A new application termed risk management is clearly emerging. (orig./HP)

  2. Use of plant-specific PRA in an EOP scope audit

    International Nuclear Information System (INIS)

    O'Brien, J.J.

    1991-01-01

    Traditionally, decisions on which accident scenarios to proceduralize as emergency operating procedures (EOPs) have been based on existing design basis analyses, engineering judgment, and probabilistic risk assessments (PRAs) on generic plants. This approach has important strengths and limits. The major limitation of generic PRAs is their inability to account for plant-specific features. Use of plant-specific PRA to determine the impact of proceduralizing, or not proceduralizing, responses to scenarios considers plant-specific features. This helps to eliminate unnecessary EOPs, thus allowing resources to be concentrated on scenarios that are more important for a particular plant. In preparation for a US Nuclear Regulatory Commission audit, a plant-specific PRA was used to assess and quantify the plant's previous decision not to implement six reference emergency response guidelines (ERGs) as procedures. The original justification for nonimplementation of the ERGs was based on engineering judgment. The PRA provided a quantitative justification for implementation/nonimplementation of each guidelines. This analysis accounted for plant-specific design features not common to all reference plants

  3. PRA studies: results, insights and applications

    International Nuclear Information System (INIS)

    Levine, S.; Stetson, F.T.

    1983-01-01

    This paper deals with Probalistic Risk Assessment (PRA) studies and their results. The PRA is a combination of logic structures and analytical techniques that can be used to estimate the likelihood and consequences of events that have not been observed because of their low frequency occurrence. At first attitudes concerning PRA reports were controversial principally because of their new techniques and complex multidisciplinary nature. However these attitudes changed following the accident at Three Mile Island in 1979. Many people after this event came to appreciate the risks associated with the operation of nuclear power plants, and since the TMI accident there has been a rapid expansion, in the use of PRA in the US and other countries. (NEA) [fr

  4. Fire PRA requantification studies. Final report

    International Nuclear Information System (INIS)

    Parkinson, W.

    1993-03-01

    This report describes the requantification of two existing fire probabilistic risk assessments (PRAs) using a fire PRA method and data that are being developed by the Electric Power Research Institute (EPRI). The two existing studies are the Seabrook Station Probabilistic Safety Assessment that was made in 1983 and the 1989 NUREG-1150 analysis of the Peach Bottom Plant. Except for the fire methods and data, the original assumptions were used. The results from the requantification show that there were excessive conservatisms in the original studies. The principal reason for a hundredfold reduction in the Peach Bottom core- damage frequency is the determination that no electrical cabinet fire in a switchgear room would damage both offsite power feeds. Past studies often overestimated the heat release from electrical cabinet fires. EPRI's electrical cabinet heat release rates are based on tests that were conducted for Sandia's fire research program. The rates are supported by the experience in the EPRI Fire Events Database for U.S. nuclear plants. Test data and fire event experience also removed excessive conservatisms in the Peach Bottom control and cable spreading rooms, and the Seabrook primary component cooling pump, turbine building relay and cable spreading rooms. The EPRI fire PRA method and data will show that there are excessive conservatisms in studies that were made for many plants and can benefit them accordingly

  5. Treatment of system dependencies and human interactions in PRA studies: a review and sensitivity study

    International Nuclear Information System (INIS)

    Orvis, D.D.; Joksimovich, V.; Worledge, D.H.

    1985-01-01

    The Electric Power Research Institute sponsored the review and comparison of five PRA studies: Arkansas Nuclear One - Unit 1, Big Rock Point, Grand Gulf, Limerick, and Zion - Unit 1. The review has been conducted in two phases. The Phase I review may be characterized as a qualitative look into many aspects of a PRA study. The Phase II review was performed to quantify the extent that differences in analytical techniques or key assumptions in these areas affect the differences in study results. In each of the PRA studies reviewed, the general descriptions of analytical approaches and descriptions of the analyses of event tree, fault tree and human interaction analyses that affected the dominant core damage sequences were reviewed. When these descriptions aroused interest because of seeming inconsistencies within the study or with other studies, they were pursued in some depth. The approaches or assumptions were contrasted to similar elements from other studies, and sensitivity analyses were performed in many cases to test the significance of results to the analytical models or assumptions. Inferences were drawn from the results regarding significance of the item to plant-specific results and, where possible, were generalized to other PRAs. This paper describes the results of the review of system dependencies and human interactions

  6. A model for assessing human cognitive reliability in PRA studies

    International Nuclear Information System (INIS)

    Hannaman, G.W.; Spurgin, A.J.; Lukic, Y.

    1985-01-01

    This paper summarizes the status of a research project sponsored by EPRI as part of the Probabilistic Risk Assessment (PRA) technology improvement program and conducted by NUS Corporation to develop a model of Human Cognitive Reliability (HCR). The model was synthesized from features identified in a review of existing models. The model development was based on the hypothesis that the key factors affecting crew response times are separable. The inputs to the model consist of key parameters the values of which can be determined by PRA analysts for each accident situation being assessed. The output is a set of curves which represent the probability of control room crew non-response as a function of time for different conditions affecting their performance. The non-response probability is then a contributor to the overall non-success of operating crews to achieve a functional objective identified in the PRA study. Simulator data and some small scale tests were utilized to illustrate the calibration of interim HCR model coefficients for different types of cognitive processing since the data were sparse. The model can potentially help PRA analysts make human reliability assessments more explicit. The model incorporates concepts from psychological models of human cognitive behavior, information from current collections of human reliability data sources and crew response time data from simulator training exercises

  7. Individual plant examination and future PRA applications

    International Nuclear Information System (INIS)

    Monty, B.S.; Sursock, J.P.; Thierry, R.J.

    1992-01-01

    PRA is being used in many areas of plant operation as has been demonstrated in previous studies. With the U.S. NRC's emphasis on the use of risk to identify plant vulnerabilities and the development of plant specific PRA models for all plants, it is expected that the use of PRA will be expanded. Key areas where this is expected to occur include the development of risk-based Technical Specifications, risk management, and risk-centered maintenance programs. This paper focuses on the Individual Plant Examination requirement and the possible uses of risk-based methods in controlling plant operation to enhance plant safety and availability, and how the IPE requirement will potentially further this area of development. (orig./DG)

  8. SHARP - a framework for incorporating human interactions into PRA studies

    International Nuclear Information System (INIS)

    Hannaman, G.W.; Joksimovich, V.; Spurgin, A.J.; Worledge, D.H.

    1985-01-01

    Recently, increased attention has been given to understanding the role of humans in the safe operation of nuclear power plants. By virtue of the ability to combine equipment reliability with human reliability probabilistic risk assessment (PRA) technology was deemed capable of providing significant insights about the contributions of human interations in accident scenarios. EPRI recognized the need to strengthen the methodology for incorporating human interactions into PRAs as one element of their broad research program to improve the credibility of PRAs. This research project lead to the development and detailed description of SHARP (Systematic Human Application Reliability Procedure) in EPRI NP-3583. The objective of this paper is to illustrate the SHARP framework. This should help PRA analysts state more clearly their assumptions and approach no matter which human reliability assessment technique is used. SHARP includes a structure of seven analysis steps which can be formally or informally performed during PRAs. The seven steps are termed definition, screening, breakdown, representation, impact assessment, quantification, and documentation

  9. Studi Awal Pra Desain Pabrik Bioetanol dari Nira Siwalan

    Directory of Open Access Journals (Sweden)

    Novarian Budisetyowati

    2017-01-01

    Full Text Available Bioetanol kini banyak dikembangkan sebagai bahan bakar alternatif pengganti bahan bakar fosil. Bioetanol untuk campuran bensin harus memiliki kemurnian sebesar 99,5-100%. Bioetanol dapat diperoleh dengan proses fermentasi yang melibatkan mikroorganisme. Pra desain pabrik bioetanol dari nira siwalan ini menggunakan proses fermentasi. Bahan baku berupa nira siwalan diasamkan dengan menggunakan H2SO4, kemudian disterilisasi sebelum difermentasi di fermentor selama 36 jam. Adapun mikroorganisme yang digunakan adalah Saccharomyces cereviceae. Bakteri ini mampu mengurai gula tanpa kehadiran oksigen dan menghasilkan etanol dan karbondioksida. Bioetanol dapat diperoleh dengan proses fermentasi yang melibatkan mikroorganisme. Pra desain pabrik bioetanol dari nira siwalan ini menggunakan proses fermentasi. Bahan baku berupa nira siwalan diasamkan dengan menggunakan H2SO4, kemudian disterilisasi sebelum difermentasi di fermentor selama 36 jam. Adapun mikroorganisme yang digunakan adalah Saccharomyces cereviceae. Setelah dari fermentor nira yang sudah difermentasi dinetralkan pH nya menggunakan NH4OH di tangki netralisasi. Dari tangki netralisasi nira dipompakan melewati preheater sebelum masuk ke kolom distilasi. Pemurnian dilakukan dengan menggunakan kolom distilasi sebanyak 2 buah. Pada distilasi yang pertama diperoleh kadar etanol sebesar 60% dan pada distilasi yang kedua diperoleh kadar 96%. Dari kolom distilasi 2 larutan didinginkan menggunakan cooler untuk didapatkan suhu 32oC agar sesuai dengan suhu proses dehidrasi dengan menggunakan Molecular Sieve yang diinginkan. Proses dehidrasi dilakukan untuk mendapat kadar etanol 99,5%. Etanol 99,5% yang dihasilkan kemudian disimpan dalam tangki penampung. Kebutuhan bioetanol dalam negeri pada tahun 2018 diperkirakan 3.166.015,13 kL/tahun. Berdasarkan analisa ekonomi yang dilakukan, diperoleh hasil sebagai berikut internal rate of return 26,53 % per tahun, pay out time 4,73 tahun, dan BEP 34,62 % Ditinjau

  10. The Angra 1 fire PRA project

    International Nuclear Information System (INIS)

    Silva, Luiz E. Massiere de C.; Kassawara, Robert

    2009-01-01

    The Angra 1 Fire PRA (Probabilistic Risk Assessment) is under development by ELETRONUCLEAR jointly with EPRI (Electric Power Research Institute). The project was started January of 2007 and it is foreseen to be finished in the middle of the next year. The study is being conducted according to the newest methodology developed by EPRI and NRC/RES (U.S. Nuclear Regulatory Commission - Office of Regulatory Research) published in 2005 as Fire PRA Methodology for Nuclear Power Facilities (NUREG/CR-6850 or EPRI TR-1011989) [1]. Starting from the Internal Events Angra 1 PRA model Level 1 the project aims to be a comprehensive plant-specific fire analysis to identify the possible consequences of a fire in the plant vital areas which threaten the integrity of systems relevant to the safety, challenging the safety functions and representing a risk of accident that can lead to a core damage. The main tasks include the plant boundary and partitioning, the fire PRA component selection and the identification of the possible fire scenarios (ignition, propagation, detection, extinction and hazards) considering human failure events to establish the fire-induced risk model for quantification of the risk for nuclear core damage taking into account the plant design and its fire protection resources. This work presents a general discussion on the methodology applied to the completed steps of the project. (author)

  11. Uncertainty and sensitivity studies supporting the interpretation of the results of TVO I/II PRA

    International Nuclear Information System (INIS)

    Holmberg, J.

    1992-01-01

    A comprehensive Level 1 probabilistic risk assessment (PRA) has been performed for the TVO I/II nuclear power units. As a part of the PRA project, uncertainties of risk models and methods were systematically studied in order to describe them and to demonstrate their impact by way of results. The uncertainty study was divided into two phases: a qualitative and a quantitative study. The qualitative study contained identification of uncertainties and qualitative assessments of their importance. The PRA was introduced, and identified assumptions and uncertainties behind the models were documented. The most significant uncertainties were selected by importance measures or other judgements for further quantitative studies. The quantitative study included sensitivity studies and propagation of uncertainty ranges. In the sensitivity studies uncertain assumptions or parameters were varied in order to illustrate the sensitivity of the models. The propagation of the uncertainty ranges demonstrated the impact of the statistical uncertainties of the parameter values. The Monte Carlo method was used as a propagation method. The most significant uncertainties were those involved in modelling human interactions, dependences and common cause failures (CCFs), loss of coolant accident (LOCA) frequencies and pressure suppression. The qualitative mapping out of the uncertainty factors turned out to be useful in planning quantitative studies. It also served as internal review of the assumptions made in the PRA. The sensitivity studies were perhaps the most advantageous part of the quantitative study because they allowed individual analyses of the significance of uncertainty sources identified. The uncertainty study was found reasonable in systematically and critically assessing uncertainties in a risk analysis. The usefulness of this study depends on the decision maker (power company) since uncertainty studies are primarily carried out to support decision making when uncertainties are

  12. Survey of seismic fragilities used in PRA studies of nuclear power plants

    International Nuclear Information System (INIS)

    Park, Y.J.; Hofmayer, C.H.; Chokshi, N.C.

    1998-01-01

    In recent years, seismic PRA studies have been performed on a large number of nuclear power plants in the USA. This paper presents a summary of a survey on fragility databases and the range of evaluated fragility values of various equipment categories based on past PRAs. The survey includes the use of experience data, the interpretations of available test data, and the quantification of uncertainties. The surveyed fragility databases are limited to data available in the public domain such as NUREG reports, conference proceedings and other publicly available reports. The extent of the availability of data as well as limitations are studied and tabulated for various equipment categories. The survey of the fragility values in past PRA studies includes not only the best estimate values, but also the dominant failure modes and the estimated uncertainty levels for each equipment category. The engineering judgments employed in estimating the uncertainty in the fragility values are also studied. This paper provides a perspective on the seismic fragility evaluation procedures for equipment in order to clearly identify the engineering analysis and judgment used in past seismic PRA studies

  13. Relay chatter and operator response after a large earthquake: An improved PRA methodology with case studies

    International Nuclear Information System (INIS)

    Budnitz, R.J.; Lambert, H.E.; Hill, E.E.

    1987-08-01

    The purpose of this project has been to develop and demonstrate improvements in the PRA methodology used for analyzing earthquake-induced accidents at nuclear power reactors. Specifically, the project addresses methodological weaknesses in the PRA systems analysis used for studying post-earthquake relay chatter and for quantifying human response under high stress. An improved PRA methodology for relay-chatter analysis is developed, and its use is demonstrated through analysis of the Zion-1 and LaSalle-2 reactors as case studies. This demonstration analysis is intended to show that the methodology can be applied in actual cases, and the numerical values of core-damage frequency are not realistic. The analysis relies on SSMRP-based methodologies and data bases. For both Zion-1 and LaSalle-2, assuming that loss of offsite power (LOSP) occurs after a large earthquake and that there are no operator recovery actions, the analysis finds very many combinations (Boolean minimal cut sets) involving chatter of three or four relays and/or pressure switch contacts. The analysis finds that the number of min-cut-set combinations is so large that there is a very high likelihood (of the order of unity) that at least one combination will occur after earthquake-caused LOSP. This conclusion depends in detail on the fragility curves and response assumptions used for chatter. Core-damage frequencies are calculated, but they are probably pessimistic because assuming zero credit for operator recovery is pessimistic. The project has also developed an improved PRA methodology for quantifying operator error under high-stress conditions such as after a large earthquake. Single-operator and multiple-operator error rates are developed, and a case study involving an 8-step procedure (establishing feed-and-bleed in a PWR after an earthquake-initiated accident) is used to demonstrate the methodology

  14. Application of determination of PRA, Ang II and IGF-1 levels in the study of typing of essential hypertension

    International Nuclear Information System (INIS)

    Lu Yongyi; Chen Qun; Yang Yongqing

    2010-01-01

    Objective: To study the clinical application of determination of plasma renin activity (PRA), Angiotensin II (Ang II ) and insulin-like growth factor-1 (IGF-1) levels in typing of essential hypertension (EH). Methods: Determined the levels of PRA and Aug II in 256 patients with EH and 70 healthy volunteers (as control group) by radioimmunoassay, and measured IGF-1 level by enzyme immunoassay. Research on the typing of EH and the difference between the groups. Results: The PRA and Ang II in control group was (0.432±0.236) μg·L -1 ·h -1 and (31.7±7.4) μg/L respectively. In 256 patients with EH, PRA was increased, normal and decreased in 18.0%, 71.8% and 10.2% respectively, while the level of Ang II was increased, normal and decreased in 12.9%, 76.2% and 10.9% respectively. The IGF-1 levels in 256 patients with EH were increased following the increase of blood pressure. Conclusion: Typing of EH patients with PRA and Ang II as well as the determination of IGF-1 were useful in treating and following up the patients with EH. (authors)

  15. Level 2 PRA for a German BWR

    International Nuclear Information System (INIS)

    Sassen, F.; Rapp, W.; Tietsch, W.; Roess, P.

    2007-01-01

    A concept for a Level 2 Probabilistic Risk Assessment (L2 PRA) for a German Boiling Water Reactor (BWR) has been developed taking into account the role of L2 PRA within the German regulatory landscape. According to this concept, a plant specific evaluation of the severe accident phenomenology as well as analyses of the accident progression for the severe accident scenarios has been performed. Furthermore a plant specific MELCOR 1.8.6 model has been developed and special MELCOR source term calculations have been performed for the different release paths. This paper will present examples from the different areas described above. (author)

  16. Urgensi Pemeriksaan Psikis Pra-Nikah (Studi Pandangan Kepala KUA dan Psikolog Kota Malang

    Directory of Open Access Journals (Sweden)

    Ika Kurnia Fitriani

    2015-06-01

    Full Text Available Beberapa negara muslim memberikan perhatian terhadap pemeriksaan psikis pra-nikah bagi calon mempelai, sebagai upaya menanggulangi masalah rumah tangga akibat gangguan kejiwaan di masa yang akan datang. Penelitian ini bertujuan menggali informasi dari Kepala KUA dan Psikolog di Kota Malang tentang pemeriksaan psikis pra-nikah dan urgensinya bagi calon mempelai. Penelitian ini termasuk dalam penelitian lapangan (field reasearch, dengan menggunakan pendekatan kualitatif.  Alanisis data dilakukan melalui tiga tahapan yaitu reduksi data, penyajian data, dan menarik kesimpulan. Pengecekan keabsahan data menggunakan triangulasi sumber yang membandingkan hasil wawancara dengan data sekunder, dan triangulasi teori. Hasil dari penelitian ini menunjukkan bahwa Kepala KUA dan Psikolog di kota Malang menyetujui diadakan pemeriksaan psikis pranikah akan tetapi harus ada aturan hukumnya dan dilakukan sosialisasi agar program menjadi efektif. Selain itu, pemeriksaan psikis pra-nikah tidak bertentangan dengan konsep maqashid al-syari’ah dan konsep sadz al-dzari’ah dalam hukum Islam.

  17. A PRA case study of extended long term decay heat removal for shutdown risk assessment

    International Nuclear Information System (INIS)

    Roglans, J.; Ragland, W.A.; Hill, D.J.

    1992-01-01

    A Probabilistic Risk Assessment (PRA) of the Experimental Breeder Reactor II (EBR-II), a Department of Energy (DOE) Category A research reactor, has recently been completed at Argonne National Laboratory (ANL). The results of this PRA have shown that the decay heat removal system for EBR-II is extremely robust and reliable. In addition, the methodology used demonstrates how the actions of other systems not normally used for actions of other systems not normally used for decay heat removal can be used to expand the mission time of the decay heat removal system and further increase its reliability. The methodology may also be extended to account for the impact of non-safety systems in enhancing the reliability of other dedicated safety systems

  18. PRA and Conceptual Design

    Science.gov (United States)

    DeMott, Diana; Fuqua, Bryan; Wilson, Paul

    2013-01-01

    Once a project obtains approval, decision makers have to consider a variety of alternative paths for completing the project and meeting the project objectives. How decisions are made involves a variety of elements including: cost, experience, current technology, ideologies, politics, future needs and desires, capabilities, manpower, timing, available information, and for many ventures management needs to assess the elements of risk versus reward. The use of high level Probabilistic Risk Assessment (PRA) Models during conceptual design phases provides management with additional information during the decision making process regarding the risk potential for proposed operations and design prototypes. The methodology can be used as a tool to: 1) allow trade studies to compare alternatives based on risk, 2) determine which elements (equipment, process or operational parameters) drives the risk, and 3) provide information to mitigate or eliminate risks early in the conceptual design to lower costs. Creating system models using conceptual design proposals and generic key systems based on what is known today can provide an understanding of the magnitudes of proposed systems and operational risks and facilitates trade study comparisons early in the decision making process. Identifying the "best" way to achieve the desired results is difficult, and generally occurs based on limited information. PRA provides a tool for decision makers to explore how some decisions will affect risk before the project is committed to that path, which can ultimately save time and money.

  19. Nasal PCR assay for the detection of Mycobacterium leprae pra gene to study subclinical infection in a community.

    Science.gov (United States)

    Arunagiri, Kamalanathan; Sangeetha, Gopalakrishnan; Sugashini, Padmavathy Krishnan; Balaraman, Sekar; Showkath Ali, M K

    2017-03-01

    Leprosy is a chronic infectious disease caused by Mycobacterium leprae. Identification of Mycobacterium leprae is difficult in part due to the inability of the leprosy bacillus to grow in vitro. A number of diagnostic methods for leprosy diagnosis have been proposed. Both serological tests and molecular probes have shown certain potential for detection and identification of Mycobacterium leprae in patients. In this study, we have investigated whether Mycobacterium leprae DNA from the nasal secretion of healthy household contacts and the non contacts could be detected through PCR amplification as a method to study the sub clinical infection in a community. A total of 200 samples, 100 each from contacts and non contacts representing all age groups and sex were included in this study. The M. leprae specific primer (proline-rich region) of pra gene was selected and PCR was performed using extracted DNA from the sample. A total of 13 samples were found to be positive for nasal PCR for pra gene among the male and female contacts out of which 7% were males and 6% were females. Even though several diagnostic tools are available to detect the cases of leprosy, they lack the specificity and sensitivity. PCR technology has demonstrated the improved diagnostic accuracy for epidemiological studies and requires minimal time. Although nasal PCR studies have been reported from many countries it is not usually recommended due to the high percentage of negative results in the contact. Copyright © 2017 Elsevier Ltd. All rights reserved.

  20. Practical PRA applications at Consumers Power Company

    International Nuclear Information System (INIS)

    Blanchard, D.P.

    1985-01-01

    Consumers Power Company has completed two probabilistic risk assessments (PRAs), one each at its Big Rock Point and Midland plants and is in the process of performing a third study at its Palisades Plant. Each PRA is summarized briefly in this paper. Each PRA has been used to evaluate specific plant design features and make operating and design recommendations to plant and Company management as well as to the regulator. This paper is a sumary of those issues on which Consumers Power Company has applied PRAs to date. The technique used in applying PRA to these issues has varied as more was learned about the plants from the PRA and about PRA itself. Some issue resolutions involved deriving technical arguments from small parts of the PRA only, such as the logic models or consequence analysis. Still others required use of the entire PRA including sequence quantification, plant and containment response, consequence analysis and eventually cost-benefit evaluation of proposed resolutions. The benefits derived from these analyses have also varied and include not only a perceived reduction in the risks associated with plant operation but also economic benefit to the Company in that cost-effective alternatives to resolving safety issues have been permitted

  1. Probabilistic risk assessment (PRA) reference document. Final report

    International Nuclear Information System (INIS)

    Murphy, J.A.

    1984-09-01

    This document describes the current status of probabilistic risk assessment (PRA) as practiced in the nuclear reactor regulatory process. The PRA studies that have been completed or are under way are reviewed. The levels of maturity of the methodologies used in a PRA are discussed. Insights derived from PRAs are listed. The potential uses of PRA results for regulatory purposes are discussed. This document was issued for comment in February 1984 entitled Probabilistic Risk Assessment (PRA): Status Report and Guidance for Regulatory Application. The comments received on the draft have been considered for this final version of the report

  2. Observations on PRA and its applications

    International Nuclear Information System (INIS)

    Yeh, Y.-C.; Shieh, S.-L.

    2004-01-01

    An overview on the experience of PRA and its prospective application in Taiwan's three nuclear power plants is presented. Through the PRA, plant design improvements are performed and several engineering findings are illuminated. The sensitivity study including the internal, seismic, and typhoon events are conducted to justify items that can significantly reduce core meltdown risk. Its resulted plant betterment plans are thus highlighted accordingly. For PRA application, a risk-based inspection program for allocating inspection human resources has been resulted following the importance ranking of each component. The developing risk-based regulation to rationalize technical specification and maintenance program will also be entailed. To enhance the accuracy of the PRA model and its reproducibility, several issues are considered to have high priority for improvement such as external event data and analyses, uncertainty, common mode failure, human reliability, and the relative component importance. Highlight of their significance along with some typical sensitivity analyses are discussed for further investigation. (author)

  3. Uses of PRA in nuclear reactor regulation

    International Nuclear Information System (INIS)

    Congel, F.

    1987-01-01

    For the past five years, more than ten probabilistic risk assessment (PRA) studies were conducted by the owners of nuclear utilities and were submitted for the review of US Nuclear Regulatory Commission staff. These PRA studies were reviewed under various types of regulatory activities depending on the nature of plant licensing stage. The reviews of these PRAs provided very valuable uses to both the staff and the licensees on safety matters of the plant operation. The licensees developed perspectives using PRA models on the safety profiles of their plants. These PRA perspectives influenced licensees' major decisions to implement improvements to plant design and operating and emergency procedures to reduce and/or eliminate the plant's vulnerability to core damage accidents. The staff's review of these PRAs particularly emphasized the dominant accident sequences. The resulting findings led to the identification of dominant risk contributors, critical areas of plant locations, mechanisms leading to potential early containment failures, and instances of noncompliances of staff's deterministic criteria. Specific examples include single failure criterion and separation requirements to assess the need for any additional measures to further improve the safety of the plant. Some of these PRAs were reviewed under regulatory activities other than safety review such as environmental review, final design review, and licensing hearings. Most importantly, the risk profiles of generic PRAs will continue to be used in reviewing and evaluating unresolved safety issues and other generic issues. The major regulatory uses of PRAs, a summary of full scope PRA review, a summary of plant improvements as a result of PRA reviews, and the future role of PRA reviews are presented

  4. Review of the turbine-building flooding study of the Oconee PRA

    International Nuclear Information System (INIS)

    Ilberg, D.; Hanan, N.A.

    1986-01-01

    A peer review of the Oconee Probabilistic Risk Assessment (OPRA) for Unit no. 3 was conducted at BNL for the NRC. This paper discusses the review of the OPRA turbine-building internal-flooding study, which is one of the dominant contributors, and was performed in great detail. This paper also includes a comparison with other flooding studies performed elsewhere. 5 refs., 1 tab

  5. The effect of uncertainties in nuclear reactor plant-specific failure data on core damage frequency

    International Nuclear Information System (INIS)

    Martz, H.F.

    1995-05-01

    It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact, only estimates which are uncertain. Even for detailed plant-specific data, the reported exposure time or number of demands is often only an estimate of the actual exposure time or number of demands. Likewise the reported number of failure events or incidents is sometimes also uncertain because incident or malfunction reports may be ambiguous. In this report we determine the corresponding uncertainty in core damage frequency which can b attributed to such uncertainties in plant-specific data using a simple but typical nuclear power reactor example

  6. The role of PRA in the safety assessment of VVER Nuclear Power Plants in Ukraine

    International Nuclear Information System (INIS)

    Kot, C.

    1999-01-01

    Ukraine operates thirteen (13) Soviet-designed pressurized water reactors, VVERS. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs), in accordance with new SAR content requirements issued in September 1995, by the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine. The requirements are in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The last two requirements, on PRA and BDBA, are new, and the DBA requirements are an expanded version of the older SAR requirements. The US Department of Energy (USDOE), as part of its Soviet-Designed Reactor Safety activities, is providing assistance and technology transfer to Ukraine to support their nuclear power plants (NPPs) in developing a Western-type technical basis for the new SARs. USDOE sponsored In-Depth Safety Assessments (ISAs) are in progress at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1, and a follow-on study has been initiated at Khmenytskyy Unit 1. The ISA projects encompass most areas of plant safety evaluation, but the initial emphasis is on performing a detailed, plant-specific Level 1 Internal Events PRA. This allows the early definition of the plant risk profile, the identification of risk significant accident sequences and plant vulnerabilities and provides guidance for the remainder of the safety assessments

  7. A desktop PRA

    International Nuclear Information System (INIS)

    Dolan, B.J.; Weber, B.J.

    1989-01-01

    This paper reports that Duke Power Company has completed full-scope PRAs for each of its nuclear stations - Oconee, McGuire and Catawba. These living PRAs are being maintained using desktop personal computers. Duke's PRA group now has powerful personal computer-based tools that have both decreased direct costs (computer analysis expenses) and increased group efficiency (less time to perform analyses). The shorter turnaround time has already resulted in direct savings through analyses provided in support of justification for continued station operation. Such savings are expected to continue with similar future support

  8. PRA quality and use

    International Nuclear Information System (INIS)

    Okrent, D.; Apostolakis, G.; Whitley, R.; Garrick, B.J.

    1982-10-01

    This report deals with several inter-related aspects of probabilistic risk assessment. Some prior opinion regarding quality assurance, methodology and questions of peer review are reviewed, followed by comments by the authors on these and related subjects. Problems arising in decision-making by different groups concerning the meaning and validity of a PRA are examined, and the role of performance criteria in helping to achieve consensus is treated. Finally, a general approach to the development of performance criteria for systems and functions by the retrospective comparison of existing PRAs is proposed and examined in a preliminary fashion

  9. Risk-based technical specifications: Development and application of an approach to the generation of a plant specific real-time risk model

    International Nuclear Information System (INIS)

    Puglia, B.; Gallagher, D.; Amico, P.; Atefi, B.

    1992-10-01

    This report describes a process developed to convert an existing PRA into a model amenable to real time, risk-based technical specification calculations. In earlier studies (culminating in NUREG/CR-5742), several risk-based approaches to technical specification were evaluated. A real-time approach using a plant specific PRA capable of modeling plant configurations as they change was identified as the most comprehensive approach to control plant risk. A master fault tree logic model representative of-all of the core damage sequences was developed. Portions of the system fault trees were modularized and supercomponents comprised of component failures with similar effects were developed to reduce the size of the model and, quantification times. Modifications to the master fault tree logic were made to properly model the effect of maintenance and recovery actions. Fault trees representing several actuation systems not modeled in detail in the existing PRA were added to the master fault tree logic. This process was applied to the Surry NUREG-1150 Level 1 PRA. The master logic mode was confirmed. The model was then used to evaluate frequency associated with several plant configurations using the IRRAS code. For all cases analyzed computational time was less than three minutes. This document Volume 2, contains appendices A, B, and C. These provide, respectively: Surry Technical Specifications Model Database, Surry Technical Specifications Model, and a list of supercomponents used in the Surry Technical Specifications Model

  10. Role of PRA in new NPP projects

    International Nuclear Information System (INIS)

    Julin, A.; Sandberg, J.; Virolainen, R.

    2012-01-01

    In Finland, a plant specific, Level 1 and 2 Probabilistic Risk Analysis (PRA) is required as a prerequisite for issuing the construction license and operating license. The use of PRA in various applications and the main insights are presented. These applications include e.g. PRA support to the design of SSCs (Systems, Structures and Components), definition of pre-service and in-service inspection programs, evaluation of the safety classification of SSCs, development of procedures, training and in definition of risk informed technical specifications, periodic testing and on-line preventive maintenance programs. In addition, PRA shall be used to assess the adequacy and coverage of the phase and system commissioning programs. Also the potential risks related to commissioning tests during nuclear test phase, shall be assessed with the help of PRA. In OL3 project, risk informed approach has been applied on a large scale for the first time in the design, construction and commissioning of a new NPP unit. Pre-nuclear commissioning tests have started at OL3 site and the plant is foreseen to begin commercial operation in 2013. Decisions have been made to launch new NPP projects. Teollisuuden Voima Oyj (TVO) is planning to build a new unit (OL4) at Olkiluoto site and a new utility, Fennovoima, is planning to build one unit at one of two alternative green field sites in Northern parts of Finland. Insights from PRAs of operating NPPs have been used in the evaluation of possible new sites to ensure that the site specific concerns and environmental conditions are adequately taken into account in the design of SSCs. Although the seismic activity at the Olkiluoto site is low, a comprehensive seismic risk analysis is being conducted. Its results support the review of the deterministic seismic design. For new sites, a probabilistic seismic hazard analysis has been carried out for the determination of the design earthquake. Experiences from OL3 licensing have been utilized in the

  11. PRA: a powerful engineering decision tool

    International Nuclear Information System (INIS)

    Carvalho, H.G. de.

    1988-03-01

    The probabilistic risk analysis (PRA) is studied and its historical development is briefly presented. Human factors, sofware and guides, improvement of utility management of nuclear power operations are discussed. The development of a standardized LWR design, optimized for safety, reliability and economy is studied. The impact of risk assessments in public acceptance of nuclear power is discussed. (M.A.C.) [pt

  12. Hiperurisemia pada Pra Diabetes

    Directory of Open Access Journals (Sweden)

    Ellyza Nasrul

    2012-09-01

    Full Text Available AbstrakAsam urat (AU merupakan produk akhir dari katabolisme adenin dan guanin yang berasal dari pemecahannukleotida purin. Urat dihasilkan oleh sel yang mengandung xanthine oxidase, terutama hepar dan usus kecil.Hiperurisemia adalah keadaan kadar asam urat dalam darah lebih dari 7,0 mg/dL.Pra diabetes adalah subjek yangmempunyai kadar glukosa plasma meningkat akan tetapi peningkatannya masih belum mencapai nilai minimaluntuk kriteria diagnosis diabetes melitus (DM. Glukosa darah puasa terganggu merupakan keadaan dimanapeningkatan kadar FPG≥100 mg/dL dan <126 mg/dL. Toleransi glukosa terganggu merupakan peningkatanglukosa plasma 2 jam setelah pembebanan 75 gram glukosa oral (≥140 mg/dL dan <200mg/dL dengan FPG<126 mg/dL.Insulin juga berperan dalam meningkatkan reabsorpsi asam urat di tubuli proksimal ginjal. Sehinggapada keadaan hiperinsulinemia pada pra diabetes terjadi peningkatan reabsorpsi yang akan menyebabkanhiperurisemia. Transporter urat yang berada di membran apikal tubuli renal dikenal sebagai URAT-1 berperandalam reabsorpsi urat.Kata kunci: Hiperurisemia, Pra DiabetesAbstractUric acid (AU is the end product of the catabolism of adenine and guanine nucleotides derived from thebreakdown of purines. Veins produced by cells containing xanthine oxidase, especially the liver and small intestine.Hyperuricemia is a state in the blood uric acid levels over 7.0 mg / dL.Pre-diabetes is a subject which has a plasmaglucose level will rise but the increase is still not reached the minimum value for the diagnostic criteria for diabetesmellitus (DM. Impaired fasting blood glucose is a condition in which increased levels of FPG ≥ 100 mg / dL and<126 mg / dL. Impaired glucose tolerance is an increase in plasma glucose 2 hours after 75 gram oral glucose load(≥ 140 mg / dL and <200mg/dl with FPG <126 mg / dL.Insulin also plays a role in increasing the reabsorption ofuric acid in renal proximal tubule. So that the hyperinsulinemia in the pre

  13. Probabilistic risk assessment (PRA): status report and guidance for regulatory application. Draft report for comment

    International Nuclear Information System (INIS)

    1984-02-01

    This document describes the current status of the methodologies used in probabilistic risk assessment (PRA) and provides guidance for the application of the results of PRAs to the nuclear reactor regulatory process. The PRA studies that have been completed or are underway are reviewed. The levels of maturity of the methodologies used in a PRA are discussed. Insights derived from PRAs are listed. The potential uses of PRA results for regulatory purposes are discussed

  14. Seabrook Station Level 2 PRA Update to Include Accident Management

    International Nuclear Information System (INIS)

    Lutz, Robert; Lucci, Melissa; Kiper, Kenneth; Henry, Robert

    2006-01-01

    A ground-breaking study was recently completed as part of the Seabrook Level 2 PRA update. This study updates the post-core damage phenomena to be consistent with the most recent information and includes accident management activities that should be modeled in the Level 2 PRA. Overall, the result is a Level 2 PRA that fully meets the requirements of the ASME PRA Standard with respect to modeling accident management in the LERF assessment and NRC requirements in Regulatory Guide 1.174 for considering late containment failures. This technical paper deals only with the incorporation of operator actions into the Level 2 PRA based on a comprehensive study of the Seabrook Station accident response procedures and guidance. The paper describes the process used to identify the key operator actions that can influence the Level 2 PRA results and the development of success criteria for these key operator actions. This addresses a key requirement of the ASME PRA Standard for considering SAMG. An important benefit of this assessment was the identification of Seabrook specific accident management insights that can be fed back into the Seabrook Station accident management procedures and guidance or the training provided to plant personnel for these procedures and guidance. (authors)

  15. Insights into PRA methodologies

    International Nuclear Information System (INIS)

    Gallagher, D.; Lofgren, E.; Atefi, B.; Liner, R.; Blond, R.; Amico, P.

    1984-08-01

    Probabilistic Risk Assessments (PRAs) for six nuclear power plants were examined to gain insight into how the choice of analytical methods can affect the results of PRAs. The PRA sreflectope considered was limited to internally initiated accidents sequences through core melt. For twenty methodological topic areas, a baseline or minimal methodology was specified. The choice of methods for each topic in the six PRAs was characterized in terms of the incremental level of effort above the baseline. A higher level of effort generally reflects a higher level of detail or a higher degree of sophistication in the analytical approach to a particular topic area. The impact on results was measured in terms of how additional effort beyond the baseline level changed the relative importance and ordering of dominant accident sequences compared to what would have been observed had methods corresponding to the baseline level of effort been employed. This measure of impact is a more useful indicator of how methods affect perceptions of plant vulnerabilities than changes in core melt frequency would be. However, the change in core melt frequency was used as a secondary measure of impact for nine topics where availability of information permitted. Results are presented primarily in the form of effort-impact matrices for each of the twenty topic areas. A suggested effort-impact profile for future PRAs is presented

  16. The tsunami probabilistic risk assessment (PRA). Example of accident sequence analysis of tsunami PRA according to the standard for procedure of tsunami PRA for nuclear power plants

    International Nuclear Information System (INIS)

    Ohara, Norihiro; Hasegawa, Keiko; Kuroiwa, Katsuya

    2013-01-01

    After the Fukushima Daiichi nuclear power plant (NPP) accident, standard for procedure of tsunami PRA for NPP had been established by the Standardization Committee of AESJ. Industry group had been conducting analysis of Tsunami PRA for PWR based on the standard under the cooperation with electric utilities. This article introduced overview of the standard and examples of accident sequence analysis of Tsunami PRA studied by the industry group according to the standard. The standard consisted of (1) investigation of NPP's composition, characteristics and site information, (2) selection of relevant components for Tsunami PRA and initiating events and identification of accident sequence, (3) evaluation of Tsunami hazards, (4) fragility evaluation of building and components and (5) evaluation of accident sequence. Based on the evaluation, countermeasures for further improvement of safety against Tsunami could be identified by the sensitivity analysis. (T. Tanaka)

  17. PRA and Risk Informed Analysis

    International Nuclear Information System (INIS)

    Bernsen, Sidney A.; Simonen, Fredric A.; Balkey, Kenneth R.

    2006-01-01

    The Boiler and Pressure Vessel Code (BPVC) of the American Society of Mechanical Engineers (ASME) has introduced a risk based approach into Section XI that covers Rules for Inservice Inspection of Nuclear Power Plant Components. The risk based approach requires application of the probabilistic risk assessments (PRA). Because no industry consensus standard existed for PRAs, ASME has developed a standard to evaluate the quality level of an available PRA needed to support a given risk based application. The paper describes the PRA standard, Section XI application of PRAs, and plans for broader applications of PRAs to other ASME nuclear codes and standards. The paper addresses several specific topics of interest to Section XI. Important consideration are special methods (surrogate components) used to overcome the lack of PRA treatments of passive components in PRAs. The approach allows calculations of conditional core damage probabilities both for component failures that cause initiating events and failures in standby systems that decrease the availability of these systems. The paper relates the explicit risk based methods of the new Section XI code cases to the implicit consideration of risk used in the development of Section XI. Other topics include the needed interactions of ISI engineers, plant operating staff, PRA specialists, and members of expert panels that review the risk based programs

  18. Methodology and application of surrogate plant PRA analysis to the Rancho Seco Power Plant: Final report

    International Nuclear Information System (INIS)

    Gore, B.F.; Huenefeld, J.C.

    1987-07-01

    This report presents the development and the first application of generic probabilistic risk assessment (PRA) information for identifying systems and components important to public risk at nuclear power plants lacking plant-specific PRAs. A methodology is presented for using the results of PRAs for similar (surrogate) plants, along with plant-specific information about the plant of interest and the surrogate plants, to infer important failure modes for systems of the plant of interest. This methodology, and the rationale on which it is based, is presented in the context of its application to the Rancho Seco plant. The Rancho Seco plant has been analyzed using PRA information from two surrogate plants. This analysis has been used to guide development of considerable plant-specific information about Rancho Seco systems and components important to minimizing public risk, which is also presented herein

  19. 'Living PRA' concept for plant risk: Reliability and availability tracking

    International Nuclear Information System (INIS)

    Sancaktar, S.; Sharp, D.R.

    1985-01-01

    The 'Living PRA' (Probabilistic Risk Assessment) is based on placing a PRA plant model on an interactive computer. This model consists of fault tree analyses for plant systems, event tree analyses for abnormal events and site specific consequence analysis for public and/or financial risks, for a nuclear power plant. A living PRA allows updates and sensitivity analyses by the plant owner throughout the lifetime of a plant. Recently, event and fault trees from two major PRAs were placed in a computerized format. The BYRON PRA study and the Living PRA and Economic Risk examples for Indian Point Unit-3 enabled analysts to gain experience and insight into the problems of plant operation. The above concept is well established for the Nuclear Power Plant evaluation. It has been also used for evaluation of processing facilities. In these studies, systems modeling was carried out by using the GRAFTER system for automated fault tree construction. Presently both the tools and the experience exists to set up useful and viable living PRA models for nuclear and chemical processing plants to enhance risk management by the plant owners through in-house use of micro computer based models

  20. Identification and screening of hazards for the external event PRA - External hazard identification, screening and studies for a new plant site

    International Nuclear Information System (INIS)

    Hellander, Juho

    2014-01-01

    Fennovoima is constructing a new nuclear power plant on a greenfield site in Northern Finland. Various evaluations for site-specific hazards are needed to ensure sufficient plant design basis values, proper design solutions and to provide input for the PRA model. This paper presents the general process used in identifying the relevant site-specific external hazards. The applicable legislative requirements, guides and standards regarding external hazards and external event PRA shall be identified. Based on these, an initial comprehensive list of events should be compiled. The initial list shall be filtered to exclude irrelevant events. Events can be screened out if the probability is very low or if the consequences are only mild. Events with similar consequences should be combined. Events can be grouped in several ways, and in this paper the risks are categorized into events related to air, water bodies, ground and human behaviour. In addition, the simultaneously occurring combinations of events should be identified. The paper also summarizes some hazard studies already performed and required in the future in Fennovoima's project. A comprehensive study is ongoing related to earthquake risks. The study aims at identifying all relevant seismic sources and taking into account various expert opinions in seismic modelling. Also frazil ice and anchor ice studies are being performed to eliminate the risk of cooling water intake blockage due to ice. In addition, some other study areas are mentioned. This paper presented a list of Finnish and international guides and standards useful in evaluating external hazards. Also a methodology was presented to identify and screen site-specific hazards in a new nuclear power plant project. The screened list of relevant events for the Hanhikivi site requiring further studies was presented. Also the studies needed in different phases of a new nuclear power plant project were discussed. Some specific studies regarding earthquakes and

  1. Review of PRA methodology for LMFBR

    International Nuclear Information System (INIS)

    Yang, J. E.

    1999-02-01

    Probabilistic Risk Assessment (PRA) has been widely used as a tool to evaluate the safety of NPPs (Nuclear Power Plants), which are in the design stage as well as in operation. Recently, PRA becomes one of the licensing requirements for many existing and new NPPs. KALIMER is a Liquid Metal Fast Breeder Reactor (LMFBR) being developed by KAERI. Since the design concept of KALIMER is similar to that of the PRISM plant developed by GE, it would be appropriate to review the PRA methodology of PRISM as the first step of KALIMER PRA. Hence, in this report summarizes the PRA methodology of PRISM plant, and the required works for the PSA of KALIMER based on the reviewed results. The PRA technology of PRISM plant consists of following five major tasks: (1) development of initiating event list, (2) development of system event tree, (3) development of core response event tree, (4) development of containment response event tree, and (5) consequences and risk estimation. The estimated individual and societal risk measures show that the risk from a PRISM module is substantially less than the NRC goal. Each task is compared to the PRA methodology of Light Water Reactor (LWR)/Pressurized Heavy Water Reactor (PHWR). In the report, each task of PRISM PRA methodology is reviewed and compared to the corresponding part of LWR/PHWR PSA performed in Korea. The parts that are not modeled appropriately in PRISM PRA are identified, and the recommendations for KALIMER PRA are stated. (author). 14 refs., 9 tabs., 4 figs

  2. Seismic PRA of a BWR plant

    International Nuclear Information System (INIS)

    Nishio, Masahide; Fujimoto, Haruo

    2014-01-01

    Since the occurrence of nuclear power plant accidents in the Fukushima Daichi nuclear power station, the regulatory framework on severe accident (SA) has been discussed in Japan. The basic concept is to typify and identify the accident sequences leading to core/primary containment vessel (PCV) damage and to implement SA measures covering internal and external events extensively. As Japan is an earthquake-prone country and earthquakes and tsunami are important natural external events for nuclear safety of nuclear power plants, JNES performed the seismic probabilistic risk assessment (PRA) on a typical nuclear power plant and evaluated the dominant accident sequences leading to core/PCV damage to discuss dominant scenarios of severe accident (SA). The analytical models and the results of level-1 seismic PRA on a 1,100 MWe BWR-5 plant are shown here. Seismic PRA was performed for a typical BWR5 plant. Initiating events with large contribution to core damage frequency are the loss of all AC powers (station blackout) and the large LOCA. The top of dominant accident sequences is the simultaneous occurrence of station blackout and large LOCA. Important components to core damage frequency are electric power supply equipment. It needs to keep in mind that the results are influenced on site geologic characteristic to a greater or lesser. In the process of analysis, issues such as conservative assumptions related to damages of building or structure and success criteria for excessive LOCA are left to be resolved. These issues will be further studied including thermal hydric analysis in the future. (authors)

  3. Linkage of PRA models. Phase 1, Results

    Energy Technology Data Exchange (ETDEWEB)

    Smith, C.L.; Knudsen, J.K.; Kelly, D.L.

    1995-12-01

    The goal of the Phase I work of the ``Linkage of PRA Models`` project was to postulate methods of providing guidance for US Nuclear Regulator Commission (NRC) personnel on the selection and usage of probabilistic risk assessment (PRA) models that are best suited to the analysis they are performing. In particular, methods and associated features are provided for (a) the selection of an appropriate PRA model for a particular analysis, (b) complementary evaluation tools for the analysis, and (c) a PRA model cross-referencing method. As part of this work, three areas adjoining ``linking`` analyses to PRA models were investigated: (a) the PRA models that are currently available, (b) the various types of analyses that are performed within the NRC, and (c) the difficulty in trying to provide a ``generic`` classification scheme to groups plants based upon a particular plant attribute.

  4. Linkage of PRA models. Phase 1, Results

    International Nuclear Information System (INIS)

    Smith, C.L.; Knudsen, J.K.; Kelly, D.L.

    1995-12-01

    The goal of the Phase I work of the ''Linkage of PRA Models'' project was to postulate methods of providing guidance for US Nuclear Regulator Commission (NRC) personnel on the selection and usage of probabilistic risk assessment (PRA) models that are best suited to the analysis they are performing. In particular, methods and associated features are provided for (a) the selection of an appropriate PRA model for a particular analysis, (b) complementary evaluation tools for the analysis, and (c) a PRA model cross-referencing method. As part of this work, three areas adjoining ''linking'' analyses to PRA models were investigated: (a) the PRA models that are currently available, (b) the various types of analyses that are performed within the NRC, and (c) the difficulty in trying to provide a ''generic'' classification scheme to groups plants based upon a particular plant attribute

  5. PRA and the implementation of quantitative safety goals

    International Nuclear Information System (INIS)

    Okrent, D.

    1983-01-01

    With the adoption by the U.S. Nuclear Regulatory Commission (NRC) in January, 1983, of a Policy Statement on Safety Goals for the Operation of Nuclear Power Plants, probabilitstic risk assessment (PRA) has taken on increased importance in nuclear reactor safety. Although the Reactor Safety Study, WASH-1400, was a major pioneering effort that revolutionized thinking about reactor safety, PRA was used only on occasion by the NRC regulatory staff prior to the accident at Three Mile Island. Since then, PRA has been used more and more as an important factor in decision making, usually for specific issues. The nuclear industry has also employed PRA, sometimes to make its case on specific issues, sometimes to present a position on overall risk. The advent of the Zion and Indian Point PRAs, with their treatment of risks from fire, wind, and earthquakes, and their examination of the course of core melt accidents, has added a new dimension to the overall picture. Although the NRC has stated that during the next two year evolution period, its quantitative design objectives and PRA are not to enter directly into the licensing process, many important issues will be influenced significantly by the results of risk and reliability studies. In fact, PRA may be coming into a position of great importance before the methodology, data, and process are sufficiently mature for the task. Large gaps still exist in our understanding of phenomena and in input information; and much of the final result depends on subjective input; large differences of opinion can and should be expected to persist. Accepted standards for quality assurance, and adequacy and depth of independent, peer review remain to be formulated and achieved. This paper will summarize the recently adopted NRC safety policy and the two-year evaluation plan, and will provide, by example, some words of caution concerning a few of the difficulties which may arise. (orig.)

  6. PERILAKU SEKS PRA-NIKAH MAHASISWA PADA SEKOLAH TINGGI MANAJEMEN DAN ILMU KOMPUTER BINA BANGSA KENDARI (STUDI KASUS)

    OpenAIRE

    Israwati; Rachman, Watief A; Ibnu, Indra Fajarwati

    2013-01-01

    Masa remaja merupakan masa transisi dari masa anak-anak menuju dewasa. Jenis penelitian ini adalah penelitian kualitatif dengan rancangan studi kasus. Informan dalam penelitian ini ditentukan dengan menggunakana snowballing yang terdiri dari 9 orang mahasiswa yang pernah melakukan hubungan seks pranikah dan 9 orang mahasiswa yang belum pernah melakukan hubungan seks pranikah. Hasil penelitian menunjukan bahwa pemahaman mahasiswa tentang perilaku seks pranikah yaitu perilaku seks yang dilakuka...

  7. Preliminary ATWS analysis for the IRIS PRA

    International Nuclear Information System (INIS)

    Maddalena Barra; Marco S Ghisu; David J Finnicum; Luca Oriani

    2005-01-01

    to be a non dominant contribution to the plant CDF. During this second phase of the IRIS PRA development, the original model has been updated with the insertion of a study of ATWS, with the purpose of confirming the assumptions previously made. Within this framework, the most significant ATWS sequences have been identified and a first set of analyses has been run. The thermal-hydraulic computer code RELAP5 is used for the accident analyses, using a conservative evaluation model based on the Westinghouse ATWS evaluation model used during the analyses that supported the development of the ATWS rule (10CFR50.62). The key figure of merit used in these ATWS analyses is the pressure peak resulting from the imbalance between the rates of energy deposition into the core and removal from the reactor coolant that could cause damage to RCS components necessary for safe plant shutdown. Core damage is assumed if the peak pressure exceeds a limiting value. To support the evaluation of the ATWS contribution to the CDF, analyses with different values of critical parameters (mainly the moderator temperature coefficient and the number of operative safety valves in the pressurizer) were performed. The use of these analyses on the ATWS event tree development and on the calculation of the ATWS to the plant CDF is discussed in this paper. (authors)

  8. Standardized procedure for tsunami PRA by AESJ

    International Nuclear Information System (INIS)

    Kirimoto, Yukihiro; Yamaguchi, Akira; Ebisawa, Katsumi

    2013-01-01

    After Fukushima Accident (March 11, 2011), the Atomic Energy Society of Japan (AESJ) started to develop the standard of Tsunami Probabilistic Risk Assessment (PRA) for nuclear power plants in May 2011. As Japan is one of the countries with frequent earthquakes, a great deal of efforts has been made in the field of seismic research since the early stage. To our regret, the PRA procedures guide for tsunami has not yet been developed although the importance is held in mind of the PRA community. Accordingly, AESJ established a standard to specify the standardized procedure for tsunami PRA considering the results of investigation into the concept, the requirements that should have and the concrete methods regarding tsunami PRA referring the opinions of experts in the associated fields in December 2011 (AESJ-SC-RK004:2011). (author)

  9. Evaluation of allowed outage time using PRA results

    International Nuclear Information System (INIS)

    Johanson, G.

    1985-01-01

    In a probabilistic risk assessment (PRA) different measures of risk importance can be established. These measures can be used as a basis for further evaluation and determination of allowed outage time for specific components, within safety systems of a nuclear power plant. In order to optimize the allowed outage time (AOT) stipulated in the plant's Technical Specification it is necessary to create a methodology which could incorporate existing PRA data into a quantitative extrapolation. In order to evaluate the plant risk status due to AOT in a quantitative manner, the risk achievement worth is utilized. Risk achievement worth is defined as follows: to measure the worth of a feature, in achieving the present risk, one approach is to remove the feature and then determine how much the risk has increased. Thus, the risk achievement worth is formally defined to be the increase in risk if the feature were assumed not be there or to be failed. Another parameter of interest for this analysis is the shutdown risk increase. The shutdown risk achievement worth must be incorporated into the accident sequence risk achievement worth to arrive at an optimal set of plant specific AOTs

  10. A powerful tool for plant specific simulations

    International Nuclear Information System (INIS)

    Boucau, J.; Ofstun, R.

    1988-01-01

    Following the Three Mile Island (TMI) accident, special emphasis has been placed by the Utilities and Safety Authorities on the training of plant operators and engineers to make them more familiar with the dynamic behavior of the plant in post-accident conditions. With a view to providing transient response under realistic operating conditions, concerns were raised over: the use of conservative safety analysis models for analyzing operational and accident transients; the ability to dynamically simulate the expected operator actions, and the need to simulate the plant during long term cooling recovery. To meet these requirements, an interactive, user friendly, cost efficient dynamic model capable of simulating two-phase conditions is needed. In response to these post-TMI concerns, Westinghouse has developed, the Transient Real-Time Engineering Analysis Tool (TREAT) which is a general purpose interactive thermal-hydraulic network code for thermal-hydraulic transient analysis. The applications of TREAT are numerous and range from engineering studies to plant operator training using the newly developed TREAT SIMULATOR. The purpose of this paper is to describe the TREAT program and potential applications. Special emphasis will be drawn at a plant specific training application performed for a French 4-loop plant

  11. Primary care practice-based care management for chronically ill patients (PraCMan: study protocol for a cluster randomized controlled trial [ISRCTN56104508

    Directory of Open Access Journals (Sweden)

    Baldauf Annika

    2011-06-01

    Full Text Available Abstract Background Care management programmes are an effective approach to care for high risk patients with complex care needs resulting from multiple co-occurring medical and non-medical conditions. These patients are likely to be hospitalized for a potentially "avoidable" cause. Nurse-led care management programmes for high risk elderly patients showed promising results. Care management programmes based on health care assistants (HCAs targeting adult patients with a high risk of hospitalisation may be an innovative approach to deliver cost-efficient intensified care to patients most in need. Methods/Design PraCMan is a cluster randomized controlled trial with primary care practices as unit of randomisation. The study evaluates a complex primary care practice-based care management of patients at high risk for future hospitalizations. Eligible patients either suffer from type 2 diabetes mellitus, chronic obstructive pulmonary disease, chronic heart failure or any combination. Patients with a high likelihood of hospitalization within the following 12 months (based on insurance data will be included in the trial. During 12 months of intervention patients of the care management group receive comprehensive assessment of medical and non-medical needs and resources as well as regular structured monitoring of symptoms. Assessment and monitoring will be performed by trained HCAs from the participating practices. Additionally, patients will receive written information, symptom diaries, action plans and a medication plan to improve self-management capabilities. This intervention is addition to usual care. Patients from the control group receive usual care. Primary outcome is the number of all-cause hospitalizations at 12 months follow-up, assessed by insurance claims data. Secondary outcomes are health-related quality of life (SF12, EQ5D, quality of chronic illness care (PACIC, health care utilisation and costs, medication adherence (MARS, depression

  12. IRIS PRA preliminary results and future direction

    International Nuclear Information System (INIS)

    Finnicum, D.J.; Kling, C.L.; Carelli, M.D.

    2004-01-01

    Westinghouse is currently conducting the pre-application licensing of the International Reactor Innovative and Secure (IRIS) on behalf of the IRIS Consortium. One of the key aspects of the IRIS design is the concept of safety-by-design. The PRA (Probabilistic Risk Analysis) is being used as an integral part of the design process. As part of this effort, a PRA of the initial design was generated to address 2 key areas. First, the IRIS PRA supported the evaluation of IRIS design issues by providing a solid risk basis for design and analyses required for the pre-licensing evaluation of the IRIS design. The PRA provides the tool for quantifying the benefit of the safety-by-design approach. Second, the current PRA task is beginning the preparation of the more complete PRA analyses and documentation eventually required for Design Certification. One of the key risk-related goals for IRIS is to reduce the EPZ (Emergency Protection Zone) to within the exclusion area by demonstrating that the off-site doses are consistent with the US Protective Action Guidelines (PAGs) for initiation of emergency response so that the required protective actions would be limited to the exclusion area. The results of the preliminary PRA indicated a core damage frequency of 1.2 E-08 for internal initiators. This is a very good result but much work is needed to meet the ambitious goal of no emergency response. The next phase of the PRA analyses will involve a two-fold expansion of the PRA. First, as the design and analyses approach a greater level of detail, the assumptions used for the initial PRA will be reviewed and the models will be revised as needed to reflect the improved knowledge of the system design and performance. Furthermore, as the full plant design advances, the PRA will be expanded to incorporate risk associated with external challenges such as seismic and fire, and to address low power and shutdowns modes of operation. As with the initial work, the PRA will serve as a tool to

  13. Management and Organization Influences in PRA

    International Nuclear Information System (INIS)

    Gertman, D.I.; Hallbert, B. P.; Blackman, H. S.

    1998-01-01

    The authors present a research program which aimed at increasing the quality of comprehensiveness of contemporary PRA (Probability Risk Assessment) by providing a tool that allows for incorporating M and O in PRA, at improving the quality of NRC assessments, at conducting research to support the risk informed regulation process, at identifying impact of management and organization, safety culture, workplace environment, down-sizing and deregulation on human performance and reliability

  14. PRA -- Now that operators have it, what do they do with it?

    International Nuclear Information System (INIS)

    Rasmussen, M.A.; Kolo, R.J.

    1996-01-01

    Many utilities have had Probabilistic Risk Assessment (PRA) projects underway for several years in order to satisfy the NRC Generic Letter 88-20 requirement for an Individual Plant Examination, or IPE. Typically the studies have reached the conclusion that there are significant differences in the contribution of different plant components to preventing core damage should a major plant transient occur. How nuclear plant operators can use this knowledge to DECREASE the overall risk of performing the routine tasks of testing and maintenance is not an easy task. 10CFR50.65; ''The Maintenance Rule,'' requires that any plant maintenance performed with the unit on line be evaluated for risk. Byron Station will satisfy the 10CFR50.65 requirement by using PRA methodology to evaluate testing and maintenance activities performed with the unit at power. The challenge is to effectively use the results of PRA studies to aid in plant operations without having to make on shift plant operations personnel experts in PRA. At Byron, PRA is used to help build the weekly work schedules. Operations personnel tasked with reviewing the work schedule are the departmental experts on the use of the PRA results. The on shift SRO's role in implementing the program is to accurately execute and monitor the work week schedule as written, and to react to unforeseen equipment failures with an appropriate level of response. The response to such emergent work items is also predefined. Handling emergent work in a prescribed manner minimizes the overall risk to the unit and also eliminates the need to have PRA expertise available to make emergent work risk evaluations. Thus the on shift operators' required knowledge of PRA methods and intricacies is minimized. PRA is just another of the many tools used by the shift operator to run the plant in a safe, conservative manner

  15. PRA (Probabilistic Risk Assessments) Participation versus Validation

    Science.gov (United States)

    DeMott, Diana; Banke, Richard

    2013-01-01

    Probabilistic Risk Assessments (PRAs) are performed for projects or programs where the consequences of failure are highly undesirable. PRAs primarily address the level of risk those projects or programs posed during operations. PRAs are often developed after the design has been completed. Design and operational details used to develop models include approved and accepted design information regarding equipment, components, systems and failure data. This methodology basically validates the risk parameters of the project or system design. For high risk or high dollar projects, using PRA methodologies during the design process provides new opportunities to influence the design early in the project life cycle to identify, eliminate or mitigate potential risks. Identifying risk drivers before the design has been set allows the design engineers to understand the inherent risk of their current design and consider potential risk mitigation changes. This can become an iterative process where the PRA model can be used to determine if the mitigation technique is effective in reducing risk. This can result in more efficient and cost effective design changes. PRA methodology can be used to assess the risk of design alternatives and can demonstrate how major design changes or program modifications impact the overall program or project risk. PRA has been used for the last two decades to validate risk predictions and acceptability. Providing risk information which can positively influence final system and equipment design the PRA tool can also participate in design development, providing a safe and cost effective product.

  16. Two decades of PRA: What next?

    International Nuclear Information System (INIS)

    Rasmussen, N.C.

    1992-01-01

    Two decades ago, in the spring of 1972, the Reactor Safety Study was undertaken for the US Atomic Energy Commission (AEC). The goal of this study was to assess the risk to the public posed by the nuclear power plants operating in the US. Some three and one-half years later in October 1975, the study group issued its final report titled The Reactor Safety Study, also commonly known by its document number WASH 1400. Because it was issued at a time of heated public debate about nuclear safety, WASH 1400 received considerable critical review. By the late 1970s, as a result of the Lewis Report and the accident at Three Mile Island, the value of the WASH 1400 methodology was gradually recognized. A number of utilities undertook such studies of their own plants. The field of probabilistic risk assessment (PRA) developed from these efforts. Challenges remain. Among these are how to effectively communicate the results of the analysis. Just what does a probability of one in a million mean? Is there a de minimis probability - one so small that it can be ignored? How should society make decisions under substantial uncertainty? A number of these questions pose real challenges for the future

  17. Utilization of NPP Krsko plant specific simulator

    International Nuclear Information System (INIS)

    Fifnja, I.; Pribozic, F.; Krajnc, J.

    2002-01-01

    NPP Krsko started with licensed operator training using its own plant-specific full scope simulator in April 2000. Today, two years after simulator was completed, the benefits of simulator use are visible in various fields. The simulator was effectively used to conduct licensed operator continuing training and practical examinations. Two-year continuous training program was designed to help maintain and improve operator performance. The simulator was also used to provide just-in-time training prior to plant evolutions. Together with licensed operators the non-licensed operators are also included into simulator training to provide affective team training opportunity and to foster good communication and increase scenario realism. Now, the first group of initial licensed operator training using plant-specific simulator is also almost completed. It is the first time that NPP Krsko training department conducted complete initial training and this will represent the great experience for future training. Besides training, the simulator was also utilized for procedure development and validation, operating standards development, testing of plant modifications and other activities, like emergency preparedness procedures validation and training exercises.(author)

  18. Applicability of PRISM PRA Methodology to the Level II Probabilistic Safety Analysis of KALIMER-600 (I) (Core Damage Event Tree Analysis Part)

    International Nuclear Information System (INIS)

    Park, S. Y.; Kim, T. W.; Ha, K. S.; Lee, B. Y.

    2009-03-01

    The Korea Atomic Energy Research Institute (KAERI) has been developing liquid metal reactor (LMR) design technologies under a National Nuclear R and D Program. Nevertheless, there is no experience of the PSA domestically for a fast reactor with the metal fuel. Therefore, the objective of this study is to establish the methodologies of risk assessment for the reference design of KALIMER-600 reactor. An applicability of the PSA of the PRISM plant to the KALIMER-600 has been studied. The study is confined to a core damage event tree analysis which is a part of a level 2 PSA. Assuming that the accident types, which can be developed from level 1 PSA, are same as the PRISM PRA, core damage categories are defined and core damage event trees are developed for the KALIMER-600 reactor. Fission product release fractions of the core damage categories and branch probabilities of the core damage event trees are referred from the PRISM PRA temporarily. Plant specific data will be used during the detail analysis

  19. Calculation of Fire Severity Factors and Fire Non-Suppression Probabilities For A DOE Facility Fire PRA

    International Nuclear Information System (INIS)

    Elicson, Tom; Harwood, Bentley; Lucek, Heather; Bouchard, Jim

    2011-01-01

    Over a 12 month period, a fire PRA was developed for a DOE facility using the NUREG/CR-6850 EPRI/NRC fire PRA methodology. The fire PRA modeling included calculation of fire severity factors (SFs) and fire non-suppression probabilities (PNS) for each safe shutdown (SSD) component considered in the fire PRA model. The SFs were developed by performing detailed fire modeling through a combination of CFAST fire zone model calculations and Latin Hypercube Sampling (LHS). Component damage times and automatic fire suppression system actuation times calculated in the CFAST LHS analyses were then input to a time-dependent model of fire non-suppression probability. The fire non-suppression probability model is based on the modeling approach outlined in NUREG/CR-6850 and is supplemented with plant specific data. This paper presents the methodology used in the DOE facility fire PRA for modeling fire-induced SSD component failures and includes discussions of modeling techniques for: Development of time-dependent fire heat release rate profiles (required as input to CFAST), Calculation of fire severity factors based on CFAST detailed fire modeling, and Calculation of fire non-suppression probabilities.

  20. Evaluation of Risk Metrics for KHNP Reference Plants Using the Latest Plant Specific Data

    International Nuclear Information System (INIS)

    Jeon, Ho Jun; Hwang, Seok Won; Ghi, Moon Goo

    2010-01-01

    As Risk-Informed Applications (RIAs) are actively implemented in the nuclear industry, an issue associated with the technical adequacy of the Probabilistic Safety Assessment (PSA) arises in its data sources. The American Society of Mechanical Engineers (ASME) PRA standard suggests the use of component failure data that represent the as-built and as-operated plant conditions. Furthermore, the peer reviews for the KHNP reference plants stated that the component failure data should be updated to reflect the latest plant specific data available. For ensuring the technical adequacy in PSA data elements, we try to update component failure data to reflect the as-operated plant conditions, and a trend analysis of the failure data is implemented. In addition, by applying the updated failure data to the PSA models of the KHNP reference plants, the risk metrics of Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) are evaluated

  1. Probabilistic risk assessment course documentation. Volume 1: PRA fundamentals

    International Nuclear Information System (INIS)

    Breeding, R.J.; Leahy, T.J.; Young, J.

    1985-08-01

    The full range of PRA topics is presented, with a special emphasis on systems analysis and PRA applications. Systems analysis topics include system modeling such as fault tree and event tree construction, failure rate data, and human Reliability. The discussion of PRA applications is centered on past and present PRA based programs, such as WASH-1400 and the Interim Reliability Evaluation Program, as well as on some of the potential future applications of PRA. The relationship of PRA to generic safety issues such as station blackout and Anticipated Transient Without Scram (ATWS) is also discussed. In addition to system modeling, the major PRA tasks of accident process analysis, and consequence analysis are presented. An explanation of the results of these activities, and the techniques by which these results are derived, forms the basis for a discussion of these topics. An additional topic which is presented in this course is the topic of PRA management, organization, and evaluation. 84 figs., 41 tabs

  2. Advances in Probabilistic Risk Assessment (PRA): a look into practitioners toolbox

    International Nuclear Information System (INIS)

    Mok, J.; Kaasalainen, S.; Donnelly, K.

    2007-01-01

    The ever-increasing emphasis on the use of Probabilistic Risk Assessment (PRA) in risk-informed decision making translates into increased expectations relating to PRA applications for the groups tasked with developing and maintaining the facility PRAs. In order to succeed in meeting the demand for PRA work, it is essential to develop methodologies and tools (or utilities) that improve the efficiency with which the PRAs are processed and manipulated to obtain a solution. Examples from the Nuclear Safety Solutions (NSS) PRA Practitioners tool box include utilities for cutting logical loops, optimizing fault trees (to decrease run-times), modularizing fault trees, and converting event trees into high level fault tree logic (an important element if the PRA study is to be used to support a risk monitor such as an Equipment Out-of-Service (EOOS) Monitor). The objective of this paper is be to briefly describe the main features of these utilities, and to illustrate the value they have in terms of improving the efficiency and effectiveness of PRA development and maintenance at NSS. (author)

  3. Plant specific basic principle simulator as a first step to plant specific full scope simulator

    International Nuclear Information System (INIS)

    Krajnc, B.; Pribozic, F.; Novsak, M.

    1996-01-01

    Nuklearna Elektrarna Krsko (NEK) decided to enhance the quality and scope of initial training of NEK technical personnel, mainly in so called Phase 1 and 2 of training for licensed personnel. This training is a prerequisite for further training on the full scope simulator for future operators and is also given to larger number of engineers, working in different important areas where thorough knowledge of nuclear technology and plant systems is required. Due to that it was decided that plant specific Basis Principle Simulators (BPS) should be developed. The other important reason for such decision was an indication that NEK specific full scope simulator will have to be purchased. Based on that it was concluded that BPS should serve as a good opportunity to learn about the state of the art approaches in the modeling area, to see in which direction development of software in conjunction with state of the art hardware is going and in particular to the extent possible verify the existence of required plant documentation in support BPS and later plant specific full scope simulator. In this paper the scope of NEK BPS simulation, experience in initial data gathering, experience with know-how transfer based on direct involvement of NEK and Izobrazevalni Center za Jedrsko Tehnnologijo (ICJT) personnel in modeling of instrumentation and control will be presented. Lessons learned, particularly in light of coming project for NEK full scope simulator, will also be addressed. The future use of the BPS in the NEK training programs will be described. It can be concluded that due to very complex technology, phase approaches in training of key NEK technical personnel, the development of NEK plant specific BPS is justifiable, regardless of the fact that NEK will also obtain specific full scope simulator. It has to be pointed out that BPS can not be supplement for plant specific full scope simulator, due to number of reasons discussed in the paper. (author)

  4. Use of PRA in the nuclear regulatory field in South Africa

    International Nuclear Information System (INIS)

    Hill, T.F.

    1994-01-01

    The nuclear regulatory authority in South Africa (since 1988 the Council for Nuclear Safety (CNS)), established in 1973 nuclear safety criteria against which to assess the level of safety of any facility using radioactive material. It is a regulatory requirement in South Africa to develop and maintain a living PRA for each facility and thereby to provide the necessary information to demonstrate compliance against these criteria. All safety submissions to the CNS must include at least a risk statement based on an accepted PRA study. The function of the CNS is to regulate all activities in South Africa involving the use of radioactive material and posing a significant risk to the public or plant personnel. This includes most aspects of the nuclear fuel cycle and the Koeberg NPS (two 2775 MW(th) PWRs). A PRA study including source terms for the two Koeberg units was presented by the contractor in 1979. This included the risk due to power and shutdown states and non reactor related accidents involving spent fuel storage, fuel handling and waste treatment related activities. At least 20 PRA studies have been performed for other nuclear facilities in the country. The CNS maintains an in-house PRA capability to perform independent assessments of licensee submission, to participate in developments of PRA methodology in the regulatory field, to perform pro-active safety work and to assist in regulatory decision making. Present ongoing work includes the development of a risk monitor, a risk management system, improvement in PRA codes, models, data collection and analysis, off-site risk assessment methodology and associated regulatory policy. (author). 1 fig

  5. PRA research and the development of risk-informed regulation at the U.S. nuclear regulatory commission

    International Nuclear Information System (INIS)

    Siu, Nathan; Collins, Dorothy

    2008-01-01

    Over the years, Probabilistic Risk Assessment (PRA) research activities conducted at the U.S. Nuclear Regulatory Commission (NRC) have played an essential role in support of the agency's move towards risk-informed regulation. These research activities have provided the technical basis for NRC's regulatory activities in key areas; provided PRA methods, tools, and data enabling the agency to meet future challenges; supported the implementation of NRC's 1995 PRA Policy Statement by assessing key sources of risk; and supported the development of necessary technical and human resources supporting NRC's risk-informed activities. PRA research aimed at improving the NRC's understanding of risk can positively affect the agency's regulatory activities, as evidenced by three case studies involving research on fire PRA, Human Reliability Analysis (HRA), and Pressurized Thermal Shock (PTS) PRA. These case studies also show that such research can take a considerable amount of time, and that the incorporation of research results into regulatory practice can take even longer. The need for sustained effort and appropriate lead time is an important consideration in the development of a PRA research program aimed at helping the agency address key sources of risk for current and potential future facilities

  6. Summary of PRA assessment of transient accident risks, human factors considerations, and PRA methods and applications

    International Nuclear Information System (INIS)

    Carnino, A.

    1984-01-01

    This chapter reviews the progress made in the probabilistic risk assessment (PRA) area to help in solving operational transient problems and to integrate human factors considerations, as discussed at the American Nuclear Society Topical Meeting on Anticipated and Abnormal Plant Transients in Light Water Reactors. Topics considered include core-melt frequency, external events (e.g., fires, floods), diagnostic errors, and operator aids. It is concluded that confidence in PRA results, predictions and uses for decisions in both the safety of the plants and their availability will improve

  7. MAAP4.0.7 analysis and justification for PRA level 1 mission success criteria

    International Nuclear Information System (INIS)

    Butler, J.S.; Kapitz, D.; Martin, R.P.; Seifaee, F.; Sundaram, R.K.

    2008-01-01

    The U.S. EPR is a 4590 MWth evolutionary pressurized water reactor that incorporates proven technology with innovative system architecture to provide an unprecedented level of safety. One of the measures of safety is provided by Probability Risk Assessment (PRA). PRA Level 1 concerns the evaluation of core damage frequency based on various initiating events and the success or failure of various plant event mitigation features. Determination of this measure requires mission success criteria, which are used to build the logic that makes up the fault trees and event trees of the Level 1 PRA. Developing mission success criteria for the wide variety of accident sequences modeled in the PRA Level 1 model requires a large number of thermal hydraulic calculations. The MAAP4 code, developed by Fauske and Associates, Inc. and distributed by EPRI, was chosen to perform these calculations because of its fast computation times relative to more sophisticated thermal-hydraulics codes This is a unique application of MAAP4, which was developed specifically for severe accident and PRA Level 2 analysis. As such, a study was performed to assess MAAP4 's thermal-hydraulic response capabilities against AREVA 's S-RELAP5 best-estimate integral systems thermal-hydraulic analysis code. (authors)

  8. Insights on PRA Review Practices: Necessity for Model Shaking

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Inn Seock; Jang, Mi suk; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

    2016-05-15

    Probabilistic risk assessment (PRA) is increasingly used as a technique to help ensure design and operational safety of nuclear power plants (NPPs) in the nuclear industry. Hence, there is considerable interest in the PRA quality, and as a result, a peer review of the PRA model is typically performed to ensure its technical adequacy as part of the PRA development process or for any other reason (e.g., regulatory requirement). For the PRA model to be used as a valuable vehicle for risk-informed applications, it is essential that the PRA model must yield correct and physically meaningful accident sequences and minimal cutsets for specific plant configurations or conditions relating to the applications. Hence, the existing peer review guidelines need to be updated to reflect these insights so that risk-informed applications could be more actively pursued with confidence.

  9. PRA: A PERSPECTIVE ON STRENGTHS, CURRENT LIMITATIONS, AND POSSIBLE IMPROVEMENTS

    Directory of Open Access Journals (Sweden)

    ALI MOSLEH

    2014-02-01

    Full Text Available Probabilistic risk assessment (PRA has been used in various technological fields to assist regulatory agencies, managerial decision makers, and systems designers in assessing and mitigating the risks inherent in these complex arrangements. Has PRA delivered on its promise? How do we gage PRA performance? Are our expectations about value of PRA realistic? Are there disparities between what we get and what we think we are getting form PRA and its various derivatives? Do current PRAs reflect the knowledge gained from actual events? How do we address potential gaps? These are some of the questions that have been raised over the years since the inception of the field more than forty years ago. This paper offers a brief assessment of PRA as a technical discipline in theory and practice, its key strengths and weaknesses, and suggestions on ways to address real and perceived shortcomings.

  10. PRA: A Perspective on Strengths, Current Limitations, And Possible Improvements

    International Nuclear Information System (INIS)

    Mosleh, Ail

    2014-01-01

    Probabilistic risk assessment (PRA) has been used in various technological fields to assist regulatory agencies, managerial decision makers, and systems designers in assessing and mitigating the risks inherent in these complex arrangements. Has PRA delivered on its promise? How do we gage PRA performance? Are our expectations about value of PRA realistic? Are there disparities between what we get and what we think we are getting form PRA and its various derivatives? Do current PRAs reflect the knowledge gained from actual events? How do we address potential gaps? These are some of the questions that have been raised over the years since the inception of the field more than forty years ago. This paper offers a brief assessment of PRA as a technical discipline in theory and practice, its key strengths and weaknesses, and suggestions on ways to address real and perceived shortcomings

  11. PRISIM: a computer program that makes PRA useful

    International Nuclear Information System (INIS)

    Fussell, J.B.; Campbell, D.J.; Glynn, J.C.; Burdick, G.R.

    1986-01-01

    PRISIM is an IBM personal computer program that translates probabilistic risk assessment (PRA) information and calculates additional PRA type information for use by those who are not PRA experts. Specifically, PRISIM was developed for the US Nuclear Regulatory Commission for use by their resident inspectors at nuclear power plants. Inspector activities are either scheduled or are in response to a particular status of a plant. PRISIM is useful for either activity

  12. Applicability of PRA methods and data to the financial risk assessment of nuclear power plants

    International Nuclear Information System (INIS)

    El-Sheik, K.A.

    1985-01-01

    Financial risk assessment, where the probability and severity of financial consequences are estimated, offers a logical framework for organizing and evaluating data pertinent to nuclear power plant accidents. Under the sponsorship of the Electric Power Research Institute, General Electric investigated the feasibility of financial risk assessment of nuclear power plants and of applying PRA methods and data in such an assessment. This paper summarizes the main findings of this investigation. Specifically, the paper discussed the following topics: definition of financial consequences and financial risk; overall approach for financial risk assessment and how it compares with the approach for PRA used in the Reactor Safety Study; and specific financial risk assessment procedures for defining initiating events, plant response sequences, institutional scenarios, and financial consequences and how they compare to analogous procedures for PRA

  13. Evaluation of hsp65 Nested PCR-Restriction Analysis (PRA) for Diagnosing Tuberculosis in a High Burden Country

    Science.gov (United States)

    Macente, Sara; Fujimura Leite, Clarice Queico; Santos, Adolfo Carlos Barreto; Siqueira, Vera Lúcia Dias; Machado, Luzia Neri Cosmo; Marcondes, Nadir Rodrigues; Hirata, Mario Hiroyuki; Hirata, Rosário Dominguez Crespo

    2013-01-01

    Current study evaluated the hsp65 Nested PCR Restriction Fragment Length Polymorphism Analysis (hsp65 Nested PCR-PRA) to detect and identify Mycobacterium tuberculosis complex directly in clinical samples for a rapid and specific diagnosis of tuberculosis (TB). hsp65 Nested PCR-PRA was applied directly to 218 clinical samples obtained from 127 patients suspected of TB or another mycobacterial infection from July 2009 to July 2010. The hsp65 Nested PCR-PRA showed 100% sensitivity and 95.0 and 93.1% specificity in comparison with culture and microscopy (acid fast bacillus smear), respectively. hsp65 Nested PCR-PRA was shown to be a fast and reliable assay for diagnosing TB, which may contribute towards a fast diagnosis that could help the selection of appropriate chemotherapeutic and early epidemiological management of the cases which are of paramount importance in a high TB burden country. PMID:24260739

  14. Certification plan for safety and PRA codes

    International Nuclear Information System (INIS)

    Toffer, H.; Crowe, R.D.; Ades, M.J.

    1990-05-01

    A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA ampersand PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan's objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations

  15. Estrogen and progesterone receptors have distinct roles in the establishment of the hyperplastic phenotype in PR-A transgenic mice

    Energy Technology Data Exchange (ETDEWEB)

    Simian, Marina; Bissell, Mina J.; Barcellos-Hoff, Mary Helen; Shyamala, Gopalan

    2009-05-11

    Expression of the A and B forms of progesterone receptor (PR) in an appropriate ratio is critical for mammary development. Mammary glands of PR-A transgenic mice, carrying an additional A form of PR as a transgene, exhibit morphological features associated with the development of mammary tumors. Our objective was to determine the roles of estrogen (E) and progesterone (P) in the genesis of mammary hyperplasias/preneoplasias in PR-A transgenics. We subjected PR-A mice to hormonal treatments and analyzed mammary glands for the presence of hyperplasias and used BrdU incorporation to measure proliferation. Quantitative image analysis was carried out to compare levels of latency-associated peptide and transforming growth factor beta 1 (TGF{beta}1) between PR-A and PR-B transgenics. Basement membrane disruption was examined by immunofluorescence and proteolytic activity by zymography. The hyperplastic phenotype of PR-A transgenics is inhibited by ovariectomy, and is reversed by treatment with E + P. Studies using the antiestrogen ICI 182,780 or antiprogestins RU486 or ZK 98,299 show that the increase in proliferation requires signaling through E/estrogen receptor alpha but is not sufficient to give rise to hyperplasias, whereas signaling through P/PR has little impact on proliferation but is essential for the manifestation of hyperplasias. Increased proliferation is correlated with decreased TGF{beta}1 activation in the PR-A transgenics. Analysis of basement membrane integrity showed loss of laminin-5, collagen III and collagen IV in mammary glands of PR-A mice, which is restored by ovariectomy. Examination of matrix metalloproteases (MMPs) showed that total levels of MMP-2 correlate with the steady-state levels of PR, and that areas of laminin-5 loss coincide with those of activation of MMP-2 in PR-A transgenics. Activation of MMP-2 is dependent on treatment with E and P in ovariectomized wild-type mice, but is achieved only by treatment with P in PR-A mice. These data

  16. Introduction of accidental procedures in the event trees of the 900MW PWR PRA

    International Nuclear Information System (INIS)

    Bars, G.; Champ, M.; Lanore, J.M.; Pochard, R.

    1985-02-01

    This paper presents the example of the small LOCA Event Trees and the studies related to the introduction of procedure actions is case of HPSI failure. The results illustrate the interest of the approach and its significant impact on the PRA. The present studies are related to the Y actions in case of small LOCAs without HPIS

  17. Development of insights from PRAs for non-PRA people

    International Nuclear Information System (INIS)

    Reilly, H.J.; Meale, B.M.

    1992-01-01

    A probabilistic risk assessment (PRA) of the Savannah River K-Reactor was completed in 1990. The PRA estimated the frequency of core damage accidents caused by operational occurrences during power operation of the reactor. The US Department of Energy (DOE) requested Idaho National Engineering Laboratory (INEL) to prepare guidance based on the PRA for use by DOE personnel at the Savannah River Site (SRS). The document had the purpose of informing the DOE system engineers and site representatives about how the information in the PRA might be used to help guide their activities. Opportunities existed to develop a document somewhat different than those developed previously by other programs. The opportunities existed because the audience is different: the principal audience for the document consists of DOE engineers who have continuing oversight responsibility for activities performed by the operating contractor at the K-Reactor, but who may not be knowledgeable about PRA

  18. Use of PRA in Shuttle Decision Making Process

    Science.gov (United States)

    Boyer, Roger L.; Hamlin, Teri L.

    2010-01-01

    How do you use PRA to support an operating program? This presentation will explore how the Shuttle Program Management has used the Shuttle PRA in its decision making process. It will reveal how the PRA has evolved from a tool used to evaluate Shuttle upgrades like Electric Auxiliary Power Unit (EAPU) to a tool that supports Flight Readiness Reviews (FRR) and real-time flight decisions. Specific examples of Shuttle Program decisions that have used the Shuttle PRA as input will be provided including how it was used in the Hubble Space Telescope (HST) manifest decision. It will discuss the importance of providing management with a clear presentation of the analysis, applicable assumptions and limitations, along with estimates of the uncertainty. This presentation will show how the use of PRA by the Shuttle Program has evolved overtime and how it has been used in the decision making process providing specific examples.

  19. PRA for emergency planning: assessing the risk profile of a 3-loop PWR on the basis of US and German risk studies

    International Nuclear Information System (INIS)

    Chakraborty, S.; Fuchs, H.; Gubler, R.; Landolt, J.; Miteff, L.

    1985-01-01

    Emergency planning around nuclear power plants should be based on a realistic assessment of their risk profile. Since the results of the Rasmussen study (WASH-1400) and later of the German risk study (Phase A) were not judged to be fully representative for NPP's in Switzerland, an investigation was started to transfer applicable US and German results to a Swiss 3-loop PWR (Goesgen) and to assess the impact of differences in plant design compared to Surry-1 and Biblis-B. The core melt probability for Goesgen was calculated to be more than a factor of ten smaller than for the US and German studies. This is mainly due to more redundancy/better separation (especially in the emergency feedwater) and to partial automation of cooldown after a small break. The results were instrumental in limiting the release categories to be used as reference cases for emergency planning. Further reduction of postulated accidental releases is expected from the current source term research

  20. Constellation Probabilistic Risk Assessment (PRA): Design Consideration for the Crew Exploration Vehicle

    Science.gov (United States)

    Prassinos, Peter G.; Stamatelatos, Michael G.; Young, Jonathan; Smith, Curtis

    2010-01-01

    Managed by NASA's Office of Safety and Mission Assurance, a pilot probabilistic risk analysis (PRA) of the NASA Crew Exploration Vehicle (CEV) was performed in early 2006. The PRA methods used follow the general guidance provided in the NASA PRA Procedures Guide for NASA Managers and Practitioners'. Phased-mission based event trees and fault trees are used to model a lunar sortie mission of the CEV - involving the following phases: launch of a cargo vessel and a crew vessel; rendezvous of these two vessels in low Earth orbit; transit to th$: moon; lunar surface activities; ascension &om the lunar surface; and return to Earth. The analysis is based upon assumptions, preliminary system diagrams, and failure data that may involve large uncertainties or may lack formal validation. Furthermore, some of the data used were based upon expert judgment or extrapolated from similar componentssystemsT. his paper includes a discussion of the system-level models and provides an overview of the analysis results used to identify insights into CEV risk drivers, and trade and sensitivity studies. Lastly, the PRA model was used to determine changes in risk as the system configurations or key parameters are modified.

  1. How the chemical industry can benefit from PRA

    International Nuclear Information System (INIS)

    Guymer, P.; Kaiser, G.D.; Mc Kelvey, T.W.; Hannaman, G.W.

    1986-01-01

    Probabilistic Risk Assessment (PRA) is a method of quantifying the frequency of occurrence and the magnitude of the consequences of accidents in systems that contain hazardous materials such as radioactive fission products, and toxic, flammable or explosive chemicals. The frequency and the magnitude of the consequences are the basic elements of any definition or risk, which is often simply expressed as the product of frequency and magnitude, summed over all accident sequences. PRA is now a mature technique that has been used to estimate risk for a number of industrial facilities. In this paper the author gives examples of beneficial uses of PRA

  2. PRA-Code Upgrade to Handle a Generic Problem

    International Nuclear Information System (INIS)

    Wilson, J. R.

    1999-01-01

    During the probabilistic risk assessment (PRA) for the proposed Yucca Mountain nuclear waste repository, a problem came up that could not be handled by most PRA computer codes. This problem deals with dependencies between sequential events in time. Two similar scenarios that illustrate this problem are LOOP nonrecovery and sequential wearout failures with units of time. The purpose of this paper is twofold: To explain the problem generically, and to show how the PRA code at the INEEL, SAPHIRE, has been modified to solve this problem correctly

  3. Applications of Living Fire PRA models to Fire Protection Significance Determination Process in Taiwan

    International Nuclear Information System (INIS)

    De-Cheng, Chen; Chung-Kung, Lo; Tsu-Jen, Lin; Ching-Hui, Wu; Lin, James C.

    2004-01-01

    The living fire probabilistic risk assessment (PRA) models for all three operating nuclear power plants (NPPs) in Taiwan had been established in December 2000. In that study, a scenario-based PRA approach was adopted to systematically evaluate the fire and smoke hazards and associated risks. Using these fire PRA models developed, a risk-informed application project had also been completed in December 2002 for the evaluation of cable-tray fire-barrier wrapping exemption. This paper presents a new application of the fire PRA models to fire protection issues using the fire protection significance determination process (FP SDP). The fire protection issues studied may involve the selection of appropriate compensatory measures during the period when an automatic fire detection or suppression system in a safety-related fire zone becomes inoperable. The compensatory measure can either be a 24-hour fire watch or an hourly fire patrol. The living fire PRA models were used to estimate the increase in risk associated with the fire protection issue in terms of changes in core damage frequency (CDF) and large early release frequency (LERF). In compliance with SDP at-power and the acceptance guidelines specified in RG 1.174, the fire protection issues in question can be grouped into four categories; red, yellow, white and green, in accordance with the guidelines developed for FD SDP. A 24-hour fire watch is suggested only required for the yellow condition, while an hourly fire patrol may be adopted for the white condition. More limiting requirement is suggested for the red condition, but no special consideration is needed for the green condition. For the calculation of risk measures, risk impacts from any additional fire scenarios that may have been introduced, as well as more severe initiating events and fire damages that may accompany the fire protection issue should be considered carefully. Examples are presented in this paper to illustrate the evaluation process. (authors)

  4. The radioprotective effect of a new aminothiol (20-PRA)

    International Nuclear Information System (INIS)

    Dolabela, M.F.; Lopes, M.T.P.; Pereira, M.T.; Steffani, G.M.; Pilo-Veloso, D.; Salas, C.E.; Nelson, D.L.

    1998-01-01

    We examined the radioprotective effect of aminothiol 2-N-propylamine-cyclohexane thiol (20-PRA) on a human leukemic cell line (K562) following various radiation doses (5,7.5 and 20 Gy) using a source of 60 Co γ-rays. At 5 Gy and 1nM 20-PRA, a substantial protective effect (58%) was seen 24 h after irradiation, followed by a decrease at 48 h (11%). At the high radiation dose (20 Gy) a low protective effect was also seen (35%). In addition, the anti tumorigenic potential of 10 nM 20-PRA was shown by the inhibition of crown gall formation induced by Agrobacterium tumefaciens. The radioprotective potency of 20-PRA is 10 5- 10 6 times higher than that of the aminothiol WR-1065 (N(2-mercaptoethyl)-1,3-diamino propane) whose protective effect is in the 0.1 to 1.0 nM range. (author)

  5. The radioprotective effect of a new aminothiol (20-PRA

    Directory of Open Access Journals (Sweden)

    M.F. Dolabela

    1998-08-01

    Full Text Available We examined the radioprotective effect of aminothiol 2-N-propylamine-cyclo-hexanethiol (20-PRA on a human leukemic cell line (K562 following various radiation doses (5, 7.5 and 20 Gy using a source of 60Co g-rays. At 5 Gy and 1 nM 20-PRA, a substantial protective effect (58% was seen 24 h after irradiation, followed by a decrease at 48 h (11%. At the high radiation dose (20 Gy a low protective effect was also seen (35%. In addition, the antitumorigenic potential of 10 nM 20-PRA was shown by the inhibition of crown gall formation induced by Agrobacterium tumefaciens. The radioprotective potency of 20-PRA is 105-106 times higher than that of the aminothiol WR-1065 (N-(2-mercaptoethyl-1,3-diaminopropane whose protective effect is in the 0.1 to 1.0 mM range.

  6. Applications of PRA in nuclear criticality safety

    International Nuclear Information System (INIS)

    McLaughlin, T.P.

    1992-01-01

    Traditionally, criticality accident prevention at Los Alamos has been based on a thorough review and understanding of proposed operations of changes to operations, involving both process supervision and criticality safety staff. The outcome of this communication was usually an agreement, based on professional judgement, that certain accident sequences were credible and had to be reduced in likelihood either by administrative controls or by equipment design and others were not credible, and thus did not warrant expenditures to further reduce their likelihood. The extent of analysis and documentation was generally in proportion to the complexity of the operation but did not include quantified risk assessments. During the last three years nuclear criticality safety related Probabilistic Risk Assessments (PRAs) have been preformed on operations in two Los Alamos facilities. Both of these were conducted in order to better understand the cost/benefit aspects of PRA's as they apply to largely ''hands-on'' operations with fissile material for which human errors or equipment failures significant to criticality safety are both rare and unique. Based on these two applications and an appreciation of the historical criticality accident record (frequency and consequences) it is apparent that quantified risk assessments should be performed very selectively

  7. Chinshan living PRA model using NUPRA software package

    International Nuclear Information System (INIS)

    Cheng, S.-K.; Lin, T.-J.

    2004-01-01

    A living probabilistic risk assessment (PRA) model has been established for Chinshan Nuclear Power Station (BWR-4, MARK-I) using NUPRA software package. The core damage frequency due to internal events, seismic events and typhoons are evaluated in this model. The methodology and results considering the recent implementation of the 5th emergency diesel generator and automatic boron injection function are presented. The dominant sequences of this PRA model are discussed, and some possible applications of this living model are proposed. (author)

  8. Plant specific PTS analysis of Kori Unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Sung-Yull, Hong; Changheui, Jang; Ill-Seok, Jeong [Korea Eletric Power Research Inst., Daejon (Korea, Republic of); Tae-Eun, Jin [Korea Power Engineering Company, Yonging (Korea, Republic of)

    1997-09-01

    Currently, a nuclear PLIM (Plant Lifetime Management) program is underway in Korea to extend the operation life of Kori-1 which was originally licensed for 30 years. For the life extension of nuclear power plants, the residual lives of major components should be evaluated for the extended operation period. According to the residual life evaluation of reactor pressure vessel, which was classified as one of the major components crucial to life extension, it was found by screening analysis that reference PTS temperature would exceed screening criteria before the target extended operation years. In order to deal with this problem, a plant-specific PTS analysis for Kori-1 RPV has been initiated. In this paper, the relationship between PTS analysis and Kori-1 PLIM program is briefly described. The plant-specific PTS analysis covers system transient analysis, downcomer mixing analysis, and probabilistic fracture mechanics analysis to check the integrity or RPV during various PTS transients. The step-by-step procedure of the analysis will be described in detail. Finally, various issues regarding RPV materials and its integrity will be briefly mentioned, and their implications on Kori-1 PTS analysis will be discussed. Despite of the screening analysis result concern, it is now expected that Kori-1 PTS issues can be handled through the plant-specific PTS analysis. (author). 14 refs, 4 figs, 2 tabs.

  9. Development of fire PRA methodologies for the analysis of typical Italian NPP designs

    International Nuclear Information System (INIS)

    Silvestri, E.; Dore, B.; Ferro, G.; Apostolakis, G.

    1987-01-01

    To compute fire induced Core Melt probability, the results of hazard and propagation analyses were combined with the Core Melt frequency computed for the initiating event and the support state as determined by the fire considered. From the PRA for internal event, the average value of this frequency was found 2.5x10 -3 event/year. Using the average fire frequency the resulting fire induced Core Melt frequency is 1.4x10 -8 event/year. Although high separation of safety systems is required in Italian PWR plants, the frequency of fire induced Core Melt can reach values not negligible with respect to Italian safety standards. For this reason, fire PRA studies for the entire plant are considered necessary and should be performed with appropriate modifications of the methods used for the American plants in order to be able to estimate lower fire induced Core Melt frequencies. (orig./HP)

  10. Overview of seismic margin insights gained from seismic PRA results

    International Nuclear Information System (INIS)

    Kennedy, R.P.; Sues, R.H.; Campbell, R.D.

    1986-01-01

    This paper presents the findings of a study conducted under NRC and EPRI sponsorship in which published seismic PRAs were reviewed in order to gain insight to the seismic margins inherent in existing nuclear plants. The approach taken was to examine the fragilities of those components which have been found to be dominant contributors to seismic risk at plants in low-to-moderate seismic regions (SSE levels between 0.12g and 0.25g). It is concluded that there is significant margin inherent in the capacity of most critical components above the plant design basis. For ground motions less than about 0.3g, the predominant sources of seismic risk are loss of offsite power coupled with random failure of the emergency diesels, non-recoverable circuit breaker trip due to relay chatter, unanchored equipment, unreinforced non-load bearing block walls, vertical water storage tanks, systems interactions and possibly soil liquefaction. Recommendations as to which components should be reviewed in seismic margin studies for margin earthquakes less than 0.3g, between 0.3g and 0.5g, and greater than 0.5g, developed by the NRC expert panel on the quantification of seismic margins (based on the review of past PRA data, earthquake experience data, and their own personal experience) are presented

  11. Probabilistic Risk Assessment (PRA): A Practical and Cost Effective Approach

    Science.gov (United States)

    Lee, Lydia L.; Ingegneri, Antonino J.; Djam, Melody

    2006-01-01

    The Lunar Reconnaissance Orbiter (LRO) is the first mission of the Robotic Lunar Exploration Program (RLEP), a space exploration venture to the Moon, Mars and beyond. The LRO mission includes spacecraft developed by NASA Goddard Space Flight Center (GSFC) and seven instruments built by GSFC, Russia, and contractors across the nation. LRO is defined as a measurement mission, not a science mission. It emphasizes the overall objectives of obtaining data to facilitate returning mankind safely to the Moon in preparation for an eventual manned mission to Mars. As the first mission in response to the President's commitment of the journey of exploring the solar system and beyond: returning to the Moon in the next decade, then venturing further into the solar system, ultimately sending humans to Mars and beyond, LRO has high-visibility to the public but limited resources and a tight schedule. This paper demonstrates how NASA's Lunar Reconnaissance Orbiter Mission project office incorporated reliability analyses in assessing risks and performing design tradeoffs to ensure mission success. Risk assessment is performed using NASA Procedural Requirements (NPR) 8705.5 - Probabilistic Risk Assessment (PRA) Procedures for NASA Programs and Projects to formulate probabilistic risk assessment (PRA). As required, a limited scope PRA is being performed for the LRO project. The PRA is used to optimize the mission design within mandated budget, manpower, and schedule constraints. The technique that LRO project office uses to perform PRA relies on the application of a component failure database to quantify the potential mission success risks. To ensure mission success in an efficient manner, low cost and tight schedule, the traditional reliability analyses, such as reliability predictions, Failure Modes and Effects Analysis (FMEA), and Fault Tree Analysis (FTA), are used to perform PRA for the large system of LRO with more than 14,000 piece parts and over 120 purchased or contractor

  12. Nuclear utility education and training becoming too plant specific?

    International Nuclear Information System (INIS)

    Wicks, F.

    1986-01-01

    As the Supervisor of a university nuclear reactor and operations curriculum, the author has also been offering education and training programs for nuclear utility technical support and operations personnel. Similar results have been reported by other universities offering similar programs. These programs also provide very important benefits to university nuclear engineering departments in terms of much needed revenues during this time of declining student enrollment and also by the information flow from the nuclear utility participants to the university personnel, which can yield both improved courses and identify research opportunities. University programs serve an important complementary function to plant-specific programs and should be continued and supported

  13. Use of plant specific PSA to evaluate incidents at nuclear power plants

    International Nuclear Information System (INIS)

    1991-06-01

    One of the possible applications of the plant specific probabilistic safety assessment (PSA) is its use in the analysis of operational events at the plant. The methodological development in that area was initiated recently in the framework of the IAEA's Incident Reporting System where determination of the safety significance of the event is essential for optimizing feedback of operating experience. This report provides details of the methodology and procedures to be used in event analysis. The report also contains three case studies which have been performed and summarizes lessons learned from those case studies. The results (event probabilities) obtained using plant specific PSA and the results of the analysis of the same events in the framework of the Accident Sequence Precursor (ASP) programmes (generic models) were compared and commented on. 6 refs, figs and tabs

  14. 77 FR 10576 - Methodology for Low Power/Shutdown Fire PRA

    Science.gov (United States)

    2012-02-22

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0295] Methodology for Low Power/Shutdown Fire PRA AGENCY.../Shutdown Fire PRA.'' In response to request from members of the public, the NRC is extending the public... risk assessment (PRA) method for quantitatively analyzing fire risk in commercial nuclear power plants...

  15. 76 FR 81998 - Methodology for Low Power/Shutdown Fire PRA

    Science.gov (United States)

    2011-12-29

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0295] Methodology for Low Power/Shutdown Fire PRA AGENCY..., ``Methodology for Low Power/Shutdown Fire PRA--Draft Report for Comment.'' DATES: Submit comments by March 01... risk assessment (PRA) method for quantitatively analyzing fire risk in commercial nuclear power plants...

  16. Giving Student Groups a Stronger Voice: Using Participatory Research and Action (PRA) to Initiate Change to a Curriculum

    Science.gov (United States)

    O'Neill, Geraldine; McMahon, Sinead

    2012-01-01

    Traditional student feedback mechanisms have been criticised for being teacher-centred in design and, in particular, for their absence of transparent follow-up actions. In contrast, this study describes the process and the evaluation of a participatory research and action (PRA) approach used in an undergraduate physiotherapy degree. This approach…

  17. Load out and offshore lifting of the PRA-1 platform modules; Embarque e icamento offshore dos modulos de PRA-1

    Energy Technology Data Exchange (ETDEWEB)

    Barbosa, Fernando; Raigorodsky, Jacques; Mitidieri, Jorge L.U.; Ricardi, Paulo S. [Construtora Norberto Odebrecht S.A., Rio de Janeiro, RJ (Brazil)

    2008-07-01

    The technology innovations are characteristics of offshore Engineering around the world. These technologies just make sense when they aim the productivity, security and costs gains compared to ordinary methods. It is in this context that the proposal of the Consorcio PRA-1 (Odebrecht e UTC) team makes sense, in the definition of basic methodology for the PRA-1 platform construction and installation. Through the innovative concept, It was defined (still in the proposal phase) the basic premise that the modules construction and assembly were onshore ending up that just few hours after the offshore installation the modules should be operational in minimal habitability conditions. This innovative method allowed the lack of Flotel, that is a platform which provide support to the offshore construction and assembly (Flotel represents a high costs to the project) and, as consequence, the contract signature by CONSORCIO PRA-1. This work aims to describe the method used for the LOUD-OUT of the PRA-1 modules and the installation of them on the jacket through a vessel provide with cranes the has performed the lifting. Theses operations became unique in Brazil due its challengers characteristics: Module 12 weight = 7203 tf and Module 35 = 5725 tf. For the accomplishment of the Load-out and offshore lifting, was performed a detailed planning and a high level of subcontract interface management. The operations mentioned above were filmed/photographed and published in the specialized media. (author)

  18. Implications of an HRA framework for quantifying human acts of commission and dependency: Development of a methodology for conducting an integrated HRA/PRA

    International Nuclear Information System (INIS)

    Barriere, M.T.; Luckas, W.J.; Brown, W.S.; Cooper, S.E.; Wreathall, J.; Bley, D.C.

    1993-01-01

    To support the development of a refined human reliability analysis (HRA) framework, to address identified HRA user needs and improve HRA modeling, unique aspects of human performance have been identified from an analysis of actual plant-specific events. Through the use of the refined framework, relationships between the following HRA, human factors and probabilistic risk assessment (PRA) elements were described: the PRA model, plant states, plant conditions, PRA basic events, unsafe human actions, error mechanisms, and performance shaping factors (PSFs). The event analyses performed in the context of the refined HRA framework, identified the need for new HRA methods that are capable of: evaluating a range of different error mechanisms (e.g., slips as well as mistakes); addressing errors of commission (EOCs) and dependencies between human actions; and incorporating the influence of plant conditions and multiple PSFs on human actions. This report discusses the results of the assessment of user needs, the refinement of the existing HRA framework, as well as, the current status on EOCs, and human dependencies

  19. Implications of an HRA framework for quantifying human acts of commission and dependency: Development of a methodology for conducting an integrated HRA/PRA

    International Nuclear Information System (INIS)

    Barriere, M.T.; Luckas, W.J.; Brown, W.S.; Cooper, S.E.; Wreathall, J.; Bley, D.C.

    1994-01-01

    To support the development of a refined human reliability analysis (HRA) framework, to address identified HRA user needs and improve HRA modeling, unique aspects of human performance have been identified from an analysis of actual plant-specific events. Through the use of the refined framework, relationships between the following HRA, human factors and probabilistic risk assessment (PRA) elements were described: the PRA model, plant states, plant conditions, PRA basic events, unsafe human actions, error mechanisms, and performance shaping factors (PSFs). The event analyses performed in the context of the refined HRA framework, identified the need for new HRA methods that are capable of: evaluating a range of different error mechanisms (e.g., slips as well as mistakes); addressing errors of commission (EOCs) and dependencies between human actions; and incorporating the influence of plant conditions and multiple PSFs on human actions. This report discusses the results of the assessment of user needs, the refinement of the existing HRA framework, as well as, the current status on EOCs, and human dependencies

  20. Plant specific severe accident management - the implementation phase

    International Nuclear Information System (INIS)

    Prior, R.

    1999-01-01

    Many plants are in the process of developing on-site guidance for technical staff to respond to a severe accident situation severe accident management guidance (SAMG). Once the guidance is developed, the SAMG must be implemented at the plant site, and this involves addressing a number of additional aspects. In this paper, approaches to this implementation phase are reviewed, including review and verification of plant specific SAMG, organizational aspects and integration with the emergency plan, training of SAMG users, validation and self-assessment and SAMG maintenance. Examples draw on experience from assisting numerous plants to implement symptom based severe accident management guidelines based on the Westinghouse Owners Group approach, in Westinghouse, non-Westinghouse and VVER plant types. It is hoped that it will be of use to those plant operators about to perform these activities.(author)

  1. Flooding PSA with Plant Specific Operating Experiences of Korean PWRs

    International Nuclear Information System (INIS)

    Choi, Sun Yeong; Yang, Joon Yull

    2006-01-01

    The purpose of this paper is to update the flooding PSA with Korean plant specific operating experience data and the appropriate estimation method for the flooding frequency to improve the PSA quality. The existing flooding PSA used the NPE (Nuclear Power Experience) database up to 1985 for the flooding frequency. They are all USA plant operating experiences. So an upgraded flooding frequency with Korean specific plant operation experience is required. We also propose a method of only using the PWR (Pressurized Water Reactor) data for the flooding frequency estimation in the case of the flooding area in the primary building even though the existing flooding PSA used both PWR and BWR (Boiled Water Reactor) data for all kinds of plant areas. We evaluate the CDF (Core Damage Frequency) with the modified flooding frequency and compare the results with that of the existing flooding PSA method

  2. ANALISIS INFLASI PRA DAN PASCA KRISIS MONETER DALAM PEREKONOMIAN INDONESIA

    Directory of Open Access Journals (Sweden)

    Deni Sri Haryati

    2014-10-01

    Full Text Available Abstrak ___________________________________________________________________ Penelitian ini menganalisis fluktuasi inflasi yang terjadi pada masa pra, saat, dan pasca krisis moneter. Terdapat 5 variabel yang berkorelasi dengan inflasi di Indonesia. Variabel-variabel tersebut adalah jumlah uang beredar (JUB, nilai tukar nominal (NTN, pertumbuhan ekonomi, pengeluaran pemerintah (PeP,dan  bahan bakar minyak (BBM. Sebenarnya variabel tersebut memiliki hubungan dengan inflasi pada seluruh era. Namun, variabel tesebut memiliki dominasi yang berbeda pada masing-masing eranya. Era prakrisis didominasi oleh 3 variabel, yakni; pertumbuhan ekonomi, NTN, dan JUB, era krisis didominasi oleh seluruh variabel yang ada, dan era pasca krisis didominasi oleh 3 variabel, yakni; PeP, NTN, dan JUB. Variabel-variabel ini akan dijelaskan pengaruhnya terhadap inflasi pada era yang didominasi dimana apakah memiliki hubungan sebanding atau berbanding terbalik. Abstract ___________________________________________________________________ This study analyzes the fluctuations in inflation that occurred in the pre, during and post the financial crisis. There are 5 variables that correlated with inflation in Indonesia. These variables are the money supply (MS, the nominal exchange rate (NER, economic growth, government expenditure (GE, and fuel oil (BBM. Actually, these variables have a relationship with inflation on the whole era. However, the variable has a predominance of different proficiency level in each era. Pre-crisis era dominated by three variables, namely; economic growth, NER, and MS, crisis era dominated by all the variables that exist, and the post-crisis era dominated by three variables, namely; GE, NER, and MS. These variables will be explained influence on inflation in an era dominated where or whether proportional or inversely proportional relationship. © 2014 Universitas Negeri Semarang

  3. PRA: an evaluation of state-of-the-art

    International Nuclear Information System (INIS)

    Joksimovich, V.

    1985-01-01

    Some elements of the probabilistic risk assessment (PRA) methodology can be characterized as mature and are even ready for some kind of a standardization effort. Other elements are still, however, in a rapid state of evolution. Questions are continuously being asked regarding maturity of PRA techniques vis-a-vis a regulatory decision-making process. Establishing a framework for evaluating state-of-the-art in any technological field is a challenging task. An implementation of a selected framework to a satisfactory conclusion is a monumental task. Of course, these types of issues can be discussed meaningfully only if they are tied to a particular application. The author's participation in the NSF-sponsored risk assessment project is discussed in the paper. The evaluation employed here makes use of the following five evaluation criteria: logical soundness, completeness, accuracy, acceptability, and practicality

  4. Use of plant specific information in life management

    International Nuclear Information System (INIS)

    Simola, K.; Talja, H.

    2002-01-01

    In plant life management decisions are made on prevention and mitigation measures of ageing phenomena. In these processes, information from several sources has to be combined, and the decisions are based on data and analyses including lots of uncertainties. In order to make good decisions, the uncertainties and limitations related to both analyses and the raw data should be recognised. A schematic presentation of the information used in the decision making with an emphasis on data needs and analyses for the technical life assessment of a component is given. On the way from the raw data to the final decision on ageing management there are several steps where engineering judgement is used or more sophisticated analyses are made. In this paper we present a view upon the decision making process in managing the ageing of components, systems and structures. Further, we propose practices to improve the transparency of ageing analyses and means to improve the availability and usability of plant specific information for ageing management purposes. The availability of plant specific information and easy access to these records are vital for the efficient ageing management. Often, the data collection and record keeping has not been organised in an efficient way and the use of experience data is very laborious. As illustrated, a lot of plant specific information is needed in ageing assessment. It is also very important to ensure that the information is up-to-date, e.g. possible modifications are taken into account in lifetime predictions. As an example of improvement in the data collection practices we shortly summarise the pipeline analysis and monitoring system that VTT is developing together with TVO. The system is meant to contain all up-to-date information necessary to analyse and monitor piping systems of an operating plant. The core of the system contains five databases. Piping database contains information like geometry, material, loading, detected cracks etc. All

  5. Organizational extension of PRA models and NASA application

    International Nuclear Information System (INIS)

    Pate-Cornell, E.

    1989-01-01

    This paper describes a probabilistic method which extends classical PRA to include some characteristics of the organization that processes or manages an engineering system. Ataxonomy of errors is presented and their organizational roots are examined. An assembly model is proposed for the analysis of the resulting spectrum of capacities of the system. The management of the Thermal Protection system of the Space Shuttle is used as an illustration. The model allows assessment of the benefits of organizational improvements of the orbiter's processing

  6. Task analysis: How far are we from usable PRA input

    International Nuclear Information System (INIS)

    Gertman, D.I.; Blackman, H.S.; Hinton, M.F.

    1984-01-01

    This chapter reviews data collected at the Idaho National Engineering Laboratory for three DOE-owned reactors (the Advanced Test Reactor, the Power Burst Facility, and the Loss of Fluids Test Reactor) in order to identify usable Probabilistic Risk Assessment (PRA) input. Task analytic procedures involve the determination of manning and skill levels as a means of determining communication requirements, in assessing job performance aids, and in assessing the accuracy and completeness of emergency and maintenance procedures. The least understood aspect in PRA and plant reliability models is the human factor. A number of examples from the data base are discussed and offered as a means of providing more meaningful data than has been available to PRA analysts in the past. It is concluded that the plant hardware-procedures-personnel interfaces are essential to safe and efficient plant operations and that task analysis is a reasonably sound way of achieving a qualitative method for identifying those tasks most strongly associated with task difficulty, severity of consequence, and error probability

  7. Preparation of plant-specific NDA reference material

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  8. EPRI/NRC-RES fire PRA guide for nuclear power facilities. Volume 1, summary and overview

    International Nuclear Information System (INIS)

    2004-01-01

    This report documents state-of-the-art methods, tools, and data for the conduct of a fire Probabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application. The methods have been developed under the Fire Risk Re-quantification Study. This study was conducted as a joint activity between EPRI and the U. S. NRC Office of Nuclear Regulatory Research (RES) under the terms of an EPRI/RES Memorandum of Understanding (RS.1) and an accompanying Fire Research Addendum (RS.2). Industry participants supported demonstration analyses and provided peer review of this methodology. The documented methods are intended to support future applications of Fire PRA, including risk-informed regulatory applications. The documented method reflects state-of-the-art fire risk analysis approaches. The primary objective of the Fire Risk Study was to consolidate recent research and development activities into a single state-of-the-art fire PRA analysis methodology. Methodological issues raised in past fire risk analyses, including the Individual Plant Examination of External Events (IPEEE) fire analyses, have been addressed to the extent allowed by the current state-of-the-art and the overall project scope. Methodological debates were resolved through a consensus process between experts representing both EPRI and RES. The consensus process included a provision whereby each major party (EPRI and RES) could maintain differing technical positions if consensus could not be reached. No cases were encountered where this provision was invoked. While the primary objective of the project was to consolidate existing state-of-the-art methods, in many areas, the newly documented methods represent a significant advancement over previously documented methods. In several areas, this project has, in fact, developed new methods and approaches. Such advances typically relate to areas of past methodological debate.

  9. RAVEN: a GUI and an Artificial Intelligence Engine in a Dynamic PRA Framework

    Energy Technology Data Exchange (ETDEWEB)

    C. Rabiti; D. Mandelli; A. Alfonsi; J. Cogliati; R. Kinoshita; D. Gaston; R. Martineau; C. Curtis

    2013-06-01

    Increases in computational power and pressure for more accurate simulations and estimations of accident scenario consequences are driving the need for Dynamic Probabilistic Risk Assessment (PRA) [1] of very complex models. While more sophisticated algorithms and computational power address the back end of this challenge, the front end is still handled by engineers that need to extract meaningful information from the large amount of data and build these complex models. Compounding this problem is the difficulty in knowledge transfer and retention, and the increasing speed of software development. The above-described issues would have negatively impacted deployment of the new high fidelity plant simulator RELAP-7 (Reactor Excursion and Leak Analysis Program) at Idaho National Laboratory. Therefore, RAVEN that was initially focused to be the plant controller for RELAP-7 will help mitigate future RELAP-7 software engineering risks. In order to accomplish this task, Reactor Analysis and Virtual Control Environment (RAVEN) has been designed to provide an easy to use Graphical User Interface (GUI) for building plant models and to leverage artificial intelligence algorithms in order to reduce computational time, improve results, and help the user to identify the behavioral pattern of the Nuclear Power Plants (NPPs). In this paper we will present the GUI implementation and its current capability status. We will also introduce the support vector machine algorithms and show our evaluation of their potentiality in increasing the accuracy and reducing the computational costs of PRA analysis. In this evaluation we will refer to preliminary studies performed under the Risk Informed Safety Margins Characterization (RISMC) project of the Light Water Reactors Sustainability (LWRS) campaign [3]. RISMC simulation needs and algorithm testing are currently used as a guidance to prioritize RAVEN developments relevant to PRA.

  10. Something important is missing from PRA

    International Nuclear Information System (INIS)

    Ward, D.A.

    1991-01-01

    This paper provides some views on priorities and directions for the future or risk management. There are some problems with the priorities and directions that now seem dominant. Norm Rasmussen of MIT and the late Saul Levine, who was then with the U.S. Atomic Energy Commission (AEC) (the NRC's predecessor), and their colleagues deserve much credit for the invention of the art of Probabilistic Risk Assessment. Certainly the elements of risk analysis were well known and used, at least implicitly, in much of engineering and technology. But, WASH-1400, The Reactor Safety Study issued in 1975, put these elements together in a comprehensive and courageously rational way

  11. Interactions among predators and plant specificity protect herbivores from top predators.

    Science.gov (United States)

    Bosc, Christopher; Pauw, Anton; Roets, Francois; Hui, Cang

    2018-05-04

    The worldwide loss of top predators from natural and agricultural systems has heightened the need to understand how important they are in controlling herbivore abundance. The effect of top predators on herbivore species is likely to depend on 1) the importance of the consumption of intermediate predators by top predators (intra-guild predation; IGP), but also on 2) plant specificity by herbivores, because specialists may defend themselves better (enemy-free space; EFS). Insectivorous birds, as top predators, are generally known to effectively control herbivorous insects, despite also consuming intermediate predators such as spiders, but how this effect varies among herbivore species in relation to the cascading effects of IGP and EFS is not known. To explore this, we excluded birds from natural fynbos vegetation in South Africa using large netted cages and recorded changes in abundance relative to control plots for 199 plant-dwelling intermediate predator and 341 herbivore morpho-species that varied in their estimated plant specificity. We found a strong negative effect of birds on the total abundance of all intermediate predators, with especially clear effects on spiders (strong IGP). In contrast with previous studies, which document a negative effect of birds on herbivores, we found an overall neutral effect of birds on herbivore abundance, but the effect varied among species: some species were negatively affected by birds, suggesting that they were mainly consumed by birds, whereas others, likely released from spiders by IGP, were positively affected. Some species were also effectively neutrally affected by birds. These tended to be more specialized to plants compared to the other species, which may imply that some plant specialists benefited from protection provided by EFS from both birds and spiders. These results suggest that the response of herbivore species to top predators may depend on cascading effects of interactions among predators and on their degree

  12. An evaluation of the reliability and usefulness of external-initiator PRA [probabilistic risk analysis] methodologies

    International Nuclear Information System (INIS)

    Budnitz, R.J.; Lambert, H.E.

    1990-01-01

    The discipline of probabilistic risk analysis (PRA) has become so mature in recent years that it is now being used routinely to assist decision-making throughout the nuclear industry. This includes decision-making that affects design, construction, operation, maintenance, and regulation. Unfortunately, not all sub-areas within the larger discipline of PRA are equally ''mature,'' and therefore the many different types of engineering insights from PRA are not all equally reliable. 93 refs., 4 figs., 1 tab

  13. An evaluation of the reliability and usefulness of external-initiator PRA (probabilistic risk analysis) methodologies

    Energy Technology Data Exchange (ETDEWEB)

    Budnitz, R.J.; Lambert, H.E. (Future Resources Associates, Inc., Berkeley, CA (USA))

    1990-01-01

    The discipline of probabilistic risk analysis (PRA) has become so mature in recent years that it is now being used routinely to assist decision-making throughout the nuclear industry. This includes decision-making that affects design, construction, operation, maintenance, and regulation. Unfortunately, not all sub-areas within the larger discipline of PRA are equally mature,'' and therefore the many different types of engineering insights from PRA are not all equally reliable. 93 refs., 4 figs., 1 tab.

  14. Pemikiran Suksesi Dalam Politik Islam Masa Pra Modern

    Directory of Open Access Journals (Sweden)

    Mazro'atus Sa'adah

    2016-12-01

    Abstrak: Pemikiran politik Islam muncul setelah Islam melalui Nabi Muhammad SAW berhasil membentuk sebuah ummat baru, dari peralihan kekuasaan kerajaan/kesukuan kepada Nabi yang kemudian kepada umat. Nabi Muhammad dinilai berhasil dalam mengatur komunitas barunya yang dikendalikan oleh ajarannya dalam seluruh lini kehidupan. Persoalan muncul kemudian setelah beliau wafat, yang akhirnya memunculkan pemikiran tentang suksesi. Artikel ini akan membahas tentang mengapa terjadi suksesi setelah Nabi Muhammad SAW wafat, bagaimana pemikiran para tokoh politik Islam masa pra modern terkait dengan suksesi, dan apa kontribusi pemikiran suksesi ini terhadap politik Islam di Indonesia. Dengan menggunakan pendekatan sejarah, ditemukan bahwa Nabi Muhammad tidak menetapkan siapa yang akan menggantikannya, dan ketika beliau wafat (632 M, para sahabat memilih seorang pemimpin (imam/khalifah. Masa pemerintahan Abu Bakar, Umar dan Usman banyak terjadi perselisihan yang awalnya terkait kepentingan agama namun berkembang menjadi kepentingan politik. Ketika Ali bin Abi Talib diangkat sebagai khalifah, konflik politik berkepanjangan berkaitan dengan pembunuhan Usman, menjadikan timbulnya perang jamal antara Aisyah dan Ali. Pada masa ini perbedaan kepentingan aqidah dipolitisir lebih jauh menjadi sebuah kepentingan politik. Dinamika politik ini kemudian melahirkan mazhab politik Islam klasik yang terbagi dalam tiga mazhab besar yaitu Sunni, Syi'ah dan Khawarij, yang darinya muncul istilah-istilah khilafah, imamah, ahlul halli wal aqdi, bay’ah, walayah dan lain-lain. Dari ketiga mazhab politik ini, kemudian muncul ide pemikiran politik Islam yang sangat kompleks dan berkepanjangan dari para tokoh politik Islam pra modern yang banyak dipengaruhi oleh filosof Yunani. Di Indonesia, pemikiran suksesi dalam politik Islam masa pra modern ini pernah diwacanakan. Namun untuk pemilihan kepala Negara belum terealisasi mengingat Indonesia bukan Negara Islam.

  15. Results and insights of a level-1 internal event PRA of a PWR during mid-loop operations

    International Nuclear Information System (INIS)

    Chu, T.L.; Musicki, Z.; Kohut, P.

    1993-01-01

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analysis that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. The objective of this paper is to present the approach utilized in the level-1 PRA for the Surry plant, and discuss the results obtained. A comparison of the results with those of other shutdown studies is provided. Relevant safety issues such as plant and hardware configurations, operator training, and instrumentation and control is discussed

  16. Human factors assessment in PRA using task analysis linked evaluation technique (TALENT)

    International Nuclear Information System (INIS)

    Wells, J.E.; Banks, W.W.

    1990-01-01

    Human error is a primary contributor to risk in complex high-reliability systems. A 1985 U.S. Nuclear Regulatory Commission (USNRC) study of licensee event reports (LERs) suggests that upwards of 65% of commercial nuclear system failures involve human error. Since then, the USNRC has initiated research to fully and properly integrate human errors into the probabilistic risk assessment (PRA) process. The resulting implementation procedure is known as the Task Analysis Linked Evaluation Technique (TALENT). As indicated, TALENT is a broad-based method for integrating human factors expertise into the PRA process. This process achieves results which: (1) provide more realistic estimates of the impact of human performance on nuclear power safety, (2) can be fully audited, (3) provide a firm technical base for equipment-centered and personnel-centered retrofit/redesign of plants enabling them to meet internally and externally imposed safety standards, and (4) yield human and hardware data capable of supporting inquiries into human performance issues that transcend the individual plant. The TALENT procedure is being field-tested to verify its effectiveness and utility. The objectives of the field-test are to examine (1) the operability of the process, (2) its acceptability to the users, and (3) its usefulness for achieving measurable improvements in the credibility of the analysis. The field-test will provide the information needed to enhance the TALENT process

  17. Human reliability analysis in support of a level 1 PRA for Surry during midloop operations

    International Nuclear Information System (INIS)

    Lin, J.C.; Bley, D.C.; Chu, T.-L.

    2004-01-01

    The objectives of this Level 1 probabilistic risk assessment (PRA) are to evaluate the important accident sequences initiated during midloop operations and to compare the qualitative and quantitative results with those for accidents initiated during power operations. The primary types of human actions analyzed in this study involve the dynamic operator actions and recovery actions that take place during the accident sequence following an initiating event. Two parts of the human actions were analyzed: failure to diagnose and failure to perform the action. The scope of the Level 1 PRA for Surry during midloop operations includes internal, fire, and flood initiating events. The major categories of dynamic operator actions taken during the accident sequence following an initiating event are: providing makeup to the reactor coolant system (RCS), restoring residual heat removal (RHR) cooling, establishing steam generator reflux cooling, establishing primary feed and spill, establishing gravity feed from refueling water storage tank (RWST), establishing high pressure recirculation, establishing recirculation spray, and cross-connecting RWSTs. All categories are not applicable to all initiating events and all plant operating states (POS). (author)

  18. Development of extreme rainfall PRA methodology for sodium-cooled fast reactor

    International Nuclear Information System (INIS)

    Nishino, Hiroyuki; Kurisaka, Kenichi; Yamano, Hidemasa

    2016-01-01

    The objective of this study is to develop a probabilistic risk assessment (PRA) methodology for extreme rainfall with focusing on decay heat removal system of a sodium-cooled fast reactor. For the extreme rainfall, annual excess probability depending on the hazard intensity was statistically estimated based on meteorological data. To identify core damage sequence, event trees were developed by assuming scenarios that structures, systems and components (SSCs) important to safety are flooded with rainwater coming into the buildings through gaps in the doors and the SSCs fail when the level of rainwater on the ground or on the roof of the building becomes higher than thresholds of doors on first floor or on the roof during the rainfall. To estimate the failure probability of the SSCs, the level of water rise was estimated by comparing the difference between precipitation and drainage capacity. By combining annual excess probability and the failure probability of SSCs, the event trees led to quantification of core damage frequency, and therefore the PRA methodology for rainfall was developed. (author)

  19. Spatially Informed Plant PRA Models for Security Assessment

    International Nuclear Information System (INIS)

    Wheeler, Timothy A.; Thomas, Willard; Thornsbury, Eric

    2006-01-01

    Traditional risk models can be adapted to evaluate plant response for situations where plant systems and structures are intentionally damaged, such as from sabotage or terrorism. This paper describes a process by which traditional risk models can be spatially informed to analyze the effects of compound and widespread harsh environments through the use of 'damage footprints'. A 'damage footprint' is a spatial map of regions of the plant (zones) where equipment could be physically destroyed or disabled as a direct consequence of an intentional act. The use of 'damage footprints' requires that the basic events from the traditional probabilistic risk assessment (PRA) be spatially transformed so that the failure of individual components can be linked to the destruction of or damage to specific spatial zones within the plant. Given the nature of intentional acts, extensive modifications must be made to the risk models to account for the special nature of the 'initiating events' associated with deliberate adversary actions. Intentional acts might produce harsh environments that in turn could subject components and structures to one or more insults, such as structural, fire, flood, and/or vibration and shock damage. Furthermore, the potential for widespread damage from some of these insults requires an approach that addresses the impacts of these potentially severe insults even when they occur in locations distant from the actual physical location of a component or structure modeled in the traditional PRA. (authors)

  20. Results and insights of a level-1 internal event PRA of a PWR during mid-loop operations

    International Nuclear Information System (INIS)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Wong, S.M.; Holmes, B.; Su, R.F.; Dang, V.; Siu, N.; Bley, D.; Johnson, D.; Lin, J.

    1994-01-01

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analysis that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by BNL and SNL. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. The objective of this paper is to present the approach utilized in the level-1 PRA for the Surry plant, and discuss the results obtained. A comparison of the results with those of other shutdown studies is provided. Relevant safety issues such as plant and hardware configurations, operator training, and instrumentation and control is discussed

  1. Development of margin assessment methodology of decay heat removal function against external hazards. (2) Tornado PRA methodology

    International Nuclear Information System (INIS)

    Nishino, Hiroyuki; Kurisaka, Kenichi; Yamano, Hidemasa

    2014-01-01

    Probabilistic Risk Assessment (PRA) for external events has been recognized as an important safety assessment method after the TEPCO's Fukushima Daiichi nuclear power station accident. The PRA should be performed not only for earthquake and tsunami which are especially key events in Japan, but also the PRA methodology should be developed for the other external hazards (e.g. tornado). In this study, the methodology was developed for Sodium-cooled Fast Reactors paying attention to that the ambient air is their final heat sink for removing decay heat under accident conditions. First, tornado hazard curve was estimated by using data recorded in Japan. Second, important structures and components for decay heat removal were identified and an event tree resulting in core damage was developed in terms of wind load and missiles (i.e. steel pipes, boards and cars) caused by a tornado. Main damage cause for important structures and components is the missiles and the tornado missiles that can reach those components and structures placed on high elevations were identified, and the failure probabilities of the components and structures against the tornado missiles were calculated as a product of two probabilities: i.e., a probability for the missiles to enter the intake or outtake in the decay heat removal system, and a probability of failure caused by the missile impacts. Finally, the event tree was quantified. As a result, the core damage frequency was enough lower than 10 -10 /ry. (author)

  2. Top event prevention analysis: A deterministic use of PRA

    International Nuclear Information System (INIS)

    Worrell, R.B.; Blanchard, D.P.

    1996-01-01

    This paper describes the application of Top Event Prevention Analysis. The analysis finds prevention sets which are combinations of basic events that can prevent the occurrence of a fault tree top event such as core damage. The problem analyzed in this application is that of choosing a subset of Motor-Operated Valves (MOVs) for testing under the Generic Letter 89-10 program such that the desired level of safety is achieved while providing economic relief from the burden of testing all safety-related valves. A brief summary of the method is given, and the process used to produce a core damage expression from Level 1 PRA models for a PWR is described. The analysis provides an alternative to the use of importance measures for finding the important combination of events in a core damage expression. This application of Top Event Prevention Analysis to the MOV problem was achieve with currently available software

  3. 40 CFR 180.1200 - Pseudomonas fluorescens strain PRA-25; temporary exemption from the requirement of a tolerance.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Pseudomonas fluorescens strain PRA-25... RESIDUES IN FOOD Exemptions From Tolerances § 180.1200 Pseudomonas fluorescens strain PRA-25; temporary... established for residues of the microbial pesticide, pseudomonas fluorescens strain PRA-25 when used on peas...

  4. SNF1-related protein kinases 2 are negatively regulated by a plant-specific calcium sensor.

    Science.gov (United States)

    Bucholc, Maria; Ciesielski, Arkadiusz; Goch, Grażyna; Anielska-Mazur, Anna; Kulik, Anna; Krzywińska, Ewa; Dobrowolska, Grażyna

    2011-02-04

    SNF1-related protein kinases 2 (SnRK2s) are plant-specific enzymes involved in environmental stress signaling and abscisic acid-regulated plant development. Here, we report that SnRK2s interact with and are regulated by a plant-specific calcium-binding protein. We screened a Nicotiana plumbaginifolia Matchmaker cDNA library for proteins interacting with Nicotiana tabacum osmotic stress-activated protein kinase (NtOSAK), a member of the SnRK2 family. A putative EF-hand calcium-binding protein was identified as a molecular partner of NtOSAK. To determine whether the identified protein interacts only with NtOSAK or with other SnRK2s as well, we studied the interaction of an Arabidopsis thaliana orthologue of the calcium-binding protein with selected Arabidopsis SnRK2s using a two-hybrid system. All kinases studied interacted with the protein. The interactions were confirmed by bimolecular fluorescence complementation assay, indicating that the binding occurs in planta, exclusively in the cytoplasm. Calcium binding properties of the protein were analyzed by fluorescence spectroscopy using Tb(3+) as a spectroscopic probe. The calcium binding constant, determined by the protein fluorescence titration, was 2.5 ± 0.9 × 10(5) M(-1). The CD spectrum indicated that the secondary structure of the protein changes significantly in the presence of calcium, suggesting its possible function as a calcium sensor in plant cells. In vitro studies revealed that the activity of SnRK2 kinases analyzed is inhibited in a calcium-dependent manner by the identified calcium sensor, which we named SCS (SnRK2-interacting calcium sensor). Our results suggest that SCS is involved in response to abscisic acid during seed germination most probably by negative regulation of SnRK2s activity.

  5. Clinical significance of determination of SAC/PRA value in patients with primary aldosteronism

    International Nuclear Information System (INIS)

    Li Liren; Dai Yaozong; Liu Jiumin

    2003-01-01

    Objective: To investigate the diagnostic significance of determining SAC/PRA valve in hyperaldosteronism. Methods: Plasma renin activity (PRA) and angiotensin (AT-II) as well as serum aldosterone contents were measured with RIA in 48 patients with primary aldosteronism and 30 controls. The SAC/PRA value was calculated. Results: Contents of PRA, AT-II and Aldo in blood of patients with primary aldosteronism were very significantly different from those in controls (p < 0.001) (PRA 0.14 ± 0.08 ng/ml/h vs 0.57 ± 0.08 ng/ml/h; AT-II 21.21 ± 7.55 ng/L vs 36.03 ± 6.11 ng/L; Aldo 1.07 ± 0.34 nmol/L vs 0.33 ± 0.04 nmol/L). Calculated SAC/PRA value was 913 ± 409 (normal upper limit 400). Conclusion: SAC/PRA value is an useful accessory diagnostic criterion for primary aldosteronism

  6. Elastin and Mechanics of Pig Pericardial Resistance Arteries (pPRA)

    DEFF Research Database (Denmark)

    Bloksgaard, Maria; Leurgans, Thomas; Rosenstand, Kristoffer

    Resistance arteries are remodeled in hypertension and diabetes. Elastin was reported to play a role herein. The parietal pericardium is opened during cardio-thoracic surgeries and might be a valuable biopsy for research in cardio-vascular diseases. We tested the hypothesis that resistance arteries...... can be isolated from the pericardium to study the micro-architecture of elastin and vascular wall mechanics. The pericardium of pigs served to test the hypothesis. pPRAs were microdissected. Their structure was examined using multiphoton excitation fluorescence microscopy. Diameter......-tension and pressure-diameter-length relationships were recorded in myographs. Findings are compared to rodent mesenteric resistance arteries and –basilar arteries (rMRA, rBA) with comparable lumen diameter (±300µm at 100mmHg). pPRA have no clear external elastic lamina (present in rMRA, but not rBA), scant elastin...

  7. Role of seismic PRA in seismic safety decisions of nuclear power plants

    International Nuclear Information System (INIS)

    Ravindra, M.K.; Kennedy, R.P.; Sues, R.H.

    1985-01-01

    This paper highlights the important roles that seismic probabilistic risk assessments (PRAs) can play in the seismic safety decisions of nuclear power plants. If a seismic PRA has been performed for a plant, its results can be utilized to evaluate the seismic capability beyond the safe shutdown event (SSE). Seismic fragilities of key structures and equipment, fragilities of dominant plant damage states and the frequencies of occurrence of these plant damage states are reviewed to establish the seismic safety of the plant beyond the SSE level. Guidelines for seismic margin reviews and upgrading may be developed by first identifying the generic classes of structures and equipment that have been shown to be dominant risk contributors in the completed seismic PRAs, studying the underlying causes for their contribution and examining why certain other items (e.g., piping) have not proved to be high-risk-contributors

  8. Hydrogeochemical processes influencing groundwater quality within the Lower Pra Basin

    International Nuclear Information System (INIS)

    Tay, Collins

    2015-12-01

    Hydrogeochemical and social impact studies were carried out within the Lower Pra Basin where groundwater serves as a source of potable water supply to majority of the communities. The main objective of the study was to investigate the hydrogeochemical processes and the anthropogenic impact that influence groundwater as well as the perception of inhabitants about the impact of their socio-economic activities on the quality of groundwater and subsequently make recommendations towards proper management and development of groundwater resources within the basin. The methodology involved quarterly sampling of selected surface and groundwater sources between January 2011 and October 2012 for major ions, minor ions, stable isotopes of deuterium ( 2 H) and oxygen-18 ( 18 O) and trace metals analyses as well as administration of questionnaires designed to collect information on the socio-economic impact on the water resources within the basin. In all, a chemical data-base on three hundred and ninety seven (397) point sources was generated and three hundred (300) questionnaires were administered. The hydrochemical results show that, the major processes responsible for chemical evolution of groundwater include: silicate (SiO 4 ) 4- weathering, ion-exchange reactions, sea aerosol spray, the leaching of biotite, chlorite and actinolite. The groundwater is mildly acidic to neutral (pH 3.5 – 7.3) due principally to natural biogeochemical processes. Groundwater acidity studies show that, notwithstanding the moderately low pH, the groundwater still has the potential to neutralize acids due largely to the presence of silicates/aluminosilicates. Results of the Total Dissolved Solids (TDS) show that 98.6 % of groundwater is fresh (TDS < 500 mg/L). The relative abundance of cations and anions is in the order: Na + > Ca 2 + > Mg 2 + > K + and HCO 3 - > Cl - > SO 4 2- respectively. Stable isotopes results show that, the groundwater emanated primarily from meteoric origin with

  9. Application of RIA of PRA, AT II and NPY in typing and therapy of EH patients

    International Nuclear Information System (INIS)

    Yang Yongqing; Wang Xiaozhou; Jiang Qinian

    2001-01-01

    Objective: To study the typing and AT II receptor inhibitor therapy for essential hypertension (EH) patients. Methods: Plasma RA, AT II and NPY levels were measured by radioimmunoassay (RIA) in 208 Patients with EH and 100 controls; plasma NPY levels were measured in 40 EH patients before and after AT II receptor inhibitor therapy. The mean coefficient of variation for intra and inter batch-assay were less than 10% and 15% respectively. Results: In 208 EH patients plasma PRA levels were increased, normal and decreased in 17.8%, 71.6% and 10.6% respectively, while in 128 EH patients Plasma AT II levels were increased, normal and decreased in 20.3%, 64.1% and 15.6% respectively. In 69 EH Plasma NPY levels were significantly higher than those in 40 control subjects. (17 grade I EH, 137.3 +- 32.6 pg/mL; 28 grade II EH, 148.5 +- 41.1 pg/mL; 24 grade III EH, 162.4 +- 42.7 pg/mL; 40 controls, 118.5 +- 30.5 pg/mL). In 40 EH patients plasma NPY levels were decreased after AT II receptor inhibitor therapy as the blood pressure decreased. Conclusion: Typing of EH patients according to levels of plasma PRA and AT II is useful in guiding treatment. AT II receptor inhibitors are indicated in those patients with increased plasma levels and NPY levels can be used for appraisal of the treatment efficacy

  10. Pengaruh Citra Merek (Brand Image) dan Harga terhadap Keputusan Pembelian Konsumen (Survei pada Mahasiswa Program Studi Administrasi Bisnis Fakultas Ilmu Administrasi Universitas Brawijaya Malang Tahun Angkatan 2013/2014 dan 2014/2015 Pengguna Kartu Pra-b

    OpenAIRE

    Venessa, Ike; Arifin, Zainul

    2017-01-01

    This study is aim to understand and explain : Significance of the influence of corporate image variable, consumers image variable, product image variable, price variable on consumer purchase decision all together; Significance of the influence of corporate image variable on consumer purchase decision; Significance of the influence of consumers image variable on consumer purchase decision; Significance of the influence of product image variable on consumer purchase decision; Significanc...

  11. Issues and insights of PRA methodology in nuclear and space applications

    International Nuclear Information System (INIS)

    Hsu, F.

    2005-01-01

    This paper presents some important issues and technical insights on the scope, conceptual framework, and essential elements of nuclear power plant Probabilistic Risk Assessments (PRAs) and that of the PRAs in general applications of the aerospace industry, such as the Space Shuttle PRA being conducted by NASA. Discussions are focused on various lessons learned in nuclear power plant PRA applications and their potential applicability to the PRAs in the aerospace and launch vehicle systems. Based on insights gained from PRA projects for nuclear power plants and from the current Space Shuttle PRA effort, the paper explores the commonalities and the differences between the conduct of the different PRAs and the key issues and risk insights derived from extensive modeling practices in both industries of nuclear and space. (author)

  12. How Can You Support RIDM/CRM/RM Through the Use of PRA

    Science.gov (United States)

    DoVemto. Tpmu

    2011-01-01

    Probabilistic Risk Assessment (PRA) is one of key Risk Informed Decision Making (RIDM) tools. It is a scenario-based methodology aimed at identifying and assessing Safety and Technical Performance risks in complex technological systems.

  13. Current and future applications of PRA in regulatory activities

    Energy Technology Data Exchange (ETDEWEB)

    Speis, T.P.; Murphy, J.A.; Cunningham, M.A. [Nuclear Regulatory Commission, Washington, DC (United States)] [and others

    1995-04-01

    Probabilistic Risk Assessments (PRAs) have proven valuable in providing the regulators, the nuclear plant operators, and the reactor designers insights into plant safety, reliability, design and operation. Both the NRC Commissioners and the staff have grown to appreciate the valuable contributions PRAs can have in the regulatory arena, though I will admit the existence of some tendencies for strict adherence to the deterministic approach within the agency and the public at large. Any call for change, particularly one involving a major adjustment in approach to the regulation of nuclear power, will meet with a certain degree of resistance and retrenchment. Change can appear threatening and can cause some to question whether the safety mission is being fulfilled. This skepticism is completely appropriate and is, in fact, essential to a proper transition towards risk and performance-based approaches. Our task in the Office of Nuclear Regulatory Research is to increase the PRA knowledge base within the agency and develop appropriate guidance and methods needed to support the transitioning process.

  14. Reliability design of a critical facility: An application of PRA methods

    International Nuclear Information System (INIS)

    Souza Vieira Neto, A.; Souza Borges, W. de

    1987-01-01

    Although a general agreement concerning the enforcement of reliability (probabilistic) design criteria for nuclear utilities is yet to be achieved. PRA methodology can still be used successfully as a project design and review tool, aimed at improving system's prospective performance or minimizing expected accident consequences. In this paper, the potential of such an application of PRA methods is examined in the special case of a critical design project currently being developed in Brazil. (orig.)

  15. ASSESSMENT OF DYNAMIC PRA TECHNIQUES WITH INDUSTRY AVERAGE COMPONENT PERFORMANCE DATA

    Energy Technology Data Exchange (ETDEWEB)

    Yadav, Vaibhav; Agarwal, Vivek; Gribok, Andrei V.; Smith, Curtis L.

    2017-06-01

    In the nuclear industry, risk monitors are intended to provide a point-in-time estimate of the system risk given the current plant configuration. Current risk monitors are limited in that they do not properly take into account the deteriorating states of plant equipment, which are unit-specific. Current approaches to computing risk monitors use probabilistic risk assessment (PRA) techniques, but the assessment is typically a snapshot in time. Living PRA models attempt to address limitations of traditional PRA models in a limited sense by including temporary changes in plant and system configurations. However, information on plant component health are not considered. This often leaves risk monitors using living PRA models incapable of conducting evaluations with dynamic degradation scenarios evolving over time. There is a need to develop enabling approaches to solidify risk monitors to provide time and condition-dependent risk by integrating traditional PRA models with condition monitoring and prognostic techniques. This paper presents estimation of system risk evolution over time by integrating plant risk monitoring data with dynamic PRA methods incorporating aging and degradation. Several online, non-destructive approaches have been developed for diagnosing plant component conditions in nuclear industry, i.e., condition indication index, using vibration analysis, current signatures, and operational history [1]. In this work the component performance measures at U.S. commercial nuclear power plants (NPP) [2] are incorporated within the various dynamic PRA methodologies [3] to provide better estimates of probability of failures. Aging and degradation is modeled within the Level-1 PRA framework and is applied to several failure modes of pumps and can be extended to a range of components, viz. valves, generators, batteries, and pipes.

  16. Dynamic Positioning System (DPS) Risk Analysis Using Probabilistic Risk Assessment (PRA)

    Science.gov (United States)

    Thigpen, Eric B.; Boyer, Roger L.; Stewart, Michael A.; Fougere, Pete

    2017-01-01

    The National Aeronautics and Space Administration (NASA) Safety & Mission Assurance (S&MA) directorate at the Johnson Space Center (JSC) has applied its knowledge and experience with Probabilistic Risk Assessment (PRA) to projects in industries ranging from spacecraft to nuclear power plants. PRA is a comprehensive and structured process for analyzing risk in complex engineered systems and/or processes. The PRA process enables the user to identify potential risk contributors such as, hardware and software failure, human error, and external events. Recent developments in the oil and gas industry have presented opportunities for NASA to lend their PRA expertise to both ongoing and developmental projects within the industry. This paper provides an overview of the PRA process and demonstrates how this process was applied in estimating the probability that a Mobile Offshore Drilling Unit (MODU) operating in the Gulf of Mexico and equipped with a generically configured Dynamic Positioning System (DPS) loses location and needs to initiate an emergency disconnect. The PRA described in this paper is intended to be generic such that the vessel meets the general requirements of an International Maritime Organization (IMO) Maritime Safety Committee (MSC)/Circ. 645 Class 3 dynamically positioned vessel. The results of this analysis are not intended to be applied to any specific drilling vessel, although provisions were made to allow the analysis to be configured to a specific vessel if required.

  17. Devonian conodonts from the Foča–Prača Paleozoic complex (Durmitor Nappe, southeastern Bosnia and Herzegovina

    Directory of Open Access Journals (Sweden)

    Bogdan Jurkovšek

    2011-06-01

    Full Text Available Conodont study of the Crna Rijeka borehole CR-17, positioned in the frontal part of the Durmitor Nappe (Foča – Prača Paleozoic complex, SE Bosnia and Herzegovina is presented. The obtained fauna indicates an Early-Middle Devonian age and due to poor preservation an identification at a generic level is possible only. The recovered conodont elements have a high Color Alteration Index (CAI = 6,5–7 indicating a degree of metamorphism corresponding to a temperature interval from 440 °C to 720 °C.

  18. PRA-1 offshore platform start-up within seven days; Operacionalizacao da plataforma offshore PRA-1 em sete dias

    Energy Technology Data Exchange (ETDEWEB)

    Barbosa, Fernando; Mitidieri, Jorge; Faria, Jose Luis Coutinho de; Ribeiro, Juan Carlos; Moura, Mario Arthur [Construtora Norberto Oderbrecht S.A., Rio de Janeiro, RJ (Brazil)

    2008-07-01

    The technologic innovations are very hard features with regards to Offshore Engineering and Construction over the worldwide. The innovations only make sense since they are focus on the high productivity, safe job and cost reduction compared with the current technologies. Inside the scenario mentioned above is Construtora Norberto Odebrecht S.A. concept for the PRA-1 platform Engineering and Construction. Through a very advanced and innovation concept, it was defined as the Main Strategic Planning of the undertaking not use a temporary platform support (named in Brazil as 'Flotel') during the 'Hook-up', commissioning and star-up offshore phase. The success of the strategic made possible through the implementation of new engineering tools, and, besides this, through a very careful offshore planning focused on minimizing and make easier as much as possible the offshore activities. The planning can be basically spitted on the following parts: A- Onshore preparations (Assembly, Integration and Commissioning of the Utilities and Accommodation Modules) B- Offshore detailed planning of the critical activities concerning the start-up of the systems responsible for leaving the platform ready for 'live'. This operation was defined as 'seven days of platform live support' (main target of this paper). (author)

  19. Treatment of complementary events in event trees in constructing linked fault trees for level 1 and level 2 PRA

    International Nuclear Information System (INIS)

    Jo, Y. G.

    2008-01-01

    Complementary events in the event trees for a PRA model should be treated properly in order to evaluate plant risk correctly. In this study, the characteristics of the following three different cut-set generation methods were investigated first in order to find the best practical way for treating complementary events: 1) exact method which treats complementary events logically, 2) no-delete term method which does not treat complementary events at all, and 3) delete term method which treats complementary events by deleting nonsense cut-sets which are generated as a result of ignoring complementary events. Then, practical methods for treating complementary events in constructing linked fault trees for level 1 and level 2 PRA in EPRI R and R workstation software environment, where CAFTA is the fault tree editor and FORTE is the cut-set engine, were suggested and demonstrated. The suggested methods deal with the following selected four typical cases: Case 1: an event tree event (E) is represented by a fault tree gate whose inputs consist of only fault tree gates, Case 2: E is represented by a single basic event, Case 3: E is represented by an OR fault tree gate which has a single basic event and a fault tree gate as inputs, and Case 4: E is represented by an AND fault tree gate which has a single basic event and a fault tree gate as inputs. In the suggested methods, first the high level logic structures of event tree events are examined and restructured, if needed. Then, the delete term method, the exact method, and the combination of the two methods are applied to Case 1, Case 2, and Cases 3 and 4, respectively. Also, it is recommended to treat complementary events, using the suggested methods, before level 1 and level 2 PRA fault trees are coupled. It should be noted that the selected four typical cases may not cover all different cases encountered in level 1 and level 2 PRA modeling. However, a process similar to the one suggested in this study may be used to find

  20. Enhanced Fire Events Database to Support Fire PRA

    International Nuclear Information System (INIS)

    Baranowsky, Patrick; Canavan, Ken; St. Germain, Shawn

    2010-01-01

    This paper provides a description of the updated and enhanced Fire Events Data Base (FEDB) developed by the Electric Power Research Institute (EPRI) in cooperation with the U.S. Nuclear Regulatory Commission (NRC). The FEDB is the principal source of fire incident operational data for use in fire PRAs. It provides a comprehensive and consolidated source of fire incident information for nuclear power plants operating in the U.S. The database classification scheme identifies important attributes of fire incidents to characterize their nature, causal factors, and severity consistent with available data. The database provides sufficient detail to delineate important plant specific attributes of the incidents to the extent practical. A significant enhancement to the updated FEDB is the reorganization and refinement of the database structure and data fields and fire characterization details added to more rigorously capture the nature and magnitude of the fire and damage to the ignition source and nearby equipment and structures.

  1. DUF581 is plant specific FCS-like zinc finger involved in protein-protein interaction.

    Directory of Open Access Journals (Sweden)

    Muhammed Jamsheer K

    Full Text Available Zinc fingers are a ubiquitous class of protein domain with considerable variation in structure and function. Zf-FCS is a highly diverged group of C2-C2 zinc finger which is present in animals, prokaryotes and viruses, but not in plants. In this study we identified that a plant specific domain of unknown function, DUF581 is a zf-FCS type zinc finger. Based on HMM-HMM comparison and signature motif similarity we named this domain as FCS-Like Zinc finger (FLZ domain. A genome wide survey identified that FLZ domain containing genes are bryophytic in origin and this gene family is expanded in spermatophytes. Expression analysis of selected FLZ gene family members of A. thaliana identified an overlapping expression pattern suggesting a possible redundancy in their function. Unlike the zf-FCS domain, the FLZ domain found to be highly conserved in sequence and structure. Using a combination of bioinformatic and protein-protein interaction tools, we identified that FLZ domain is involved in protein-protein interaction.

  2. Practical Application of PRA as an Integrated Design Tool for Space Systems

    Science.gov (United States)

    Kalia, Prince; Shi, Ying; Pair, Robin; Quaney, Virginia; Uhlenbrock, John

    2013-01-01

    This paper presents the application of the first comprehensive Probabilistic Risk Assessment (PRA) during the design phase of a joint NASA/NOAA weather satellite program, Geostationary Operational Environmental Satellite Series R (GOES-R). GOES-R is the next generation weather satellite primarily to help understand the weather and help save human lives. PRA has been used at NASA for Human Space Flight for many years. PRA was initially adopted and implemented in the operational phase of manned space flight programs and more recently for the next generation human space systems. Since its first use at NASA, PRA has become recognized throughout the Agency as a method of assessing complex mission risks as part of an overall approach to assuring safety and mission success throughout project lifecycles. PRA is now included as a requirement during the design phase of both NASA next generation manned space vehicles as well as for high priority robotic missions. The influence of PRA on GOES-R design and operation concepts are discussed in detail. The GOES-R PRA is unique at NASA for its early implementation. It also represents a pioneering effort to integrate risks from both Spacecraft (SC) and Ground Segment (GS) to fully assess the probability of achieving mission objectives. PRA analysts were actively involved in system engineering and design engineering to ensure that a comprehensive set of technical risks were correctly identified and properly understood from a design and operations perspective. The analysis included an assessment of SC hardware and software, SC fault management system, GS hardware and software, common cause failures, human error, natural hazards, solar weather and infrastructure (such as network and telecommunications failures, fire). PRA findings directly resulted in design changes to reduce SC risk from micro-meteoroids. PRA results also led to design changes in several SC subsystems, e.g. propulsion, guidance, navigation and control (GNC

  3. Examination of Conservatism in Early/Latent Fatality Estimation in Level 3 PRA

    International Nuclear Information System (INIS)

    Kim, Sung-yeop; Lee, Haneol; Yim, Man-Sung

    2014-01-01

    Due to the computational model driven-nature of the work, there exist various sources of uncertainty in level 3 PRA. They are related with source release, environmental transport and deposition, human behavior involved in dosimetry, health effect and risk assessment. For instance, a total of 376 parameters have been considered in Probabilistic Accident Consequence Uncertainty Assessment Using COSYMA and the details on the number of parameters in each analysis are listed in Table 1. In 2012, the report of NPP accident consequence simulation was distributed by the Korean Federation for Environmental Movement (KFEM). They insisted that Kori Nuclear Power Plant (NPP) accident would lead to 48,000 early fatalities and 850,000 cancer fatalities in Busan and Hanbit NPP accident would lead to 550,000 cancer fatalities in Seoul. This report exemplifies the misuse of collective dose, that is effective dose multiplied by population and time. Even though very low effective dose is considered, collective dose could give over-conservative estimate when high population and long time period is multiplied. International Commission on Radiological Protection (ICRP) forewarned about the misuse of collective dose, in their ICRP Publication 103, such as applying it to simplified calculation of fatality and risk. As part of investigation of conservatism in early and latent fatality estimation, the existing methods of early and latent fatality calculation was reviewed and the results from the use of the existing methodology were examined in this study. The method of early and latent fatality estimation in level 3 PRA was investigated and the conservatism in the result was examined in this study. For the purpose of estimating both early and latent fatality, appropriate dose distributions among the affected population are found to be important. This study showed that large conservatism may be involved in the estimated fatality if the distribution of population dose as a function of

  4. Examination of Conservatism in Early/Latent Fatality Estimation in Level 3 PRA

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung-yeop; Lee, Haneol; Yim, Man-Sung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-10-15

    Due to the computational model driven-nature of the work, there exist various sources of uncertainty in level 3 PRA. They are related with source release, environmental transport and deposition, human behavior involved in dosimetry, health effect and risk assessment. For instance, a total of 376 parameters have been considered in Probabilistic Accident Consequence Uncertainty Assessment Using COSYMA and the details on the number of parameters in each analysis are listed in Table 1. In 2012, the report of NPP accident consequence simulation was distributed by the Korean Federation for Environmental Movement (KFEM). They insisted that Kori Nuclear Power Plant (NPP) accident would lead to 48,000 early fatalities and 850,000 cancer fatalities in Busan and Hanbit NPP accident would lead to 550,000 cancer fatalities in Seoul. This report exemplifies the misuse of collective dose, that is effective dose multiplied by population and time. Even though very low effective dose is considered, collective dose could give over-conservative estimate when high population and long time period is multiplied. International Commission on Radiological Protection (ICRP) forewarned about the misuse of collective dose, in their ICRP Publication 103, such as applying it to simplified calculation of fatality and risk. As part of investigation of conservatism in early and latent fatality estimation, the existing methods of early and latent fatality calculation was reviewed and the results from the use of the existing methodology were examined in this study. The method of early and latent fatality estimation in level 3 PRA was investigated and the conservatism in the result was examined in this study. For the purpose of estimating both early and latent fatality, appropriate dose distributions among the affected population are found to be important. This study showed that large conservatism may be involved in the estimated fatality if the distribution of population dose as a function of

  5. 40 CFR 60.1170 - What plant-specific training must I provide?

    Science.gov (United States)

    2010-07-01

    ...) December 6, 2001. (3) The date before an employee assumes responsibilities that affect operation of the... 40 Protection of Environment 6 2010-07-01 2010-07-01 false What plant-specific training must I provide? 60.1170 Section 60.1170 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR...

  6. 40 CFR 62.15110 - Who must complete the plant-specific training course?

    Science.gov (United States)

    2010-07-01

    ...-specific training course? All employees with responsibilities that affect how a municipal waste combustion... 40 Protection of Environment 8 2010-07-01 2010-07-01 false Who must complete the plant-specific training course? 62.15110 Section 62.15110 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

  7. 40 CFR 60.1655 - Who must complete the plant-specific training course?

    Science.gov (United States)

    2010-07-01

    ...-specific training course? All employees with responsibilities that affect how a municipal waste combustion... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Who must complete the plant-specific training course? 60.1655 Section 60.1655 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

  8. DNA binding by the plant-specific NAC transcription factors in crystal and solution

    DEFF Research Database (Denmark)

    Welner, Ditte Hededam; Lindemose, Søren; Grossmann, J. Günter

    2012-01-01

    angle X-ray scattering on complexes with oligonucleotides, mutagenesis and (DNase I and uranyl photo-) footprinting, is combined to form a structural view of DNA-binding, and for the first time provide experimental evidence for the speculated relationship between plant-specific NAC proteins, WRKY...

  9. Using level-I PRA for enhanced safety of the advanced neutron source reactor

    International Nuclear Information System (INIS)

    Ramsey, C.T.; Linn, M.A.

    1995-01-01

    The phase-1, level-I probabilistic risk assessment (PRA) of the Advanced Neutron Source (ANS) reactor has been completed as part of the conceptual design phase of this proposed research facility. Since project inception, PRA and reliability concepts have been an integral part of the design evolutions contributing to many of the safety features in the current design. The level-I PRA has been used to evaluate the internal events core damage frequency against project goals and to identify systems important to safety and availability, and it will continue to guide and provide support to accident analysis, both severe and nonsevere. The results also reflect the risk value of defense-in-depth safety features in reducing the likelihood of core damage

  10. System 80+TM PRA insights on severe accident prevention and mitigation

    International Nuclear Information System (INIS)

    Finnicum, D.J.; Jacob, M.C.; Schneider, R.E.; Weston, R.A.

    2004-01-01

    The System 80 + design is ABB-CE's standardized evolutionary Advanced Light Water Reactor (ALWR) design. It incorporates design enhancements based on Probabilistic Risk Assessment (PRA) insights, guidance from the ALWR Utility Requirements Document (URD), and US NRC's Severe Accident Policy. Major severe accident prevention and mitigation design features of the System 80 + design are described. The results of the System 80 + PRA are presented and the insights gained from the PRA sensitivity analyses are discussed. ABB-CE considered defense-in-depth for accident prevention and mitigation early in the design process and used robust design features to ensure that the System 80 + design achieved a low core damage frequency, low containment conditional failure probability, and excellent deterministic containment performance under severe accident conditions and to ensure that the risk was properly allocated among design features and between prevention and mitigation. (author)

  11. Perfluoroalkyl acids (PFAAs) in the Pra and Kakum River basins and associated tap water in Ghana.

    Science.gov (United States)

    Essumang, David K; Eshun, Albert; Hogarh, Jonathan N; Bentum, John K; Adjei, Joseph K; Negishi, Junya; Nakamichi, Shihori; Habibullah-Al-Mamun, Md; Masunaga, Shigeki

    2017-02-01

    Perfluoroalkyl acids (PFAAs) are persistent environmental pollutants that have been detected in various media including human serum. Due to concerns regarding their bioaccumulation and possible negative health effects, an understanding of routes of human exposure is necessary. PFAAs are recalcitrant in many water treatment processes, making drinking water a potential source of human exposure. This study presents the first report on contamination from PFAAs in river and drinking water in Ghana. The targeted PFAAs were perfluoroalkyl carboxylic acids (PFCAs) with C 4-14 carbon chain and perfluoroalkane sulphonic acids (PFSAs) with C 6, 8, 10 . Five PFAA congeners - PFOA, PFOS, PFHxA, PFDA and PFPeA - were commonly detected in river and tap water. The mean concentrations of ∑PFAAs in the Kakum and Pra Rivers were 281 and 398ng/L, while tap water (supplied from the treatment of water from those rivers) contained concentrations of 197 and 200ng/L, respectively. PFOA and PFOS constituted about 99% of the ∑PFAAs. The risk quotient (RQ) attributed to drinking of tap water was estimated at 1.01 and 1.74 for PFOA and PFOS, respectively. For a country that has not produced these compounds, the RQs were unexpectedly high, raising concerns particularly about contamination from such emerging pollutants in local water sources. The study revealed limitations of local tap water treatment in getting rid of these emerging pollutants. Copyright © 2016 Elsevier B.V. All rights reserved.

  12. Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

    International Nuclear Information System (INIS)

    Lee, Joung Hoon; Yu, Dong Han

    2010-01-01

    According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

  13. Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Joung Hoon; Yu, Dong Han [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2010-10-15

    According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

  14. Correlative study between myopia and ocular relative accommodation

    Directory of Open Access Journals (Sweden)

    Qiao-Ya Lin

    2015-07-01

    Full Text Available AIM: To research the characteristics of positive relative accommodation(PRA, negative relative accommodation(NRAand PRA/NRA ratio in myopes. To analyze the relationship among PRA, NRA, PRA/NRA ratio, spherical equivalent degree, years and habbits of wearing glasses, myopia development, and pupil diameter.METHODS: Aretrospective study of ninety eyes in the 180th Hospital of Quanzhou from August 2014 to December 2014. PRA, NRA and PRA/NRA ratio were compared among low, moderate, high myopes and emmetropes. The correlation were analyzed among PRA, NRA, PRA/NRA ratio, spherical equivalent degree, years and habbits of wearing glasses, myopia development and pupil diameter. PRA, NRA, PRA/NRA ratio, years and habbits of wearing glasses and pupil diameter were compared between progress group and non-progress group.RESULTS:(1Without statistical differences in age, sex and intraocular pressure, PRA and PRA/NRA ratio of myopes were lower than emmetropes, while NRA was higher.(2Without statistical differences in age, sex and intraocular pressure, PRA, PRA/NRA ratio and NRA had no statistical differences while years and habbits of wearing glasses had statistical differences among low, moderate, high myopes.(3With longer years of wearing glasses, PRA, PRA/NRA ratio were larger and NRA, pupils were smaller.(4Without statistical differences in age, diopter and intraocular pressure, one group which were not easy to deepen degree had more often-wear-glasses myopia patiens and longer years of wearing glasses, the other group which were easy to deepen degree had more seldom-wear-glasses myopia patiens and shorter years of wearing glasses.CONCLUSION: PRA and PRA/NRA ratio of myopes were lower than emmetropes, while NRA was higher. No correlated relation was detected among PRA, NRA, PRA/NRA ratio, spherical equivalent degree and myopia development. It suggests the onset and progress of myopia are related to many factors. Wearing-glass timely and accurately can

  15. Mutation of praR in Rhizobium leguminosarum enhances root biofilms, improving nodulation competitiveness by increased expression of attachment proteins.

    Science.gov (United States)

    Frederix, Marijke; Edwards, Anne; Swiderska, Anna; Stanger, Andrew; Karunakaran, Ramakrishnan; Williams, Alan; Abbruscato, Pamela; Sanchez-Contreras, Maria; Poole, Philip S; Downie, J Allan

    2014-08-01

    In Rhizobium leguminosarum bv. viciae, quorum-sensing is regulated by CinR, which induces the cinIS operon. CinI synthesizes an AHL, whereas CinS inactivates PraR, a repressor. Mutation of praR enhanced biofilms in vitro. We developed a light (lux)-dependent assay of rhizobial attachment to roots and demonstrated that mutation of praR increased biofilms on pea roots. The praR mutant out-competed wild-type for infection of pea nodules in mixed inoculations. Analysis of gene expression by microarrays and promoter fusions revealed that PraR represses its own transcription and mutation of praR increased expression of several genes including those encoding secreted proteins (the adhesins RapA2, RapB and RapC, two cadherins and the glycanase PlyB), the polysaccharide regulator RosR, and another protein similar to PraR. PraR bound to the promoters of several of these genes indicating direct repression. Mutations in rapA2, rapB, rapC, plyB, the cadherins or rosR did not affect the enhanced root attachment or nodule competitiveness of the praR mutant. However combinations of mutations in rapA, rapB and rapC abolished the enhanced attachment and nodule competitiveness. We conclude that relief of PraR-mediated repression determines a lifestyle switch allowing the expression of genes that are important for biofilm formation on roots and the subsequent initiation of infection of legume roots. © 2014 The Authors. Molecular Microbiology published by John Wiley & Sons Ltd.

  16. Selecting the seismic HRA approach for Savannah River Plant PRA revision 1

    International Nuclear Information System (INIS)

    Papouchado, K.; Salaymeh, J.

    1993-10-01

    The Westinghouse Savannah River Company (WSRC) has prepared a level I probabilistic risk assessment (PRA), Rev. 0 of reactor operations for externally-initiated events including seismic events. The SRS PRA, Rev. 0 Seismic HRA received a critical review that expressed skepticism with the approach used for human reliability analysis because it had not been previously used and accepted in other published PRAs. This report provides a review of published probabilistic risk assessments (PRAs), the associated methodology guidance documents, and the psychological literature to identify parameters important to seismic human reliability analysis (HRA). It also describes a recommended approach for use in the Savannah River Site (SRS) PRA. The SRS seismic event PRA performs HRA to account for the contribution of human errors in the accident sequences. The HRA of human actions during and after a seismic event is an area subject to many uncertainties and involves significant analyst judgment. The approach recommended by this report is based on seismic HRA methods and associated issues and concerns identified from the review of these referenced documents that represent the current state-of-the- art knowledge and acceptance in the seismic HRA field

  17. Probabilistic risk assessment course documentation. Volume 2. Probability and statistics for PRA applications

    International Nuclear Information System (INIS)

    Iman, R.L.; Prairie, R.R.; Cramond, W.R.

    1985-08-01

    This course is intended to provide the necessary probabilistic and statistical skills to perform a PRA. Fundamental background information is reviewed, but the principal purpose is to address specific techniques used in PRAs and to illustrate them with applications. Specific examples and problems are presented for most of the topics

  18. MATILDA: A Military Laser Range Safety Tool Based on Probabilistic Risk Assessment (PRA) Techniques

    Science.gov (United States)

    2014-08-01

    3 2.1 UK Need for a PRA-Based Approach ............................................................... 3 2.2 A Risk-Based Approach to...Figure 6: MATILDA Coordinate Transformations ....................................................... 22  Figure 7: Geocentric and MICS Coordinates...Star-Shaped Condition ................................................................................. 27  Figure 11: Points of Closest Approach

  19. An integrated PRA module for fast determination of risk significance and improvement effectiveness

    International Nuclear Information System (INIS)

    Chao, Chun-Chang; Lin, Jyh-Der

    2004-01-01

    With the widely use of PRA technology in risk-informed applications, to predict the changes of CDF and LERF becomes a standard process for risk-informed applications. This paper describes an integrated PRA module prepared for risk-informed applications. The module contains a super risk engine, a super fault tree engine, an advanced PRA model and a tool for data base maintenance. The individual element of the module also works well for purpose other than risk-informed applications. The module has been verified and validated through a series of scrupulous benchmark tests with similar software. The results of the benchmark tests showed that the module has remarkable accuracy and speed even for an extremely large-size top-logic fault tree as well as for the case in which large amount of MCSs may be generated. The risk monitor for nuclear power plants in Taiwan is the first application to adopt the module. The results predicted by the risk monitor are now accepted by the regulatory agency. A tool to determine the risk significance according to the inspection findings will be the next application to adopt the module in the near future. This tool classified the risk significance into four different color codes according to the level of increase on CDF. Experience of application showed that the flexibility, the accuracy and speed of the module make it useful in any risk-informed applications when risk indexes must be determined by resolving a PRA model. (author)

  20. Manutenção de brinquedo em praças públicas

    Directory of Open Access Journals (Sweden)

    Fabio Namiki

    2007-12-01

    Full Text Available O artigo apresenta o jacaré, um dos brinquedos executados no âmbito do Programa Centros de Bairro, que foi responsável pela implantação de cerca de 50 praças na cidade de São Paulo entre 2002 e 2004. O conjunto dos brinquedos deste programa foi apresentado e analisado no mestrado “Manutenção de praças na cidade de São Paulo. Estudo de caso: brinquedos do programa Centros de Bairro”, segundo metodologia que pode ser também aplicada para outros componentes de uma praça e mesmo para a praça em si. Espera-se que esta metodologia sirva como instrumento para o planejamento das ações de manutenção de praças e de mobiliários urbanos de modo geral. Neste texto, são apresentadas informações (da mesma forma que seriam em um manual de uso, operação e manutenção do projeto do brinquedo, obtidas junto aos responsáveis pelo programa, em entrevista com o executor dos brinquedos e através dos desenhos e documentos produzidos para a licitação e execução das peças. São também apresentadas as informações obtidas a partir das inspeções a campo e estimativas do custo de manutenção preventiva. Frente ao custo de reposição de um brinquedo novo, os valores da manutenção nos provam a importância econômica de tais ações.

  1. Clinical evaluation of the new TGDc-01 "PRA" palpebral tonometer: comparison with contact and non-contact tonometry.

    Science.gov (United States)

    García Resúa, Carlos; Giráldez Fernández, Maria J; Cerviño Expósito, Alejandro; González Pérez, Javier; Yebra-Pimentel, Eva

    2005-02-01

    The TGDc-01 "PRA" (Ryazan State Instrument, Ryazan, Russia) tonometer is a new portable small-sized tonometer that measures intraocular pressure (IOP) through the eyelid. The purpose of this study is to assess the repeatability of the TGDc-01 IOP measurements by comparing them against those obtained with Goldmann tonometer and with those from Perkins applanation tonometer, Xpert (Reichert, Depew, NY) noncontact tonometer, and Tono-Pen XL (Medtronic Solan, Jacksonville, FL) digital tonometer. Fifty-eight right eyes of 58 young subjects were measured with each of the tonometers. Noncontact tonometry was performed first, followed by Goldmann and Perkins applanation tonometer (in random order), digital Tono-Pen XL, and finally TGDc-01 tonometer (sitting and supine position). Correlation analysis was used to evaluate the relationship between the Goldmann tonometer and the remaining tonometers used in this study. Plotting the difference between the methods against mean was also done to compare the tonometers. The hypothesis of zero bias was examined by a paired t-test. The 95% limits of agreement (LoA) were also calculated. TGDc-01 showed no statistical difference between the IOP measurements obtained in sitting and supine positions. A poor relationship between the TGDc-01 and Goldmann tonometer was found (r = 0.173; p = 0.001). Although the mean differences between Goldmann and Tonopen XL, Xpert, and TGDc-01 IOP measurements were statistically significant, the wider 95% LoA was observed when comparing the Goldmann and TGDc-01 tonometers. Computation of the 95% LoA resulted in a wide bias range when comparing the TGDc-01 with all the tonometers used in this study. The TGDc-01 "PRA" tonometer was not comparable with the other techniques used in the study. The wide dispersion range of the values obtained shows low repeatability of the TGDc-01 for screening purposes. These results could be because of the technique of measurement and/or interindividual variables.

  2. The Evaluation of the Adequacy of PRA Results for Risk-informed Decision Makings With Respect to Incompleteness

    International Nuclear Information System (INIS)

    Kang, Kyungmin; Jae, Moosung

    2007-01-01

    PRA(Probabilistic Risk Assessment), as a quantitative tool, has many strengths as well as weaknesses. There are several limitations on the use of PRA techniques for risk modeling and analysis. First, the true values of most model inputs are unknown. Ideally, probability distribution models are well developed and assigned to the unknown input parameters to reflect the analyst's state of knowledge of the values of this input parameter. The problem of overconfidence and lack of confidence in the values of certain model input parameters can lead to inaccurate PRA results. Secondly, the analyst's lack of knowledge of a system's practical application as opposed to its theoretical operation can lead to modeling errors. The quality of PRAs has been addressed by a number of regulatory and industry organizations Some have argued that a good PRA should be a complete, full scope, three level PRA, while others have claimed that the quality of a PRA should be measured with respect to the application and decision supported. we show by way of an example that the adequacy of a PRA results is important to risk-informed decision making process and should be measured with respect to the application and decision supported

  3. Probabilistic risk assessment (PRA) update in light of the accident at Fukushima Daiichi Nuclear Power Station - 15461

    International Nuclear Information System (INIS)

    Maeda, K.; Abe, H.; Hirokawa, N.; Satou, C.

    2015-01-01

    We have performed internal and external event probabilistic risk assessments (PRA) for boiling water reactor power nuclear plants to identify the important accident sequence groups and to evaluate the effectiveness of the additional severe accident measures, regarding to the new regulatory requirements implemented after the accident at Fukushima Daiichi Nuclear Power Station in Japan in 2011. In addition, we will further update our PRA by extracting problems and improvements from the current PRA, by catching up the state-of-the-art knowledge, modern PRA methodologies in order to contribute voluntarily to safety improvement as well as to comply with regulations. In this document, prior to the extensive PRA updates, we would describe technical contents and qualitative results about PRA updates that have been performed preliminary so far, especially about the external event (seismic) PRA and how to model the additionally deployed severe accident measures (e.g. power supply car, fire engine) so that they can be function external hazards, such as component failure rate of equipment, human reliability 'out of control room', and mission time extension. (authors)

  4. Impact of Gold mining activities on the water quality of the lower pra river

    International Nuclear Information System (INIS)

    Dwamena, Offei Samuel K.

    2013-07-01

    This study was conducted to assess the extent of Mercury (THg) contamination at four locations within the Shama-Mporhor Wassa catchment area of the Lower Pra River. Water, fish and sediment samples were taken twice with the longitudinal transect method at Daboase, Beposo, Bokorkope and Shama during the minor rainy season in October and at the apex of the dry season in March. Careful investigation of the Shama-Mporhor Wassa catchment area revealed that two of the locations Daboase and Beposo had been continuously impacted by the activities of Artisanal Gold miners (AGM). From the study, Total Mercury (THg) levels were found to have persisted in River water several kilometers downstream the second Artisanal Gold mining (AGM) location at Shama estuary for both seasons. Ten trace elements Mercury (Hg), Selenium (Se), Copper (Cu), Chromium (Cr), Lead (Pb), Iron (Fe), Manganese (Mn), Nickel (Ni), Zinc (Zn) and Cadmium (Cd) were determined in water, fish and sediment samples using the Atomic Absorption Spectroscopy (AAS) equipped with both Hydride Generation (HGAAS) for Selenium (Se) and Cold Vapour (CVAAS) for Total Mercury (THg). The levels of Total Mercury (THg) were largely above the WHO and USEPA guidelines for drinking water (1μg/L) and sediments (200 μg/Kg) respectively for the four locations investigated. Total Mercury (THg) exceeded the WHO, 2011 guideline value of 0.5 mg/Kg for fish species Clarias submarginatus but was below the guideline value for Xenomystus nigri. Mean concentration of Cd and Fe exceeded the WHO, 2011 guideline values for drinking water for the wet season. The other trace elements Zn, Ni, Cu, Cr, Se, Mn, and Pb had their mean concentration below the WHO, 2011 guideline values for drinking water. Apart from the mean concentration of Cd that exceeded the Canadian Interim Sediment Quality (ISQG) guideline value of 0.6 mg/Kg for the wet season, Cr, Cu, Zn, Ni and Pb were below their respective guideline values for both seasons. Statistical

  5. Plant specification of a generic human-error data through a two-stage Bayesian approach

    International Nuclear Information System (INIS)

    Heising, C.D.; Patterson, E.I.

    1984-01-01

    Expert judgement concerning human performance in nuclear power plants is quantitatively coupled with actuarial data on such performance in order to derive plant-specific human-error rate probability distributions. The coupling procedure consists of a two-stage application of Bayes' theorem to information which is grouped by type. The first information type contains expert judgement concerning human performance at nuclear power plants in general. Data collected on human performance at a group of similar plants forms the second information type. The third information type consists of data on human performance in a specific plant which has the same characteristics as the group members. The first and second information types are coupled in the first application of Bayes' theorem to derive a probability distribution for population performance. This distribution is then combined with the third information type in a second application of Bayes' theorem to determine a plant-specific human-error rate probability distribution. The two stage Bayesian procedure thus provides a means to quantitatively couple sparse data with expert judgement in order to obtain a human performance probability distribution based upon available information. Example calculations for a group of like reactors are also given. (author)

  6. Comments of the PRA Senior Review Panel on the meeting held December 1--3, 1987

    International Nuclear Information System (INIS)

    Sharp, D.A.

    1988-01-01

    This memorandum records the minutes of the PRA Senior Review Panel meeting held at Savannah River Laboratory (SRL) on December 1--3, 1987, and the report on that meeting written subsequently by the panel members. The minutes are contained as Attachment 2 of this memorandum, and the report as Attachment 1. The Panel indicated two principal concerns in their report: (1) that insufficient emphasis is being placed on the reliability data development program, and (2) that excessive detail is being built into the fault trees. These concerns have been addressed in a subsequent meeting with the Panel, held March 2--4, 1988. In addition, the members have been provided with a program document (Reference 1) indicating the extent, the timing, and the limitations of the data analysis effort for the PRA

  7. Advanced Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Technical Exchange Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-09-01

    During FY13, the INL developed an advanced SMR PRA framework which has been described in the report Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Detailed Technical Framework Specification, INL/EXT-13-28974 (April 2013). In this framework, the various areas are considered: Probabilistic models to provide information specific to advanced SMRs Representation of specific SMR design issues such as having co-located modules and passive safety features Use of modern open-source and readily available analysis methods Internal and external events resulting in impacts to safety All-hazards considerations Methods to support the identification of design vulnerabilities Mechanistic and probabilistic data needs to support modeling and tools In order to describe this framework more fully and obtain feedback on the proposed approaches, the INL hosted a technical exchange meeting during August 2013. This report describes the outcomes of that meeting.

  8. Expected proton signal sizes in the PRaVDA Range Telescope for proton Computed Tomography

    International Nuclear Information System (INIS)

    Price, T.; Parker, D.J.; Green, S.; Esposito, M.; Waltham, C.; Allinson, N.M.; Poludniowski, G.; Evans, P.; Taylor, J.; Manolopoulos, S.; Anaxagoras, T.; Nieto-Camero, J.

    2015-01-01

    Proton radiotherapy has demonstrated benefits in the treatment of certain cancers. Accurate measurements of the proton stopping powers in body tissues are required in order to fully optimise the delivery of such treaments. The PRaVDA Consortium is developing a novel, fully solid state device to measure these stopping powers. The PRaVDA Range Telescope (RT), uses a stack of 24 CMOS Active Pixel Sensors (APS) to measure the residual proton energy after the patient. We present here the ability of the CMOS sensors to detect changes in the signal sizes as the proton traverses the RT, compare the results with theory, and discuss the implications of these results on the reconstruction of proton tracks

  9. Clinical analysis of the changes of plasma PRA, AT-II and Aid levels in patients with acute renal failure

    International Nuclear Information System (INIS)

    Zhang Qiuyue; Yang Yongqing

    2002-01-01

    Objective: To investigate the role of changes of plasma PRA, AT-II and Ald levels in the pathogenesis of acute renal failure. Methods: Plasma PRA, AT-II and Ald levels were determined with RIA in 40 normal subjects and 72 cases of acute renal failure. Results: Plasma PRA, AT-II and Ald levels in the patients were markedly increased as compared with those in normal subjects (p < 0.05, p < 0.01, p < 0.001 respectively). There were no linearity and exponential relationship between plasma PRA, AT-II, Ald levels and the 24 h urinary sodium excretion amount (within the range of 89.1 - 365.2 mEq). Conclusion: Acute renal failure could activate the RAAS function

  10. The Prenylated Rab GTPase Receptor PRA1.F4 Contributes to Protein Exit from the Golgi Apparatus.

    Science.gov (United States)

    Lee, Myoung Hui; Yoo, Yun-Joo; Kim, Dae Heon; Hanh, Nguyen Hong; Kwon, Yun; Hwang, Inhwan

    2017-07-01

    Prenylated Rab acceptor1 (PRA1) functions in the recruitment of prenylated Rab proteins to their cognate organelles. Arabidopsis ( Arabidopsis thaliana ) contains a large number of proteins belonging to the AtPRA1 family. However, their physiological roles remain largely unknown. Here, we investigated the physiological role of AtPRA1.F4, a member of the AtPRA1 family. A T-DNA insertion knockdown mutant of AtPRA1.F4 , atpra1.f4 , was smaller in stature than parent plants and possessed shorter roots, whereas transgenic plants overexpressing HA:AtPRA1.F4 showed enhanced development of secondary roots and root hairs. However, both overexpression and knockdown plants exhibited increased sensitivity to high-salt stress, lower vacuolar Na + /K + -ATPase and plasma membrane ATPase activities, lower and higher pH in the vacuole and apoplast, respectively, and highly vesiculated Golgi apparatus. HA:AtPRA1.F4 localized to the Golgi apparatus and assembled into high-molecular-weight complexes. atpra1.f4 plants displayed a defect in vacuolar trafficking, which was complemented by low but not high levels of HA : AtPRA1.F4 Overexpression of HA:AtPRA1.F4 also inhibited protein trafficking at the Golgi apparatus, albeit differentially depending on the final destination or type of protein: trafficking of vacuolar proteins, plasma membrane proteins, and trans-Golgi network (TGN)-localized SYP61 was strongly inhibited; trafficking of TGN-localized SYP51 was slightly inhibited; and trafficking of secretory proteins and TGN-localized SYP41 was negligibly or not significantly inhibited. Based on these results, we propose that Golgi-localized AtPRA1.F4 is involved in the exit of many but not all types of post-Golgi proteins from the Golgi apparatus. Additionally, an appropriate level of AtPRA1.F4 is crucial for its function at the Golgi apparatus. © 2017 American Society of Plant Biologists. All Rights Reserved.

  11. Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors (U)

    International Nuclear Information System (INIS)

    Tinnes, S.P.; Cramer, D.S.; Logan, V.E.; Topp, S.V.; Smith, J.A.; Brandyberry, M.D.

    1990-01-01

    This paper reports on a full-scope probabilistic risk assessment (PRA) performed for the Savannah River Site (SRS) production reactors. The Level 1 PRA for the K Reactor has been completed and includes the assessment of reactor systems response to accidents and estimates of the severe core melt frequency (SCMF). The internal events spectrum includes those events related directly to plant systems and safety functions for which transients or failures may initiate an accident

  12. Development of a methodology for conducting an integrated HRA/PRA --

    International Nuclear Information System (INIS)

    Luckas, W.J.; Barriere, M.T.; Brown, W.S.; Wreathall, J.; Cooper, S.E.

    1993-01-01

    During Low Power and Shutdown (LP ampersand S) conditions in a nuclear power plant (i.e., when the reactor is subcritical or at less than 10--15% power), human interactions with the plant's systems will be more frequent and more direct. Control is typically not mediated by automation, and there are fewer protective systems available. Therefore, an assessment of LP ampersand S related risk should include a greater emphasis on human reliability than such an assessment made for power operation conditions. In order to properly account for the increase in human interaction and thus be able to perform a probabilistic risk assessment (PRA) applicable to operations during LP ampersand S, it is important that a comprehensive human reliability assessment (HRA) methodology be developed and integrated into the LP ampersand S PRA. The tasks comprising the comprehensive HRA methodology development are as follows: (1) identification of the human reliability related influences and associated human actions during LP ampersand S, (2) identification of potentially important LP ampersand S related human actions and appropriate HRA framework and quantification methods, and (3) incorporation and coordination of methodology development with other integrated PRA/HRA efforts. This paper describes the first task, i.e., the assessment of human reliability influences and any associated human actions during LP ampersand S conditions for a pressurized water reactor (PWR)

  13. Development of a methodology for conducting an integrated HRA/PRA --

    Energy Technology Data Exchange (ETDEWEB)

    Luckas, W.J.; Barriere, M.T.; Brown, W.S. (Brookhaven National Lab., Upton, NY (United States)); Wreathall, J. (Wreathall (John) and Co., Dublin, OH (United States)); Cooper, S.E. (Science Applications International Corp., McLean, VA (United States))

    1993-01-01

    During Low Power and Shutdown (LP S) conditions in a nuclear power plant (i.e., when the reactor is subcritical or at less than 10--15% power), human interactions with the plant's systems will be more frequent and more direct. Control is typically not mediated by automation, and there are fewer protective systems available. Therefore, an assessment of LP S related risk should include a greater emphasis on human reliability than such an assessment made for power operation conditions. In order to properly account for the increase in human interaction and thus be able to perform a probabilistic risk assessment (PRA) applicable to operations during LP S, it is important that a comprehensive human reliability assessment (HRA) methodology be developed and integrated into the LP S PRA. The tasks comprising the comprehensive HRA methodology development are as follows: (1) identification of the human reliability related influences and associated human actions during LP S, (2) identification of potentially important LP S related human actions and appropriate HRA framework and quantification methods, and (3) incorporation and coordination of methodology development with other integrated PRA/HRA efforts. This paper describes the first task, i.e., the assessment of human reliability influences and any associated human actions during LP S conditions for a pressurized water reactor (PWR).

  14. Use of probabilistic risk assessment (PRA) in expert systems to advise nuclear plant operators and managers

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1988-01-01

    The use of expert systems in nuclear power plants to provide advice to managers, supervisors and/or operators is a concept that is rapidly gaining acceptance. Generally, expert systems rely on the expertise of human experts or knowledge that has been codified in publications, books, or regulations to provide advice under a wide variety of conditions. In this work, a probabilistic risk assessment (PRA) of a nuclear power plant performed previously is used to assess the safety status of nuclear power plants and to make recommendations to the plant personnel. Nuclear power plants have many redundant systems and can continue to operate when one or more of these systems is disabled or removed from service for maintenance or testing. PRAs provide a means of evaluating the risk to the public associated with the operation of nuclear power plants with components or systems out of service. While the choice of the source term and methodology in a PRA may influence the absolute probability and consequences of a core melt, the ratio of the PRA calculations for two configurations of the same plant, carried out on a consistent basis, can readily identify the increase in risk associated with going from one configuration to the other

  15. An approach for using risk assessment in risk-informed decisions on plant-specific changes to the licensing basis

    International Nuclear Information System (INIS)

    Caruso, Mark A.; Cheok, Michael C.; Cunningham, Mark A.; Holahan, Gary M.; King, Thomas L.; Parry, Gareth W.; Ramey-Smith, Ann M.; Rubin, Mark P.; Thadani, Ashok C.

    1999-01-01

    This paper discusses an acceptable approach that the US Nuclear Regulatory Commission staff has proposed for using Probabilistic Risk Assessment in making decisions on changes to the licensing basis of a nuclear power plant. First, the overall philosophy of risk-informed decision-making, and the process framework are described. The philosophy is encapsulated in five principles, one of which states that, if the proposed change leads to an increase in core damage frequency or risk, the increases must be small and consistent with the intent of the Nuclear Regulatory Commission's Safety Goal Policy Statement. The second part of the paper discusses the use of PRA to demonstrate that this principle has been met. The discussion focuses on the acceptance guidelines, and on comparison of the PRA results with those guidelines. The difficulties that arise because of limitations in scope and analytical uncertainties are discussed and approaches to accommodate these difficulties in the decision-making are described

  16. Comparison and lessons learned from plant specific PSA of German NPP

    International Nuclear Information System (INIS)

    Balfanz, Hans-Peter; Berg, H.P.

    2000-01-01

    PSA are launched in frame of Periodic Safety Reviews (PSR) in Germany. The aims are to identify overall safety level and relative weak points. Some backfitting measures have been realized for older plants to remove relative weak points and to bring these plants to the state of the art. In this field PSA is well accepted today and is seen as a valuable tool supplementing the deterministic analysis. Main application of PSA within PSR is planned to become mandatory as part of the revision of the German Atomic Energy Act. According to the German PSA Guideline plant specific PSA level 1+ were performed for all 19 In comparison with international practice German PSA are very detailed. Otherwise they do not handle all external events, non-power states and accident management measures as discussed before. The New PSA guideline will cover these aspects and therefore analysts have to take them into account in further PSA. Moreover gathering of plant specific data is needed. The development in this field is driven by the utilities (for instance in frame of their so-called ZEDB project). Public discussion about quantitative risk of industrial hazards is quite limited in Germany and PSA results have only few impacts to this respect. Independent from this PSA for NPP is understood as a diverse tool in supporting the deterministic licensing and supervision process. Risk based decision making as well as informed regulation are just only of the beginning. State of PSA of NPP in Germany, comparison of PSA result of different NPP, German PSA guideline and state of discussion of further development and recommendation of further development of PSA of NPP are discussed in this paper in more detail. (S.Y.)

  17. Comparison and lessons learned from plant specific PSA of German NPP

    Energy Technology Data Exchange (ETDEWEB)

    Balfanz, Hans-Peter [TUEV Nord, Hamburg (Germany); Berg, H.P.

    2000-07-01

    PSA are launched in frame of Periodic Safety Reviews (PSR) in Germany. The aims are to identify overall safety level and relative weak points. Some backfitting measures have been realized for older plants to remove relative weak points and to bring these plants to the state of the art. In this field PSA is well accepted today and is seen as a valuable tool supplementing the deterministic analysis. Main application of PSA within PSR is planned to become mandatory as part of the revision of the German Atomic Energy Act. According to the German PSA Guideline plant specific PSA level 1+ were performed for all 19 In comparison with international practice German PSA are very detailed. Otherwise they do not handle all external events, non-power states and accident management measures as discussed before. The New PSA guideline will cover these aspects and therefore analysts have to take them into account in further PSA. Moreover gathering of plant specific data is needed. The development in this field is driven by the utilities (for instance in frame of their so-called ZEDB project). Public discussion about quantitative risk of industrial hazards is quite limited in Germany and PSA results have only few impacts to this respect. Independent from this PSA for NPP is understood as a diverse tool in supporting the deterministic licensing and supervision process. Risk based decision making as well as informed regulation are just only of the beginning. State of PSA of NPP in Germany, comparison of PSA result of different NPP, German PSA guideline and state of discussion of further development and recommendation of further development of PSA of NPP are discussed in this paper in more detail. (S.Y.)

  18. Perbandingan Tinggi Tulang Maksila dan Mandibula di Regio Interisisivi Sentral antara Pra dan Pasca Perawatan Ortodontik dengan Pencabutan ke Empat Gigi Premolar Pertama (Kajian pada Foto Panoramik

    Directory of Open Access Journals (Sweden)

    Wayan Ardhana

    2012-12-01

    Full Text Available Latar belakang. Perawatan ortodontik pada kasus-kasus gigi berjejal dan protusif sering membutuhkan pencabutan gigi premolar untuk penyediaan ruang agar gigi berjejal dapat dirapikan dan gigi depan yang protusif dapat diundurkan. Gigi insisivus sentral merupakan salah satu gigi yang paling banyak mengalami pergerakan selama proses retrusi. Pergerakan gigi insisivus mengakibatkan terjadinya perubahan pada puncak tulang alveolar selama perawatan yang mungkin akan mempengaruhi tinggi tulang maksila dan mandibula pasca perawatan. Tujuan penelitian. Membandingkan tinggi tulang maksila dan mandibula di daerah interdental gigi insisivi sentral pada foto panoramic antara pra dan pasca perawatan maloklusi dengan pencabutan ke empat gigi premolar pertama. Metode penelitian. Digunakan 30 pasang foto panoramic pra dan pasca perawatan yang dipilih sesuai dengan kriteria penelitian dari pasien-pasien peneliti yang telah selesai mendapat perawatan aktif dengan teknik edgewise. Analisis Kolmogorov-Smirnov dan Shaviro-Wilk digunakan untuk uji normalitas dan Student t-test data berpasangan digunakan untuk menguji perbedaan tinggi tulang maksila dan mandibula antara pra dan pasca perawatan. Hasil Penelitian. Tidak didapatkan perbedaan (p>0,05 tinggi tulang maksila dan amndibula antara pra dan pasca perawatan ortodontik dengan pencabutan keempat gigi premolar pertama.   Background. In orthodontic treatment, premolar extractions are often needed in crowding and prostrusive cases to provide space for the teeth can be aligned and retracted to their desire position. Central incisor teeth are the teeth that mostly undergone more movement during retrusion. The change of the alveolar bone crest in this incisors might affect the maxillary and mandibular bone height post-treatment. Research objectives. The present study aimed to compare the bone height in the interdental maxillary and mandibular central incisors regions before and after orthodontic treatment with four

  19. Loss of spent fuel pool cooling PRA: Model and results

    International Nuclear Information System (INIS)

    Siu, N.; Khericha, S.; Conroy, S.; Beck, S.; Blackman, H.

    1996-09-01

    This letter report documents models for quantifying the likelihood of loss of spent fuel pool cooling; models for identifying post-boiling scenarios that lead to core damage; qualitative and quantitative results generated for a selected plant that account for plant design and operational practices; a comparison of these results and those generated from earlier studies; and a review of available data on spent fuel pool accidents. The results of this study show that for a representative two-unit boiling water reactor, the annual probability of spent fuel pool boiling is 5 x 10 -5 and the annual probability of flooding associated with loss of spent fuel pool cooling scenarios is 1 x 10 -3 . Qualitative arguments are provided to show that the likelihood of core damage due to spent fuel pool boiling accidents is low for most US commercial nuclear power plants. It is also shown that, depending on the design characteristics of a given plant, the likelihood of either: (a) core damage due to spent fuel pool-associated flooding, or (b) spent fuel damage due to pool dryout, may not be negligible

  20. Use of PRA methodology for enhancing operational safety and reliability

    International Nuclear Information System (INIS)

    Chu, B.; Rumble, E.; Najafi, B.; Putney, B.; Young, J.

    1985-01-01

    This paper describes a broad scope, on-going R and D study, sponsored by the Electric Power Research Institute (EPRI) to utilize key features of the state-of-the-art plant information management and system analysis techniques to develop and demonstrate a practical engineering tool for assisting plant engineering and operational staff to perform their activities more effectively. The study is foreseen to consist of two major activities: to develop a user-friendly, integrated software system; and to demonstrate the applications of this software on-site. This integrated software, Reliability Analysis Program with In-Plant Data (RAPID), will consist of three types of interrelated elements: an Executive Controller which will provide engineering and operations staff users with interface and control of the other two software elements, a Data Base Manager which can acquire, store, select, and transfer data, and Applications Modules which will perform the specific reliability-oriented functions. A broad range of these functions has been envisaged. The immediate emphasis will be focused on four application modules: a Plant Status Module, a Technical Specification Optimization Module, a Reliability Assessment Module, and a Utility Module for acquiring plant data

  1. Improvement of human reliability analysis method for PRA

    International Nuclear Information System (INIS)

    Tanji, Junichi; Fujimoto, Haruo

    2013-09-01

    It is required to refine human reliability analysis (HRA) method by, for example, incorporating consideration for the cognitive process of operator into the evaluation of diagnosis errors and decision-making errors, as a part of the development and improvement of methods used in probabilistic risk assessments (PRAs). JNES has been developed a HRA method based on ATHENA which is suitable to handle the structured relationship among diagnosis errors, decision-making errors and operator cognition process. This report summarizes outcomes obtained from the improvement of HRA method, in which enhancement to evaluate how the plant degraded condition affects operator cognitive process and to evaluate human error probabilities (HEPs) which correspond to the contents of operator tasks is made. In addition, this report describes the results of case studies on the representative accident sequences to investigate the applicability of HRA method developed. HEPs of the same accident sequences are also estimated using THERP method, which is most popularly used HRA method, and comparisons of the results obtained using these two methods are made to depict the differences of these methods and issues to be solved. Important conclusions obtained are as follows: (1) Improvement of HRA method using operator cognitive action model. Clarification of factors to be considered in the evaluation of human errors, incorporation of degraded plant safety condition into HRA and investigation of HEPs which are affected by the contents of operator tasks were made to improve the HRA method which can integrate operator cognitive action model into ATHENA method. In addition, the detail of procedures of the improved method was delineated in the form of flowchart. (2) Case studies and comparison with the results evaluated by THERP method. Four operator actions modeled in the PRAs of representative BWR5 and 4-loop PWR plants were selected and evaluated as case studies. These cases were also evaluated using

  2. Analytical support of plant specific SAMG development validation of SAMG using MELCOR 1.8.5

    International Nuclear Information System (INIS)

    Duspiva, Jiri

    2006-01-01

    They are two NPPs in operation in Czech Republic. Both of NPPs operated in CR have already implemented EOPs, developed under collaboration with the WESE. The project on SAMG development has started and follows the previous one for EOPs also with the WESE as the leading organization. Plant specific SAMGs for the Temelin as well as Dukovany NPPs are based on the WOG generic SAMGs. The analytical support of plant specific SAMGs development is performed by the NRI Rez within the validation process. Basic conditions as well as their filling by NRI Rez are focused on analyst, analytical tools and their applications. More detail description is attended to the approach of the preparation of the MELCOR code application to the evaluation of hydrogen risk, validation of recent set of hydrogen passive autocatalytic recombiners and definition of proposals to amend system of hydrogen removal. Such kind of parametric calculations will request to perform very wide set of runs. It could not be possible with the whole plant model and decoupling of such calculation with storing of mass and energy sources into the containment is only one way. The example of this decoupling for the LOCA scenario is shown. It includes seven sources - heat losses from primary and secondary circuits, fluid blowndown through cold leg break, fission products blowndown through cold leg break, fluid blowndown through break in reactor pressure vessel bottom head, fission products through break in reactor pressure vessel bottom head, melt ejection from reactor pressure vessel to cavity and gas masses and heat losses from corium in cavity. The stand alone containment analysis was tested in two configurations - with or without taking of fission products into account. Testing showed very good agreement of all calculations until lower head failure and acceptable agreement after that. Also some problematic features appeared. The stand alone test with fission product was possible only after the changes in source code

  3. Broadening failure rate distributions in PRA uncertainty analyses

    International Nuclear Information System (INIS)

    Martz, H.F.

    1984-01-01

    Several recent nuclear power plant probabilistic risk assessments (PRAs) have utilized broadened Reactor Safety Study (RSS) component failure rate population variability curves to compensate for such things as expert overvaluation bias in the estimates upon which the curves are based. A simple two-components of variation empirical Bayes model is proposed for use in estimating the between-expert variability curve in the presence of such biases. Under certain conditions this curve is a population variability curve. Comparisons are made with the existing method. The popular procedure appears to be generally much more conservative than the empirical Bayes method in removing such biases. In one case the broadened curve based on the popular method is more than two orders of magnitude broader than the empirical Bayes curve. In another case it is found that the maximum justifiable degree of broadening of the RSS curve is to increase α from 5% to 12%, which is significantly less than 20% value recommended in the popular approach. 15 references, 1 figure, 5 tables

  4. The RISMC approach to perform advanced PRA analyses - 15332

    International Nuclear Information System (INIS)

    Mandelli, D.; Smith, C.; Riley, T.; Nielsen, J.; Alfonsi, A.; Rabiti, C.; Cogliati, J.

    2015-01-01

    The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power up-rates. In order to evaluate the impact of these two factors on the safety of the plant, the RISMC (Risk Informed Safety Margin Characterization) Pathway aims to develop simulation-based tools and methods to assess risks for existing nuclear power plants in order to optimize safety. This pathway, by developing new methods, is extending the state-of-the-practice methods that have been traditionally based on logic structures such as Event-Trees and Fault-Trees. These static types of models mimic system response in an inductive and deductive way respectively, yet are restrictive in the ways they can represent spatial and temporal constructs. RISMC analyses are performed by using a combination of thermal-hydraulic codes and a stochastic analysis tool (RAVEN)currently under development at the Idaho National Laboratory. This paper presents a case study in order to show the capabilities of the RISMC methodology to assess impact of power up-rate of a boiling water reactor system during a station blackout accident scenario. We employ the system simulator code, RELAP5-3D, coupled with RAVEN which perform the stochastic analysis. Our analysis is in fact performed by: 1) sampling values of a set of parameters from the uncertainty space of interest, 2) simulating the system behavior for that specific set of parameter values and 3) analyzing the set of simulation runs. Results obtained give a detailed investigation of the issues associated with a plant power up-rate including the effects of station blackout accident scenarios. We are able to quantify how the timing of specific events was impacted by a higher nominal reactor core power. Such safety insights can provide useful information to the decision makers to perform risk informed margins management

  5. Effect of antigravity suit inflation on cardiovascular, PRA, and PVP responses in humans.

    Science.gov (United States)

    Kravik, S E; Keil, L C; Geelen, G; Wade, C E; Barnes, P R; Spaul, W A; Elder, C A; Greenleaf, J E

    1986-08-01

    Blood pressure, pulse rate (PR), serum osmolality and electrolytes, as well as plasma vasopressin (PVP) and plasma renin activity (PRA), were measured in five men and two women [mean age 38.6 +/- 3.9 (SE) yr] before, during, and after inflation of an antigravity suit that covered the legs and abdomen. After 24 h of fluid deprivation the subjects stood quietly for 3 h: the 1st h without inflation, the 2nd with inflation to 60 Torr, and the 3rd without inflation. A similar control noninflation experiment was conducted 10 mo after the inflation experiment using five of the seven subjects except that the suit was not inflated during the 3-h period. Mean arterial pressure increased by 14 +/- 4 (SE) Torr (P less than 0.05) with inflation and decreased by 15 +/- 5 Torr (P less than 0.05) after deflation. Pulse pressure (PP) increased by 7 +/- 2 Torr (P less than 0.05) with inflation and PR decreased by 11 +/- 5 beats/min (P less than 0.05); PP and PR returned to preinflation levels after deflation. Plasma volume decreased by 6.1 +/- 1.5% and 5.3 +/- 1.6% (P less than 0.05) during hours 1 and 3, respectively, and returned to base line during inflation. Inflation decreased PVP from 6.8 +/- 1.1 to 5.6 +/- 1.4 pg/ml (P less than 0.05) and abolished the significant rise in PRA during hour 1. Both PVP and PRA increased significantly after deflation: delta = 18.0 +/- 5.1 pg/ml and 4.34 +/- 1.71 ng angiotensin I X ml-1 X h-1, respectively. Serum osmolality and Na+ and K+ concentrations were unchanged during the 3 h of standing.(ABSTRACT TRUNCATED AT 250 WORDS)

  6. Review of KSNP LPSD PSA model based of ANS LPSD PRA standard, rev.0

    International Nuclear Information System (INIS)

    Jang, S. C.; Park, J. H.; Kim, T. W.; Lim, H. G.; Yang, J. E.; Ha, J. J.

    2004-02-01

    Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-based Operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-informed In-service Inspection (RI-ISI). However, in Korea, there have been no attempts to evaluate the quality of PSA model itself. Therefore, we cannot be sure about the quality of PSA whether or not the present PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of PSA model quality is the basis for the RIPBO. In this report, we have evaluated the quality of PSA model at Low power and Shutdown operation model for Yongkwang 5 and 6 units based on the ANS LPSD PRA Standard. We, also, have derived what items are to be improved to upgrade the quality of LPSD PSA model and how it can be improved. This report can be used as the base of RIPBO work in Korea

  7. Overview of OVATE FAMILY PROTEINS, a novel class of plant-specific growth regulators

    Directory of Open Access Journals (Sweden)

    Shucai eWang

    2016-03-01

    Full Text Available OVATE FAMILY PROTEINS (OFPs are a class of proteins with a conserved OVATE domain. OVATE protein was first identified in tomato as a key regulator of fruit shape. OFPs are plant-specific proteins that are widely distributed in the plant kingdom including mosses and lycophytes. Transcriptional activity analysis of Arabidopsis OFPs (AtOFPs in protoplasts suggests that they act as transcription repressors. Functional characterization of OFPs from different plant species including Arabidopsis, rice, tomato, pepper and banana suggests that OFPs regulate multiple aspects of plant growth and development, which is likely achieved by interacting with different types of transcription factors including the KNOX and BELL classes, and/or directly regulating the expression of target genes such as Gibberellin 20 oxidase (GA20ox. Here, we examine how OVATE was originally identified, summarize recent progress in elucidation of the roles of OFPs in regulating plant growth and development, and describe possible mechanisms underpinning this regulation. Finally, we review potential new research directions that could shed additional light on the functional biology of OFPs in plants.

  8. Use of probabilistic risk assessment (PRA) in expert systems to advise nuclear plant operators and managers

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1988-01-01

    The use of expert systems in nuclear power plants to provide advice to managers, supervisors and/or operators is a concept that is rapidly gaining acceptance. Generally, expert systems rely on the expertise of human experts or knowledge that has been modified in publications, books, or regulations to provide advice under a wide variety of conditions. In this work, a probabilistic risk assessment (PRA) 3 of a nuclear power plant performed previously is used to assess the safety status of nuclear power plants and to make recommendations to the plant personnel. 5 refs., 1 fig., 2 tabs

  9. Application of the NUREG/CR-6850 EPRI/NRC Fire PRA Methodology to a DOE Facility

    International Nuclear Information System (INIS)

    Elicson, Tom; Harwood, Bentley; Yorg, Richard; Lucek, Heather; Bouchard, Jim; Jukkola, Ray; Phan, Duan

    2011-01-01

    The application NUREG/CR-6850 EPRI/NRC fire PRA methodology to DOE facility presented several challenges. This paper documents the process and discusses several insights gained during development of the fire PRA. A brief review of the tasks performed is provided with particular focus on the following: Tasks 5 and 14: Fire-induced risk model and fire risk quantification. A key lesson learned was to begin model development and quantification as early as possible in the project using screening values and simplified modeling if necessary. Tasks 3 and 9: Fire PRA cable selection and detailed circuit failure analysis. In retrospect, it would have been beneficial to perform the model development and quantification in 2 phases with detailed circuit analysis applied during phase 2. This would have allowed for development of a robust model and quantification earlier in the project and would have provided insights into where to focus the detailed circuit analysis efforts. Tasks 8 and 11: Scoping fire modeling and detailed fire modeling. More focus should be placed on detailed fire modeling and less focus on scoping fire modeling. This was the approach taken for the fire PRA. Task 14: Fire risk quantification. Typically, multiple safe shutdown (SSD) components fail during a given fire scenario. Therefore dependent failure analysis is critical to obtaining a meaningful fire risk quantification. Dependent failure analysis for the fire PRA presented several challenges which will be discussed in the full paper.

  10. The plant-specific impact of different pressurization rates in the probabilistic estimation of containment failure modes

    International Nuclear Information System (INIS)

    Ahn, Kwang Il; Yang, Joon Eon; Ha, Jae Joo

    2003-01-01

    The explicit consideration of different pressurization rates in estimating the probabilities of containment failure modes has a profound effect on the confidence of containment performance evaluation that is so critical for risk assessment of nuclear power plants. Except for the sophisticated NUREG-1150 study, many of the recent containment performance analyses (through level 2 PSAs or IPE back-end analyses) did not take into account an explicit distinction between slow and fast pressurization in their analyses. A careful investigation of both approaches shows that many of the approaches adopted in the recent containment performance analyses exactly correspond to the NUREG-1150 approach for the prediction of containment failure mode probabilities in the presence of fast pressurization. As a result, it was expected that the existing containment performance analysis results would be subjected to greater or less conservatism in light of the ultimate failure mode of the containment. The main purpose of this paper is to assess potential conservatism of a plant-specific containment performance analysis result in light of containment failure mode probabilities

  11. Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors

    International Nuclear Information System (INIS)

    Tinnes, S.P.; Cramer, D.S.; Logan, V.E.; Topp, S.V.; Smith, J.A.; Brandyberry, M.D.

    1990-01-01

    A full-scope probabilistic risk assessment (PRA) is being performed for the Savannah River site (SRS) production reactors. The Level 1 PRA for the K Reactor has been completed and includes the assessment of reactor systems response to accidents and estimates of the severe core melt frequency (SCMF). The internal events spectrum includes those events related directly to plant systems and safety functions for which transients or failures may initiate an accident. The SRS PRA has three principal objectives: improved understanding of SRS reactor safety issues through discovery and understanding of the mechanisms involved. Improved risk management capability through tools for assessing the safety impact of both current standard operations and proposed revisions. A quantitative measure of the risks posed by SRS reactor operation to employees and the general public, to allow comparison with declared goals and other societal risks

  12. Cernavoda NPP Unit 1: Operating experience program and plant specific performance indicators (level 2)

    International Nuclear Information System (INIS)

    Teodor, Vasile; Popa, Viorel

    1998-01-01

    The basis for the Operating Experience Program was set in place since early stages of the commissioning phase (1993), when a system based on the Canadian approach was implemented for reporting, reviewing, assessing and establishing of the necessary corrective action for unplanned events. This system provided excellent opportunity to train staff in unplanned event assessment methodology, and prepare the station for the formal reporting process following criticality in accordance with the licensing requirements. The formal process, set in place after criticality is described in Station Instruction Procedure SI-01365-P13 'Unplanned Event Report' and was developed under the supervision of Safety and Compliance Department. In parallel, a program for information exchange and trending of performance indicators was developed by Technical Services Department. The WANO recommendations following August 1997 Peer Review provided the opportunity for a better understanding and reconsideration of the Operating Experience Program. As a result, all the activities related to this topic were assigned to a new structure, within Safety and Compliance Department. As such an Operating Experience Group was created and a new program is now being developed in an integrated and centralized manner. The content of the paper is the following: - Overview; - Operating Experience Program; - Event Analysis (Unplanned Events Assessment System - UEIR Process- and Systematic Analysis of Operational Events - ACR Process); - Information Exchange Program; - Monitoring of Operating Experience - Plant Specific Performance Indicators; - Purpose; - Level 2 Performance Indicators. Four appendices are added containing: - A. Station performance indicators/targets (Level 2); - B. SPI (Station Performance Indicators - Level 2) - Graphics; - C. UEIR, LRS (Safety and Licensing Review Sheet), UEFR (Unplanned Event Follow-up Report), ACR and OPEX forms. (authors)

  13. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  14. Review of UCN 5,6 Fire PSA Model based on ANS Fire PRA Standard

    International Nuclear Information System (INIS)

    Yang, Joon Eon; Lee, Yoon Hwan

    2006-12-01

    Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). This approach uses the fire risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In fire risk informed/performance-based decision/operation, fire PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of fire PSA. ANS (American Nuclear Society) has developed a guidance called 'ANS Fire PRA Methodology Standard'. However, in Korea, there have been no attempts to evaluate the quality of fire PSA model itself. Therefore, we cannot be sure about the quality of fire PSA whether or not the present fire PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of fire PSA model quality is the basis for the fire risk informed/performance-based decision/operation. In this report, we have evaluated the quality of fire PSA model for Ulchin 5 and 6 units based on the ANS Fire PRA Standard. We, also, have derived what items are to be improved to upgrade the quality of fire PSA model and how it can be improved. This report can be used as the base of the fire risk informed/performance-based decision/operation work in Korea

  15. Medical Updates Number 5 to the International Space Station Probability Risk Assessment (PRA) Model Using the Integrated Medical Model

    Science.gov (United States)

    Butler, Doug; Bauman, David; Johnson-Throop, Kathy

    2011-01-01

    The Integrated Medical Model (IMM) Project has been developing a probabilistic risk assessment tool, the IMM, to help evaluate in-flight crew health needs and impacts to the mission due to medical events. This package is a follow-up to a data package provided in June 2009. The IMM currently represents 83 medical conditions and associated ISS resources required to mitigate medical events. IMM end state forecasts relevant to the ISS PRA model include evacuation (EVAC) and loss of crew life (LOCL). The current version of the IMM provides the basis for the operational version of IMM expected in the January 2011 timeframe. The objectives of this data package are: 1. To provide a preliminary understanding of medical risk data used to update the ISS PRA Model. The IMM has had limited validation and an initial characterization of maturity has been completed using NASA STD 7009 Standard for Models and Simulation. The IMM has been internally validated by IMM personnel but has not been validated by an independent body external to the IMM Project. 2. To support a continued dialogue between the ISS PRA and IMM teams. To ensure accurate data interpretation, and that IMM output format and content meets the needs of the ISS Risk Management Office and ISS PRA Model, periodic discussions are anticipated between the risk teams. 3. To help assess the differences between the current ISS PRA and IMM medical risk forecasts of EVAC and LOCL. Follow-on activities are anticipated based on the differences between the current ISS PRA medical risk data and the latest medical risk data produced by IMM.

  16. 77 FR 29391 - An Approach for Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific...

    Science.gov (United States)

    2012-05-17

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0110] An Approach for Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment. SUMMARY: The U.S. Nuclear Regulatory...

  17. Workshop on the use of PRA methodology for the analysis of reactor events and operational data: Proceedings

    International Nuclear Information System (INIS)

    Rasmuson, D.M.

    1992-06-01

    A workshop entitled ''The Use of PRA Methodology for the Analysis of Reactor Events and Operational Data'' was held on January 29--30, 1992 in Annapolis, Maryland. Over 50 participants from the NRC, its contractors, and others participated in the meetings. During the first day, presentations were made by invited speakers to discuss issues in relevant topics. On the second day, discussion groups were held to focus on three areas: risk significance of operational events, industry risk profile and generic concerns, and risk monitoring and risk-based performance indicators. Important considerations identified from the workshop are the following: Improve the Accident Sequence Precursor models and data. Improve the SCSS and NPRDS (e.g., by adding detailed performance information on selected components, by improving narratives on failure causes). Develop risk-based performance indicators. Use risk insights to help focus trending and performance analyses of components, systems, initiators, and sequences. Improve the statistical quality of trending and performance analyses. Flag implications of special conditions (e.g., external events, containment performance) during data studies. Trend common cause and human performance using appropriate models to obtain a better understanding of the impact and causes of failure. Develop a method for producing an industry risk profile

  18. Loss of coolant accident (LOCA) analysis for McMaster Nuclear Reactor through probabilistic risk assessment (PRA)

    Energy Technology Data Exchange (ETDEWEB)

    Ha, T.; Garland, W.J. [McMaster Univ., Dept. of Engineering Physics, Hamilton, Ontario (Canada)]. E-mail: hats@mcmaster.ca

    2006-07-01

    A probabilistic risk assessment (PRA) was conducted for the loss of coolant accident (LOCA) sequence in the McMaster Nuclear Reactor (MNR). A level 1 PRA was completed including event sequence modeling, system modeling, and quantification. To support the quantification of the accident sequence identified, data analysis using the Bayesian method and human reliability analysis (HRA) using the ASEP approach were performed. Since human performance in research reactors is significantly different from that in power reactors, a different time-oriented HRA model was proposed and applied for the estimation of the human error probability (HEP) of core relocation. This HEP estimate was less than that by the ASEP approach by a factor of about 2. These two HEP estimates were used for sensitivity analysis, and modeling uncertainty in the PRA models was quantified. This showed the necessity of appropriate human reliability models in PRA for research reactors. This method could be implemented for the operators' actions which require extensive manual execution with little cognitive load, as might be the case for some maintenance operations in power reactors. (author)

  19. "VEM PRA RUA": THE POLITICAL AND THE POLITICS ON THE WEB

    Directory of Open Access Journals (Sweden)

    Benedito Fernando Pereira

    2014-12-01

    Full Text Available Considering the political and the social division of senses, this paper seeks to check how is the process of signification in a society increasingly challenged by electronic discourse and the ways in which political and policy find themselves affected by it. In order do that, we make the analysis of discursive statements “vem pra rua” and “somos a rede social” that were present in banners and posters in street protests in Brazil in 2013, which were organized and delivered, in large part, by virtual means. We observed that such utterances go through a process of appropriation and re-signification, with shifting meanings that run of market logic, go to the social politics and go back to the market logic. We had also observed how the urban environment is affected by the electronic discourse that now constitutes the ways it makes sense.

  20. Validation needs of seismic probabilistic risk assessment (PRA) methods applied to nuclear power plants

    International Nuclear Information System (INIS)

    Kot, C.A.; Srinivasan, M.G.; Hsieh, B.J.

    1985-01-01

    An effort to validate seismic PRA methods is in progress. The work concentrates on the validation of plant response and fragility estimates through the use of test data and information from actual earthquake experience. Validation needs have been identified in the areas of soil-structure interaction, structural response and capacity, and equipment fragility. Of particular concern is the adequacy of linear methodology to predict nonlinear behavior. While many questions can be resolved through the judicious use of dynamic test data, other aspects can only be validated by means of input and response measurements during actual earthquakes. A number of past, ongoing, and planned testing programs which can provide useful validation data have been identified, and validation approaches for specific problems are being formulated

  1. Use of PRA techniques to optimize the design of the IRIS nuclear power plant

    International Nuclear Information System (INIS)

    Muhlheim, M.D.; Cletcher, J.W. II

    2003-01-01

    True design optimization of a plants inherent safety and performance characteristics results when a probabilistic risk assessment (PRA) is integrated with the plant-level design process. This is the approach being used throughout the design of the International Reactor Innovative and Secure (IRIS) nuclear power plant to maximize safety. A risk-based design optimization tool employing a 'one-button' architecture is being developed by the Oak Ridge National Laboratory to evaluate design changes; new modeling approaches, methods, or theories modeling uncertainties and completeness; physical assumptions; and data changes on component, cabinet, train, and system bases. Unlike current PRAs, the one-button architecture allows components, modules, and data to be interchanged at will with the probabilistic effect immediately apparent. Because all of the current and previous design, and data sets are available via the one-button architecture, the safety ramifications of design options are evaluated, feedback on design alternatives is immediate, and true optimization and understanding can be achieved. Thus, for the first time, PRA analysts and designers can easily determine the probabilistic implications of different design configurations and operating conditions in various combinations for the entire range of initiating events. The power of the one-button architecture becomes evident by the number of design alternatives that can be evaluated C11 component choices yielded 160 design alternatives. Surprisingly, the lessons learned can be counter-intuitive and significant. For example, one of the alternative designs for IRIS evaluated via this architecture revealed that because of common-cause failure probabilities, using the most reliable components actually decreased systems' reliability. (author)

  2. Hubungan antara Pengetahuan, Sikap, dan Perilaku terhadap Pemeliharaan Kebersihan Gigi dan Mulut dengan Status Kesehatan Periodontal Pra Lansia di Posbindu Kecamatan Indihiang Kota Tasikmalaya

    Directory of Open Access Journals (Sweden)

    Culia Rahayu

    2014-06-01

    Full Text Available Proses penuaan merupakan salah satu faktor sistemik yang mempengaruhi respon tubuh terhadap terjadinya penyakit periodontal. Penelitian ini bertujuan untuk mengetahui hubungan antara pengetahuan, sikap dan perilaku terhadap pemeliharaan kebersihan gigi dan mulut dengan status kesehatan periodontal pra lansia. Penelitian ini merupakan penelitian non eksperimental, dengan rancangan cross sectional. Subjek penelitian berjumlah 225 orang pra lansia dari 9 Posbindu di Kecamatan Indihiang Tasikmalaya, yang diambil dengan cara purposive sampling. Variabel pengaruh terdiri dari pengetahuan, sikap dan perilaku terhadap pemeliharaan kebersihan gigi dan mulut. Variabel pengetahuan diukur menggunakan kuesioner tertutup dengan pilihan jawaban benar atau salah. Variabel sikap dan perilaku diukur menggunakan kuesioner dibuat menurut skala Likert. Kuesioner telah diuji validitas (koefisien korelasi ≥ 0,30 dan uji reliabilitas (alpha cronbach >0,60. Variabel terpengaruh adalah status kesehatan periodontal yang diukur menggunakan indeks CPITN. Analisa data menggunakan analisis korelasi dan regresi berganda. Hasil analisis regresi berganda menunjukkan bahwa variabel pengetahuan, sikap dan perilaku terhadap pemeliharaan kebersihan gigi dan mulut mempunyai hubungan signifikan terhadap status kesehatan periodontal (F =30,681 dan p =0,001, dan memberikan kontribusi pengaruh sebesar 29,4% (R² = 0,294 terhadap status kesehatan periodontal. Perilaku terhadap pemeliharaan kebersihan gigi dan mulut memberikan kontribusi pengaruh paling besar terhadap status kesehatan periodontal yaitu sebesar 6,9%. Kesimpulan dari penelitian ini adalah semakin baik pengetahuan, sikap dan perilaku terhadap pemeliharaan kebersihan gigi dan mulut, semakin baik status kesehatan periodontal pra lansia. Perilaku terhadap pemeliharaan kebersihan gigi dan mulut memberikan kontribusi pengaruh paling besar terhadap status kesehatan periodontal pra lansia. Correlation Between Knowledge, Attitude

  3. Evaluation of safety issues on newly regulated nuclear power plant by tsunami-level 1 PRA

    International Nuclear Information System (INIS)

    Tsuji, Yutaro; Miwa, Shuichiro; Mori, Michitsugu

    2014-01-01

    The tsunami caused by the Great East Japan Earthquake triggered severe accidents involving the units 1 to 4 at the Fukushima Dai-ichi nuclear power station (NPS). In order to re-operate existing nuclear power plants it should be necessary to reduce the core damage frequency on risk by tsunami. In this work, effects of the off-site power supply installation on resuming operation of nuclear power plants were investigated by utilizing the Tsunami-Level 1 Probability Risk Assessment (PRA). Unit 2 of the Onagawa nuclear power station, which resembled units 2 and 3 of Fukushima Dai-ichi, was selected for PRA. First, event-tree was created for the units of the Onagawa nuclear power station with the safety systems such as Emergency Core Cooling System (ECCS), investigating the plant situation at the time of the earthquake and tsunami occurrences. It was assumed that the magnitude of the tsunami was equivalent to the Great East Japan Earthquake. The accident-analytical progression-time was 36 hours, determined from the core-damage occurrence of the unit 3 of Fukushima Dai-ichi nuclear power station. Failure probabilities were calculated by the fault tree, which was created from the elements listed in the event tree. For the calculation, failure rates reported by the NUCIA (NUClear Information Archives) were primarily utilized. Then, obtained failure probabilities were embedded to the event tree. Core damage probabilities were evaluated by calculating success and failure rates for each accidental progression and scenarios. Restoration of the failed equipment and machineries was not considered in the analysis. Installation of the power supply vehicles at the nuclear power plant site reduced the core damage probability from 2.58×10 -6 to 8.56×10 -7 . However, continued addition of the power supply vehicles could not lower the core damage probability further more. In the case of Unit 2 of Onagawa nuclear power station, there could be a limit to lower the core damage

  4. Comparison of SKIFS 2004:1 and Tillsynshandbok PSA against the ASME PRA Standard and European requirements on PSA

    International Nuclear Information System (INIS)

    Hellstroem, Per

    2005-04-01

    Requirements on PSA for risk informed applications are expressed in different international documents. The ASME PRA standard published in spring 2002 is one such document, PSA requirements are also expressed in the European Utility Requirements (EUR) for new reactors. The Swedish PSA requirements are provided in the Swedish regulators (SKI) statutes SKIFS 2004:1. SKI also has a review handbook for PSA activities (SKI report 2003:48). The review handbook is a support during review of the utilities PSA activities and the PSAs themselves. The review handbook expresses SKIs expectations by providing so called important aspects for both the PSA work and the PSAs, A comparison of SKIFS requirements and the important aspects in the Review handbook, on one side, and the requirements on PSA in EUR and ASME on the other side, is presented. The comparison shows a large difference in the level of detail in the different documents, where ASME is most detailed and specific. This is expected since the SKI review handbook not is a 'PSA guide' in the same way as the ASME PRA standard. A direct comparison of the ASME PRA standard requirements with the important aspects in the review handbook cannot answer the question which ASME capacity level that is achieved by a PSA meeting all important aspects. The conclusion is that it is not likely to achieve capacity level 2 and 3, since very few ASME level 3 attributes are explicitly expressed as important aspects, though many are expressed in general terms. The review handbook important aspects that are most similar to the ASME capacity level 1 attributes are initiating events, sequence analysis, and system analysis while less similarity is found for analysis of operator actions data analysis, quantification and containment analysis (level 2). Less similarity is found for capacity level 2 and 3. However, the number of additional ASME attributes on capacity level 2 and 3 are few. There are also important aspects in the review handbook that

  5. Analysis of climate and anthropogenic impacts on runoff in the Lower Pra River Basin of Ghana.

    Science.gov (United States)

    Awotwi, Alfred; Anornu, Geophrey Kwame; Quaye-Ballard, Jonathan; Annor, Thompson; Forkuo, Eric Kwabena

    2017-12-01

    The Lower Pra River Basin (LPRB), located in the forest zone of southern Ghana has experienced changes due to variability in precipitation and diverse anthropogenic activities. Therefore, to maintain the functions of the ecosystem for water resources management, planning and sustainable development, it is important to differentiate the impacts of precipitation variability and anthropogenic activities on stream flow changes. We investigated the variability in runoff and quantified the contributions of precipitation and anthropogenic activities on runoff at the LPRB. Analysis of the precipitation-runoff for the period 1970-2010 revealed breakpoints in 1986, 2000, 2004 and 2010 in the LPRB. The periods influenced by anthropogenic activities were categorized into three periods 1987-2000, 2001-2004 and 2005-2010, revealing a decrease in runoff during 1987-2000 and an increase in runoff during 2001-2004 and 2005-2010. Assessment of monthly, seasonal and annual runoff depicted a significant increasing trend in the runoff time series during the dry season. Generally, runoff increased at a rate of 9.98 × 10 7 m 3 yr -1 , with precipitation variability and human activities contributing 17.4% and 82.3% respectively. The dominant small scale alluvial gold mining activity significantly contributes to the net runoff variability in LPRB.

  6. Application of FIVE methodology in probabilistic risk assessment (PRA) of fire events

    International Nuclear Information System (INIS)

    Lopez Garcia, F.J.; Suarez Alonso, J.; Fiolamengual, M.J.

    1993-01-01

    This paper reflects the experience acquired during the process of evaluation and updating of the fire analysis within the Cofrentes NPP PRA. It determines which points are the least precise, either because of their greater uncertainty or because of their excessive conservatism, as well as the subtasks which have involved a larger work load and could be simplified. These aspects are compared with the steps followed in methodology FIVE (Fire Vulnerability Evaluation Methodology) to assess whether application of this methodology would optimize the task, by making it more systematic and realistic and reducing uncertainties. On the one hand, the FIVE methodology does not have the scope sufficient to carry out a quantitative risk evaluation, but it can easily be complemented -without detriment to its systematic nature- by quantifying core damage in significant areas. On the other hand, certain issues such as definition of the fire growth software program which has to be used, are still not fully closed. Nevertheless, the conclusions derived from this assessment are satisfactory, since it is considered that this methodology would serve to unify the criteria and data of the analysis of fire-induced risks, providing a progressive screening method which would considerably simplify the task. (author)

  7. Value impact analysis utilizing PRA techniques combined with a hybrid plant model

    International Nuclear Information System (INIS)

    Edson, J.L.; Stillwell, D.W.

    1989-01-01

    A value impact analysis (VIA) has been performed by the INEL to support a NRC Regulatory Analysis for resolution of Generic Issue (GI) 29, Bolting Degradation or Failure in Nuclear Power Plants. A VIA for replacing the reactor coolant pressure boundary (RCPB) bolts of BWRs and PWRs was previously prepared by Pacific Northwest Laboratories in 1985 under instructions limiting the VIA to the potential for failure of primary pressure boundary bolting. Subsequently the INEL was requested to perform a VIA that included non primary systems and component support bolts to be compatible with the resolution of the broader issue. Because the initial list of systems and bolting applications that could be included in the VIA was very large, including them all in the VIA would likely result in analyzing some that have little if any effect on public risk. This paper discusses how PRA techniques combined with a hybrid plant model were used to determine which bolts have the potential to be significant contributors to public risk if they were to fail, and therefore were included in the VIA

  8. PRA Procedures Guide: a guide to the performance of probabilistic risk assessments for nuclear power plants. Final report, Volume 1 - Chapters 1-8

    International Nuclear Information System (INIS)

    1983-01-01

    This document, the Probabilistic Risk Assessment (PRA) Procedures Guide, is intended to provide an overview of the risk-assessment field as it exists today and to identify acceptable techniques for the systematic assessment of the risk from nuclear power plants. Topics discussed include: organization of PRA; accident-sequence definition and system modeling; human-reliability analysis; data-base development; accident-sequence quantification; physical processes of core-melt accidents; and radionuclide release and transport

  9. Interaction of CREDO [Centralized Reliability Data Organization] with the EBR-II [Experimental Breeder Reactor II] PRA [probabilistic risk assessment] development

    International Nuclear Information System (INIS)

    Smith, M.S.; Ragland, W.A.

    1989-01-01

    The National Academy of Sciences review of US Department of Energy (DOE) class 1 reactors recommended that the Experimental Breeder Reactor II (EBR-II), operated by Argonne National Laboratory (ANL), develop a level 1 probabilistic risk assessment (PRA) and make provisions for level 2 and level 3 PRAs based on the results of the level 1 PRA. The PRA analysis group at ANL will utilize the Centralized Reliability Data Organization (CREDO) at Oak Ridge National Laboratory to support the PRA data needs. CREDO contains many years of empirical liquid-metal reactor component data from EBR-II. CREDO is a mutual data- and cost-sharing system sponsored by DOE and the Power Reactor and Nuclear Fuels Development Corporation of Japan. CREDO is a component based data system; data are collected on components that are liquid-metal specific, associated with a liquid-metal environment, contained in systems that interface with liquid-metal environments, or are safety related for use in reliability/availability/maintainability (RAM) analyses of advanced reactors. The links between the EBR-II PRA development effort and the CREDO data collection at EBR-II extend beyond the sharing of data. The PRA provides a measure of the relative contribution to risk of the various components. This information can be used to prioritize future CREDO data collection activities at EBR-II and other sites

  10. Application of multivariate statistical technique for hydrogeochemical assessment of groundwater within the Lower Pra Basin, Ghana

    Science.gov (United States)

    Tay, C. K.; Hayford, E. K.; Hodgson, I. O. A.

    2017-06-01

    Multivariate statistical technique and hydrogeochemical approach were employed for groundwater assessment within the Lower Pra Basin. The main objective was to delineate the main processes that are responsible for the water chemistry and pollution of groundwater within the basin. Fifty-four (54) (No) boreholes were sampled in January 2012 for quality assessment. PCA using Varimax with Kaiser Normalization method of extraction for both rotated space and component matrix have been applied to the data. Results show that Spearman's correlation matrix of major ions revealed expected process-based relationships derived mainly from the geochemical processes, such as ion-exchange and silicate/aluminosilicate weathering within the aquifer. Three main principal components influence the water chemistry and pollution of groundwater within the basin. The three principal components have accounted for approximately 79% of the total variance in the hydrochemical data. Component 1 delineates the main natural processes (water-soil-rock interactions) through which groundwater within the basin acquires its chemical characteristics, Component 2 delineates the incongruent dissolution of silicate/aluminosilicates, while Component 3 delineates the prevalence of pollution principally from agricultural input as well as trace metal mobilization in groundwater within the basin. The loadings and score plots of the first two PCs show grouping pattern which indicates the strength of the mutual relation among the hydrochemical variables. In terms of proper management and development of groundwater within the basin, communities, where intense agriculture is taking place, should be monitored and protected from agricultural activities. especially where inorganic fertilizers are used by creating buffer zones. Monitoring of the water quality especially the water pH is recommended to ensure the acid neutralizing potential of groundwater within the basin thereby, curtailing further trace metal

  11. Plant-specific responses to zinc contamination in a semi-field lysimeter and on hydroponics

    International Nuclear Information System (INIS)

    Bernhard, Roland; Verkleij, Jos A.C.; Nelissen, Hans J.M.; Vink, Jos P.M.

    2005-01-01

    The species Agrostis stolonifera, Brassica napus and Trifolium repens representing different ecological strategies, were selected to study the effect of Zn contamination on Zn tolerance, uptake and accumulation patterns. Parallel tests were carried out with increasing concentrations of Zn in a semi-field lysimeter and hydroponics in the climate chamber. A significant reduction in biomass production or root length and an increase in shoot Zn concentration was observed for all species at increasing external Zn concentrations. However, shoot biomass production, Zn tolerance and Zn accumulation differed significantly among the tested species. The results in both experimental set-ups were quite similar concerning Zn tolerance and accumulation and improved the validity of the findings. The rather specific responses of the different plant species to Zn contamination interfere with the more generic approach used in risk assessment studies. Maximum amounts of Zn in shoot are not likely to cause a risk to herbivores. - Effects of Zn contamination showed different responses in uptake and accumulation patterns of site-specific plant species, which were similar in a semi-field experiment and under controlled conditions

  12. Plant-specific responses to zinc contamination in a semi-field lysimeter and on hydroponics

    Energy Technology Data Exchange (ETDEWEB)

    Bernhard, Roland [Department of Ecology and Physiology of Plants, Vrije Universiteit, De Boelelaan 1085, NL-1081 HV Amsterdam (Netherlands); Verkleij, Jos A.C. [Department of Ecology and Physiology of Plants, Vrije Universiteit, De Boelelaan 1085, NL-1081 HV Amsterdam (Netherlands)]. E-mail: jos.verkleij@falw.vu.nl; Nelissen, Hans J.M. [Department of Ecology and Physiology of Plants, Vrije Universiteit, De Boelelaan 1085, NL-1081 HV Amsterdam (Netherlands); Vink, Jos P.M. [Department of Chemistry and Ecotoxicology, RIZA, PO Box 17, NL-8200 AA Lelystad (Netherlands)

    2005-11-15

    The species Agrostis stolonifera, Brassica napus and Trifolium repens representing different ecological strategies, were selected to study the effect of Zn contamination on Zn tolerance, uptake and accumulation patterns. Parallel tests were carried out with increasing concentrations of Zn in a semi-field lysimeter and hydroponics in the climate chamber. A significant reduction in biomass production or root length and an increase in shoot Zn concentration was observed for all species at increasing external Zn concentrations. However, shoot biomass production, Zn tolerance and Zn accumulation differed significantly among the tested species. The results in both experimental set-ups were quite similar concerning Zn tolerance and accumulation and improved the validity of the findings. The rather specific responses of the different plant species to Zn contamination interfere with the more generic approach used in risk assessment studies. Maximum amounts of Zn in shoot are not likely to cause a risk to herbivores. - Effects of Zn contamination showed different responses in uptake and accumulation patterns of site-specific plant species, which were similar in a semi-field experiment and under controlled conditions.

  13. PIP-II Cryogenic System and the evolution of Superfluid Helium Cryogenic Plant Specifications

    Energy Technology Data Exchange (ETDEWEB)

    Chakravarty, Anindya [Fermilab; Rane, Tejas [Fermilab; Klebaner, Arkadiy [Fermilab

    2017-07-06

    The PIP-II cryogenic system consists of a Superfluid Helium Cryogenic Plant (SHCP) and a Cryogenic Distribution System (CDS) connecting the SHCP to the Superconducting (SC) Linac consisting of 25 cryomodules. The dynamic heat load of the SC cavities for continuous wave (CW) as well as pulsed mode of operation has been listed out. The static heat loads of the cavities along with the CDS have also been discussed. Simulation study has been carried out to compute the supercritical helium (SHe) flow requirements for each cryomodule. Comparison between the flow requirements of the cryomodules for the CW and pulsed modes of operation have also been made. From the total computed heat load and pressure drop values in the CDS, the basic specifications for the SHCP, required for cooling the SC Linac, have evolved.

  14. Plant specific risk informed decision making -a vision for Indian PHWR

    International Nuclear Information System (INIS)

    Guptan, Rajee; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    The objective of Nuclear Power Plant (NPP) safety is to ensure and demonstrate that the risk from NPP to public and plant personnel is acceptably low. As a supplement to the deterministic approach, use of probabilistic techniques has been gaining grounds. Probabilistic Safety Assessment (PSA) is a popular international practice to calculate plant risk to the public, environment and plant personnel, in the event of an accident taking place in the plant. The risk posed by Nuclear Reactors to the Public at large is a very important issue in the public acceptance of a Nuclear Power Programme in any country. Risk Definition, generally accepted at present as the measure of possibility for an accidental event and severity of its effects to occur, simultaneously comprises both the probability (frequency) of potential damage occurrence and extent of this damage. NPCIL' s vision is to provide safe, reliable and cost effective energy to the nation by ensuring safe operation of the plants, limiting radiation exposure to plant personnel and public within prescribed limits. To achieve this vision our mission is to enhance the technical competency, resources and the awareness towards improved safety culture specific to Probabilistic Safety Assessment for applying PSA Studies to Risk Informed Decision making. This mission translates into the goal of completion of full scope PSA, with the co-operation and synergetic efforts of the Head quarters and Operating Station experts. NPCIL will then be self sufficient in applying Probabilistic Studies in Risk Informed Decision making to minimize risk and back fitting design changes to optimize the existing design and operating practices, thus providing for safe, reliable and cost effective energy to the nation. (author)

  15. Case study on the use of PSA methods: Backfitting decisions

    International Nuclear Information System (INIS)

    1991-04-01

    This case study illustrates the process of using probabilistic risk assessment (PRA) method to evaluate proposed backfits of nuclear power plants (NPP), which are intended to enhance the plant safety by improving equipment operability. Some examples of situations in which PRA techniques have been used to address backfit issues at operating NPPs are summarized. 2 refs, 5 figs, 4 tabs

  16. Longitudinální studium lidského vývoje: historie, výsledky a perspektivy pražské a brněnské studie celoživotního vývoje člověka

    Czech Academy of Sciences Publication Activity Database

    Blatný, Marek; Kebza, V.

    2011-01-01

    Roč. 55, č. 5 (2011), s. 422-432 ISSN 0009-062X R&D Project s: GA ČR GAP407/10/2410 Institutional research plan: CEZ:AV0Z70250504 Keywords : life -span development * longitudinal study * optimal development * personality * well-being * human strenghts Subject RIV: AN - Psychology Impact factor: 0.087, year: 2011

  17. DCD – a novel plant specific domain in proteins involved in development and programmed cell death

    Directory of Open Access Journals (Sweden)

    Doerks Tobias

    2005-07-01

    Full Text Available Abstract Background Recognition of microbial pathogens by plants triggers the hypersensitive reaction, a common form of programmed cell death in plants. These dying cells generate signals that activate the plant immune system and alarm the neighboring cells as well as the whole plant to activate defense responses to limit the spread of the pathogen. The molecular mechanisms behind the hypersensitive reaction are largely unknown except for the recognition process of pathogens. We delineate the NRP-gene in soybean, which is specifically induced during this programmed cell death and contains a novel protein domain, which is commonly found in different plant proteins. Results The sequence analysis of the protein, encoded by the NRP-gene from soybean, led to the identification of a novel domain, which we named DCD, because it is found in plant proteins involved in development and cell death. The domain is shared by several proteins in the Arabidopsis and the rice genomes, which otherwise show a different protein architecture. Biological studies indicate a role of these proteins in phytohormone response, embryo development and programmed cell by pathogens or ozone. Conclusion It is tempting to speculate, that the DCD domain mediates signaling in plant development and programmed cell death and could thus be used to identify interacting proteins to gain further molecular insights into these processes.

  18. Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants. Specific Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    The objective of this Safety Guide is to provide recommendations for meeting the IAEA safety requirements in performing or managing a level 2 probabilistic safety assessment (PSA) project for a nuclear power plant; thus it complements the Safety Guide on level 1 PSA. One of the aims of this Safety Guide is to promote a standard framework, standard terms and a standard set of documents for level 2 PSAs to facilitate regulatory and external peer review of their results. It describes all elements of the level 2 PSA that need to be carried out if the starting point is a fully comprehensive level 1 PSA. Contents: 1. Introduction; 2. PSA project management and organization; 3. Identification of design aspects important to severe accidents and acquisition of information; 4. Interface with level 1 PSA: Grouping of sequences; 5. Accident progression and containment analysis; 6. Source terms for severe accidents; 7. Documentation of the analysis: Presentation and interpretation of results; 8. Use and applications of the PSA; Annex I: Example of a typical schedule for a level 2 PSA; Annex II: Computer codes for simulation of severe accidents; Annex III: Sample outline of documentation for a level 2 PSA study.

  19. The use of plant-specific pyrolysis products as biomarkers in peat deposits

    Science.gov (United States)

    Schellekens, Judith; Bradley, Jonathan A.; Kuyper, Thomas W.; Fraga, Isabel; Pontevedra-Pombal, Xabier; Vidal-Torrado, Pablo; Abbott, Geoffrey D.; Buurman, Peter

    2015-09-01

    Peatlands are archives of environmental change that can be driven by climate and human activity. Proxies for peatland vegetation composition provide records of (local) environmental conditions that can be linked to both autogenic and allogenic factors. Analytical pyrolysis offers a molecular fingerprint of peat, and thereby a suite of environmental proxies. Here we investigate analytical pyrolysis as a method for biomarker analysis. Pyrolysates of 48 peatland plant species were compared, comprising seventeen lichens, three Sphagnum species, four non-Sphagnum mosses, eleven graminoids (Cyperaceae, Juncaceae, Poaceae), five Ericaceae and six species from other families. This resulted in twenty-one potential biomarkers, including new markers for lichens (3-methoxy-5-methylphenol) and graminoids (ferulic acid methyl ester). The potential of the identified biomarkers to reconstruct vegetation composition is discussed according to their depth records in cores from six peatlands from boreal, temperate and tropical biomes. The occurrence of markers for Sphagnum, graminoids and lichens in all six studied peat deposits indicates that they persist in peat of thousands of years old, in different vegetation types and under different conditions. In order to facilitate the quantification of biomarkers from pyrolysates, typically expressed as proportion (%) of the total quantified pyrolysis products, an internal standard (5-α-androstane) was introduced. Depth records of the Sphagnum marker 4-isopropenylphenol from the upper 3 m of a Sphagnum-dominated peat, from samples analysed with and without internal standard showed a strong positive correlation (r2 = 0.72, P use of analytical pyrolysis in biomarker research by avoiding quantification of a high number of products.

  20. Recovery actions in PRA [probabilistic risk assessment] for the Risk Methods Integration and Evaluation Program (RMIEP): Volume 1, Development of the data-based method

    International Nuclear Information System (INIS)

    Weston, L.M.; Whitehead, D.W.; Graves, N.L.

    1987-06-01

    In a probabilistic risk assessment (PRA) for a nuclear power plant, the analyst identifies a set of potential core damage events consisting of equipment failures and human errors and their estimated probabilities of occurrence. If operator recovery from an event within some specified time is considered, then the probability of this recovery can be included in the PRA. This report provides PRA analysts with an improved methodology for including recovery actions in a PRA. A recovery action can be divided into two distinct phases: a Diagnosis Phase (realizing that there is a problem with a critical parameter and deciding upon the correct course of action) and an Action Phase (physically accomplishing the required action). In this methodology, simulator data are used to estimate recovery probabilities for the diagnosis phase. Different time-reliability curves showing the probability of failure of diagnosis as a function of time from the compelling cue for the event are presented. These curves are based on simulator exercises, and the actions are grouped based upon their operational similarities. This is an improvement over existing diagnosis models that rely greatly upon subjective judgment to obtain such estimates. The action phase is modeled using estimates from available sources. The methodology also includes a recommendation on where and when to apply the recovery action in the PRA process

  1. KONSELING PRA NIKAH DALAM MEWUJUDKAN KELUARGA BAHAGIA (STUDI PENDEKATAN HUMANISTIK CARL R. ROGERS)

    OpenAIRE

    Mubasyaroh Mubasyaroh

    2017-01-01

    Pernikahan merupakan sunnatullah, karena semua yang ada di dunia ini diciptakan berpasang-pasangan. Sebagaimana difirmankan Allah SWT dalam QS.Adza-Dzariyat: 47-49. “Dan langit itu Kami bangun dengan kekuasaan (Kami) dan seseungguhnya Kami benar-benar meluaskannya. Dan Bumi itu Kami hamparkan maka sebaik-baik yang menghamparkan (adalah Kami). Dan segala sesuatu Kami ciptakan berpasang-pasangan supaya kamu mengingat akan kebesaran Allah” ( Adz-Dzariyat:47-49). Pada tulisan ini penulis akan men...

  2. Advanced methods for a probabilistic safety analysis of fires. Development of advanced methods for performing as far as possible realistic plant specific fire risk analysis (fire PSA)

    International Nuclear Information System (INIS)

    Hofer, E.; Roewekamp, M.; Tuerschmann, M.

    2003-07-01

    In the frame of the research project RS 1112 'Development of Methods for a Recent Probabilistic Safety Analysis, Particularly Level 2' funded by the German Federal Ministry of Economics and Technology (BMWi), advanced methods, in particular for performing as far as possible realistic plant specific fire risk analyses (fire PSA), should be developed. The present Technical Report gives an overview on the methodologies developed in this context for assessing the fire hazard. In the context of developing advanced methodologies for fire PSA, a probabilistic dynamics analysis with a fire simulation code including an uncertainty and sensitivity study has been performed for an exemplary scenario of a cable fire induced by an electric cabinet inside the containment of a modern Konvoi type German nuclear power plant taking into consideration the effects of fire detection and fire extinguishing means. With the present study, it was possible for the first time to determine the probabilities of specified fire effects from a class of fire events by means of probabilistic dynamics supplemented by uncertainty and sensitivity analyses. The analysis applies a deterministic dynamics model, consisting of a dynamic fire simulation code and a model of countermeasures, considering effects of the stochastics (so-called aleatory uncertainties) as well as uncertainties in the state of knowledge (so-called epistemic uncertainties). By this means, probability assessments including uncertainties are provided to be used within the PSA. (orig.) [de

  3. Plant-specific Histone Deacetylases HDT½ Regulate GIBBERELLIN 2-OXIDASE 2 Expression to Control Arabidopsis Root Meristem Cell Number

    KAUST Repository

    Li, Huchen

    2017-08-31

    Root growth is modulated by environmental factors and depends on cell production in the root meristem (RM). New cells in the meristem are generated by stem cells and transit-amplifying cells, which together determine RM cell number. Transcription factors and chromatin-remodelling factors have been implicated in regulating the switch from stem cells to transit-amplifying cells. Here we show that two Arabidopsis thaliana paralogs encoding plant-specific histone deacetylases, HDT1 and HDT2, regulate a second switch from transit-amplifying cells to expanding cells. Knockdown of HDT½ (hdt1,2i) results in an earlier switch and causes a reduced RM cell number. Our data show that HDT½ negatively regulate the acetylation level of the C19-GIBBERELLIN 2-OXIDASE 2 (GA2ox2) locus and repress the expression of GA2ox2 in the RM and elongation zone. Overexpression of GA2ox2 in the RM phenocopies the hdt1,2i phenotype. Conversely, knockout of GA2ox2 partially rescues the root growth defect of hdt1,2i. These results suggest that by repressing the expression of GA2ox2, HDT½ likely fine-tune gibberellin metabolism and they are crucial for regulating the switch from cell division to expansion to determine RM cell number. We propose that HDT½ function as part of a mechanism that modulates root growth in response to environmental factors.

  4. Sequence variations and protein expression levels of the two immune evasion proteins Gpm1 and Pra1 influence virulence of clinical Candida albicans isolates.

    Science.gov (United States)

    Luo, Shanshan; Hipler, Uta-Christina; Münzberg, Christin; Skerka, Christine; Zipfel, Peter F

    2015-01-01

    Candida albicans, the important human fungal pathogen uses multiple evasion strategies to control, modulate and inhibit host complement and innate immune attack. Clinical C. albicans strains vary in pathogenicity and in serum resistance, in this work we analyzed sequence polymorphisms and variations in the expression levels of two central fungal complement evasion proteins, Gpm1 (phosphoglycerate mutase 1) and Pra1 (pH-regulated antigen 1) in thirteen clinical C. albicans isolates. Four nucleotide (nt) exchanges, all representing synonymous exchanges, were identified within the 747-nt long GPM1 gene. For the 900-nt long PRA1 gene, sixteen nucleotide exchanges were identified, which represented synonymous, as well as non-synonymous exchanges. All thirteen clinical isolates had a homozygous exchange (A to G) at position 73 of the PRA1 gene. Surface levels of Gpm1 varied by 8.2, and Pra1 levels by 3.3 fold in thirteen tested isolates and these differences influenced fungal immune fitness. The high Gpm1/Pra1 expressing candida strains bound the three human immune regulators more efficiently, than the low expression strains. The difference was 44% for Factor H binding, 51% for C4BP binding and 23% for plasminogen binding. This higher Gpm1/Pra1 expressing strains result in enhanced survival upon challenge with complement active, Factor H depleted human serum (difference 40%). In addition adhesion to and infection of human endothelial cells was increased (difference 60%), and C3b surface deposition was less effective (difference 27%). Thus, variable expression levels of central immune evasion protein influences immune fitness of the human fungal pathogen C. albicans and thus contribute to fungal virulence.

  5. Role of the plant-specific endoplasmic reticulum stress-inducible gene TIN1 in the formation of pollen surface structure in Arabidopsis thaliana

    KAUST Repository

    Iwata, Yuji; Nishino, Tsuneyo; Iwano, Megumi; Takayama, Seiji; Koizumi, Nozomu

    2012-01-01

    Accumulation of unfolded proteins in the endoplasmic reticulum (ER) of eukaryotic cells triggers the transcriptional activation of ER-resident molecular chaperones and folding enzymes to maintain cellular homeostasis. This process is known as the ER stress response or the unfolded protein response. We have identified tunicamycin induced 1 (TIN1), a plant-specific ER stress-inducible Arabidopsis thaliana gene. The TIN1 protein is localized in the ER; however, its molecular function has yet to be clarified. In this study, we performed functional analysis of TIN1 in planta. RT-PCR analysis showed that TIN1 is highly expressed in pollen. Analysis using the β-glucuronidase reporter gene demonstrated that the TIN1 promoter is active throughout pollen development, peaking at the time of flowering and in an ovule of an open flower. Although a T-DNA insertion mutant of TIN1 grows normally under ambient laboratory conditions, abnormal pollen surface morphology was observed under a scanning electron microscope. Based on the current and previous observations, a possible physiological function of TIN1 during pollen development is discussed. © 2012 The Japanese Society for Plant Cell and Molecular Biology.

  6. Karakteristik Reverse Transcriptase Gen Polymerase Virus Hepatitis B Pada Penderita Hepatitis B Kronis Asimptomatik Pra-Pengobatan

    Directory of Open Access Journals (Sweden)

    Turyadi Turyadi

    2018-01-01

    Full Text Available Abstrak Antiviral nucleos(tide analogue (NUCs merupakan pengobatan utama pada hepatitis B kronis (HBK. Pemberian jangka panjang dinilai cukup efektif menekan progresivitas penyakit, namun dapat menimbulkan mutasi resisten. Studi ini melihat karakteristik gen polimerase yang berkaitan dengan resistensi NUCs pada penderita HBK asimptomatik pra-pengobatan. Penelitian dilakukan di Laboratorium Hepatitis, Lembaga Biologi Molekuler Eijkman, Jakarta. Sebanyak 38 sampel individu dengan hepatitis B surface antigen (HBsAg positif dikarakterisasi dengan PCR-sekuensing. Genotipe dan subtipe ditentukan berdasarkan sekuens HBsAg. Sebanyak 37 (97,4% sampel menunjukkan mutasi rtQ238H/N dan satu sampel wildtype. Sebanyak 23 (62,2% memiliki mutasi rtQ238H, 10 (27,0% rtQ238N, dan empat (10,8% dengan mutasi ganda rtA194T dan rtQ238H. Genotipe B ditemukan pada 26 (68,4% sampel, genotipe C pada 11 (28,9%, dan genotipe D pada satu (2,6% sampel. Secara statistik, mutasi rtQ238H berasosiasi dengan genotipe B (p<0,001 dan mutasi rtQ238N dengan genotipe C (p<0,001. Subtipe ayw ditemukan pada 25 (65,8% sampel, adr pada 11 (28,9%, dan adw pada dua (5,3% sampel. Sebagian besar sampel tidak menunjukkan mutasi yang berkaitan dengan resistensi NUCs, sehingga pemberian NUCs masih. Mutasi rtQ238H merupakan varian yang berkaitan dengan genotipe B dan rtQ238N dengan genotipe C. Kata kunci: virus hepatitis B; mutasi; pengobatan; polymerase.   Reverse-Transcriptase Characteristics of Hepatitis B Virus Polymerase Gene in Treatment-Naïve Asymptomatic Chronic Hepatitis B Individuals Abstract Nucleos(tide analogues (NUCs remain the main treatment for chronic hepatitis B (CHB. Long-term use of NUCs significantly reduces disease progression; however, it might lead to resistance-associated mutations. We studied characteristics of polymerase gene related to NUCs resistance in naïve hepatitis B surface antigen (HBsAg-positive individuals. The research was done at Laboratory of Hepatitis

  7. MENELAAH HUKUM WARIS PRA-ISLAM DAN AWAL ISLAM SERTA PELETAKAN DASAR-DASAR HUKUM KEWARISAN ISLAM

    Directory of Open Access Journals (Sweden)

    Asrizal Saiin

    2017-03-01

    [Dalam sejarahnya, pembagian harta warisan sudah ada sebelum Islam (pra-Islam. Adapun sistem pewarisannya adalah sistem keturunan dan sistem sebab. Pembagian harta warisan bersifat patrilinear, artinya anak-anak yang belum dewasa dan kaum perempuan tidak berhak mendapatkan harta warisan, sekalipun mereka merupakan ahli waris dari yang telah meninggal. Seseorang baru bisa mendapatkan harta apabila; adanya pertalian kerabat, janji ikatan prasetia, dan pengangkatan anak. Sementara pada masa awal Islam seseorang bisa mendapatkan harta warisan apabila; adanya pertalian kerabat, pengangkatan anak, adanya hijrah dan adanya persaudaraan. Pewarisan, baru terjadi jika ada sebab-sebab yang mengikat pewaris dengan ahli warisnya, seperti adanya perkawinan, kekerabatan, dan wala’. Adapun hal-hal yang dapat menggugurkan hak seseorang menerima warisan adalah; perbudakan, pembunuhan, berlainan agama, murtad, karena hilang tanpa berita dan berlainan negara. Sebelum pembagian warisan ada beberapa hak yang harus dipenuhi terlebih dahulu, seperti; hak yang berkaitan dengan zat harta peninggalan, biaya perawatan jenazah, pelunasan hutang dan pemberian wasiat

  8. Emergence of Participatory Rural Appraisal (PRA Technique as a Strategy towards Sustainable Development: A Sri Lankan Experience

    Directory of Open Access Journals (Sweden)

    D. N. Koralagama

    2007-10-01

    Full Text Available In this millennium all the development activities are mostly focused on sustainable development, i.e. the development which fulfils the requirements of the present without disturbing the utilization of future generation. Basically, the sustainable development deals with environmental, social, and economical initiations. In relation to these three objectives, community participation plays a key role as an effective strategy for sustainable development. Among the numerous types of participation, Participatory Rural Appraisal (PRA technique is the most relevant effective method to receive the participation. Because, it has been strengthen by bottom up approach, well defined objectives, practicable solutions, and remedies. Hence, the out come of such an event is most productive rather than a top bottom approach techniques. In fact, a PRA was practiced to develop a strategic plan for tsunami affected village – Bambaranda east, in southern province of Sri Lanka. PRA sessions were carried out during February, 2007 by the Department of Agric. Economics of Ruhuna University, Sri Lanka in collaboration with Japanese Green Resource Agency, Japan.Participatory mapping, venn diagram, matrix ranking, preference ranking, and pair - wise ranking were demonstrated to gather information from the community. The tsunami affected area, including the paddy fields, four irrigation canals were shown by the group with the help of the participatory map. Preference ranking was resulted the reconstruction of irrigation canals as the most important rehabilitation activity to recover the livelihood of villagers. Intrusion of sea water into the paddy fields was the main limitation revealed by the pair - wise ranking. The second limitation marked as unavailability of enough fertilizer and the dilapidated irrigation canals was the third that has to be solved. Matrix ranking was employed to identify the most facilitated sectors by the government and other institutes in order

  9. The Sanskrit and Arabic Sources of the Praśnatantra Attributed to Nīlakaṇṭha

    Directory of Open Access Journals (Sweden)

    Martin Gansten

    2014-12-01

    Full Text Available The highly popular Praśnatantra attributed to Nīlakaṇṭha of Kāśī (fl. late 16th century and sometimes regarded as the third volume of his Tājikanīlakaṇṭhī is shown to depend for its basic structure on an abridged Sanskrit version of the Kitāb fi l-masāʾil wa-l-aḥkām by Sahl ibn Bishr (early 9th century, apparently authored by Samarasiṃha in the 13th century, to which quotations primarily from Sanskrit astrological works in the classical Indian style have been added, resulting in a hybrid of Indian and Perso-Arabic interrogational astrology.

  10. Review of UCN 3,4 PSA model based on NEI PRA peer review process guidance, rev.0

    International Nuclear Information System (INIS)

    Yang, Joon Eon; Kang, D. I.; Kim, K. Y.; Lee, Y. H.; Jang, S. C.; Ha, J. J.; Han, S. H.; Han, S. J.; Hwang, M. J.

    2003-05-01

    Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-Based Operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-Informed In-Service Inspection (RI-ISI). However, in Korea, there have been no attempts to evaluate the quality of PSA model itself. Therefore, we cannot be sure about the quality of PSA whether or not the present PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of PSA model quality is the basis for the RIPBO. In this report, we have evaluated the quality of PSA model for Ulchin 3 and 4 units based on the NEI guidance. We, also, have derived what items are to be improved to upgrade the quality of PSA model and how it can be improved. This report can be used as the base of RIPBO work in Korea. The review result based on ASME Standard is published as the separated technical report of KAERI

  11. Evaluating the influence of plant-specific physiological parameterizations on the partitioning of land surface energy fluxes

    Science.gov (United States)

    Sulis, Mauro; Langensiepen, Matthias; Shrestha, Prabhakar; Schickling, Anke; Simmer, Clemens; Kollet, Stefan

    2015-04-01

    Vegetation has a significant influence on the partitioning of radiative forcing, the spatial and temporal variability of soil water and soil temperature. Therefore plant physiological properties play a key role in mediating and amplifying interactions and feedback mechanisms in the soil-vegetation-atmosphere continuum. Because of the direct impact on latent heat fluxes, these properties may also influence weather generating processes, such as the evolution of the atmospheric boundary layer (ABL). In land surface models, plant physiological properties are usually obtained from literature synthesis by unifying several plant/crop species in predefined vegetation classes. In this work, crop-specific physiological characteristics, retrieved from detailed field measurements, are included in the bio-physical parameterization of the Community Land Model (CLM), which is a component of the Terrestrial Systems Modeling Platform (TerrSysMP). The measured set of parameters for two typical European mid-latitudinal crops (sugar beet and winter wheat) is validated using eddy covariance measurements (sensible heat and latent heat) over multiple years from three measurement sites located in the North Rhine-Westphalia region, Germany. We found clear improvements of CLM simulations, when using the crop-specific physiological characteristics of the plants instead of the generic crop type when compared to the measurements. In particular, the increase of latent heat fluxes in conjunction with decreased sensible heat fluxes as simulated by the two new crop-specific parameter sets leads to an improved quantification of the diurnal energy partitioning. These findings are cross-validated using estimates of gross primary production extracted from net ecosystem exchange measurements. This independent analysis reveals that the better agreement between observed and simulated latent heat using the plant-specific physiological properties largely stems from an improved simulation of the

  12. Primer uticaja filtriranja slike u sistemima za praćenje ciljeva primenom termovizije / An example of image filtering in target tracking systems with thermal imagery

    Directory of Open Access Journals (Sweden)

    Zvonko M. Radosavljević

    2003-07-01

    Full Text Available U radu je dat primer primene jedne vrste niskofrekventnog filtriranja sa usrednjavanjem, koje se primenjuje u sistemima za detekciju i praćenje ciljeva u vazdušnom prostoru primenom termovizije. Date su dve metode filtriranja slike. Prva metoda koristi niskofrekventno konvoluciono filtriranje a druga usrednjavajući filtar na osnovu srednje vrednosti nivoa sivog. Ovi filtri su primenjeni u sistemima za praćenje uz pomoć infracrvenih senzora. Određivanje nivoa praga filtriranja vrši se uz pomoć statističkih osobina slike. Veoma važan korak u procesu praćenja je određivanje prozora praćenja, koji maze biti, po dimenzijama, fiksan ili adaptibilan. Pogrešna procena o postojanju cilja u prozoru može se doneti u slučaju prisustva šuma pozadine, predpojačavača, detektora, itd. Filtriranje je neophodan korak u ovim sistemima, kao značajan činilac U povećanju brzine i tačnosti praćenja. / A case of image filtering in air target detecting and tracking systems is described in this paper. Two image filtering methods are given. The first method is performed using a low pass convolving filter and the second one uses the mean value of gray level filter. The main goal of the cited filtering is implementation in IR (infra red systems. Some statistical features of the images were used for selecting the threshold level. The next step in the algorithm is the determination of a 'tracking window' that can be fixed or adaptive in size. A false estimation of a target existing in the window may be influenced by the background noise, low noise amplifier detector, etc.

  13. Presença de ovos de Toxocara spp em praças públicas da cidade de Uberlândia, Minas Gerais, Brasil Presence of Toxocara spp eggs in public squares of Uberlândia city, Minas Gerais, Brazil

    Directory of Open Access Journals (Sweden)

    Julia Maria Costa-Cruz

    1994-02-01

    Full Text Available O objetivo deste trabalho foi verificar a presença de ovos de Toxocara spp nos solos de praças públicas da cidade de Uberlândia, região do Triângulo Mineiro, no período de outubro de 1991 a janeiro de 1992. A cidade possui 89 praças distribuídas em 39 bairros. Para que se tivesse um perfil da ocorrência do parasita, foram colhidas amostras de terra e areia (quando existente de uma praça, determinada por sorteio, por bairro. As amostras de solo homogeneizadas de 5 pontos distintos das 39 praças foram colhidas em frascos plásticos e analisadas empregando-se os métodos de flutuação em solução saturada de cloreto de sódio e de solução saturada de sulfato de magnésio contendo 5% de iodeto de potássio. Para cada amostra foram realizados os dois métodos em duplicata. Os resultados mostraram estarem contaminados os solos de 9 praças (23,07%, das quais 6 localizavam-se próximas ao centro da cidade. A realização de mais de um método laboratorial permitiu a identificação do agente em maior porcentagem de locais.The objective of this study was to verify the presence of Toxocara spp eggs in the public squares ground in Uberlândia, region of Triângulo Mineiro, from October 1991 to January 1992. The city has 89 squares distributed in 39 boroughs. In order to have an outline of the parasite's occurrence, ground and sand (when existent samples were collected from one square per boroughors. The squares were determined by draw. The homogenized ground samples of distinct points of the 39 squares, were colected in plastic flasks and analysed by the methods of fluctuation in sodium chloride saturated solution and magnesium sulphate saturated solution which contained 5% of potassium iodate. Both methods were executed twice for each sample. The results showed that the ground of 9 squares (23.07% was contaminated, 6 of which were located near downtown. The execution of more than one laboratorial method permited the agent's identification

  14. Ovos de Toxocara sp. e larvas de Ancylostoma sp. em praça pública de Lavras, MG Toxocara sp. eggs and Ancylostoma sp. larva in public parks, Brazil

    Directory of Open Access Journals (Sweden)

    Antônio Marcos Guimarães

    2005-04-01

    Full Text Available Larva migrans visceral e cutânea são zoonoses parasitárias causadas pela infecção da larva de Toxocara sp. e Ancylostoma sp., respectivamente. O objetivo do estudo foi verificar a contaminação por ovos de Toxocara sp. e ovos e larvas de Ancylostoma sp. em amostras de solos coletadas de praças públicas e de áreas de recreação infantil de Lavras, Estado de Minas Gerais, por meio da técnica de centrífugo-flutuação e do método de Baermann. A ocorrência de ovos de Toxocara sp. e, ovos e larvas de Ancylostoma sp. foi observada em 69,6% (16/23 das amostras de solo coletadas de praças públicas. A contaminação somente por ovos de Ancylostoma sp. em amostras de solo coletadas em escolas/creches foi de 22,2% (4/18. A percentagem de amostras de areia coletadas de escolas/creches contaminadas somente com larvas de Ancylostoma sp. foi de 11,1% (2/18. Praças públicas são as áreas com maior risco potencial de infecção por Toxocara sp. e Ancylostoma sp. Exame coproparasitológico realizado em 174 amostras de fezes de cães observou 58% e 23%, respectivamente, com ovos de Ancylostoma sp. e Toxocara sp.Visceral and cutaneous larva migrans are parasitic zoonoses caused by the infection of larval nematodes Toxocara sp. and Ancylostoma sp. respectively. The objective of this study was to investigate the contamination by Toxocara sp. eggs and Ancylostoma sp. eggs and larva of soil samples collected from public parks and children's playground areas in state of Minas Gerais, Brazil, using both Baermann's method and centrifugal flotation technique. Toxocara sp. and Ancylostoma sp. eggs were observed in soil samples collected from public squares in 17.4% (4/23 and 69.6 (16/23 respectively. In schools and child day care settings the contamination by Ancylostoma sp. larva in sand samples was 11.1% (2/18. Public parks are settings of more potential risk of Toxocara sp. eggs and Ancylostoma sp. infection. Stool parasitology testing of 174 stool

  15. Failure cause and failure rate evaluation on pumps of BWR plants in PSA. Hypothesis testing for typical or plant specific failure rate of pumps

    International Nuclear Information System (INIS)

    Sanada, Takahiro; Nakamura, Makoto

    2009-01-01

    In support of domestic nuclear industry effort to gather and analyze failure data of components concerning nuclear power plants, Nuclear Information Archives (NUCIA) are published for useful information to help PSA. This report focuses on NUCIA pertaining to pumps in domestic nuclear power plants, and provides the reliable estimation on failure rate of pumps resulting from failure cause analysis and hypothesis testing of classified and plant specific failure rate of pumps for improving quality in PSA. The classified and plant specific failure rate of pumps are estimated by analyzing individual domestic nuclear power plant's data of 26 Boiling Water Reactors (BWRs) concerning functionally structurally classified pump failures reported from beginning of commercial operation to March 31, 2007. (author)

  16. Recent case studies and advancements in probabilistic risk assessment

    International Nuclear Information System (INIS)

    Garrick, B.J.

    1985-01-01

    During the period from 1977 to 1984, Pickard, Lowe and Garrick, Inc., had the lead in preparing several full scope probabilistic risk assessments for electric utilities. Five of those studies are discussed from the point of view of advancements and lessons learned. The objective and trend of these studies is toward utilization of the risk models by the plant owners as risk management tools. Advancements that have been made are in presentation ad documentation of the PRAs, generation of more understandable plant level information, and improvements in methodology to facilitate technology transfer. Specific areas of advancement are in the treatment of such issues as dependent failures, human interaction, and the uncertainty in the source term. Lessons learned cover a wide spectrum and include the importance of plant specific models for meaningful risk management, the role of external events in risk, the sensitivity of contributors to choice of risk index, and the very important finding that the public risk is extremely small. The future direction of PRA is to establish less dependence on experts for in-plant application. Computerizing the PRAs such that they can be accessed on line and interactively is the key

  17. Pra que time ele joga?: a produção da identidade homossexual em um vídeo educativo

    Directory of Open Access Journals (Sweden)

    Nilson Fernandes Dinis

    2009-01-01

    Full Text Available This work aims to analyze the discourse about homosexuality by means of a research with undergraduate students of Physical Education. For this purpose, it made use of the film "Pra que time ele joga?" as a tool of discussing the theme with the research group, aiming to observe what kind of opinions these students have about homosexuality, as well as the discursive production of the image of homosexual subject produced by the educational videotape.

  18. Incorporating organizational factors into Probabilistic Risk Assessment (PRA) of complex socio-technical systems: A hybrid technique formalization

    International Nuclear Information System (INIS)

    Mohaghegh, Zahra; Kazemi, Reza; Mosleh, Ali

    2009-01-01

    This paper is a result of a research with the primary purpose of extending Probabilistic Risk Assessment (PRA) modeling frameworks to include the effects of organizational factors as the deeper, more fundamental causes of accidents and incidents. There have been significant improvements in the sophistication of quantitative methods of safety and risk assessment, but the progress on techniques most suitable for organizational safety risk frameworks has been limited. The focus of this paper is on the choice of 'representational schemes' and 'techniques.' A methodology for selecting appropriate candidate techniques and their integration in the form of a 'hybrid' approach is proposed. Then an example is given through an integration of System Dynamics (SD), Bayesian Belief Network (BBN), Event Sequence Diagram (ESD), and Fault Tree (FT) in order to demonstrate the feasibility and value of hybrid techniques. The proposed hybrid approach integrates deterministic and probabilistic modeling perspectives, and provides a flexible risk management tool for complex socio-technical systems. An application of the hybrid technique is provided in the aviation safety domain, focusing on airline maintenance systems. The example demonstrates how the hybrid method can be used to analyze the dynamic effects of organizational factors on system risk

  19. Incorporating organizational factors into Probabilistic Risk Assessment (PRA) of complex socio-technical systems: A hybrid technique formalization

    Energy Technology Data Exchange (ETDEWEB)

    Mohaghegh, Zahra [Center for Risk and Reliability, University of Maryland, College Park, MD 20742 (United States)], E-mail: mohagheg@umd.edu; Kazemi, Reza; Mosleh, Ali [Center for Risk and Reliability, University of Maryland, College Park, MD 20742 (United States)

    2009-05-15

    This paper is a result of a research with the primary purpose of extending Probabilistic Risk Assessment (PRA) modeling frameworks to include the effects of organizational factors as the deeper, more fundamental causes of accidents and incidents. There have been significant improvements in the sophistication of quantitative methods of safety and risk assessment, but the progress on techniques most suitable for organizational safety risk frameworks has been limited. The focus of this paper is on the choice of 'representational schemes' and 'techniques.' A methodology for selecting appropriate candidate techniques and their integration in the form of a 'hybrid' approach is proposed. Then an example is given through an integration of System Dynamics (SD), Bayesian Belief Network (BBN), Event Sequence Diagram (ESD), and Fault Tree (FT) in order to demonstrate the feasibility and value of hybrid techniques. The proposed hybrid approach integrates deterministic and probabilistic modeling perspectives, and provides a flexible risk management tool for complex socio-technical systems. An application of the hybrid technique is provided in the aviation safety domain, focusing on airline maintenance systems. The example demonstrates how the hybrid method can be used to analyze the dynamic effects of organizational factors on system risk.

  20. Development of a methodology for conducting an integrated HRA/PRA --. Task 1, An assessment of human reliability influences during LP&S conditions PWRs

    Energy Technology Data Exchange (ETDEWEB)

    Luckas, W.J.; Barriere, M.T.; Brown, W.S. [Brookhaven National Lab., Upton, NY (United States); Wreathall, J. [Wreathall (John) and Co., Dublin, OH (United States); Cooper, S.E. [Science Applications International Corp., McLean, VA (United States)

    1993-06-01

    During Low Power and Shutdown (LP&S) conditions in a nuclear power plant (i.e., when the reactor is subcritical or at less than 10--15% power), human interactions with the plant`s systems will be more frequent and more direct. Control is typically not mediated by automation, and there are fewer protective systems available. Therefore, an assessment of LP&S related risk should include a greater emphasis on human reliability than such an assessment made for power operation conditions. In order to properly account for the increase in human interaction and thus be able to perform a probabilistic risk assessment (PRA) applicable to operations during LP&S, it is important that a comprehensive human reliability assessment (HRA) methodology be developed and integrated into the LP&S PRA. The tasks comprising the comprehensive HRA methodology development are as follows: (1) identification of the human reliability related influences and associated human actions during LP&S, (2) identification of potentially important LP&S related human actions and appropriate HRA framework and quantification methods, and (3) incorporation and coordination of methodology development with other integrated PRA/HRA efforts. This paper describes the first task, i.e., the assessment of human reliability influences and any associated human actions during LP&S conditions for a pressurized water reactor (PWR).

  1. Progressive retinal atrophy in the Polski Owczarek Nizinny dog: a clinical and genetic study.

    Science.gov (United States)

    Svensson, Marika; Olsén, Lena; Winkler, Paige A; Petersen-Jones, Simon M; Bergström, Tomas; Garncarz, Yacek; Narfström, Kristina

    2016-05-01

    To describe ophthalmic, functional, structural, and genetical characteristics of progressive retinal atrophy (PRA) in the polski owczarek nizinny (PON) breed of dog. Client-owned PON dogs (n = 82) from Sweden. Routine examination for presumed inherited eye disease was performed in all dogs. Bilateral full-field electroretinography (ERG) was performed in 11 affected and 4 control dogs. Eyes from one affected dog were studied with light microscopy. DNA samples from 34 Swedish and 30 PON dogs collected by Michigan State University (MSU) were tested for the mutations causing the rcd4 and prcd forms of PRA. Sixteen of the eighty-two Swedish dogs were diagnosed with PRA. Slight vascular attenuation, first seen at 4.5 years of age, preceded changes in tapetal reflectivity. The initial ERG changes in affected dogs showed markedly diminished rod responses, while cone responses were barely affected. Eventually, cone responses were also reduced. Retinal morphology showed approximately a 50% reduction of photoreceptor nuclei in the outer nuclear layer. Fourteen of fifteen PRA-affected Swedish dogs and eighteen of twenty of the MSU PRA-affected dogs tested genetically were positive for the rcd4 mutation. All tested dogs were negative for the mutation causing prcd-PRA. PRA of PON dogs is a late-onset degenerative disease with slow progression. There is early loss of rod function, while the cone system deteriorates later. The rcd4 mutation in the C2ORF71 gene was associated with the majority of the PRA cases tested. The possibility of additional forms of PRA in the breed cannot be excluded. © 2015 American College of Veterinary Ophthalmologists.

  2. PRA insights applicable to the design of the Broad Applications Test Reactor

    International Nuclear Information System (INIS)

    Khericha, S.T.; Reilly, H.J.

    1993-01-01

    Design insights applicable to the design of a new Broad Applications Test Reactor (BATR), being studied at Idaho National Engineering Laboratory, are summarized. Sources of design insights include past probabilistic risk assessments and related studies for department of Energy-owned Class A reactors and for commercial reactors. The report includes a preliminary risk allocation scheme for the BATR

  3. NOVOS LETRAMENTOS NA CULTURA DIGITAL: O REMIX VEM PRA RUA - O GIGANTE ACORDOU COMO UM HÍBRIDO

    Directory of Open Access Journals (Sweden)

    Rosivaldo Gomes

    2015-07-01

    Full Text Available A utilização da internet, das mídias e redes sociais digitais e de celulares se constituiu como um diferencial importantíssimo no grande movimento social que mexeu com o País e com as visões sobre ele nas manifestações ocorridas em junho de 2013. Essas mídias e redes sociais digitais (YouTube, Flickr, Facebook, Instagram, Twitter, etc. se constituíram como canais de informação, ambientes comunicacionais, pontos de encontro, enfim, em redes e, às vezes, até em comunidades que facilitaram os relacionamentos entre os que estavam conectados e dispostos a se manifestarem de algum modo. Nessa direção, os novos letramentos digitais e o novo ethos como defendido por Lankshear e Knobel (2007 proporcionaram contribuições significativas para o uso das tecnologias digitais de informação e comunicação na propagação dessas manifestações, e, buscando compreender o modo como esses novos letramentos favoreceram isso, neste artigo buscamos, a partir das noções de hibridismo e intercalação (GARCÍA CANCLINI, 2008 [1989]; BAKHTIN, 2002 [1934-5] e  nas discussões de Lankshear e Knobel (2007; 2008 sobre remix e sobre linguagens hipermidiática e híbrido digital (SANTAELLA, 2003; 2004, realizar uma análise qualitativa do remix digita Vem pra rua - O gigante acordou,  no que diz respeito as técnicas de produção e constituição desse gênero na construção de novos significado, considerando o horizonte espacial e temporal (VOLOCHINOV/BAKHTIN, [1926]1976 nos quais foi produzido

  4. PENILAIAN PROGRAM PRAKTIKUM TERHADAP PENINGKATAN KUALITI GURU PRA PERKHIDMATAN: ANALISIS BERDASARKAN LATENT GROWTH CURVE MODELLING

    Directory of Open Access Journals (Sweden)

    Azizah Sarkowi

    2015-12-01

    Full Text Available Practicum is an important component in teacher education programs. This study identify the improvement in the quality of pre-service teachers for three phases practicum. Multi-point prospective panel study has been conducted on a 541 pre-service teachers at the Institute of Teacher Education. Teacher’s quality is measured based on the achievement of program learning outcomes. Based on matching last six digit identification card number for three studies series, 337 questionnaires were analyzed using a latent growth curve model using AMOS 18.0. Latent Analysis shows that the model achieve goodness of fit. There is a linear trend of improvement in the performance of the three phases of the practicum. This increase varies between individuals and the rate of growth depends on the level of achievement at practicum phase I. Studies indicate that the increase in the practicum period of teacher education policy should be continued.

  5. Failure Modes Taxonomy for Reliability Assessment of Digital Instrumentation and Control Systems for Probabilistic Risk Analysis - Failure modes taxonomy for reliability assessment of digital I and C systems for PRA

    International Nuclear Information System (INIS)

    Amri, A.; Blundell, N.; ); Authen, S.; Betancourt, L.; Coyne, K.; Halverson, D.; Li, M.; Taylor, G.; Bjoerkman, K.; Brinkman, H.; Postma, W.; Bruneliere, H.; Chirila, M.; Gheorge, R.; Chu, L.; Yue, M.; Delache, J.; Georgescu, G.; Deleuze, G.; Quatrain, R.; Thuy, N.; Holmberg, J.-E.; Kim, M.C.; Kondo, K.; Mancini, F.; Piljugin, E.; Stiller, J.; Sedlak, J.; Smidts, C.; Sopira, V.

    2015-01-01

    Digital protection and control systems appear as upgrades in older nuclear power plants (NPP), and are commonplace in new NPPs. To assess the risk of NPP operation and to determine the risk impact of digital systems, there is a need to quantitatively assess the reliability of the digital systems in a justifiable manner. Due to the many unique attributes of digital systems (e.g., functions are implemented by software, units of the system interact in a communication network, faults can be identified and handled online), a number of modelling and data collection challenges exist, and international consensus on the reliability modelling has not yet been reached. The objective of the task group called DIGREL has been to develop a taxonomy of failure modes of digital components for the purposes of probabilistic risk analysis (PRA). An activity focused on the development of a common taxonomy of failure modes is seen as an important step towards standardised digital instrumentation and control (I and C) reliability assessment techniques for PRA. Needs from PRA has guided the work, meaning, e.g., that the I and C system and its failures are studied from the point of view of their functional significance point of view. The taxonomy will be the basis of future modelling and quantification efforts. It will also help to define a structure for data collection and to review PRA studies. The proposed failure modes taxonomy has been developed by first collecting examples of taxonomies provided by the task group organisations. This material showed some variety in the handling of I and C hardware failure modes, depending on the context where the failure modes have been defined. Regarding the software part of I and C, failure modes defined in NPP PRAs have been simple - typically a software CCF failing identical processing units. The DIGREL task group has defined a new failure modes taxonomy based on a hierarchical definition of five levels of abstraction: 1. system level (complete

  6. PRA insights applicable to the design of a broad applications test reactor

    International Nuclear Information System (INIS)

    Khericha, S.T.; Reilly, H.J.

    1993-01-01

    Design insights applicable to the design of a new Broad Applications Test Reactor (BATR), studied during Fiscal Years 1992 an d1993 at Idaho National Engineering Laboratory (INEL), are summarized. Sources of design insights include past probabilistic risk assessments (PRAs) and related studies for Department of Energy (DOE)-owned Class A reactors and for commercial reactors. The report includes preliminary risk allocations for the BATR. The survey addressed those design insights that would affect the reactor core damage frequency (CDF). The design insights, while selected specifically for BATR, should be applicable to any new advanced test reactor

  7. Soil Erosion and Sediment Yield Modelling in the Pra River Basin of ...

    African Journals Online (AJOL)

    kusimi

    sediment delivery ratio; soil erosion modelling; sediment yield modelling. .... The basin falls within the wet semi-equitorial climatic belt which is ... influence of the moist south-west monsoons during the rainy season, with high .... availability of good satellite images covering the study area; because of thick cloud cover most.

  8. Probabilistic risk assessment (PRA) on the effectiveness of a core rescue system (SSN) for PWRs

    International Nuclear Information System (INIS)

    Petrangeli, G.; Valeri, A.

    1983-01-01

    Safety systems for the prevention of LWR core severe damage have recently been studied, which are based on automatic primary system depressurization and on borated water injection by low pressure accumulators. These systems have been named Core Rescue System (SSN). The present study evaluates the reduction in core melt probability brought about by the installation of a SSN system on the RSS (WASH 1400) PWR plant (Surry 1). The calculated result is a core melt probability reduction factor of about 250. Taking into account the possible effect of external or internal unknown events of negligible, yet undefined, probability it is concluded that a SSN system can make a plant ten times safer. The first part of a review report by Prof. N.C.Rasmussen, MIT, dealing with general comment, is attached

  9. Human factors assessment in PRA using Task Analysis Linked Evaluation Technique (TALENT)

    International Nuclear Information System (INIS)

    Wells, J.E.; Banks, W.W.

    1991-01-01

    Thirty years ago the US military and US aviation industry, and more recently, in response to the US Three Mile Island and USSR Chernobyl accidents, the US commercial nuclear power industry, acknowledged that human error, as an immediate precursor, and as a latent or indirect influence in the form of training, maintainability, inservice test, and surveillance programs, is a primary contributor to unreality and risk in complex high-reliability systems. A 1985 Nuclear Regulatory Commission (NRC) study of Licensee Event Reports (LERs) suggests that upwards of 65% of commercial nuclear system failures involve human error. Despite the magnitude and nature of human error cited in that study, there has been limited attention to personnel-centered issues, especially person-to-person issues involving group processes, management and organizational environment. The paper discusses NRC integration and applications research with respect to the Task Analysis Linked Evaluation Technique (TALENT) in risk assessment applications

  10. Celebrity marketing pražských muzikálů

    OpenAIRE

    Kuzmová, Tereza

    2017-01-01

    This Diploma Thesis deals with the issue of Prague musicals celebrity marketing, which is a significant characteristics of the contemporary Prague musical scene. The theoretical part of this thesis introduces the basic theories of celebrity studies and the specifics of marketing mix of musicals, in which celebrities play a significant role. On the margine, the thesis is also focused on current overproduction of musicals and related problems in marketing activities of musical productions. The ...

  11. Prävalenz des Drogenkonsums in der Anästhesie-Ambulanz

    OpenAIRE

    Kondschak, Johannes

    2017-01-01

    The abuse of illicit substances and prescription drugs is a worldwide problem. Supportive strategies seem more appropriate and effective than confrontative strategies when treating and preventing substance abuse. However, supportive strategies are neither sufficiently evaluated nor widely established. The pre-anaesthetic assessment clinic of the Charité – Universitäts Medizin Berlin is a potential contact point for people with risky consumption of narcotic substances. Some initial studie...

  12. Scientific and technological monitoring: international overview on R. and D. related to Pra's

    International Nuclear Information System (INIS)

    Llory, M.; Stioui, A.

    1993-03-01

    In 1989, the R and D Division of Electricite de France launched a programme for a Technological and Scientific Overview (TSO) covering a certain number of topics considered to be important for the future of EDF. Probabilistic approaches to studies related to safety were considered to be strategically important to EDF, and therefore this area was selected for further study. A TSO is a process which can only start on the basis of a structured state-of-the-art organized as a basis of knowledge, together with the highlighting of a certain number of scientific and strategic ''set of references . The state-of-the-art of R and D related to Probabilistic Safety Assessment (PSA) was carried out in collaboration between the EDF R and D Division (SR branch) and SRI International. The approach chosen included: segmentation of the wide field of PSAs into subject areas, topics and sensitive points to be monitored; conception of a grid for the interviews; approximately thirty in-depth interviews of organizations and experts representative of the domain; analysis leading to identify certain problems areas or particularly important features. Emerging themes for research and further consideration in relation to PSAs, their application and their limits were also identified. Based on this state-of-the-art, various themes of monitoring were defined (living PSAs, limits of PSAs,...) and an organizational structure for monitoring was set up in the branch. The state of the art is not static, it is the reason why an in-depth extension of the study was undertaken on issues of special interest for EDF. (authors). 2 figs., 2 refs

  13. POTENSI ALELOPAT DAUN PINUS (Pinus spp. SEBAGAI BIOHERBISIDA PRA TUMBUH PADA GULMA KROKOT (Portulaca oleracea

    Directory of Open Access Journals (Sweden)

    Lutfy Ditya Cahyanti

    2015-06-01

    Full Text Available The aim of this experiment was to study the effectof pine leaf as allelophaty on purslane germination. Theexperiment were conducted at screen house Departmentof Biology, Faculty of Mathematics and Science, BrawijayaUniversity. The research is experimental design by nonfactorial Completely Randomized Blok Design, with threereplications, consisted of eleven levels. Purslane seeds sprout with control treatment, signifi cantly different from seedssprout ability in treatment solution leaves Pinus merkusii 2000ppm, and solution leaves of P. longaeva 2000 ppm. The resultshowed that 2000 ppm of P. merkusii extraction signifi cantlysuppressed 46% of purslane germination whereas 2000 ppmPinus longeava extraction signifi cantly suppressed of 41%campared to without any treatments (control.

  14. TERAPI BERMAIN MENDONGENG DAPAT MENURUNKAN TINGKAT KECEMASAN PADA ANAK USIA PRA SEKOLAH AKIBAT HOSPITALISASI

    Directory of Open Access Journals (Sweden)

    Aji Kiyat W ,

    2014-04-01

    Full Text Available Background: Child is a unique individual and can also be sick with a greater risk so they need ahospitalization for diagnosing and treating thedisease. Hospitalization can trigger anxiety. Reaction toanxiety can be shown by, among others: crying, being afraid, being agressive, curiosity, control-lost,confusion, refusing to eat, and refusing invasive treatment. Implementation of care for children can not beseparated with the play therapy as an attempt to decrease anxiety, enhance cooperative behaviour, andstimulate the growth and development of children during their hospitalization. One of the recommendedintervention is storytelling play therapy.Objective:Determine the influence of storytelling play therapy on the level of anxiety in pre-schoolchildren due to hospitalization at cempaka ward RAA Soewondo Pati Hospital.Methods:This study is quassy-experimental research design with a “one-group-before-after” (pretest-posttest design without control group. Total sampel in this study were 19 pre-school children using totalsampling technique. Data collection was performed before and after the treatment using the instrument toknow the level of anxiety that knew as HARS-A and statistic test which used is Wilcoxon signed rank test(α= 0,05.Result:The result of statistic analysis using Wilcoxon signed rank test shows significant p-value=0,000(α= 0,05. It means storytelling play therapy has an influence on the level of anxiety in pre-school childrendue to hospitalization at Cempaka ward RAA Soewondo Pati Hospital.Conclusion:Storytelling play therapy has an effect to decrease the level of anxiety in pre-schoolchildren

  15. HUBUNGAN ANTARA POLA ASUH ORANG TUA DENGAN KETRAMPILAN MOTORIK ANAK PRA SEKOLAH

    Directory of Open Access Journals (Sweden)

    Didik Budijanto

    2012-11-01

    Full Text Available The growth of nucleus family, a couple (wife and husband have to work outdoor, prosecute their role in caring their children. The  pattern in caring the children changed, which the husband has to do more actively. The objective of the study was to learn the relationship between parents role in caring children with motoric creatively among pre-pupil. The population of this study was pre-pupil of Dharma Wanita II/IKIP kindergarten Surabaya. 42 children and their parents were selected by applying simple random sampling. Data was collected by observation and interview. Variables were measured from children motoric creativity, parents  guidence in caring children, parents interaction, interfere of the 3 m person, the quantity of children that should be nursed. Data was analized by applying multiple logistic regression. The result shows that just the parents guidence in caring children can influence the children motoric creativity. Pattern of caring children which dominated by mother causes the decrease of children motoric creativity reaches double in comparason with care system that hasn't domination/balance (OR= 1,9286. The pattern wich dominated by father will have risk to the children motoric creativity decrease (9x comparaed to the balance care (OR = 8,999. This condition in line with Haditono's opinion (1988 that there are many factors which most important is the system which is professed and-doneby parent in daily life. Hurlock (1973 said that, in order to build the children motoric creativity faster, needed stimulant, the main and first support received from their parents at home. Hendy Margono (1996 said that a child will be grown up better, can interac with the society easily if the care system is created together with both-father and mother­ which is the couple (husband and  wife  have the same positioning taking care their children.

  16. PERAWATAN PRA PROSTODONTIK DENGAN SPLIN OKLUSAL PADA KASUS KEHILANGAN GIGI YANG DISERTAI GANGGUAN SENDI TEMPOROMANDIBULA

    Directory of Open Access Journals (Sweden)

    Ira S Wardani

    2015-08-01

    Full Text Available Pre-prosthetic treatment is very important step to get a successful prosthodontic treatment. This study reported a case of patient with missing teeth on left and right lower first and second molar, with TMJ symptoms. Other symptoms felt by the patients were ear pain, and shoulder pain. After detailed examination, pre-prosthetic treatment needed by the patient was the TMJ treatment. The usage of occlusal splint as one of the methods to treat the TMD were i.e. to eliminate the occlusal disorder, to reduce the neuromuscular activity, and to regain a stable centric relation. After splint treatment, an open bite on the posterior teeth appeared. To solve this problem, a removable frame prosthesis enhanced with overlay rest was fabricated. With this prosthesis, the TMJ symptoms stopped recurring. It was concluded that to achieve a successful prosthesis, a detailed and comprehensive treatment was needed, including the pre-prosthetic treatment, along with the patient’s motivation and cooperation.

  17. MEDIA REKAM JEJAK TAHAPAN PRA DESAIN DENGAN POSTER : MENINGKATKAN KINERJA DAN LUARAN PADA STUDIO PERANCANGAN ARSITEKTUR

    Directory of Open Access Journals (Sweden)

    Fibria Conytin Nugrahini

    2015-12-01

    Full Text Available A Pre-design process in studio design class includes observation phase, analysis and programming, a directed process of searching and recording information. Based on an early observation, currently pre-design activities in class or studio often has been less optimal due to the low of students performance and the creativities. This causes the output generated from pre-design process was not maximized while undocumented or do not have a good track records. This paper aims to explore the use of posters as a creative ideas in the documentation of of pre-design stage. This is a class-action research as the result of the development of pre-design activities with inquiry methods using the poster as a medium track record in architectural design studio. Research methods include observation and assessment pre-design student outcomes, and questionnaire. Poster outcomes observation were ratings based on several criterias. The questionnnaires tested the posters feasibility in improving the performance and outcomes based on the process and student experiences. Because it is class-action reasearch, this study is limited to the studio class where the author conducted lectures and studio guidance. The results showed an increase in the performance of students in search of matter, observations, material analysis, as well as programming in the use of posters as track record media. In addition, students were satisfied and more creatively visualize their ideas in the pr e-design phase by using the poster media

  18. Development of risk assessment methodology against natural external hazards for sodium-cooled fast reactors: project overview and strong Wind PRA methodology - 15031

    International Nuclear Information System (INIS)

    Yamano, H.; Nishino, H.; Kurisaka, K.; Okano, Y.; Sakai, T.; Yamamoto, T.; Ishizuka, Y.; Geshi, N.; Furukawa, R.; Nanayama, F.; Takata, T.; Azuma, E.

    2015-01-01

    This paper describes mainly strong wind probabilistic risk assessment (PRA) methodology development in addition to the project overview. In this project, to date, the PRA methodologies against snow, tornado and strong wind were developed as well as the hazard evaluation methodologies. For the volcanic eruption hazard, ash fallout simulation was carried out to contribute to the development of the hazard evaluation methodology. For the forest fire hazard, the concept of the hazard evaluation methodology was developed based on fire simulation. Event sequence assessment methodology was also developed based on plant dynamics analysis coupled with continuous Markov chain Monte Carlo method in order to apply to the event sequence against snow. In developing the strong wind PRA methodology, hazard curves were estimated by using Weibull and Gumbel distributions based on weather data recorded in Japan. The obtained hazard curves were divided into five discrete categories for event tree quantification. Next, failure probabilities for decay heat removal related components were calculated as a product of two probabilities: i.e., a probability for the missiles to enter the intake or out-take in the decay heat removal system, and fragility caused by the missile impacts. Finally, based on the event tree, the core damage frequency was estimated about 6*10 -9 /year by multiplying the discrete hazard probabilities in the Gumbel distribution by the conditional decay heat removal failure probabilities. A dominant sequence was led by the assumption that the operators could not extinguish fuel tank fire caused by the missile impacts and the fire induced loss of the decay heat removal system. (authors)

  19. Heterogeneity of soil surface ammonium concentration and other characteristics, related to plant specific variability in a Mediterranean-type ecosystem

    International Nuclear Information System (INIS)

    Cruz, Cristina; Bio, Ana M.F.; Jullioti, Aldo; Tavares, Alice; Dias, Teresa; Martins-Loucao, Maria Amelia

    2008-01-01

    Heterogeneity and dynamics of eight soil surface characteristics essential for plants-ammonium and nitrate concentrations, water content, temperature, pH, organic matter, nitrification and ammonification rates-were studied in a Mediterranean-type ecosystem on four occasions over a year. Soil properties varied seasonally and were influenced by plant species. Nitrate and ammonium were present in the soil at similar concentrations throughout the year. The positive correlation between them at the time of greatest plant development indicates that ammonium is a readily available nitrogen source in Mediterranean-type ecosystems. The results presented here suggest that plant cover significantly affects soil surface characteristics. - In Mediterranean-type ecosystems ammonium is present in the soil throughout the year and its concentration is dependent on plant cover

  20. Pulsa o coração da cidade: errâncias, afectos e potências no dia e na noite da Praça do Ferreira

    Directory of Open Access Journals (Sweden)

    Alice Dote

    2017-12-01

    Full Text Available O presente artigo aborda a potência dos usos, contra-usos e modos de habitar dos artistas de rua da Praça do Ferreira, na cidade de Fortaleza, Ceará. O trabalho apoia-se nos percursos e nas errâncias urbanas da vivência na e da Praça do Ferreira em diferentes temporalidades (diurna e noturna, especialmente no contexto de apresentações noturnas do Grupo As 10 Graças de Palhaçaria aos moradores da Praça. Através desses que têm a rua como casa, agem pelas brechas e proliferam-se pelas margens, proponho-me a perceber a potência da arte de rua, do encontro e da experiência de alteridade na Praça do Ferreira. Finalizo o texto apontando que esse local, assim ocupado, se impregna de significados outros e revela-se como um território de criação, de inventividade, de existência e resistência, portanto, de potência de vida que é, em si, potência política. Palavras-chave: Praça do Ferreira; Fortaleza; cidade; arte urbana; artista de rua

  1. Can we trust PRA?

    Energy Technology Data Exchange (ETDEWEB)

    Epstein, S. [ABS Consulting, Koraku Mori, Building, 1-4-14 Koraku Chome, Bunkyo-ku, Tokyo 112-0004 (Japan)]. E-mail: sepstein@absconsulting.com; Rauzy, A. [Institut de Mathematique de Luminy (IML/CNRS), 163 Avenue de Luminy, Case 907, Marseille, Cedex 913288 (France)]. E-mail: arauzy@iml.univ-mrs.fr

    2005-06-01

    The Fault-Tree/Event-Tree method is widely used in industry as the underlying formalism of probabilistic risk assessment. Almost all of the tools available to assess Event-Tree models implement the 'classical' assessment technique based on minimal cutsets and the rare event approximation. Binary decision diagrams (BDDs) are an alternative approach, but they were up to now limited to medium size models because of the exponential blow up of the memory requirements. We have designed a set of heuristics, which make it possible to quantify, by means of BDD, all of the sequences of a large Event-Tree model coming from the nuclear industry. For the first time, it was possible to compare results of the classical approach with those of the BDD approach, i.e. with exact results. This article reports this comparison and shows that the minimal cutsets technique gives overestimated results in a significant proportion of cases and underestimated results in some cases as well. Hence, the (indeed provocative) question in the title of this article.

  2. Praça adaptada de um centro de reabilitação em Pelotas/RS: a visão de profissionais e estagiários atuantes no local / An adapted square in a rehabilitation center in Pelotas/RS: the view of professionals and trainees working there

    Directory of Open Access Journals (Sweden)

    Franciele Costa Berní

    2018-01-01

    Full Text Available O terapeuta ocupacional é o profissional que estuda a ocupação humana, intervindo no desempenho das habilidades físicas, mentais, sociais e ambientais de cada indivíduo, a fim de proporcionar a participação deste nas atividades em casa, na escola e no trabalho. O brincar favorece a intervenção terapêutica e está presente em diversos contextos da vida das crianças e adolescentes, inclusive no contexto de uma praça adaptada. Desta forma, este estudo tem como objetivo verificar a percepção de profissionais de um centro de reabilitação de crianças e adolescentes com deficiência, e estagiários de Terapia Ocupacional, sobre a utilização de uma praça adaptada como um recurso terapêutico e de recreação. Para isto, identificou-se uma amostra composta por 20 sujeitos, de ambos os sexos. Foram utilizados dois questionários semiestruturados para coleta dos dados, ambos com a mesma finalidade, porém com linguagens adaptadas a cada área de atuação. A partir disto, constatou-se idade média de 33 anos, e diferenças nas respostas dos profissionais e estagiários em relação as atividades e objetivos propostos na praça adaptada, bem como na identificação desta como um recurso terapêutico. Todos os pesquisados qualificaram a praça como importante para instituição. Este estudo identificou que a praça adaptada é um ambiente utilizado como recurso terapêutico/pedagógico pelos sujeitos, porém, ainda é uma área inovadora para a Terapia Ocupacional, a qual busca aprimorar o desempenho ocupacional dos indivíduos. No entanto, são necessários novos estudos que possam auxiliar na fidedignidade destes resultados, e evidenciar as possibilidades de atuação do terapeuta ocupacional neste âmbito. Abstract An occupational therapist is a professional who studies human occupation by intervening in the performance of physical, mental, social and environmental skills of each subject in order to provide their participation in

  3. Espaços livres em praças inglesas do século XVII: o caso de Convent Garden

    Directory of Open Access Journals (Sweden)

    Maria Fernanda Derntl

    2006-12-01

    Full Text Available Covent Garden é considerada uma experiência modelar entre as primeiras transformações no espaço urbano ainda de aparência medieval de Londres no século XVII. A partir da iconografia da época e das indicações da bibliografia pertinente, procura-se apresentar uma análise abrangente da configuração formal dessa praça. Destaca-se a existência de diferentes tipos de espaços livres contribuindo para determinar seu desenho: além do espaço central, também fizeram parte da praça o pátio da igreja de St. Paul, a oeste e os jardins da mansão Bedford, ao sul. Conclui-se que o desenho apresentado por Covent Garden não era completamente regular ou simétrico e teria sido bem diferente das squares londrinas dos séculos XVII e XVIII.

  4. Avaliação qualitativa e quantitativa da arborização das praças de Vinhedo, SP.

    Directory of Open Access Journals (Sweden)

    Roberval de Cássia Salvador Ribeiro

    2006-06-01

    Full Text Available O inventário das espécies arbóreas e dos respectivos números de indivíduos das praças da cidade de Vinhedo foi realizado no perímetro urbano, excetuando-se os condomínios, as áreas de parques e as de preservação de mananciais. Para a localização das áreas, consultou-se a planta do município de 1997. Realizou-se o inventário da vegetação arbórea, considerando-se apenas os indivíduos com CAP (circunferência à altura do peito acima de 10 cm listando-se as seguintes informações: nomes comum e científico das espécies; CAP; altura; aspecto geral; diâmetro de copa; presença de pragas, doenças ou parasitas; ocorrência de podas (drástica e/ou de condução; fitossanidade da raiz, tronco e copa. Foram registradas 22 praças por nome, localização e número total de árvores, totalizando 764 indivíduos pertencentes a 23 famílias botânicas e 53 espécies, além de 32 indivíduos não identificados. A espécie de maior abundância relativa foi Syagrus romanzoffiana (jerivá, com 31,94% do número total de indivíduos. Em 63,64% das praças 33,13% das espécies eram exóticas. A maior parte dos indivíduos tinha aspecto geral normal, demonstrando prática de tratos culturais adequados. Na maioria dos casos, as podas foram feitas corretamente, ou não houve a necessidade de nenhuma intervenção. Do total de 22 praças, apenas cinco tinham bom estado geral de conservação dos elementos naturais (arbustos, canteiros e gramados. Em 68,18% das praças as árvores tinham altura superior a 6 metros, indicando que essas áreas necessitavam apenas de procedimentos de manutenção de rotina. E 22,72% necessitavam de práticas de manutenção mais direcionadas ao desenvolvimento das árvores, tais como adubações periódicas, capinas, podas de condução e, finalmente, em 13,64% deveriam ocorrer intervenções tanto de manutenção, como de recuperação por meio de novos plantios, ou mesmo, de planejamento para remodelação da área.

  5. Praça da Matemática: as faces da história na construção de um monumento

    OpenAIRE

    Pimentel, Augusto Cesar Aguiar

    2008-01-01

    O presente trabalho consiste na investigação histórico-cultural da construção de uma praça, com um monumento em homenagem à Matemática, idealizado por um prefeito visionário, de 29 anos, na cidade de Itaocara, interior do Estado do Rio de Janeiro, no ano de 1943. O que é hoje uma atração turística, surgiu da criatividade do jovem político que apesar de advogado, via na matemática sua fonte de prazer. Para essa pesquisa, realizou-se entrevistas com o próprio prefeito da época...

  6. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  7. Tortura e transição democrática: uma análise histórica do filme “Pra frente, Brasil”

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    Paulo Jorge Corrêa Campos

    2014-06-01

    Full Text Available O presente trabalho pretende analisar o filme “Pra frente, Brasil” situando o mesmo no contexto da abertura democrática dos anos 1980. Para tal, busca-se tecer o contexto e o lugar social onde foi concebido o filme. Na análise, atenta-se para o papel da tortura presente na obra cinematográfica e para os elementos semióticos usados no filme para incutir uma visão específica no espectador. Ademais, considerando-se que o mesmo sofre censura prévia do governo, procura-se questionar a superficialidade da democracia mesmo no agonizar da ditadura civil-militar.

  8. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  9. Contamination of public parks in Presidente Prudente (São Paulo, Brazil by Toxocara spp. eggs Contaminação de praças públicas de Presidente Prudente, São Paulo, Brasil, por ovos de Toxocara spp

    Directory of Open Access Journals (Sweden)

    Vamilton Alvares Santarém

    2012-09-01

    Full Text Available This study aims to evaluate soil contamination by Toxocara spp. eggs in public parks in Presidente Prudente, São Paulo, Brazil. Soil samples (500 g were collected every month over a 12-month period, from 25 parks in different parts of the city (northern, southern, eastern, western and central areas. Two 10-g aliquots of the material collected from each park were subjected to the centrifuge-flotation method to recover Toxocara spp. eggs. Twenty-four out of the 25 squares studied (96.0% were contaminated and the number of eggs recovered ranged from 1 to 398 per sample. Eggs were recovered all over the year. Despite the number being greater in autumn (p O objetivo do estudo foi avaliar a contaminação do solo de praças públicas por ovos de Toxocara spp. em Presidente Prudente, São Paulo. Amostras de solo (500 g foram coletadas mensalmente, durante um período de 12 meses, de 25 praças de cinco diferentes setores da cidade (norte, sul, leste, oeste e central. Duas alíquotas de 10 g do material coletado foram submetidas ao método de centrífugo-flutuação (sulfato de zinco; d = 1.200 g/cm³, para recuperação dos ovos. Das 25 praças estudadas, 24 (96,0% estavam contaminadas e o número variou de 1 a 398 ovos por amostra analisada. A recuperação foi verificada durante todos os meses do ano, sendo maior no outono (p < 0,001. Entretanto, não houve correlação entre o número de ovos e a temperatura média (r = -0,492; p = 0,148 e a precipitação pluviométrica (r = -0,299; p = 0,402 mensal. Não houve influência da localização dos parques sobre a quantidade de ovos (p = 0,7116. Devido ao alto nível de contaminação de parques públicos por ovos de Toxocara spp., a prevenção da contaminação de áreas públicas pelos agentes de larva migrans é indicada.

  10. Genome-wide survey and expression analysis of the plant-specific NAC transcription factor family in soybean during development and dehydration stress.

    Science.gov (United States)

    Le, Dung Tien; Nishiyama, Rie; Watanabe, Yasuko; Mochida, Keiichi; Yamaguchi-Shinozaki, Kazuko; Shinozaki, Kazuo; Tran, Lam-Son Phan

    2011-08-01

    Plant-specific NAC transcription factors (TFs) play important roles in regulating diverse biological processes, including development, senescence, growth, cell division and responses to environmental stress stimuli. Within the soybean genome, we identified 152 full-length GmNAC TFs, including 11 membrane-bound members. In silico analysis of the GmNACs, together with their Arabidopsis and rice counterparts, revealed similar NAC architecture. Next, we explored the soybean Affymetrix array and Illumina transcriptome sequence data to analyse tissue-specific expression profiles of GmNAC genes. Phylogenetic analysis using stress-related NAC TFs from Arabidopsis and rice as seeding sequences identified 58 of the 152 GmNACs as putative stress-responsive genes, including eight previously reported dehydration-responsive GmNACs. We could design gene-specific primers for quantitative real-time PCR verification of 38 out of 50 newly predicted stress-related genes. Twenty-five and six GmNACs were found to be induced and repressed 2-fold or more, respectively, in soybean roots and/or shoots in response to dehydration. GmNAC085, whose amino acid sequence was 39%; identical to that of well-known SNAC1/ONAC2, was the most induced gene upon dehydration, showing 390-fold and 20-fold induction in shoots and roots, respectively. Our systematic analysis has identified excellent tissue-specific and/or dehydration-responsive candidate GmNAC genes for in-depth characterization and future development of improved drought-tolerant transgenic soybeans.

  11. Variáveis meteorológicas e cobertura vegetal de espécies arbóreas em praças urbanas em Cuiabá, Brasil

    Directory of Open Access Journals (Sweden)

    Angela Santana de Oliveira

    2013-12-01

    Full Text Available A influência da vegetação nas variáveis meteorológicas foi avaliada por meio do índice de área foliar (IAF e índice de sombreamento arbóreo (ISA em duas praças públicas em Cuiabá-MT, Brasil. Medidas de temperatura do ar (T e umidade relativa (UR foram obtidas sob a copa das árvores em diferentes sítios da cidade para o período seco e chuvoso no ano de 2009. A análise dos valores médios destas variáveis mostraram maiores valores de T e menores UR ocorrendo durante o período seco e sendo semelhantes nas duas praças. Com relação à UR, entretanto, não houve diferenças significativas entre a medida sob as árvores e a atmosfera. O índice de área foliar foi calculado e variou em função das espécies arbóreas das praças, e mostrou valores entre 5,64 e 2,79 m². m-2, sendo a média do IAF e do ISA na Praça Popular superiores ao da Praça 8 de Abril. Conclui-se que as espécies arbóreas melhoraram o ambiente térmico em virtude da atenuação da radiação proporcionada pelo sombreamento das diferentes espécies, principalmente no horário com menor ângulo solar.

  12. Avaliação da influência sazonal na incidência de ovos e larvas de parasitos intestinais em praças no município de Macapá-AP | Evaluation of seasonal influence on the incidence of eggs and larvae of intestinal parasites in squares in the city of Macapá-AP

    Directory of Open Access Journals (Sweden)

    Felipe Ferreira Rêgo

    2017-05-01

    Full Text Available Doenças relacionadas a parasitoses mostram-se um relevante problema de saúde pública devido às diferentes complicações que estas podem causar, e o fornecimento de dados epidemiológicos tem o objetivo de reverter esse quadro. O trabalho visou avaliar a frequência de ovos e larvas de helmintos no município de Macapá, assim como a influência da sazonalidade na incidência da contaminação das praças públicas nos períodos compreendidos como inverno e verão. Nesse estudo foi analisado uma amostra contendo três pontos estratégicos de solo de cada praça, totalizando 39 praças, divididas em diferentes bairros. A escolha foi feita de acordo com as zonas que dividem o município, totalizando 39 amostras em recipientes devidamente vedados. Os métodos utilizados foram: Hoffman, Direto, Willis e Baermann Moraes. Os resultados mostraram a alta carga parasitária nos locais públicos, principalmente na época do inverno, onde se notou a alta prevalência de ovos Toxocara spp. no período do verão e, no período do inverno, obteve-se a prevalência maior de ovos de Ancylostoma spp., o que justifica uma ação imediata do poder público em relação a presença desses agentes no meio ambiente, com controle de animais, saneamento básico, disponibilização de tratamento e manutenção periódica das praças públicas. ============================================ Diseases related to parasitosis are a relevant public health problem due to the different complications that these can cause, and the provision of epidemiological data is aimed at reversing this situation. The objective of this work was to evaluate the frequency of eggs and larvae of helminths in the county of Macapá, as well as the influence of seasonality on the incidence of contamination of public squares in seasons from winter to summer. In this study 1 sample containing 3 strategic points of soil of each square was analyzed, totaling 39 squares, divided in different

  13. As praças dr. Augusto Silva e Leonardo Venerando Pereira, 1701 Lavras - MG, segundo a visão dos seus freqüentadores The park dr. Augusto Silva, Lavras - MG, according to viewpoint of its users

    Directory of Open Access Journals (Sweden)

    Alessandra Teixeira da Silva

    2008-12-01

    Full Text Available As praças públicas, além de contribuírem para o embelezamento das cidades, também desempenham uma função importante no contexto urbanístico ambiental. A Praça Dr. Augusto Silva, situada no município de Lavras, MG, também já foi chamada de Largo da Matriz, Praça Central e Jardim Municipal, que foi inaugurado oficialmente em 29 de novembro de 1908, quando passou a ter o nome de um ilustre médico lavrense. A praça Dr. Augusto Silva, possui atualmente, área de 7.552,65 m² e apresenta como prolongamento a praça Leonardo Venerando Pereira, com área atual de 2.041,72 m². Até 1940, esse prolongamento era denominado de Praça da Bandeira. Constatou-se, que desde o início da década de 1910, o local foi palco de grandes celebrações e encontros políticos e também foi muito freqüentado pela população. A Praça possui rica vegetação, onde se destacam uma centenária Tipuana (Tipuana tipu, diversos ipês (Tabebuia spp., palmeiras-imperiais (Roystonea oleracea. Objetivando-se avaliar a situação atual e usos, foi realizada uma avaliação, mediante análise quantitativa e pesquisa junto à população. Foram feitas uma série de avaliações referentes aos seguintes itens: aspectos urbanísticos, físicos e a vegetação. A pesquisa de opinião foi aplicada a aproximadamente 600 usuários, na própria praça, em dias da semana e horários diferentes, por meio de um questionário com perguntas diretas ao próprio entrevistado. Os dados coletados foram analisados estatisticamente utilizando o Software SPSS, de onde foram obtidas as freqüências porcentuais. A maior parte dos entrevistados julga a praça como um ponto de encontro entre amigos, onde contemplam a sua beleza e descansam. Por meio de pesquisa de opinião realizada com os usuários da praça, pôde-se identificar que se trata de um local muito freqüentado por várias faixas etárias, em diferentes períodos do dia. A praça Dr. Augusto Silva mostra-se de grande import

  14. Análise quali-quantitativa da arborização na praça XV de novembro em Ribeirão Preto - SP, Brasil

    Directory of Open Access Journals (Sweden)

    Gustavo de Nobrega Romani

    2012-06-01

    Full Text Available A Praça XV de Novembro, implantada em meados do século XIX, tem grande valor histórico-cultural, além de se constituir em uma das principais áreas verdes do centro da cidade de Ribeirão Preto. Visando ao conhecimento detalhado da vegetação para fins de orientação do manejo e conservação dessa área, foi feito um levantamento quali-quantitativo e fitossociológico das árvores e palmeiras da praça. Foram medidas altura e Diâmetro à Altura do Peito (DAP e identificados todos os indivíduos de porte arbóreo (árvores e palmeiras presentes na Praça, em nível de espécie. A praça ocupa uma área de 15.456,00 m², onde foram amostradas 42 espécies distribuídas por 19 famílias, num total de 161 indivíduos. Apesar de o local apresentar arborização com alto índice de diversidade de espécies (Shannon-Weaver de 3,14, os exemplares necessitam de maior atenção quanto a problemas ligados à fitossanidade e podas adequadas, fazendo que resulte em espaço seguro para os frequentadores e em boa qualidade paisagística.

  15. Application of sensitivity analysis in nuclear power plant probabilistic risk assessment studies

    International Nuclear Information System (INIS)

    Hirschberg, S.; Knochenhauer, M.

    1986-01-01

    Nuclear power plant probabilistic risk assessment (PRA) studies utilise many models, simplifications and assumptions. Also subjective judgement is widely applied due to lack of actual data. This results in significant uncertainties. Three general types of uncertainties have been identified: (1) parameter uncertainties, (2) modelling uncertainties, and (3) completeness uncertainties. The significance of some of the modelling assumptions and simplifications cannot be investigated by assignment and propagation of parameter uncertainties. In such cases the impact of different options may (and should) be studied by performing sensitivity analyses, which concentrate on the most critical elements. This paper describes several items suitable for close examination by means of application of sensitivity analysis, when performing a level 1 PRA. Sensitivity analyses are performed with respect to: (1) boundary conditions (success criteria, credit for non-safety systems, degree of detail in modelling of support functions), (2) operator actions, (3) treatment of common cause failures (CCFs). The items of main interest are continuously identified in the course of performing a PRA study, as well as by scrutinising the final results. The practical aspects of sensitivity analysis are illustrated by several applications from a recent PRA study. The critical importance of modelling assumptions is also demonstrated by implementation of some modelling features from another level 1 PRA into the reference model. It is concluded that sensitivity analysis leads to insights important for analysts, reviewers and decision makers. (author)

  16. Relationship between regulatory issues and probabilistic risk assessments

    International Nuclear Information System (INIS)

    Ilberg, D.; Papazoglou, I.

    1985-01-01

    The objective of this study was to obtain some perspective on the characteristics and the relative number of regulatory issues that are PRA related, i.e., can be effectively addressed by plant specific PRA studies. It was also aimed at developing approaches to resolution of regulatory issues as part of plant specific PRAs. Several ongoing NRC programs include a number of safety-related issues which are applicable to operating plants. A number of these issues include aspects that strongly interact with items addressed in PRA studies. The resolution of several generic issues using PRA studies has already started. A review of over 335 issues included in three NRC programs was conducted: Generic Issue Program (GI); Systematic Evaluation Program (SEP); and TMI Action Plan (TMI). The review identifid 240 items related to PRA, 120 of which were judged to have significant effect on core damage frequency. It is believed that these items can be effectively treated in a PRA study that includes internal and external events

  17. O gigante adormecido vem pra rua: construções enunciativas de Johnnie Walker e Fiat durante as manifestações brasileiras de 2013

    Directory of Open Access Journals (Sweden)

    Carolina Fernandes da Silva Mandaji

    2014-04-01

    Full Text Available O tema deste trabalho são as manifestações ocorridas nos meses de junho e julho de 2013 em todo o Brasil. Trata-se de uma reflexão sobre as construções enunciativas de discursos midiáticos no cenário nacional e internacional.  Esta investigação se propõe a entender os processos enunciativos, e portanto, discursivos e interacionais no uso da materialidade sincrética e audiovisual de anúncios publicitários das marcas Johnnie Walker e Fiat. Tanto a campanha “Keep walking, Brazil” como  a “Vem pra rua” da Fiat foram (re contextualizadas em outros processos enunciativos durante as manifestações brasileiras. Será possível identificar que tipo de interação discursiva ocorre entre marcas e público a partir de tal (re contextualização? Qual relação enunciativa existe entre as marcas e as manifestações e quais são os papeis enunciativos e discursivos propostos por tal relação?  Tais perguntas irão nos levar ao contexto de produção das campanhas, mas também a uma nova apreensão de sentido pautada por processos enunciativos que não os das próprias marcas, mas sim, de novas posições enunciativas. A base metodológica guia-se pelos estudos da Semiótica Discursiva de A. J. Greimas e pelos pressupostos teóricos da Sociossemiótica proposto por Eric Landowski e nas pesquisas de Ana Claudia de Oliveira.

  18. A cultura organizacional do restaurante chalé da praça XV em Porto Alegre: espaços e tempos sendo revelados

    Directory of Open Access Journals (Sweden)

    Letícia Dias Fantinel

    2010-02-01

    Full Text Available Este estudo busca desvendar aspectos da cultura organizacional de um restaurante, ponto turístico da cidade de Porto Alegre, compreendendo sua dimensão simbólica por meio das representações sociais que circulam em seu ambiente, notadamente no que tange às categorias espaço e tempo. Em virtude da complexidade do tema, foram utilizados conceitos e quadros de referência teóricos da antropologia e de outras ciências humanas. O Chalé da Praça XV é um patrimônio que se localiza no centro histórico da cidade, espaço antigo, valorizado no passado pela população e hoje considerado uma vítima da degradação urbana. O método etnográfico foi utilizado na identificação das representações que circulam nesse espaço. O trabalho de campo etnográfico foi conduzido no restaurante entre fevereiro e maio de 2008. Identificaram-se as representações de tempo e espaço elaboradas por clientes e funcionários do restaurante, e desvendaram-se as homogeneidades e as heterogeneidades de sua cultura organizacional. As categorias de análise estabelecidas evidenciam as heterogeneidades presentes em seu espaço como lugar antropológico. Por fim, apresentam-se algumas alternativas para que se pense a gestão do estabelecimento, considerando, entre outros aspectos, seu potencial turístico insuficientemente explorado.

  19. PENGARUH PROGRAM PEMBERIAN MAKANAN TAMBAHAN TERHADAP KEADAAN GIZI ANAK-ANAK PRA-SEKOLAH DI LINGKUNGAN KEBON KELAPA BOGOR

    Directory of Open Access Journals (Sweden)

    Darwin Karyadi

    2012-11-01

    Full Text Available Pengaruh program pemberian makanan tambahan terhadap ke­adaan gizi anak2 prasekolah di Lingkungan Kebon Kelapa, Bogor. (The effect of food supplementation program on the nutritional status of pre-school children. Presented at the Second National Pediatric Congress. Bandung. 1971. One of the main nutrition problems in developing countries is protein calorie malnutrition. The age group that has been most affected is the pre-school child. Serious dietary deficiency will impair his physical and mental developments. The pilot project was designed for the care of pre-school children with signs of malnutrition through a supplementary feeding program. The approach is to educate mothers on how to feed, with locally available foods, and care for their pre-school children; using techniques that are compatible with their under­standing and financial   limitation through   active participation. The duration of the supplementary feeding program was three months. In order to evaluate the program some anthro­pometric measurements, dietary intake study and clinical assess­ment were carried out before and after the program. The results of the study reveal that this program-approach can be recommended in the prevention and in combating malnu­trition in the pre-school child.

  20. Study of prognostic significance of antenatal ultrasonography and renin angiotensin system activation in predicting disease severity in posterior urethral valves

    Directory of Open Access Journals (Sweden)

    Divya Bhadoo

    2015-01-01

    Full Text Available Aims: Study on prognostic significance of antenatal ultrasonography and renin angiotensin system activation in predicting disease severity in posterior urethral valves. Materials and Methods: Antenatally diagnosed hydronephrosis patients were included. Postnatally, they were divided into two groups, posterior urethral valve (PUV and non-PUV. The studied parameters were: Gestational age at detection, surgical intervention, ultrasound findings, cord blood and follow up plasma renin activity (PRA values, vesico-ureteric reflux (VUR, renal scars, and glomerular filtration rate (GFR. Results: A total of 25 patients were included, 10 PUV and 15 non-PUV. All infants with PUV underwent primary valve incision. GFR was less than 60 ml/min/1.73 m 2 body surface area in 4 patients at last follow-up. Keyhole sign, oligoamnios, absent bladder cycling, and cortical cysts were not consistent findings on antenatal ultrasound in PUV. Cord blood PRA was significantly higher (P < 0.0001 in PUV compared to non-PUV patients. Gestational age at detection of hydronephrosis, cortical cysts, bladder wall thickness, and amniotic fluid index were not significantly correlated with GFR while PRA could differentiate between poor and better prognosis cases with PUV. Conclusions: Ultrasound was neither uniformly useful in diagnosing PUV antenatally, nor differentiating it from cases with non-PUV hydronephrosis. In congenital hydronephrosis, cord blood PRA was significantly higher in cases with PUV compared to non-PUV cases and fell significantly after valve ablation. Cord blood PRA could distinguish between poor and better prognosis cases with PUV.

  1. Entre la literatura y la práctica política. Una aproximación a la Venezuela de Rómulo Gallegos

    Directory of Open Access Journals (Sweden)

    Lisandro Angelini

    2014-01-01

    Full Text Available La trayectoria de Rómulo Gallegos, reflejada en sus obras literarias, así como en su rol intelectual y político, resulta una opción pertinente para el análisis del pensamiento de este autor durante el período de consolidación del modelo de Estado-Nación venezolano moderno. Así, el objetivo general de este trabajo es determinar la interacción entre la producción literaria de Rómulo Gallegos y el pro- ceso de construcción del Estado-Nación, teniendo como referencia las condiciones sociales, culturales y políticas del espacio venezolano y el contexto latinoamericano del siglo XX. En tanto que como objetivos específicos se persigue, en primer lugar, identificar el rol intelectual de Gallegos y princi- palmente el impacto de su obra durante la primera mitad del siglo XX. En segundo lugar, analizar las preocupaciones políticas del autor, y el modo en que estas condicionan y contribuyen al contenido de sus narraciones literarias. Respecto al abordaje metodológico de la investigación, este se ha planteado en términos cuali- tativos, debido al carácter del problema y los objetivos definidos. Se ha realizado paralelamente una lectura profunda de las fuentes obtenidas, así como de la bibliografía en general, procediendo a su recolección y organización de las mismas siguiendo la lógica de los objetivos propuestos. Los resultados a los que nos ha conducido el relevamiento de las fuentes y la bibliografía, po- nen de manifiesto que el intento de reconfigurar el relato fundacional venezolano desde la ficción literaria, por un lado, y el objetivo de consolidar un proyecto político renovador, por otro, si bien gozaron de una amplia difusión editorial, no pudieron verse materializados desde la práctica polí- tica, ya que un golpe de Estado, que alejó a Gallegos tempranamente del poder ejecutivo, reinstauró en Venezuela una visión republicana tradicional y un gobierno elitista y autoritario.

  2. Revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (PRA). Updating requirements based on the lessons learned from the Fukushima Dai-ichi NPP Accidents (3). Fragility evaluation and outline of the updated points

    International Nuclear Information System (INIS)

    Yamaguchi, Akira; Nakamura, Susumu; Mihara, Yoshinori

    2014-01-01

    Lessons learned from Great East Japan earthquake and other new findings had been accumulated on the fragility evaluation of buildings and components. And also new analysis and evaluation method had been proposed with the advancement of recent analysis and evaluation technology. These were reflected in revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (PRA). Scope of the fragility evaluation were extended to all equipment on the site, severe accident management equipment including portable equipment and earthquake concomitant incident (such as tsunami) countermeasure equipment. This article described outlines of updating points of the fragility evaluation of the AESJ Standard for Seismic PRA; (1) requirements for seismic induced other risk evaluations such as fire, inundation and tsunami, (2) simulation technology based on recent findings such as three dimensional responses of buildings / structures and its effect on equipment, (3) requirements of the fragility evaluation for various failure mode of several equipment such as severe accident management equipment, fine failure mode of buildings / structures, failures of equipment related with earthquake concomitant incidents (embankment and seawall) and spent fuel pool, and (4) requirements for the fragility evaluation of aftershocks and soil deformation due to fault displacement. (T. Tanaka)

  3. The nucleobase cation symporter 1 of Chlamydomonas reinhardtii and that of the evolutionarily distant Arabidopsis thaliana display parallel function and establish a plant-specific solute transport profile.

    Science.gov (United States)

    Schein, Jessica R; Hunt, Kevin A; Minton, Janet A; Schultes, Neil P; Mourad, George S

    2013-09-01

    The single cell alga Chlamydomonas reinhardtii is capable of importing purines as nitrogen sources. An analysis of the annotated C. reinhardtii genome reveals at least three distinct gene families encoding for known nucleobase transporters. In this study the solute transport and binding properties for the lone C. reinhardtii nucleobase cation symporter 1 (CrNCS1) are determined through heterologous expression in Saccharomyces cerevisiae. CrNCS1 acts as a transporter of adenine, guanine, uracil and allantoin, sharing similar - but not identical - solute recognition specificity with the evolutionary distant NCS1 from Arabidopsis thaliana. The results suggest that the solute specificity for plant NCS1 occurred early in plant evolution and are distinct from solute transport specificities of single cell fungal NCS1 proteins. Copyright © 2013 Elsevier Masson SAS. All rights reserved.

  4. Catalogue of requirements for a plant-specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events; Anforderungskatalog fuer anlagenbezogene Ueberpruefungen deutscher Kernkraftwerke unter Beruecksichtigung der Ereignisse in Fukushima-I (Japan)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-03-30

    The catalogue of requirements for a plant-specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events worked out by the German RSK (reactor safety commission) includes the following inspection topics: natural events like earth quakes, floods, weather-based consequences and possible superposition; civilization-based events like airplane crash, gas release, reactor accident consequences for neighboring units, terroristic impacts, external attacks on computer-based control systems. Further event-independent assumptions have to be considered: station blackout, long-term emergency power supply requirement, failure of auxiliary cooling water supply, efficacy of preventive measures, aggravating boundary conditions for the performance of emergency measures.

  5. Reduced uncertainty of regional scale CLM predictions of net carbon fluxes and leaf area indices with estimated plant-specific parameters

    Science.gov (United States)

    Post, Hanna; Hendricks Franssen, Harrie-Jan; Han, Xujun; Baatz, Roland; Montzka, Carsten; Schmidt, Marius; Vereecken, Harry

    2016-04-01

    Reliable estimates of carbon fluxes and states at regional scales are required to reduce uncertainties in regional carbon balance estimates and to support decision making in environmental politics. In this work the Community Land Model version 4.5 (CLM4.5-BGC) was applied at a high spatial resolution (1 km2) for the Rur catchment in western Germany. In order to improve the model-data consistency of net ecosystem exchange (NEE) and leaf area index (LAI) for this study area, five plant functional type (PFT)-specific CLM4.5-BGC parameters were estimated with time series of half-hourly NEE data for one year in 2011/2012, using the DiffeRential Evolution Adaptive Metropolis (DREAM) algorithm, a Markov Chain Monte Carlo (MCMC) approach. The parameters were estimated separately for four different plant functional types (needleleaf evergreen temperate tree, broadleaf deciduous temperate tree, C3-grass and C3-crop) at four different sites. The four sites are located inside or close to the Rur catchment. We evaluated modeled NEE for one year in 2012/2013 with NEE measured at seven eddy covariance sites in the catchment, including the four parameter estimation sites. Modeled LAI was evaluated by means of LAI derived from remotely sensed RapidEye images of about 18 days in 2011/2012. Performance indices were based on a comparison between measurements and (i) a reference run with CLM default parameters, and (ii) a 60 instance CLM ensemble with parameters sampled from the DREAM posterior probability density functions (pdfs). The difference between the observed and simulated NEE sum reduced 23% if estimated parameters instead of default parameters were used as input. The mean absolute difference between modeled and measured LAI was reduced by 59% on average. Simulated LAI was not only improved in terms of the absolute value but in some cases also in terms of the timing (beginning of vegetation onset), which was directly related to a substantial improvement of the NEE estimates in

  6. Learning Astronomy by Playing in a Park. (Spanish Title: Aprender AstronoMía Jugando en Una Plaza.) Aprender Astronomia Brincando em Uma Praça

    Science.gov (United States)

    Camino, Néstor

    2012-12-01

    trabalho alguns jogos de praça, considerados como módulos didáticos para imaginar processos astronômicos, a partir da concepção de que a aprendizagem em Astronomia deve-se desenvolver fortalecendo a relação do próprio corpo com o espaço tridimensional e com o tempo, tal como se vive ao observar o céu, construindo um "diálogo" entre o mundo real e as aprendizagens a construir. Os jogos apresentados (carrosséis e tobogãs) foram desenhados para trabalhar sobre a translação da Terra em torno do Sol, as fases da Lua e a gravidade, e sobre o que um observador percebe dos mesmos. Dá-se a descrição de cada jogo, discutem-se seus fundamentos físicos e astronômicos, e desenvolve-se uma crítica didática dos mesmos. Finalmente, comenta-se o papel que deveriam ter os docentes no apoio aos aprendizes no processo de interação com os jogos apresentados.

  7. A study on the impact of CYP2C19 genotype and platelet reactivity assay on patients undergoing PCI

    Directory of Open Access Journals (Sweden)

    P.C. Rath

    2015-03-01

    Conclusion: Clopidogrel resistance was observed to be 16.5% in our study population. PRA was useful in monitoring the efficacy of thienopyridines. By having this test, one can be safely maintained on clopidogrel in non-carriers, or with increased dose of clopidogrel in intermediate metabolizers or with newer drugs such as ticagrelor or prasugrel in poor metabolizers. Patients on ticagrelor and prasugrel identified as non-carriers of gene mutations for clopidogrel metabolism could be offered clopidogrel resulting in economic benefits to the patients. Patients at high risk of bleeding were also identified by the PRA.

  8. A paisagem urbana como herança cultural: a praça Santos Dumont, Umuarama, Estado do Paraná, Brasil = The urban landscape as a cultural heritage: Santos Dumont plaza, Umuarama, Paraná State, Brazil

    Directory of Open Access Journals (Sweden)

    Alexander Fabbri Hulsmeyer

    2011-04-01

    Full Text Available A paisagem urbana possui uma forte conotação histórica, e pode ser considerada uma herança cultural. Neste contexto, os espaços livres públicos podem converter-se em registros importantes, fortalecendo tradições, valores e identidades. Nos quatro principais núcleosurbanos projetados pela Companhia de Terras do Norte do Paraná CTNP, e denominada Companhia Melhoramentos Norte do Paraná CMNP após 1942, as praças exercem o papel de elementos ordenadores na configuração dos centros cívico, religioso e comercial, demonstrando a íntima relação entre os espaços livres públicos e seu entorno. Esta pesquisa1 teve o objetivo de analisar, a partir da pesquisa dos registros fotográficos, jornais de época e bibliografia referente àsraízes conceituais do traçado morfológico da cidade e seu contexto histórico, a Praça Santos Dumont, maior praça e palco de importantes momentos da história da jovem cidade de Umuarama, Estado do Paraná.The urban landscape has strong historical meaning because it can be considered as cultural heritage. In this context, public open spaces are important registries, reinforcing traditions, values and identities. In the four main cities projected by the Companhia Melhoramentos Norte do Paraná (CMNP, the squares and plazas carry out the task of ordination elements for the configuration of the civic, religious and commercial centers, reinforcing the close relation between public open spaces and their surroundings. This research was done under the Scientific Initiation Program of Universidade Paranaense, and is about Santos Dumont Plaza, the biggest one that supported important historical moments of earlyUmuarama, in northwestern Paraná, Brazil. The analysis was based on the research of photographic registries, newspapers, and the publications about the conceptual roots of the urban morphology of the city and its historical context.

  9. Toxocara spp. eggs in public squares of Sorocaba, São Paulo State, Brazil Ovos de Toxocara spp. em praças públicas no município de Sorocaba, São Paulo, Brasil

    Directory of Open Access Journals (Sweden)

    Lina Maria De Petrini da Silva COELHO

    2001-08-01

    Full Text Available The visceral larva migrans (VLM is a syndrome observed in human infection with helminth larval eggs such as the Toxocara spp. that usually infects dogs and cats. Among the risk factors involved in the occurrence of VLM, particularly important is the size of these animal populations. Sorocaba is a city with a dog population twice as large as that recommended by the World Health Organization. This fact has led to a survey of the presence of Toxocara spp. eggs in public square soils of this city. Thirty squares were selected, fifteen located in the outskirts of the city and fifteen downtown. Soil samples were collected from five distinct sites in the same area. The material was homogenized and drained and 100 g was mixed with a saturated solution of magnesium sulfate and 5% potassium iodine. The floating material was analyzed under the light microscope. Toxocara spp. eggs were found in 16 squares, nine of which were located in the outskirts of the city and seven downtown. It was concluded that Sorocaba squares present a high rate of contamination with Toxocara spp. eggs. The squares in the outskirts of the city presented a higher occurrence of these eggs in comparison with those downtown, although the difference was not statistically significant (p > 0.05.A larva migrans visceral - LMV - é uma síndrome causada pela infecção humana por ovos larvados de helmintos como o Toxocara spp., que usualmente compromete o cão e o gato. Dentre os fatores de risco para a ocorrência da LMV, destaca-se o tamanho da população desses animais. Sorocaba é uma cidade com uma população canina duas vezes superior à recomendada pela Organização Mundial de Saúde. Este fato levou à pesquisa da presença de ovos de Toxocara spp. no solo de áreas públicas nessa cidade. Foram escolhidas 30 praças, sendo 15 de regiões periféricas e 15 centrais. Coletaram-se amostras de solo de 5 locais distintos da mesma área. O material foi homogeneizado, tamisado e, em

  10. ANALYSIS OF AGRO-ECOLOGICAL SITUATION FOR IDENTIFICATION OF PROBLEMS BY PRA TECHNIQUES IN ADAPTIVE VILLAGE OF KRISHI VIGYAN KENDRA UNDER NEW ALLUVIA ZONE OF MURSHIDABAD DISTRICT OF WEST BENGAL

    Directory of Open Access Journals (Sweden)

    Abhishake Naskar

    2011-07-01

    Full Text Available Agro Ecosystem analysis using the Participatory Rural Appraisal (PRA techniques of an adaptive village (Jainpur of New Alluvial Zone of Murshidabad-Jiaganj block in Murshidabad district, West Bengal revealed that the village basically has rice and jute based farming system. The cropping intensity of the village is 233%. Out of 363 household 80% is engaged in Agriculture, Animal Husbandry and other allied activities. The land availability per household is 0.40 ha. The villagers are mostly scheduled caste. By snow ball technique major problems were identified .On the basis of bio-physical and socio-economic problems, thrust area were selected. Area specific On Farm Trials (OFT in farmers' were conducted on some researchable issues. Front Line Demonstration (FLD, training programme, health camp, awareness camp and other different extension activities were arranged to mitigate the problems.

  11. Can professors be socialized in good teaching practices? The case of the Project Visibilidad Socialización Docente de Profesores Universitarios Españoles con Buenas Prácticas Docentes Podem os Professores socializar-se em boas práticas de ensino? O caso do Projeto Visibilidade

    Directory of Open Access Journals (Sweden)

    María Muradás López

    2010-08-01

    Full Text Available The purpose of this study is to analyze the socialization to teaching experience of faculty who participated in the project Visibilidad. The main objective of this project was to obtain knowledge related to teaching from faculty who are considered good teachers in Spanish universities. This knowledge could enlighten how the socialization to teaching occurs as well as insights on how to improve the process. Based on the international literature on socialization to teaching in higher education and using a methodology of generating themes inductively, the experiences of faculty at the beginning of their careers were analyzed. The data was collected using semi-structured interviews. We found that role models of socialization, self-reflection and formal socialization are the most common experiences reported by participants. This suggests that reinforcing these elements deliberately at an institutional level, it is possible to improve the socialization process of new faculty in higher education as well as their teaching practices. El propósito de este estudio es el análisis de la experiencia de socialización docente vivida por los profesores participantes en el proyecto Visibilidad, cuyo objetivo principal fue la extracción del conocimiento experto de docentes señalados como buenos profesores en universidades españolas. El conocimiento experto de estos docentes puede dar luz a cómo hasta ahora se ha producido la socialización docente y pistas de cómo mejorar este proceso. Con base en la literatura internacional sobre socialización en Educación Superior y siguiendo un modelo inductivo de generación de categorías, se analizaron las vivencias en el inicio de la carrera docente de profesores universitarios. Los datos fueron obtenidos de entrevistas semiestructuradas. Se encontró que los modelos de referencia de socialización, la reflexión autodidacta por parte de los profesores, y su formación son los tópicos con ma

  12. Real-time risk assessment of operational events

    International Nuclear Information System (INIS)

    Perryman, L.J.; Foster, N.A.S.; Nicholls, D.R.; Grobbelaar, J.F.

    1996-01-01

    Probabilistic risk assessment (PRA) has always been fundamental to the licensing process of Koeberg nuclear power station. Furthermore, over the past 8 years PRA has assisted in many areas of operation. One of these areas is the real-time assessment of abnormal operating events. Over the years, considerable experience has been gained in using PRA to improve plant safety and performance. This paper presents some of the insights obtained in using PRA in such a dynamic role and demonstrates that, by developing and using the plant-specific 'living' PRA, considerable safety and financial gains can be obtained. These insights specifically concern the prerequisites before optimal use of a plant-specific 'living' PRA can be made. Finally, examples are presented of occurrences when PRA was used to improve plant safety and performance. These examples serve to demonstrate the advantages that can be obtained if sufficient resources are placed at the disposal of the PRA team. (orig.)

  13. A praça: intervenções contemporâneas em espaços de património The square: contemporary interventions in heritage places

    Directory of Open Access Journals (Sweden)

    Flavio Barbini

    2012-12-01

    Full Text Available Na cidade portuguesa contemporânea, a praça constitui uma herança urbanística de matriz europeia cujo valor patrimonial é fundamental como parte da história urbana, mas também de sua vivência e memória. Essa matriz foi, posteriormente, exportada para países não europeus, tornando-se indispensável na cidade colonial. Nos últimos 20 anos, as políticas urbanas de salvaguarda e conservação dos centros históricos deram origem a três tipos de ações de remodelação de praças: intervenções da responsabilidade dos serviços técnicos das câmaras municipais; intervenções resultantes de concursos públicos, lideradas por arquitetos; intervenções sob encomenda direta, geralmente coordenadas por arquitetos de reconhecido mérito nacional e internacional. Nesse contexto, existem duas metodologias de projeto fundamentais: de cariz estritamente conservacionista ou mais abertas a uma reinterpretação contemporânea de modelos, desenhos e sistemas construtivos resultantes da cultura urbana local. A opção por uma dessas abordagens é, frequentemente, marcada pela época em que é realizada e está fortemente relacionada com a produção teórica e as cartas e recomendações de organismos internacionais existentes e também com uma prática associada a uma disciplina de intervenção em arquitetura, regida por influências globalizantes. Neste artigo, propõe-se a análise do contexto português, tendo como ponto de chegada um duplo objetivo: fornecer uma análise urbana da intervenção na cidade consolidada, identificando as inflexões fundamentais que lhe deram origem; e estabelecer as bases para um projeto de investigação congénere no espaço da lusofonia, que identifique eventuais semelhanças e dissemelhanças, conducentes ao estudo de uma hipótese de existência de lusofilias urbanas contemporâneas dentro dessa temática.

  14. Inactivation of the β(1,2)-xylosyltransferase and the α(1,3)-fucosyltransferase genes in Nicotiana tabacum BY-2 Cells by a Multiplex CRISPR/Cas9 Strategy Results in Glycoproteins without Plant-Specific Glycans.

    Science.gov (United States)

    Mercx, Sébastien; Smargiasso, Nicolas; Chaumont, François; De Pauw, Edwin; Boutry, Marc; Navarre, Catherine

    2017-01-01

    Plants or plant cells can be used to produce pharmacological glycoproteins such as antibodies or vaccines. However these proteins carry N -glycans with plant-typical residues [β(1,2)-xylose and core α(1,3)-fucose], which can greatly impact the immunogenicity, allergenicity, or activity of the protein. Two enzymes are responsible for the addition of plant-specific glycans: β(1,2)-xylosyltransferase (XylT) and α(1,3)-fucosyltransferase (FucT). Our aim consisted of knocking-out two XylT genes and four FucT genes (12 alleles altogether) in Nicotiana tabacum BY-2 suspension cells using CRISPR/Cas9. Three XylT and six FucT sgRNAs were designed to target conserved regions. After transformation of N. tabacum BY-2 cells with genes coding for sgRNAs, Cas9, and a selectable marker ( bar ), transgenic lines were obtained and their extracellular as well as intracellular protein complements were analyzed by Western blotting using antibodies recognizing β(1,2)-xylose and α(1,3)-fucose. Three lines showed a strong reduction of β(1,2)-xylose and α(1,3)-fucose, while two lines were completely devoid of them, indicating complete gene inactivation. The absence of these carbohydrates was confirmed by mass spectrometry analysis of the extracellular proteins. PCR amplification and sequencing of the targeted region indicated small INDEL and/or deletions between the target sites. The KO lines did not show any particular morphology and grew as the wild-type. One KO line was transformed with genes encoding a human IgG2 antibody. The IgG2 expression level was as high as in a control transformant which had not been glycoengineered. The IgG glycosylation profile determined by mass spectrometry confirmed that no β(1,2)-xylose or α(1,3)-fucose were present on the glycosylation moiety and that the dominant glycoform was the GnGn structure. These data represent an important step toward humanizing the glycosylation of pharmacological proteins expressed in N. tabacum BY-2 cells.

  15. A dominant mutation in mediator of paramutation2, one of three second-largest subunits of a plant-specific RNA polymerase, disrupts multiple siRNA silencing processes.

    Science.gov (United States)

    Sidorenko, Lyudmila; Dorweiler, Jane E; Cigan, A Mark; Arteaga-Vazquez, Mario; Vyas, Meenal; Kermicle, Jerry; Jurcin, Diane; Brzeski, Jan; Cai, Yu; Chandler, Vicki L

    2009-11-01

    Paramutation involves homologous sequence communication that leads to meiotically heritable transcriptional silencing. We demonstrate that mop2 (mediator of paramutation2), which alters paramutation at multiple loci, encodes a gene similar to Arabidopsis NRPD2/E2, the second-largest subunit of plant-specific RNA polymerases IV and V. In Arabidopsis, Pol-IV and Pol-V play major roles in RNA-mediated silencing and a single second-largest subunit is shared between Pol-IV and Pol-V. Maize encodes three second-largest subunit genes: all three genes potentially encode full length proteins with highly conserved polymerase domains, and each are expressed in multiple overlapping tissues. The isolation of a recessive paramutation mutation in mop2 from a forward genetic screen suggests limited or no functional redundancy of these three genes. Potential alternative Pol-IV/Pol-V-like complexes could provide maize with a greater diversification of RNA-mediated transcriptional silencing machinery relative to Arabidopsis. Mop2-1 disrupts paramutation at multiple loci when heterozygous, whereas previously silenced alleles are only up-regulated when Mop2-1 is homozygous. The dramatic reduction in b1 tandem repeat siRNAs, but no disruption of silencing in Mop2-1 heterozygotes, suggests the major role for tandem repeat siRNAs is not to maintain silencing. Instead, we hypothesize the tandem repeat siRNAs mediate the establishment of the heritable silent state-a process fully disrupted in Mop2-1 heterozygotes. The dominant Mop2-1 mutation, which has a single nucleotide change in a domain highly conserved among all polymerases (E. coli to eukaryotes), disrupts both siRNA biogenesis (Pol-IV-like) and potentially processes downstream (Pol-V-like). These results suggest either the wild-type protein is a subunit in both complexes or the dominant mutant protein disrupts both complexes. Dominant mutations in the same domain in E. coli RNA polymerase suggest a model for Mop2-1 dominance

  16. Technological Development of High-Performance MALDI Mass Spectrometry Imaging for the Study of Metabolic Biology

    Energy Technology Data Exchange (ETDEWEB)

    Feenstra, Adam D. [Iowa State Univ., Ames, IA (United States)

    2016-12-17

    This thesis represents efforts made in technological developments for the study of metabolic biology in plants, specifically maize, using matrix-assisted laser desorption/ ionization-mass spectrometry imaging.

  17. Effect of antigravity suit inflation on cardiovascular, PRA, and PVP responses in humans. [Plasma Renin Activity and Plasma VasoPressin

    Science.gov (United States)

    Kravik, S. E.; Keil, L. C.; Geelen, G.; Wade, C. E.; Barnes, P. R.

    1986-01-01

    The effects of lower body and abdominal pressure, produced by antigravity suit inflation, on blood pressure, pulse rate, fluid and electrolyte shift, plasma vasopressin and plasma renin activity in humans in upright postures were studied. Five men and two women stood upright for 3 hr with the suit being either inflated or uninflated. In the control tests, the suit was inflated only during the latter part of the trials. Monitoring was carried out with a sphygnomanometer, with sensors for pulse rates, and using a photometer and osmometer to measure blood serum characteristics. The tests confirmed earlier findings that the anti-g suit eliminates increases in plasma renin activity. Also, the headward redistribution of blood obtained in the tests commends the anti-g suit as an alternative to water immersion or bed rest for initial weightlessness studies.

  18. “Quem está preparado pra isso?”... Reflexões sobre a formação docente para as homossexualidades

    Directory of Open Access Journals (Sweden)

    Anderson Ferrari

    2013-06-01

    Full Text Available Using a question asked by a student in a training course about sexualities, this paper aims to problematize this training process, which together with gender and sexuality constructions provoke us to think the individuals’ constitution processes. In order to do so, the methodology employed was observation and analyses of the authors’ experience in three courses for teachers. The discourse produced in such contexts was brought to the text. Such issues favor the authors’ contact with post-structuralism and Foucault studies, whose focus is on discourses and practices which constitute the subject and on power relations. As the main result, the paper points to the need to count on “detachment of the self” which involves training in investment on questioning rather than on answers and “truths”.

  19. Uji Biologis Konsumsi Pakan, Populasi Bakteri Rumen dan pH Pellet Complete Calf Starter pada Pedet Friesian Holstein Pra Sapih

    Directory of Open Access Journals (Sweden)

    Nadia Maharani

    2015-04-01

    Full Text Available (Biological test feed intake, population rumen bacteria and ph pellet complete calf starter friesian holstein on pre weaning calf  ABSTRACT. The study aims to assess the quality of the formula Complete Calf Starter (CCS with 5% molasses instead of milk to the development of rumen microbial calf Holstein Friesian (HF pre-weaning. The material used is 20 head calf FH pre weaning age of 2 weeks. Feed intake data taken from 20 respondents consisted of 16 females and 4 calf tail male calf. Data rumen bacterial populations and pH were taken from 5 head of cattle slaughtered at the age of 2 weeks (one tail, 4 weeks (2-tailed and 6 weeks (2-tailed. The study was designed as a descriptive non-parametric. Parameters measured were rumen bacterial populations, pH and feed intake. The results showed the average consumption of dry matter (DM and CCS calf milk FH ages 2, 4, 6 weeks respectively at 506, 517, 528 grams. Rumen bacterial populations in calves aged 2, 4, and 6 weeks of 80x106, 45x106 and 19x106 kol/m. ruminal pH in calves aged 2, 4 and 6 weeks was 5.71, 5.36 and 5.55. Biological test showed that the use of complete calf starter (CCS in the form of pellets FH calves at the age of 2 weeks to stimulate the development of the rumen (feed intake, the population of bacteria and pH but not in calves aged 4 and 6 weeks. This is because the number of bacterial populations declined due to impaired absorption is impaired absorption of VFA marked low rumen pH.

  20. German risk study of PWR's

    International Nuclear Information System (INIS)

    Kafka, P.

    1983-01-01

    In this paper, first the status of German Risk Study is presented briefly. Specific reference is made to the investigations in Phase B of the study and related programs. Significant elements involved in the risk assessment for NPPs, mainly in the field of system and structural reliability analyses are mentioned. In particular, important outcomes and limiting facts in the process of a Probabilistic Risk Assessment (PRA) to evaluate the safety standard and above all the influence of individual components or subsystems on core melt frequency are discussed. (orig.)

  1. A aplicação da teoria da aprendizagem significativa de Ausubel na prática improvisatória

    Directory of Open Access Journals (Sweden)

    César Albino

    2008-12-01

    Full Text Available This article deals with the application of D. P. Ausubel’s Theory of Meaningful Learning in the musical teaching processes, mainly in the improvisational practice. It is sub- divided into three parts: the first one analyses various teaching approaches, especially the traditional and the constructivist; the second one specifically deals with the theory; the third one refers to some theoretical concepts that can be applied in the improvisational practice. Part of the narrative was taken from the Master of Arts dissertation The importance of the teaching of musical improvisation in the interpreter’s development (Institute of Arts – São Paulo State University. In addition to D. P. Ausubel, this study also relied on works by other scholars, among them Vera Jardim, Liliana Bollos, Maria da Graça N. Mizukami and Gilles Deleuze. The use of this theory represents an excellent opportunity of interaction between the musical theory and practice, making use of cognitive processes already in use in the field of education but not so valued by musical education, particularly in matters of musical improvisation teaching.

  2. Bioremediation system on-line for removal radionuclides in radioactive waters; Sistema de biorremediation on-line pra la eliminacion de radionuclidos en aguas radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Belinchon, J. A.; Garcia, A. M.; Ruibal, C.; Moreno, D. A.

    2010-07-01

    In previous studies developed in Cofrentes Nuclear Power Plant (Valencia, Spain), has been observed that the microorganisms in the radioactive waters of the spent nuclear fuel pool are capable of colonizing the metallic surfaces of the walls and pipes and perform biofilm. These biofilm retain the nuclides contributing to decontaminate the water. In this project, carried out in Cofrentes Nuclear Power Plant, a pilot plant has been designed for the bio decontamination of the radioactive water. At present, the radioactive water coming from the spent nuclear fuel pools, pass through ionic exchange resins. After, these resins are managed as radioactive waste. In this project, the water passes through a bioreactor with stainless steel balls capable of being colonized by the microorganisms in the water. Inside the bioreactor the water gets in contact with the material of the balls, and a biofilm, which retains the nuclides in the water, is developed. The biofilm is easily removed by any conventional procedure of radiochemical decontamination of materials and the nuclides can be collected in a small volume for recovery final disposition or containment. Later, the material of the bioreactor could be managed as not radioactive material. (Author) 9 refs.

  3. Applying the results of probablistic safety analysis of nuclear power plants: a survey of experience

    International Nuclear Information System (INIS)

    Andrews, W.B.; Herttrich, M.; Koeberlein, K.; Schwager.

    1985-01-01

    To date, discussions of the many different types of potential applications of PRA/PSA results and insights to safety-decision-making have been mainly theoretical. Various safety goals have been proposed as decision criteria. However, the discussion on the role of PRA/PSA and Safety Goals in safety-decision-making, especially in licensing, is controversial. A Working Group of the OECD Nuclear Energy Agency is completing a compilation and evaluation of real examples of past and present practical experience with the application of probabilistic methods in reactor safety decision-making, with the idea of developing a common understanding in this area. More than fifty different cases where PRA has influenced decision-making have been surveyed. These include, for example, regulatory changes, fixing of licensing requirements, plant specific modifications of design of operation, prioritization of safety issues and emergency planning. This feedback of experience - both positive and negative - with PRA/PSA applications is considered to provide guidance on how probabilistic approaches can be introduced into current safety practices, and on desirable future developments in probabilistic methods and specific PSA/PRA studies. Generic insights from the survey are given

  4. Overview of NRC PRA research program

    International Nuclear Information System (INIS)

    Cunningham, M.A.; Drouin, M.T.; Ramey-Smith, A.M.; VanderMolen, M.T.

    1997-01-01

    The NRC's research program in probabilistic risk analysis includes a set of closely-related elements, from basic research to regulatory applications. The elements of this program are as follows: (1) Development and demonstration of methods and advanced models and tools for use by the NRC staff and others performing risk assessments; (2) Support to agency staff on risk analysis and statistics issues; (3) Reviews of risk assessments submitted by licensees in support of regulatory applications, including the IPEs and IPEEEs. Each of these elements is discussed in the paper, providing highlights of work within an element, and, where appropriate, describing important support and feedback mechanisms among elements

  5. Applications of PRA in nuclear criticality safety

    International Nuclear Information System (INIS)

    McLaughlin, T.P.

    1992-01-01

    Traditionally, criticality accident prevention at Los Alamos National Laboratory (LANL) has been based on a thorough review and understanding of proposed operations or changes to operations involving both process supervision and criticality safety staff. The outcome of this communication was usually an agreement, based on professional judgment, that certain accident sequences were credible and had to be precluded by design; others were incredible and thus did not warrant expenditures to further reduce their likelihood. The extent of documentation was generally in proportion to the complexity of the operation but never as detailed as that associated with quantified risk assessments. During the last 3 yr, nuclear criticality safety-related probabilistic risk assessments (PRAs) have been performed on operations in two LANL facilities. Both of these were conducted in order to better understand the cost/benefit aspects of PRAs as they apply to largely hands-on operations with fissile material

  6. Trial application of PRATOOL: Performance of sensitivity studies on service water systems

    International Nuclear Information System (INIS)

    Gregg, R.E.; Wood, S.T.

    1991-03-01

    PRATOOL is a computer program developed to supplement the Integrated Reliability and Risk Analysis System (IRRAS) probabilistic risk assessment (PRA) computer program. It is intended to be a tool for performing PRA sensitivity analyses. This will allow a PRA's results to be easily reevaluated to show its sensitivity to changing parameter (system, component type, basic event, etc.) values (i.e., failure rates). This report documents a trial application of PRATOOL. It evaluates the sensitivity of core damage frequency to service water system availability at several nuclear power plants. For the purpose of this trail application of PRATOOL, service water system sensitivity studies were performed using the results of several NUREG- 1150 PRAs. These plants were chosen because their PRAs were already loaded into the IRRAS data base. Therefore, they are readily available for this type of study. PRATOOL contains a small subset of the functions provided by IRRAS. The user can select sets of parameters that will act as the bases for sensitivity analyses. Depending on the PRA used, the parameters selected can include: systems, component types, trains, locations, failure modes, and basic events. It will also perform and AND-ing operation on selected parameters. This allows the user define any number of possible combinations of parameters. The results of the four sensitivity studies would tend to indicate that the SWS availability is important for BWRs but unimportant for PWRs. Both BWRs showed significant increases in CDF if their SWS failure rates are allowed to increase. From the results of the four sensitivity studies, it is interesting to note that no improvements made to any of the SWSs' failure rates would result in a significant decrease on CDF. 10 figs

  7. KESINAMBUNGAN MOTIF HIAS MASA PRA-ISLAM STUDI KASUS PADA MIMBAR MASJID KAJORAN THE CONTINUITY OF ORNAMENTAL MOTIVES IN PRE-ISLAMIC PERIOD A CASE STUDY INTHE PODIUMOF KAJORAN MOSQUE

    Directory of Open Access Journals (Sweden)

    Endang Widyastuti

    2016-06-01

    ABSTRAK             Masuknya agama Islam memberikan warna baru dalam bidang kesenian khususnya seni hias. Dalam agama Islam terdapat larangan untuk menggambar makhluk hidup sehingga dilakukan upaya untuk menyamarkannya. Pada mimbar masjid Kajoran terdapat hiasan dengan motif binatang dan tumbuh-tumbuhan. Berdasarkan pengamatan diketahui bahwa selain motif-motif geometris, pada mimbar tersebut juga terdapat motif-motif berupa gajah, naga, burung, dan bunga teratai. Kemungkinan makna motif-motif hias tersebut masih relevan dengan ajaran Islam. Hal ini menunjukkan besarnya toleransi agama Islam terhadap kebudayaan yang telah ada pada suatu daerah, selama tidak bertentangan dengan ajaran agama Islam.   Kata Kunci: mimbar, motif hias, masjid Kajoran

  8. DETECÇÃO DO COMPLEXO Mycobacterium tuberculosis NO LEITE PELA REAÇÃO EM CADEIA DA POLIMERASE SEGUIDA DE ANÁLISE DE RESTRIÇÃO DO FRAGMENTO AMPLIFICADO (PRA DETECTION OF Mycobacterium tuberculosis COMPLEX BY PCR-RESTRICTION FRAGMENT LENGTH POLYMORFISM ANALYSIS OF THE HSP65 GENE

    Directory of Open Access Journals (Sweden)

    Joab Trajano Silva

    2008-12-01

    Full Text Available Mycobacterium bovis é membro do complexo Mycobacterium tuberculosis (MTBC, grupo este composto por espécies com grande homologia genética. É o agente etiológico da tuberculose bovina, importante zoonose transmissível ao homem, principalmente através da inalação do bacilo e/ou pelo consumo de leite e derivados não-pasteurizados provenientes de vacas tuberculosas. O objetivo deste estudo foi padronizar a identificação de micobactérias do complexo M. tuberculosis presentes no leite, por metodologia molecular. Fez-se a extração de DNA diretamente do leite contaminado e realizou-se a identificação molecular pela reação em cadeia da polimerase seguida de análise de restrição do fragmento amplificado (PRA. Utilizaram-se inhagens de referência e leite cru artificialmente contaminado com M. bovis IP. Um fragmento de 441pb do gene hsp65 foi amplificado, tratado com BstEII e HaeIII e empregou-se o perfil de restrição enzimática obtido para identificar o complexo M. tuberculosis no leite. Com a PRA foi possível detectar com especificidade e sensibilidade a presença de M. bovis em até 10 UFC/mL de leite. A metodologia padronizada poderá auxiliar os métodos microbiológicos e bioquímicos tradicionalmente usados na identificação do bacilo em alimentos suspeitos de contaminação, como, por exemplo, o leite proveniente de animais suspeitos de infecção por M. bovis.

    Palavras-chaves: Análise de perfil de restrição enzimática (PRA, complexo Mycobacterium tuberculosis, leite, Mycobacterium bovis, limite de detecção (PCR. Mycobacterium bovis is a member of the M. tuberculosis complex, a group composed by species with high genetic homology. The pathogen is the etiological agent of bovine tuberculosis, an important zoonosis that is mainly transmitted by inhalation of infectious droplet nuclei or by ingestion of milk and crude milk derivative products from tuberculosis cows. The definitive identification of M. bovis

  9. 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)

  10. The Optimal Approach for Laparoscopic Adrenalectomy through Mono Port regarding Left or Right Sides: A Comparative Study

    Directory of Open Access Journals (Sweden)

    Wooseok Byon

    2014-01-01

    Full Text Available Introduction. Several studies have shown the feasibility and safety of both transperitoneal and posterior retroperitoneal approaches for single incision laparoscopic adrenalectomy, but none have compared the outcomes according to the left- or right-sided location of the adrenal glands. Materials and Methods. From 2009 to 2013, 89 patients who received LAMP (laparoscopic adrenalectomy through mono port were analyzed. The surgical outcomes attained using the transperitoneal approach (TPA and posterior retroperitoneal approach (PRA were analyzed and compared. Results and Discussion. On the right side, no significant differences were found between the LAMP-TPA and LAMP-PRA groups in terms of patient characteristics and clinicopathological data. However, outcomes differed in which LAMP-PRA group had a statistically significant shorter mean operative time (84.13 ± 41.47 min versus 116.84 ± 33.17 min; P=0.038, time of first oral intake (1.00 ± 0.00 days versus 1.21 ± 0.42 days; P=0.042, and length of hospitalization (2.17 ± 0.389 days versus 3.68 ± 1.38 days; P≤0.001, whereas in left-sided adrenalectomies LAMP-TPA had a statistically significant shorter mean operative time (83.85 ± 27.72 min versus 110.95 ± 29.31 min; P=0.002. Conclusions. We report that LAMP-PRA is more appropriate for right-sided laparoscopic adrenalectomies due to anatomical characteristics and better surgical outcomes. For left-sided laparoscopic adrenalectomies, however, we propose LAMP-TPA as a more suitable method.

  11. Auxiliary feedwater system risk-based inspection guide for the North Anna nuclear power plants

    International Nuclear Information System (INIS)

    Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1992-10-01

    In a study sponsored by the US Nuclear regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. North Anna was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the North Anna plant

  12. Auxiliary feedwater system risk-based inspection guide for the Palo Verde Nuclear Power Plant

    International Nuclear Information System (INIS)

    Bumgardner, J.D.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Sloan, J.A.

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Palo Verde was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Palo Verde plants

  13. Auxiliary feedwater system risk-based inspection guide for the McGuire nuclear power plant

    International Nuclear Information System (INIS)

    Bumgardner, J.D.; Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1994-05-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. McGuire was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant

  14. Auxiliary feedwater system risk-based inspection guide for the South Texas Project nuclear power plant

    International Nuclear Information System (INIS)

    Bumgardner, J.D.; Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1993-12-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. South Texas Project was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the South Texas Project plant

  15. Auxiliary feedwater system risk-based inspection guide for the Beaver Valley, Units 1 and 2 nuclear power plants

    International Nuclear Information System (INIS)

    Lloyd, R.C.; Vehec, T.A.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Rossbach, L.W.; Sena, P.P. III

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Beaver Valley Units 1 and 2 were selected as two of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at Beaver Valley Units 1 and 2

  16. Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gore, B.F.; Vo, T.V.; Moffitt, N.E.; Bumgardner, J.D.

    1992-10-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. The information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Maine Yankee was selected as one of a series of plants for study. ne product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Maine Yankee plant

  17. Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants

    International Nuclear Information System (INIS)

    Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1991-07-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Byron and Braidwood were selected for the fourth study in this program. The produce of this effort is a prioritized listing of AFW failures which have occurred at the plants and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Byron/Braidwood plants. 23 refs., 1 fig., 1 tab

  18. Auxiliary feedwater system risk-based inspection guide for the H. B. Robinson nuclear power plant

    International Nuclear Information System (INIS)

    Moffitt, N.E.; Lloyd, R.C.; Gore, B.F.; Vo, T.V.; Garner, L.W.

    1993-08-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. H. B. Robinson was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the H. B. Robinson plant

  19. Auxiliary feedwater system risk-based inspection guide for the J.M. Farley Nuclear Power Plant

    International Nuclear Information System (INIS)

    Vo, T.V.; Pugh, R.; Gore, B.F.; Harrison, D.G.

    1990-10-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment(PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. J. M. Farley was selected as the second plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important at the J. M. Farley plant. 23 refs., 1 fig., 1 tab

  20. Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

    International Nuclear Information System (INIS)

    Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Vehec, T.A.

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant

  1. Auxiliary feedwater system risk-based inspection guide for the Ginna Nuclear Power Plant

    International Nuclear Information System (INIS)

    Pugh, R.; Gore, B.F.; Vo, T.V.; Moffitt, N.E.

    1991-09-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Ginna was selected as the eighth plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Ginna plant. 23 refs., 1 fig., 1 tab

  2. Parasitas zoonóticos em fezes de cães em praças públicas do município de Itabuna, Bahia, Brasil Zoonotic parasites in dog feces at public squares in the municipality of Itabuna, Bahia, Brazil

    Directory of Open Access Journals (Sweden)

    Pedro C. Campos Filho

    2008-12-01

    Full Text Available Avaliou-se a contaminação de praças públicas da área urbana do município de Itabuna, BA, Brasil, por parasitos zoonóticos presentes em fezes de cães. Foram coletadas 119 amostras fecais de cães em 10 praças. Logo após, estas fezes foram encaminhadas ao Laboratório de Parasitologia da UESC e analisadas pelo método de Mariano e Carvalho. Do total das amostras analisadas, 56,3% continham alguma forma evolutiva parasitária, sendo o parasita mais freqüente Ancylostoma sp. com 47,9%, seguido por 6,7% de Strongyloides stercortalis, 4,2% tanto para ovos de Toxocara canis quanto de Trichuris vulpis, 2,5% para cistos de Endolimax nana, e 0,8% tanto para cistos de Giardia intestinalis quanto para os de Entamoeba coli.The contamination of public squares by zoonotic potential parasites was evaluated at the urban areas in the municipality of Itabuna Brasil. For such, 119 fecal samples of dogs were collected at 10 public squares. After that, these feces samples were transported to the Parasitology Laboratory in the UESC and they were analyzed by Mariano and Carvalho's method. Of the total analized samples, 56.3% show some parasitic evolutive form. Ancylostoma sp. was the most frequently (47.9%, followed by Strongyloides stercortalis (6.7%, Toxocara canis and Trichuris vulpis eggs (4.2% each, Endolimax nana cysts (2.5%, and Giardia intestinalis and Entamoeba coli cysts (0.8% each.

  3. NRC wants plant-specific responses on Thermo-Lag

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Dissatisfied with recent industry-backed efforts to assure fire safety at nuclear power plants, the Nuclear Regulatory Commission announced on November 24 that it would direct all nuclear plant owners to specify the actions they would take to assure that the use of the Thermo-Lag 330 fire barrier material would not lead to insufficient protection of electrical cables connected to safe-shutdown systems. Previously, the NRC had been content to let the matter wait until tests sponsored by the Nuclear Management and Resources Council (Numarc) could show whether Thermo-Lag, used and installed in certain ways, would provide sufficient protection, but the NRC and Numarc have disagreed over the test methodology, and the Numarc tests are now considered to be several months behind schedule

  4. Functional analyses of plant-specific histone deacetylases

    NARCIS (Netherlands)

    Li, Huchen

    2017-01-01

    Plants have a sessile lifestyle. To ensure survival, they develop a potential to respond to environmental cues to set up an adaptive growth and development. This adaptation involves transcriptional reprogramming of the genome through chromatin-based mechanisms relying on the dynamic interplay of

  5. Development of Nuclear Plant Specific Analysis Simulators with ATLAS

    International Nuclear Information System (INIS)

    Jakubowski, Z.; Draeger, P.; Horche, W.; Pointner, W.

    2006-01-01

    The simulation software ATLAS, based on the best-estimate code ATHLET, has been developed by the GRS for a range of applications in the field of nuclear plant safety analysis. Through application of versatile simulation tools and graphical interfaces the user should be able to analyse with ATLAS all essential accident scenarios. Detailed analysis simulators for several German and Russian NPPs are being constructed on the basis of ATLAS. An overview of the ATLAS is presented in the paper, describing its configuration, functions performed by main components and relationships among them. A significant part of any power plant simulator are the balance-of-plant (BOP) models, not only because all the plant transients and non-LOCA accidents can be initiated by operation of BOP systems, but also because the response of the plant to transients or accidents is strongly influenced by the automatic operation of BOP systems. Modelling aspects of BOP systems are shown in detail, also the interface between the process model and BOP systems. Special emphasis has been put on the BOP model builder based on the methodology developed in the GRS. The BOP modeler called GCSM-Generator is an object oriented tool which runs on the online expert system G2. It is equipped with utilities to edit the BOP models, to verification them and to generate a GCSM code, specific for the ATLAS. The communication system of ATLAS presents graphically the results of the simulation and allows interactively influencing the execution of the simulation process (malfunctions, manual control). Displays for communications with simulated processes and presentation of calculations results are also presented. In the framework of the verification of simulation models different tools are used e.g. the PC-codes MATHCAD for the calculation and documentation, ATLET-Input-Graphic for control of geometry data and the expert system G2 for development of BOP-Models. The validation procedure and selected analyses results compared to measured plant data are presented. (author)

  6. [Plant-specific pressured thermal shock safety analysis report

    International Nuclear Information System (INIS)

    Selby, D.L.

    1985-01-01

    Information is presented concerning plant data; determination of detailed PTS sequences for analysis; fracture mechanics analysis; integration of analysis; sensitivity and uncertainty analyses of through-wall crack frequencies; and effect of corrective actions on vessel through-wall crack frequency

  7. Implementation of condition-dependent probabilistic risk assessment using surveillance data on passive components

    International Nuclear Information System (INIS)

    Lewandowski, Radoslaw; Denning, Richard; Aldemir, Tunc; Zhang, Jinsuo

    2016-01-01

    Highlights: • Condition-dependent probabilistic risk assessment (PRA). • Time-dependent characterization of plant-specific risk. • Containment bypass involving in secondary system piping and SCC in SG tubes. - Abstract: A great deal of surveillance data are collected for a nuclear power plant that reflect the changing condition of the plant as it ages. Although surveillance data are used to determine failure probabilities of active components for the plant’s probabilistic risk assessment (PRA) and to indicate the need for maintenance activities, they are not used in a structured manner to characterize the evolving risk of the plant. The present study explores the feasibility of using a condition-dependent PRA framework that takes a first principles approach to modeling the progression of degradation mechanisms to characterize evolving risk, periodically adapting the model to account for surveillance results. A case study is described involving a potential containment bypass accident sequence due to the progression of flow-accelerated corrosion in secondary system piping and stress corrosion cracking of steam generator tubes. In this sequence, a steam line break accompanied by failure to close of a main steam isolation valve results in depressurization of the steam generator and induces the rupture of one or more faulted steam generator tubes. The case study indicates that a condition-dependent PRA framework might be capable of providing early identification of degradation mechanisms important to plant risk.

  8. A Study on Plasma Renin Activity in Korean Hemorrhagic Fever

    International Nuclear Information System (INIS)

    Kim, Suhng Gwon; Cho, Bo Yun; Lee, Jung Sang; Koh, Won Soon; Lee, Mun Ho; Kim, Won Dong; Yun, Hong Jin

    1976-01-01

    To evaluate the possible pathophysiologic role of renin in acute renal failure observed in Korean hemorrhagic fever (KHF), the author measured the basal plasma renin activity (PRA) and the stimulated PRA by radioimmunoassay for angiotensin I in 15 normal controls and 42 KHF patients who are admitted in Seoul National University Hospital and Nation Army Hospital from Jan. 1975 to Jan. 1976. The results obtained were as follows:The mean basal PRA in normal control group was 2.9±2.16 ng/ml/hr in the patients during the oliguric phase of KHF, the mean basal PRA was 4.7±2.13 ng/ml/hr, and there was statistically significant increase compared to the normal control. In the patients during the diuretic phase of KHF, the mean basal PRA was 3.4±2.09 ng/ml/hr, and there was statistically significant decrease compared to the oliguric phase of KHF. In normal control group, the mean basal PRA was 2.9±2.16 ng/ml/hr. And the PRA 1 hour after the administration of Lasix 40 mg intravenously (stimulated PRA) was 5.3±2.20 ng/ml/hr and there was statistically significant increase compared to basal level. In oliguric phase of KHF, the mean basal PRA was 4.6±2.01 ng/ml/hr. And stimulated PRA was 4.4±2.34 ng/ml/hr and there was no significant changes. In diuretic phase of KHF, the mean basal PR was 3.3±1.86 ng/ml/hr. And stimulated PRA was 5.2±2.58 ng/ml/hr and there was statistically significant increase compared to basal level. There were statistically no significant correlations between basal PRA and stimulated PRA and serum creatinine. BUN, urine volume and peritoneal dialysis.

  9. O processo de renovação das áreas centrais na cidade contemporânea: O caso do conjunto arquitetônico e paisagístico da Praça do Congresso, em Criciúma (SC

    Directory of Open Access Journals (Sweden)

    Gustavo Rogério De Lucca

    2015-05-01

    Full Text Available A expansão urbana desordenada no Brasil e a consolidação da cidade corporativa têm estimulado, com a conivência do Estado neoliberal, a propagação de modos de ocupação cada vez mais vinculados a interesses imobiliários imediatos. A ausência de planejamento urbano de caráter social é percebida principalmente nos médios e grandes centros urbanos, onde se registra um agressivo processo de renovação das áreas centrais, cada vez mais ousado, alterando inclusive, irreversivelmente, a paisagem de núcleos históricos. É o caso de setores da centralidade urbana de Criciúma/SC, cidade produzida sob influências econômicas da mineração de carvão e, posteriormente, por outras atividades industriais. É destaque o conjunto arquitetônico e paisagístico da Praça do Congresso, objeto de estudo deste artigo, formado a partir das primeiras décadas do século XX com residências em estilos variados, desde chalés com influências no Romantismo europeu a exemplares da arquitetura modernista. Juntas com a praça, configuravam um espaço de referência em qualidade de vida e importante para a preservação de vínculos identitários e de memória. Considera-se, no entanto, que as transformações mais recentes são parte de um quadro nacional de empobrecimento da urbanização e demonstram que a subserviência das políticas públicas a interesses econômicos imediatos tendem a desaparecer, em breve, com parte importante da diversidade dos conjuntos históricos brasileiros.

  10. A literatura infanto-juvenil como “suporte” na formação didática de professores de língua materna: uma reflexão teórico-metodológica a partir do texto de Elias José, em Uma escola assim, eu quero pra mim

    Directory of Open Access Journals (Sweden)

    Maria Lúcia Ribeiro de Oliveira

    2010-11-01

    Full Text Available ResumoO objetivo deste estudo é chamar a atenção dos docentes que trabalham na formação de professores delíngua materna, notadamente nos cursos de pedagogia e letras, para a função didática da literatura infantojuvenil.Em Uma escola assim, eu quero pra mim, publicada em 1997. Elias José, formado em letras epedagogia, aborda problemas e soluções de caráter sociolinguístico que podem ocorrer no contexto da salade aula. Ele conta a trajetória escolar de um menino que falava diferente por ser da zona rural e que, graçasa uma professora cheia de criatividade e intuição pedagógica, consegue transformar o inferno em que elevivia na escola, inicialmente, com uma professora bastante repressora e cheia de preconceito, numverdadeiro paraíso em que estudar era algo prazeroso, lúdico e transformador.

  11. STATUS GIZI IBU SEBELUM HAMIL SEBAGAI PREDIKSI BERAT DAN PANJANG BAYI LAHIR DI KECAMATAN BOGOR TENGAH, KOTA BOGOR: STUDI KOHOR PROSPEKTIF TUMBUH KEMBANG ANAK TAHUN 2012 - 2013

    Directory of Open Access Journals (Sweden)

    Anies Irawati

    2015-04-01

    Full Text Available ABSTRACTWeight and length at birth are the good indicators to evaluate the possibility of survival, growth, and chronic disease as adults. This analysis aims to assess the effect of maternal nutritional status as pre-pregnant and pregnant on birth weight and length of infants at risk of chronic disease in adulthood. The design of this study was a prospective cohort, starting from pre pregnancy, during pregnancy until infant birth. Data analysis used multiple logistic regression. The result showed that 6 percent of infants birth weight <2500 g and 26.4 percent of infants birth weight to chronic disease risk (<3000 g. Approximately 30.1 percent of infants stunted at birth (<48 cm and 62.6 percent infants at birth length <50 cm (standard WHO 2006. Mean of height pre-pregnancy is 151.9±5.6 cm and mean of body mass index (BMI pre-pregnancy is 20.6±3.1 kg/m2. Maternal BMI pre-pregnancy is a major risk factor for birth weight infants < 3000 g after controlled by maternal height, weight gain during pregnancy, maternal age, parity, diarrhea, energy and protein intake and sex of the baby. Maternal height is a major risk factor for infant birth length (<50 cm after controlled by pre-pregnant maternal BMI, maternal age, parity, weight gain during pregnancy, diarrhea, energy and protein intake. Conclusions, maternal nutritional status is a risk factor for pre-pregnant weight and birth length.Keywords: infant, birth weight, body mass index, length, maternalABSTRAKBerat dan panjang saat lahir merupakan indikator yang baik untuk melihat kemungkinan kelangsungan hidup, pertumbuhan, dan penyakit kronis ketika dewasa. Analisis ini bertujuan menilai pengaruh status gizi ibu ketika pra hamil dan hamil terhadap berat dan panjang bayi lahir yang berisiko pada penyakit kronis ketika dewasa. Disain penelitian adalah kohor prospektif sejak ibu pra hamil sampai bayi lahir. Studi kohor ini dimulai sejak tahun 2012 dan direncanakan berlanjut sampai tahun 2030. Data yang

  12. Study on information dissemination for effective nuclear risk communication

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The aim of this study are to develop an information system and guideline for nuclear risk communication between expert and citizens as well as between both experts in terms of lessons learned from serious disaster such as Fukushima Dai-ich NPP accident. Technical standards for disseminating a result and process of seismic/tsunami PRA (Probabilistic Risk Assessment) of nuclear facility as well as nuclear risk information in an emergency, and risk communication in normal times are needed. Tins study examines the framework, contents, and technical basis for developing an information system for nuclear risk communication. In addition, this study identifies the communication issues of nuclear risk communication concerning the seismic/tsunami PRA through the testing information systems in areas around nuclear facilities and by providing effective implementation guidelines. JNES has developed the information system specified as Protection of Nuclear Power Plants against Tsunamis and Post Earthquake considerations in the External Zone (TiPEEZ) as part of IAEA International Seismic Safety Centre (ISSC) Extra Budgetary Programme (EBP). The EBP is currently preparing technical documents (TECDOC) regarding the implementation of the TiPEEZ. After the Fukushima accident, there has been increasing demand for disaster mitigation systems to share risk information between nuclear organizations and local municipalities. JNES and Niigata Institute of Technology conduct implementation of TiPEEZ for the practical use based on the corroborative works with Kashiwazaki city and citizens. (author)

  13. Study on information dissemination for effective nuclear risk communication

    International Nuclear Information System (INIS)

    2013-01-01

    The aim of this study are to develop an information system and guideline for nuclear risk communication between expert and citizens as well as between both experts in terms of lessons learned from serious disaster such as Fukushima Dai-ich NPP accident. Technical standards for disseminating a result and process of seismic/tsunami PRA (Probabilistic Risk Assessment) of nuclear facility as well as nuclear risk information in an emergency, and risk communication in normal times are needed. Tins study examines the framework, contents, and technical basis for developing an information system for nuclear risk communication. In addition, this study identifies the communication issues of nuclear risk communication concerning the seismic/tsunami PRA through the testing information systems in areas around nuclear facilities and by providing effective implementation guidelines. JNES has developed the information system specified as Protection of Nuclear Power Plants against Tsunamis and Post Earthquake considerations in the External Zone (TiPEEZ) as part of IAEA International Seismic Safety Centre (ISSC) Extra Budgetary Programme (EBP). The EBP is currently preparing technical documents (TECDOC) regarding the implementation of the TiPEEZ. After the Fukushima accident, there has been increasing demand for disaster mitigation systems to share risk information between nuclear organizations and local municipalities. JNES and Niigata Institute of Technology conduct implementation of TiPEEZ for the practical use based on the corroborative works with Kashiwazaki city and citizens. (author)

  14. Analysis of dependent failures in the ORNL precursor study

    International Nuclear Information System (INIS)

    Ballard, G.M.

    1985-01-01

    The study of dependent failures (or common cause/mode failures) in the safety assessment of potentially hazardous plant is one of the significant areas of uncertainty in performing probabilistic safety studies. One major reason for this uncertainty is that data on dependent failures is apparently not readily available in sufficient quantity to assist in the development and validation of models. The incident reports that were compiled for the ORNL study on Precursors to Severe Core Damage Accidents (NUREG/CR-2497) provide an opportunity to look at the importance of dependent failures in the most significant incidents of recent reactor operations, to look at the success of probabilistic risk assessment (PRA) methods in accounting for the contribution of dependent failures, and to look at the dependent failure incidents with the aim of identifying the most significant problem areas. In this paper an analysis has been made of the incidents compiled in NUREG/CR-2497 and events involving multiple failures which were not independent have been identified. From this analysis it is clear that dependent failures are a very significant contributor to the precursor incidents. The method of enumeration of accident frequency used in NUREG-2497 can be shown to take account of dependent failures and this may be a significant factor contributing to the apparent difference between the precursor accident frequency and typical PRA frequencies

  15. Ve službách československé vědy (Přínos ruské emigrace k rozvoji pražské byzantologie a medievistické balkanistiky)

    Czech Academy of Sciences Publication Activity Database

    Havlíková, Lubomíra

    2006-01-01

    Roč. 31, - (2006), s. 17-47 ISSN 0081-007X Institutional research plan: CEZ:AV0Z90920516 Keywords : history * Russian emigration * Balkan studies * Byzantine studies * Middle Ages Subject RIV: AB - History

  16. Konsolidasi Tanah: Studi Kasus Kecamatan Gedebage, Kota Bandung

    Directory of Open Access Journals (Sweden)

    Marenda Ishak S

    2011-06-01

    Full Text Available To create equal distribution of development, Gedebage region was developed as activity centre initiated by building a Sport Centre. In order to do so, a land consolidation program to collect citizen land was launched.  The program was carefully designed to protect people’s right on land and support the whole process. This study examines Land Consolidation Program. The research is carried out by Participatory Rural Appraisal (PRA approach, using focus group discussion to collect data. The research showed that land consolidation activity was failed due to the absence of land legal document, lack of people participation and lack of government roles. Guna menciptakan pemerataan pembangunan, wilayah Gedebage dikembangkan sebagai pusat aktivitas yang diawali dengan pembangunan Pusat Olahraga (Sport Centre. Untuk itu, program konsolidasi tanah guna mengumpulkan tanah warga diluncurkan. Program tersebut dirancang dengan cermat untuk melindungi hak warga atas tanah, serta mendukung keseluruhan proses. Kajian ini meneliti Program Konsolidasi Tanah Gedebage, dengan pendekatan Participatory Rural Appraisal (PRA, yang menggunakan diskusi kelompok terarah guna mengumpulkan data. Hasilnya, terlihat bahwa aktivitas konsolidasi tanah telah mengalami kegagalan karena ketiadaan dokumen legal menyangkut status tanah, kurangnya partisipasi penduduk, dan lemahnya peran pemerintah.

  17. Criteria of quality in radio guided surgery for detection and removal of sentinel node in non-palpable lesions; Criterios de calidad en cirugia radioguiada pra deteccion y extirpacion de ganclio centinela en lesiones no palpables

    Energy Technology Data Exchange (ETDEWEB)

    Prieto, D.; Esteve, S.; Sanchez, K.; Rodriguez, P.; Barquero, R.; Ferrer, N.; Arranz, L.

    2013-07-01

    The first objective of this study is to carry out a theoretical study of the dose absorbed in the breast, comparing different types of source used, and according to location of the same. On the other hand, for the location of these nodes, or tumors in the operating room, can be used as well as portable gamma-cameras, intraoperative sensor probes of gamma radiation, facilitating the work the surgeon. Currently there is no protocol at national level describing quality control tests to be carried out on these computers. The second objective of the study is to collect a series of tests that enable to verify the correct operation of an intraoperative probe. These tests are classified according to their frequency, specialist, and test type, and allow you to check if the effectiveness of the operation of the probe is provided in your acquisition. Among the parameters that let you check the performance specifications are sensitivity, angular resolution and spatial resolution. (Author)

  18. A study on the pressurized water reactor (PWR) containment response analysis methodologies for postulated severe accident

    International Nuclear Information System (INIS)

    Ahn, Kwang Il

    1992-02-01

    The present study contains two major parts: one is the treatment of uncertainties involved in the current APET and the other is the importance analysis of the APET uncertainty inputs. A clear disadvantage of the expert opinion polling process approach for uncertainty analysis of the current probabilistic risk assessment (PRA) is that the sufficient robustness in the final results may not be attained against the ambiguity of the information upon which the experts base their judgement or the judgmental uncertainty arising under various imprecise and incomplete information. For the treatment of such type of uncertainty, a new approach based on fuzzy set theory is proposed. Then its potential use to the uncertainty analysis of the current PRA is proved through an analysis of accident progression event tree (APET). As a product, a formal procedure with computational algorithms suitable for application of the fuzzy set theory to the APET analysis is provided. Comparing with the uncertainty analysis results obtained by the statistical approach currently used in PRA, the present approach has several major advantages: Firstly, it greatly enhances the robustness in the final results of APET uncertainty analysis by modeling the judgmental uncertainty that arises in the probabilistic quantification of APET top events. Secondly, the modeling of APET uncertainty analysis is far more convenient because of the nonprobabilistic features of fuzzy probabilities used for uncertainty quantification of the APET top events. Thirdly, the APET model can easily be operated by means of a well defined formal propagation logic of fuzzy set theory without going through a tedious sampling procedure. Finally, the fuzzy outcomes provide at least as much information as the existing methods based on the statistical approach. Thus, the present approach can be used as a valuable alternative approach to uncertainty analysis used in the current PRA. Two importance measures for the importance analysis of

  19. Scientific and technological monitoring: international overview on R. and D. related to Pra`s; Veille technologique et scientifique: etat de l`art de la R. et D. dans le domaine des EPS

    Energy Technology Data Exchange (ETDEWEB)

    Llory, M; Stioui, A

    1993-03-01

    In 1989, the R and D Division of Electricite de France launched a programme for a Technological and Scientific Overview (TSO) covering a certain number of topics considered to be important for the future of EDF. Probabilistic approaches to studies related to safety were considered to be strategically important to EDF, and therefore this area was selected for further study. A TSO is a process which can only start on the basis of a structured state-of-the-art organized as a basis of knowledge, together with the highlighting of a certain number of scientific and strategic ``set of references{sup .} The state-of-the-art of R and D related to Probabilistic Safety Assessment (PSA) was carried out in collaboration between the EDF R and D Division (SR branch) and SRI International. The approach chosen included: segmentation of the wide field of PSAs into subject areas, topics and sensitive points to be monitored; conception of a grid for the interviews; approximately thirty in-depth interviews of organizations and experts representative of the domain; analysis leading to identify certain problems areas or particularly important features. Emerging themes for research and further consideration in relation to PSAs, their application and their limits were also identified. Based on this state-of-the-art, various themes of monitoring were defined (living PSAs, limits of PSAs,...) and an organizational structure for monitoring was set up in the branch. The state of the art is not static, it is the reason why an in-depth extension of the study was undertaken on issues of special interest for EDF. (authors). 2 figs., 2 refs.

  20. EFFECT OF PRETREATMENTS ON CHEMICAL AND ANTIOXIDANT PROPERTIES OF SKY FRUIT (Swietenia macrophylla SEED OIL [Pengaruh Pra-perlakuan Terhadap Sifat Kimia dan Antioksidan Minyak Biji Buah Tunjuk Langit (Swietenia macrophylla

    Directory of Open Access Journals (Sweden)

    Hayati Mohd Yusof

    2012-12-01

    Full Text Available The objective of this study was to investigate the effect of pretreatments on chemical and antioxidant properties of sky fruit (Swietenia macrohylla seed oil. The seeds were treated with different heat pretreatments (roasting, steaming, and microwaving and subsequently subjected to oil extraction by using a Bligh and Dyer method. It was found that different pretreatments significantly (p<0.05 affected yield and peroxide value of the extracted oils. However, no significant effect of pretreatment was observed on free fatty acid content of the seed oils. The oils exhibited significantly different levels of 1, 1-diphenyl-2-picrylhydrazyl (DPPH scavenging activity due to different heat pretreatments. The results revealed that the mean percentages of DPPH scavenging activity of untreated (control seed oil (87.69% and steamed seed oil (83.40% were significantly higher than those of roasted seed oil (75.71% as well as the microwaved one (63.98%. In contrast, the pretreatments did not significantly affect total phenolic content (TPC of the seed oils with the TPC mean values ranging from 0.016 to 0.022 mg/g (as gallic acid. Data gained from this study provided valuable information for edible oil industries in searching for alternative source of edible oil with medicinal benefits.

  1. A configuração da via pública interferindo na apreensão da praça: o caso de conjuntos habitacionais em Teresina

    Directory of Open Access Journals (Sweden)

    Wilza Gomes Reis Lopes

    2007-06-01

    Full Text Available Commerce and spaces of leisure already had been together for much time, in the Average Age the market assumed the role that today fits to the square of collective space of leisure. Today the market acquires the consumption function eminently, more is not lived deeply the environment and the people. The incessant search for the profit, or same for the survival, moves our society and each place that can potentially relieve money is explored to the maximum. Located houses next to moving streets are changedded quickly into commercial points, modifying the configuration of a space created for housing in commerce environment. But these ways are not populated only by private establishments, them also present public spaces, that suffer the consequences of these alterations. The present work presents a study of three squares located in the habitacionais sets Itararé, Piauí Park and Promorar Park, in the city of Teresina, Piauí, observing as the changes in the original function of the streets of entorno, that they had been projected, initially, as surrounding residential, have modified the performance of the public spaces.

  2. "É melhor pra você!": normatização social da infância e da família no Brasil "It will be in your favor!": social regulation of childhood and family in Brazil

    Directory of Open Access Journals (Sweden)

    Nelson Gomes de Sant'Ana e Silva Júnior

    2007-12-01

    Full Text Available O trabalho analisa os discursos/práticas especialistas, em funcionamento desde fins do século XIX, como mecanismos de normatização de valores e comportamentos da infância/família brasileira. Utilizou-se a abordagem genealógica para pesquisar conteúdos veiculados nos Arquivos Brasileiros de Higiene Mental. Objetivou-se promover visibilidade de especialistas do conhecimento, fomentando uma desnaturalização de práticas/saberes considerados verdades universais. Identificaram-se fundamentos políticos, ideológicos e morais que sustentam discursos/práticas contemporâneos supostamente neutros e, frequentemente, acrescidos de assistencialismo e/ou militância. Aponta-se para necessidade de reavaliações das implicações políticas, éticas e sociais presentes tanto na formação como nas práticas psi.This report analyzes specialist speeches/practices which have acted as mechanisms for Brazilian children/families since the end of the 19 century. A genealogic approach was used to carry out a study on the contents published in the Brazilian Mental Hygiene Archives. It also aims at enhancing the experts of the knowledge which make unnatural practices/opinions considered as universal truths. This analysis has identified political, ideological and moral bases supporting contemporaneous speeches/practices disguised as neutrality, which are often increased by "assistentialism" and/or militancy. It shows the need for revaluation of political and social consequences in the graduation and in the psychology practice.

  3. Application of probabilistic risk assessment in the operation of Koeberg nuclear power station

    International Nuclear Information System (INIS)

    Nicholls, D.R.

    1991-01-01

    Probabilistic risk assessment (PRA) calculates the probability that a set of multiple failures could occur, the frequency with which the safety circuits will be required and the consequences of the failure of the safety systems. In this way the frequency with which major accident situations can be expected to happen, can be derived. The world history of PRA is presented, together with the South African history of PRA. The theory of PRA is explained and the application of PRA studies is described. In the last twenty years, PRA has gone from being a theoretical idea to a practical tool for assisting in plant management. 2 figs., 1 ill

  4. SHARP1: A revised systematic human action reliability procedure

    International Nuclear Information System (INIS)

    Wakefield, D.J.; Parry, G.W.; Hannaman, G.W.; Spurgin, A.J.

    1990-12-01

    Individual plant examinations (IPE) are being performed by utilities to evaluate plant-specific vulnerabilities to severe accidents. A major tool in performing an IPE is a probabilistic risk assessment (PRA). The importance of human interactions in determining the plant response in past PRAs is well documented. The modeling and quantification of the probabilities of human interactions have been the subjects of considerable research by the Electric Power Research Institute (EPRI). A revised framework, SHARP1, for incorporating human interactions into PRA is summarized in this report. SHARP1 emphasizes that the process stages are iterative and directed at specific goals rather than being performed sequentially in a stepwise procedure. This expanded summary provides the reader with a flavor of the full report content. Excerpts from the full report are presented, following the same outline as the full report. In the full report, the interface of the human reliability analysis with the plant logic model development in a PRA is given special attention. In addition to describing a methodology framework, the report also discusses the types of human interactions to be evaluated, and how to formulate a project team to perform the human reliability analysis. A concise description and comparative evaluation of the selected existing methods of quantification of human error are also presented. Four case studies are also provided to illustrate the SHARP1 process

  5. A study on the estimation method of nuclear accident risk cost

    International Nuclear Information System (INIS)

    Matsuo, Yuji

    2016-01-01

    The methodology of estimating nuclear accident risk cost, as a part of nuclear power generation cost, has hardly been established due mainly to the extremely wide range of the estimation of the accident frequency. This study estimates the expected nuclear accident frequency for Japan, making use of the method of Bayesian statistics, which exploits both the information obtained by Probabilistic Risk Assessment (PRA) and the observed historical accident frequencies. Using the PRA estimation of the Containment Failure Frequency (CFF) for Tomari nuclear power plant unit 3 of Hokkaido Electric Power Company (average: 2.1 x 10 -4 , 95th percentile: 7.7 x 10 -4 ) and the actual large-scale accident frequency (once in 1,460 reactor-years), the posterior CFF was estimated at 3.8 x 10 -4 . This study also took into account the 'external' factor causing unexpected nuclear accidents, concluding that such factor could result in higher CFF estimations, especially with larger observed accident numbers. (author)

  6. The influence of surgeon personality factors on risk tolerance: a pilot study.

    Science.gov (United States)

    Contessa, Jack; Suarez, Luis; Kyriakides, Tassos; Nadzam, Geoffrey

    2013-01-01

    This study attempts to assess the association between surgeon personality factors (measured by the Myers-Briggs Type Indicator personality inventory (MBTI(®))) and risk tolerance (measured by the Revised Physicians' Reactions to Uncertainty (PRU) and Physician Risk Attitude (PRA) scales). Instrument assessing surgeon personality profile (MBTI) and 2 questionnaires measuring surgeon risk tolerance and risk aversion (PRU and PRA). Saint Raphael campus of Yale New Haven Hospital in New Haven, Connecticut. Twenty categorical surgery residents and 7 surgical core faculty members. The following findings suggest there might be a relationship between surgeon personality factors and risk tolerance. In certain areas of risk assessment, it appears that surgeons with personality factors E (Extravert), T (Thinking), and P (Perception) demonstrated higher tolerance for risk. Conversely, as MBTI(®) dichotomies are complementary, surgeons with personality factors I (Introvert), F (Feeling), and J (Judgment) suggest risk aversion on these same measures. These findings are supported by at least 2 studies outside medicine demonstrating that personality factors E, N, T, and P are associated with risk taking. This preliminary research project represents an initial step in exploring what may be considered a fundamental component in a "successful" surgical personality. © 2013 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  7. Model Penilaian untuk Kematangan Perencanaan Keselamatan dalam Tahap Pra Konstruksi

    Directory of Open Access Journals (Sweden)

    Bambang Endroyo

    2015-10-01

    Full Text Available The construction sector still has a low achievement in safety issues. Fatal accident rate in construction is higher than average rate in other industries. Because of it, need some attention to minimize the rate of accident in construction. This research examined the key factors of safety planning in the pre-construction stage, and it was based on the theories of accidents causation having the upstream approach. Some theories were: Constraint-Response Theory (CR; Construction Design Management (CDM, and the Process Protocol (Pp. This research broke down the three theories above (CR; CDM; Pp into the concept of the key factors of safety planning in pre-construction. Then, the concept was verified by construction practitioners and academician, using Delphi method three rotations. During the verification, from the first to the third round, there were reduction and the addition concept and language appropriateness. The findings of this research were assessment models of maturity safety planning in the pre construction stages. There were two models, the model of "radar chart" or MISAP 1 and the model of "worksheet" or MISAP 2.

  8. Pra Desain Pabrik Dimethyl Ether (DME dari Gas Alam

    Directory of Open Access Journals (Sweden)

    Ajeng Puspitasari Yudiputri

    2014-09-01

    Full Text Available Berdasarkan data PT Pertamina (Persero, total konsumsi LPG 2008 mencapai 1,85 juta ton dan 600.000 ton di antaranya untuk program konversi. Pada 2009 kebutuhan LPG akan meningkat menjadi 3,67 juta ton dan 2 juta ton di antaranya untuk program konversi sampai akhir tahun. Namun, sumber pasokan LPG dari dalam negeri diperkirakan tidak akan beranjak dari angka 1,8 juta ton per tahun dalam beberapa tahun mendatang. Sehingga, Indonesia harus menutup kebutuhan dengan mengimpor LPG dalam jumlah cukup besar. Maka dari itu dibutuhkan bahan bakar gas lain yang mampu mengatasi permasalahan yang ditimbulkan tersebut. Dimethyl Ether (DME merupakan senyawa ether yang paling sederhana dengan rumus kimia CH3OCH3. Produksi DME dapat dihasilkan melalui sintesis gas alam. DME berbentuk gas yang tidak berwarna pada suhu ambien, zat kimia yang stabil, dengan titik didih -25,1oC. Tekanan uap DME sekitar 0,6 Mpa pada 25oC dan dapat dicairkan seperti halnya LPG. Viskositas DME 0,12-0,15 kg/ms, setara dengan viskositas propana dan butane (konstituen utama LPG, sehingga infrastruktur untuk LPG dapat juga digunakan untuk DME. Berdasarkan data Departemen ESDM pada Januari 2012, total cadangan gas alam Indonesia tercatat mencapai 150,70 Trillion Square Cubic Feet (TSCF. Berdasarkan jumlah tersebut, sebanyak 103,35 TSCF merupakan gas alam terbukti, sementara 47,35 TSCF sisanya masih belum terbukti. Berdasarkan hal tersebut, diketahui bahwa senyawa DME merupakan senyawa yang sesuai untuk bahan substitusi LPG. Dan ditinjau dari analisa ekonomi, didapatkan besar Investasi : $ 636,447,074.69 ; Internal Rate of Return\t: 20.51%; POT: 4.13 tahun; BEP : 37.36 %; dan NPV 10 year : $ 518,848,692. Dari ketiga parameter sensitifitas yaitu fluktuasi biaya investasi, harga bahan baku, dan harga jual dari produk, terlihat bahwa ketiganya tidak memberikan pengaruh yang cukup signifikan terhadap kenaikan atau penurunan nilai IRR pabrik. Sehingga pabrik DME dari Gas Alam ini layak untuk didirikan.

  9. Quantification methodology for the French 900 MW PWR PRA

    International Nuclear Information System (INIS)

    Ducamp, F.; Lanore, J.M.; Duchemin, B.; De Villeneuve, M.J.

    1985-02-01

    This paper develops some improvements brought to provide to the classical way of risk assessment. The calculation of the contribution to the risk of one peculiar sequence of an event tree is composed of four stages: creation of a fault tree for each system which appears in the event trees, in terms of component faults; simplification of these fault trees into smaller ones, in terms of macrocomponents; creation of one ''super-tree'' by regrouping the fault trees of down systems (systems which fail in the sequence) under an AND gate and calculation of minimal cut sets of this super-tree, taking into account the up systems (systems that do not fail in the sequence) and peculiarities related to the initiating event if needed; quantification of the minimal cut sets so obtained, taking into account the duration of the scenario depicted by the sequence and the possibilities of repair. Each of these steps is developed in this article

  10. PENGARUH TRADISI ARAB PRA ISLAM TERHADAP HUKUMAN RAJAM

    OpenAIRE

    Ali Ali

    2014-01-01

    This article was written to answer the question of how the punishment of adultery in the tradition of pre-Islamic Arabia and whether the punishment of stoning in adultery punishment traditions influenced by pre-Islamic? This is also done as most of the literature (especially fiqh) which is likely to assume muhsan stoning sentence for the perpetrator is Sunnah and is therefore considered final. This is different from the Qur'an which contains only the caning without perpetrator category. The a...

  11. Top event prevention analysis - a deterministic use of PRA

    International Nuclear Information System (INIS)

    Blanchard, D.P.; Worrell, R.B.

    1995-01-01

    Risk importance measures are popular for many applications of probabilistic analysis. Inherent in the derivation of risk importance measures are implicit assumptions that those using these numerical results should be aware of in their decision making. These assumptions and potential limitations include the following: (1) The risk importance measures are derived for a single event at a time and are therefore valid only if all other event probabilities are unchanged at their current values. (2) The results for which risk importance measures are derived may not be complete for reasons such as truncation

  12. Pra Desain Pabrik Sorbitol dari Tepung Tapioka dengan Hidrogenasi Katalitik

    Directory of Open Access Journals (Sweden)

    Hellen Kartika Dewi

    2014-03-01

    Full Text Available Sorbitol yang dikenal juga sebagai glusitol, adalah suatu gula alkohol yang dimetabolisme lambat di dalam tubuh. Sorbitol banyak digunakan sebagai bahan baku untuk industri barang konsumsi dan makanan seperti pasta gigi, permen, kosmetika, farmasi, vitamin C, termasuk industri tekstil dan kulit. Pembuatan sorbitol dari bahan baku tepung tapioka. Pabrik sorbitol ini direncanakan akan didirikan di Propinsi Jawa Tengah tepatnya di Kabupaten Batang dengan kapasitas produksi 30.000 ton/tahun. Proses produksi Sorbitol menggunakan proses hidrogenasi katalitik. Pembuatan sorbitol dari bahan baku pati melalui dua tahap proses utama yaitu proses perubahan starch menjadi glukosa melalui hidrolisa double enzym. Enzim yang digunakan yaitu α-amylase dan glukoamylase. Proses hidrogenasi katalitik dilakukan dengan mereaksikan larutan dekstrose dan gas hidrogen bertekanan tinggi dengan menambahkan katalis nikel dalam reaktor (Reaktor Hidrogenasi. Gas hidrogen masuk dari bawah reaktor secara bubbling dan larutan dekstrose diumpankan dari atas reaktor sehingga kontak yang terjadi semakin baik. Sorbitol yang di hasilkan dalam pradesain pabrik sorbitol ini dengan konsentrasi 58,2%. Pendirian pabrik sorbitol memerlukan biaya investasi modal tetap (fixed capital sebesar Rp 168.801.192.952, modal kerja (working capital  Rp 29.788.445.815, investasi total Rp 198.589.638.767, Biaya produksi per tahun Rp 368.832.813.809 dan  hasil penjualan per tahun Rp 540.000.078.750. Dari analisa ekonomi didapatkan BEP sebesar 26,32%. ROI sesudah pajak 48,5 %, POT sesudah pajak 2,14 tahun. Dari segi teknis dan ekonomis, pabrik ini layak untuk didirikan.

  13. KONTRIBUSI PEMIKIRAN MUHAMMAD SAW PRA DAN PASCA KENABIAN ERA MAKKIAH

    Directory of Open Access Journals (Sweden)

    Agus Jaya

    2011-11-01

    Full Text Available Abstract:Muhammad is the greatest phenomenon in human history. Signs He enshrined in the presence of the holy scriptures is  as a justification former glory. His presence was expected by every group and interest, although later become a boomerang for them because the treatise was carrying remodel beliefs and traditions handed down from their ancestors. The suffering experiences completed His life’s history  as a candidate of  a prophet. Born with orphan status, grew by profession and lived as a shepherd, had suffering experiences has  formed  the identity of Muhammad to become an intelligent and wise leader. Muhammad's intelligence and wisdom in deciding the issue and genius as well as the accuracy of missionary strategy embedded in the period of Mecca is the contribution of thinking which is priceless. Keywords: the contribution of ideas, leadership training, intelligence, wisdom, leadership characteristics

  14. Causative mutations for progressive retinal atrophy (PRA) in the dog

    Czech Academy of Sciences Publication Activity Database

    Dostál, Jaromír; Horák, Pavel; Bechyňová, Renata; Přibáňová, M.; Stratil, Antonín; Schröffelová, D.

    2008-01-01

    Roč. 25, č. 1 (2008), s. 55-58 ISSN 1803-4403. [Genetické dny /23./. České Budějovice, 10.09.2008-12.09.2008] Institutional research plan: CEZ:AV0Z50450515 Keywords : progressive retinal atrophy * dog Subject RIV: EB - Genetics ; Molecular Biology

  15. EVNTRE, Code System for Event Progression Analysis for PRA

    International Nuclear Information System (INIS)

    2002-01-01

    1 - Description of program or function: EVNTRE is a generalized event tree processor that was developed for use in probabilistic risk analysis of severe accident progressions for nuclear power plants. The general nature of EVNTRE makes it applicable to a wide variety of analyses that involve the investigation of a progression of events which lead to a large number of sets of conditions or scenarios. EVNTRE efficiently processes large, complex event trees. It can assign probabilities to event tree branch points in several different ways, classify pathways or outcomes into user-specified groupings, and sample input distributions of probabilities and parameters. PSTEVNT, a post-processor program used to sort and reclassify the 'binned' data output from EVNTRE and generate summary tables, is included. 2 - Methods: EVNTRE processes event trees that are cast in the form of questions or events, with multiple choice answers for each question. Split fractions (probabilities or frequencies that sum to unity) are either supplied or calculated for the branches of each question in a path-dependent manner. EVNTRE traverses the tree, enumerating the leaves of the tree and calculating their probabilities or frequencies based upon the initial probability or frequency and the split fractions for the branches taken along the corresponding path to an individual leaf. The questions in the event tree are usually grouped to address specific phases of time regimes in the progression of the scenario or severe accident. Grouping or binning of each path through the event tree in terms of a small number of characteristics or attributes is allowed. Boolean expressions of the branches taken are used to select the appropriate values of the characteristics of interest for the given path. Typically, the user specifies a cutoff tolerance for the frequency of a pathway to terminate further exploration. Multiple sets of input to an event tree can be processed by using Monte Carlo sampling to generate approximate mapping from input to output. 3 - Restrictions on the complexity of the problem: A preprocessor program supplied can be used to replace a PARAMETER statement if array sizes require adjustment

  16. PERUBAHAN PANDANGAN ONTOLOGI PADA WAYANG MASA ISLAM DAN PRA ISLAM

    Directory of Open Access Journals (Sweden)

    Nurhadi Siswanto

    2017-03-01

    Full Text Available Puppet has developments and changes over time. Puppet continues to grow and develop in accordance with the development of the dominant civilization that accompanies it. A change in the function of puppet strikingly occurs in Islam and pre-Islamic era. Puppet that previously acted as a form of religious ritual to worship the ancestors and the ‘Dewa’ has been changes in function to serve as a media for the sake of religion propaganda and education. There was also a change on the ontological view in puppet. The changes occur due to difference concept of Deity’s thought in Islam and Hinduism. The Islam belief that does not recognize the concept ‘dewa’, it is not eliminating the existence of ‘dewa’ in various puppet stories, but instead desecrated it. ‘Dewa’ no longer considered sacred, perfect and unbeatable, but the god is considered common creatures that could also be defeated and make mistakes.

  17. Validation and verification plan for safety and PRA codes

    International Nuclear Information System (INIS)

    Ades, M.J.; Crowe, R.D.; Toffer, H.

    1991-04-01

    This report discusses a verification and validation (V ampersand V) plan for computer codes used for safety analysis and probabilistic risk assessment calculations. The present plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River Office (DOE-SRO) to bring the essential safety analysis and probabilistic risk assessment codes in compliance with verification and validation requirements

  18. POLA ASUH KELUARGA DAN PERKEMBANGAN EMOSIONAL ANAK PRA SEKOLAH

    OpenAIRE

    WANDA, RUNI; NYOKO, YUNETI OCTAVIANUS; KODY, MARTHA METI; AGUSTINE, ULY

    2017-01-01

    Introduction:The family is the first and main vehicle for character education. If a family fails to educate character on its children, it will be difficult for other institutions outside the family to improve it and will affect the child's own emotional development. Based on the observation of some students who have not been active during the learning process is going on, often disrupt his friends while playing, fighting and grabbing toys. The purpose of this research is to know the descripti...

  19. A Feasibility Study of Bevacizumab Plus Dose-Dense Doxorubicin–Cyclophosphamide (AC) Followed by Nanoparticle Albumin–Bound Paclitaxel in Early-Stage Breast Cancer

    Science.gov (United States)

    McArthur, Heather L.; Rugo, Hope; Nulsen, Benjamin; Hawks, Laura; Grothusen, Jill; Melisko, Michelle; Moasser, Mark; Paulson, Matthew; Traina, Tiffany; Patil, Sujata; Zhou, Qin; Steingart, Richard; Dang, Chau; Morrow, Monica; Cordeiro, Peter; Fornier, Monica; Park, John; Seidman, Andrew; Lake, Diana; Gilewski, Theresa; Theodoulou, Maria; Modi, Shanu; D’Andrea, Gabriella; Sklarin, Nancy; Robson, Mark; Moynahan, Mary Ellen; Sugarman, Steven; Sealey, Jane E.; Laragh, John H.; Merali, Carmen; Norton, Larry; Hudis, Clifford A.; Dickler, Maura N.

    2016-01-01

    Purpose Bevacizumab confers benefits in metastatic breast cancer but may be more effective as adjuvant therapy. We evaluated the cardiac safety of bevacizumab plus dose-dense doxorubicin–cyclophosphamide (ddAC)→nanoparticle albumin−bound (nab)-paclitaxel in human epidermal growth factor receptor 2 normal early-stage breast cancer. Experimental Design Eighty patients with normal left ventricular ejection fraction (LVEF) were enrolled. Bevacizumab was administered for 1 year, concurrently with ddAC→nab-paclitaxel then as a single agent. LVEF was evaluated at months 0, 2, 6, 9, and 18. This regimen was considered safe if fewer than three cardiac events or fewer than two deaths from left ventricular dysfunction occurred. Correlative studies of cardiac troponin (cTn) and plasma renin activity (PRA) were conducted. Results The median age was 48 years (range, 27−75 years), and baseline LVEF was 68% (53%−82%). After 39 months’ median follow-up (5−45 months): median LVEF was 68% (53%−80%) at 2 months (n=78), 64% (51%−77%) at 6 months (n=66), 63% (48%−77%) at 9 months (n=61), and 66% (42%−76%) at 18 months (n=54). One patient developed symptomatic LV dysfunction at month 15. Common toxicities necessitating treatment discontinuation were hypertension (HTN, 4%), wound-healing complications (4%), and asymptomatic LVEF declines (4%). Neither cTn nor PRA predicted CHF or HTN, respectively. Conclusions Bevacizumab with ddAC→nab-paclitaxel had a low rate of cardiac events; cTn and PRA levels are not predictive of CHF or HTN, respectively. The efficacy of bevacizumab as adjuvant treatment will be established in several ongoing phase III trials. PMID:21350003

  20. Development of infrastructure for the regulatory authority to implement risk-informed regulation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    It is important to assure the technical adequacy of probabilistic risk assessment (PRA) to implement risk-informed regulation of nuclear power plants (NPPs). JNES has been conducting various activities, such as development of PRA model, method, and data base, in order to assure the technical adequacy of PRA as development of the infrastructure for the regulatory authority to implement risk-informed regulation. In 2012, JNES updated the reliability data base used in PRA and improved PRA models to enhance the technical bases of PRA. In addition, JNES has been establishing the PRA model for fuel damage in the spent fuel storage pool in NPPs. As for improvement of PRA model for core damage in reactor, JNES conducted the study including feasibility of a simplified reliability model for digital I and C system developed by the digital I and C task group of OECD/NEA CSNI WGRISK by reproducing the sample calculation, and improvement of PRA models of individual NPPs in Japan. JNES is making effort to develop the procedures of internal fire PRA and internal flooding PRA. To improve the internal fire PRA, JNES is participating in OECD/NEA FIRE project to obtain the latest information and to validate and improve the fire propagation analysis codes and the parameters. JNES is establishing a method for analyzing internal influence due to flooding in NPPs, and this method is the base to develop the procedure of internal flooding PRA. (author)

  1. Conceptual design study of fusion experimental reactor (FY86 FER)

    International Nuclear Information System (INIS)

    Seki, Yasushi; Iida, Hiromasa; Honda, Tsutomu.

    1987-08-01

    This report describes the study on safety for FER(Fusion Experimental Reactor) which has been designed as a next step machine to the JT-60. Though the final purpose of this study is to have an image of design base accident, maximum credible accident and to assess their risk or probability, etc., as FER plant system, the emphasis of this years study is placed on fuel-gas circulation system where the tritium inventory is maximum. This report consists of two chapters. The first chapter of this report summaries the FER system and describes FMEA(Failure Mode and Effect Analysis) and related accident progression sequence for FER plant system as a whole. The second chapter of this report is focused on fuel-gas circulation system including the purification, isotope separation system and storage system. Here, probability of risk is assessed by the probabilistic risk analysis (PRA) procedure based on FMEA, ETA and FTA. (author)

  2. Effects of aqueous extract of Hibiscus sabdariffa on the renin-angiotensin-aldosterone system of Nigerians with mild to moderate essential hypertension: A comparative study with lisinopril.

    Science.gov (United States)

    Nwachukwu, Daniel Chukwu; Aneke, Eddy Ikemefuna; Obika, Leonard Fidelis; Nwachukwu, Nkiru Zuada

    2015-01-01

    The present study investigated the effects of aqueous extract of Hibiscus sabdariffa (HS) on the three basic components of renin-angiotensin-aldosterone system: Plasma renin, serum angiotensin-converting enzyme (ACE), and plasma aldosterone (PA) in mild to moderate essential hypertensive Nigerians and compared with that of lisinopril, an ACE inhibitor. A double-blind controlled randomized clinical study was used. Seventy-eight newly diagnosed but untreated mild to moderate hypertensive subjects attending Medical Outpatients Clinic of Enugu State University Teaching Hospital, Enugu were recruited for the study. Those in Group A received placebo (150 mg/kg/day), Group B were given lisinopril (10 mg once daily) while those in Group C received aqueous extract of HS (150 mg/kg/day). After 4 weeks of treatment, the levels of plasma renin, serum ACE, and PA were determined. HS and lisinopril significantly (P < 0.001) reduced PA compared to placebo by 32.06% and 30.01%, respectively. Their effects on serum ACE and plasma renin activity (PRA) were not significant compared to placebo; they reduced ACE by 6.63% and 5.67% but increased plasma PRA by 2.77% and 5.36%, respectively. HS reduced serum ACE and PA in mild to moderate hypertensive Nigerians with equal efficacy as lisinopril. These actions are possibly due to the presence of anthocyanins in the extract.

  3. Radioisotope-pharmacodynamic studies without exposure to radiation

    International Nuclear Information System (INIS)

    Graul, H.

    1983-01-01

    On the basis of a clinico-pharmacological study using a new diuretic combination it is shown that not only the RIA determination, but also the measurement of the total amount of potassium in the body with the aid of the 40 K potassium-nuclide confirmed therapeutic efficacy. Furosemide (30 mg) and the combination furosemide-retard (30 mg) and triamterene (50 mg) influence the plasmarenin-aldosterone system (PRA-system) differently. After both furosemide alone and the combination, the plasma-renin activity increased significantly (p 40 /K potassium nuclide - decreased after 8 days of treatment with the combination of furosemide-retard and triamterene. Both methods have proved of value in the clinico-pharmacological examination of diuretics. They are of great importance, easy to apply, involve no exposure to radiation, and are inexpensive. (orig.) [de

  4. Case studies: Risk-based analysis of technical specifications

    International Nuclear Information System (INIS)

    Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

    1987-01-01

    The SOCRATES computer program uses the results of a Probabilistic Risk Assessment (PRA) or a system level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at a plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns with no adverse impacts on risk. Three summaries of case study applications are included to demonstrate the types of results that can be achieved through risk-based evaluation of technical specifications. (orig.)

  5. Screening for primary aldosteronism in an argentinian population: a multicenter prospective study.

    Science.gov (United States)

    Leal Reyna, Mariela; Gómez, Reynaldo M; Lupi, Susana N; Belli, Susana H; Fenili, Cecilia A; Martínez, Marcela S; Ruibal, Gabriela F; Rossi, María A; Chervin, Raúl A; Cornaló, Dora; Contreras, Liliana N; Costa, Liliana; Nofal, María T; Damilano, Sergio A; Pardes, Ester M

    2015-10-01

    Primary aldosteronism (PA) is characterized by the autonomous overproduction of aldosterone. Its prevalence has increased since the use of the aldosterone (ALD)/plasma renin activity (PRA) ratio (ARR). The objective of this study is to determine ARR and ARC (ALD/plasma renin concentration ratio) cut-off values (COV) and their diagnostic concordance (DC%) in the screening for PA in an Argentinian population.Design multicenter prospective study. We studied 353 subjects (104 controls and 249 hypertensive patients). Serum aldosterone, PRA and ARR were determined. In 220 randomly selected subjects, 160 hypertensive patients and 60 controls, plasma renin concentration (PRC) was simultaneously measured and ARC was determined. According to the 95th percentile of controls, we determined a COV of 36 for ARR and 2.39 for ARC, with ALD ≥ 15 ng/dL. In 31/249 hypertensive patients, ARR was ≥ 36. PA diagnosis was established in 8/31 patients (23/31 patients did not complete confirmatory tests). DC% between ARR and ARC was calculated. A significant correlation between ARR and ARC (r = 0.742; p 0.3 ng/mL/h and PRC > 5 pg/mL. DC% for ARR and ARC above or below 36 and 2.39 was 79.1%, respectively. This first Argentinian multicenter study determined a COV of 36 for ARR and 2.39 for ARC. Applying an ARR ≥ 36 in the hypertensive group, we confirmed PA in a higher percentage of patients than the previously reported one in our population. As for ARC, further studies are needed for its clinical application, since DC% is acceptable only for medium range renin values.

  6. Probabilistic commentary: the rise and fall, and rise again, of risk assessment

    International Nuclear Information System (INIS)

    Hendrie, J.M.

    1985-02-01

    Probabilistic risk assessment is mainly concerned with assessing the risks of nuclear power plants. Historically, the field of PRA began with a Senate request for a report on the safety of nuclear reactors in 1972. A quantitative report called WASH-1400 was eventually prepared and published in 1975, and in summary, it stated that nuclear reactors warranted only a low-grade concern in modern society. Criticism of this report and public perception of its results were highly visible subjects in the media, and the criticism led to the fact that PRA fell into disfavor. After Three Mile Island, it was recognized that PRA was a valuable tool for understanding such accidents, and PRA became a bit more popular again by the end of 1979. The usefulness of PRA was also supported by a German study in 1979. PRA played a significant role in the hearings on the Indian Point reactor. The present NRC regards PRA as an important tool in regulatory practice

  7. Prioritization of motor operated valves based on risk importances

    International Nuclear Information System (INIS)

    Vesely, W.E.; Weidenhamer, G.H.

    1994-01-01

    The plant Probabilistic Risk Assessment (PRA) can be a potentially useful and powerful tool for helping to define an effective response to GL 89-10. The plant PRA can be used to prioritize the Motor Operated Valves (MOV) dynamic test. The plant PRA can also be used to determine test schedules for the MOVs. In order for the PRA to be validly used to respond to GL 89-10, various issues need to be validly addressed. Eleven issues are specifically identified and responses to these issues are outlined. The issues of joint MOV importance, PRA truncation, and validation of the proposed approach are specifically highlighted and more detailed response considerations are described. As in all PRA applications, sensitivity studies and uncertainty considerations should be incorporated in the PRA evaluations. 4 refs, 3 tabs

  8. Plant-specific volatile organic compound emission rates from young and mature leaves of Mediterranean vegetation

    Science.gov (United States)

    Bracho-Nunez, Araceli; Welter, Saskia; Staudt, Michael; Kesselmeier, Jürgen

    2011-08-01

    The seasonality of vegetation, i.e., developmental stages and phenological processes, affects the emission of volatile organic compounds (VOCs). Despite the potential significance, the contributions of seasonality to VOC emission quality and quantity are not well understood and are therefore often ignored in emission simulations. We investigated the VOC emission patterns of young and mature leaves of several Mediterranean plant species in relation to their physiological and developmental changes during the growing period and estimated Es. Foliar emissions of isoprenoids and oxygenated VOCs like methanol and acetone were measured online by means of a proton transfer reaction mass spectrometer (PTR-MS) and offline with gas chromatography coupled with a mass spectrometer and flame ionization detector. The results suggest that VOC emission is a developmentally regulated process and that quantitative and qualitative variability is plant species specific. Leaf ontogeny clearly influenced both the VOC Es and the relative importance of different VOCs. Methanol was the major compound contributing to the sum of target VOC emissions in young leaves (11.8 ± 10.4 μg g-1 h-1), while its contribution was minor in mature leaves (4.1 ± 4.1 μg g-1 h-1). Several plant species showed a decrease or complete subsidence of monoterpene, sesquiterpene, and acetone emissions upon maturity, perhaps indicating a potential response to the higher defense demands of young emerging leaves.

  9. Design of Instrumentation and Control Systems for Nuclear Power Plants. Specific Safety Guide

    International Nuclear Information System (INIS)

    2016-01-01

    This publication is a revision and combination of two Safety Guides, IAEA Safety Standards Series No. NS-G-1.1 and No. NS-G-1.3. The revision takes into account developments in instrumentation and control (I&C) systems since the publication of the earlier Safety Guides. The main changes relate to the continuing development of computer applications and the evolution of the methods necessary for their safe, secure and practical use. In addition, account is taken of developments in human factors engineering and the need for computer security. This Safety Guide references and takes into account other IAEA Safety Standards and Nuclear Security Series publications that provide guidance relating to I&C design

  10. Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-01-15

    This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances.

  11. 77 FR 58421 - Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force...

    Science.gov (United States)

    2012-09-20

    ... Item Improvement Process AGENCY: Nuclear Regulatory Commission. ACTION: Notice of availability. SUMMARY... Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online... currently require operating the ventilation system for at least 10 continuous hours with the heaters...

  12. Development of Genome Engineering Tools from Plant-Specific PPR Proteins Using Animal Cultured Cells.

    Science.gov (United States)

    Kobayashi, Takehito; Yagi, Yusuke; Nakamura, Takahiro

    2016-01-01

    The pentatricopeptide repeat (PPR) motif is a sequence-specific RNA/DNA-binding module. Elucidation of the RNA/DNA recognition mechanism has enabled engineering of PPR motifs as new RNA/DNA manipulation tools in living cells, including for genome editing. However, the biochemical characteristics of PPR proteins remain unknown, mostly due to the instability and/or unfolding propensities of PPR proteins in heterologous expression systems such as bacteria and yeast. To overcome this issue, we constructed reporter systems using animal cultured cells. The cell-based system has highly attractive features for PPR engineering: robust eukaryotic gene expression; availability of various vectors, reagents, and antibodies; highly efficient DNA delivery ratio (>80 %); and rapid, high-throughput data production. In this chapter, we introduce an example of such reporter systems: a PPR-based sequence-specific translational activation system. The cell-based reporter system can be applied to characterize plant genes of interested and to PPR engineering.

  13. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Russian Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    The objective of this Safety Guide is to provide harmonized guidance to designers, operators, regulators and providers of technical support on deterministic safety analysis for nuclear power plants. It provides information on the utilization of the results of such analysis for safety and reliability improvements. The Safety Guide addresses conservative, best estimate and uncertainty evaluation approaches to deterministic safety analysis and is applicable to current and future designs. Contents: 1. Introduction; 2. Grouping of initiating events and associated transients relating to plant states; 3. Deterministic safety analysis and acceptance criteria; 4. Conservative deterministic safety analysis; 5. Best estimate plus uncertainty analysis; 6. Verification and validation of computer codes; 7. Relation of deterministic safety analysis to engineering aspects of safety and probabilistic safety analysis; 8. Application of deterministic safety analysis; 9. Source term evaluation for operational states and accident conditions; References

  14. The use of plant-specific pyrolysis products as biomarkers in peat deposits

    NARCIS (Netherlands)

    Schellekens, J.; Bradley, J.A.; Kuyper, T.W.; Fraga, I.; Pontevedra Pombal, X.; Buurman, P.

    2015-01-01

    Peatlands are archives of environmental change that can be driven by climate and human activity. Proxies for peatland vegetation composition provide records of (local) environmental conditions that can be linked to both autogenic and allogenic factors. Analytical pyrolysis offers a molecular

  15. Overview of plant specific source terms and their impact on risk

    International Nuclear Information System (INIS)

    Desaedeleer, G.

    2004-01-01

    Probabilistic risk assesment and safety assessment focuses on systems and measures to prevent core meltdown, and it integrates many aspects of design and operation. It provides mapping of initiating event, frequencies onto plant damage state and through plant systems analysis, utilizes fault tree and event tree logic models, may include 'external event' analysis such as fire, flood, wind, seismic events. Percent contribution of sequences to the core damage frequency are shown for the following plants, taken as examples ZION, EDISON, OCONEE 3, SEABROOK, SIZEWELL B, MILLSTONE 3, RINGHALS 2. The presentation includes comparison of the following initiating event frequencies: loss of off-site power; small LOCA; large LOCA, steam generator tube rupture; loss of feedwater; turbine trip; reactor trip. Consequence analysis deals with: dispersion and depletion of radioactivity in the atmosphere, health effects, factors in the off-site emergency plan analyzed with codes that address the weather conditions; provision of mapping of source terms; risk diagram for early fatalities and for latent cancer fatalities

  16. Preliminary design of the Carrisa Plains solar central receiver power plant. Volume II. Plant specifications

    Energy Technology Data Exchange (ETDEWEB)

    Price, R. E.

    1983-12-31

    The specifications and design criteria for all plant systems and subsystems used in developing the preliminary design of Carrisa Plains 30-MWe Solar Plant are contained in this volume. The specifications have been organized according to plant systems and levels. The levels are arranged in tiers. Starting at the top tier and proceeding down, the specification levels are the plant, system, subsystem, components, and fabrication. A tab number, listed in the index, has been assigned each document to facilitate document location.

  17. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education. The IAEA takes seriously the enduring challenge for users and regulators everywhere: that of ensuring a high level of safety in the use of nuclear materials and radiation sources around the world. Their continuing utilization for the benefit of humankind must be managed in a safe manner, and the IAEA safety standards are designed to facilitate the achievement of that goal.

  18. Optimal test intervals of standby components based on actual plant-specific data

    International Nuclear Information System (INIS)

    Jones, R.B.; Bickel, J.H.

    1987-01-01

    Based on standard reliability analysis techniques, both under testing and over testing affect the availability of standby components. If tests are performed too often, unavailability is increased since the equipment is being used excessively. Conversely if testing is performed too infrequently, the likelihood of component unavailability is also increased due to the formation of rust, heat or radiation damage, dirt infiltration, etc. Thus from a physical perspective, an optimal test interval should exist which minimizes unavailability. This paper illustrates the application of an unavailability model that calculates optimal testing intervals for components with a failure database. (orig./HSCH)

  19. Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide (Russian Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances

  20. Comparison of plant-specific probabilistic safety assessments and lessons learned

    International Nuclear Information System (INIS)

    Balfanz, H.P.; Berg, H.P.; Steininger, U.

    2001-01-01

    Probabilistic safety assessments (PSA) have been performed for all German nuclear power plants in operation. These assessments are mainly based on the recent German PSA guide and an earlier draft, respectively. However, comparison of these PSA show differences in the results which are discussed in this paper. Lessons learned from this comparison and further development of the PSA methodology are described. (orig.) [de

  1. Comparison of plant-specific probabilistic safety assessments and lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Balfanz, H.P. [TUeV Nord, Hamburg (Germany); Berg, H.P. [Bundesamt fuer Strahlenschutz, Salzgitter (Germany); Steininger, U. [TUeV Energie- und Systemtechnik GmbH, Unternehmensgruppe TUeV Sueddeutschland, Muenchen (Germany)

    2001-11-01

    Probabilistic safety assessments (PSA) have been performed for all German nuclear power plants in operation. These assessments are mainly based on the recent German PSA guide and an earlier draft, respectively. However, comparison of these PSA show differences in the results which are discussed in this paper. Lessons learned from this comparison and further development of the PSA methodology are described. (orig.) [German] Probabilistische Sicherheitsanalysen (PSA) sind fuer alle in Betrieb befindlichen deutschen Kernkraftwerke durchgefuehrt worden. Diese Analysen basierten in der Regel auf dem aktuellen deutschen PSA-Leitfaden bzw. einem frueheren Entwurf. Ein Vergleich dieser PSA zeigt Unterschiede in den Ergebnissen, die in diesem Beitrag diskutiert werden. Erfahrungen und Erkenntnisse, die aus diesem Vergleich abgeleitet werden koennen, und weitere Entwicklungen der PSA-Methoden werden beschrieben. (orig.)

  2. Plant-specific evaluations of Transamerica Delaval diesel engines for nuclear service

    International Nuclear Information System (INIS)

    Dingee, D.A.; Laity, W.W.; Nesbitt, J.F.

    1985-03-01

    This paper discusses the approach taken to evlauate the readiness of Transamerica Delaval, Inc. (TDI) diesel generators for nuclear service at five power plants: Catawba, Comanche Peak, Grand Gulf, San Onofre, and Shoreham. TDI engines in these and other nuclear power plants have been the subject of a coordinated effort by 13 nuclear utilities to address reliability and quality issues. The utilities formed the TDI Diesel Generator Owners' Group and prepared a comprehensive plan for requalifying the engines as emergency power sources. Prior to full implementation of the plan by the Owners' Group and final review of the findings by the US Nuclear Regulatory Commission, several member plants became candidates for operating licenses. The TDI engines in those plants, including the five listed above, were evaluated on a case-by-case basis, taking into consideration the factors discussed in this paper. 2 refs

  3. Digital I and C system pre-tests using plant specific simulators

    International Nuclear Information System (INIS)

    Holl, B.; Probst, H.; Wischert, W.

    2006-01-01

    The paper focuses on strategic aspects of the implementation of modern digital instrumentation and control system (I and C) in nuclear power plant (NPP) training simulators and points out the way to identify the most appropriate implementation method of the digital I and C system in the simulator development environment which fulfils the requirement imposed by the nuclear power plants. This regards mainly training aspects, simulator as a test bed for design verification and validation (V and V), and software maintenance aspects with respect to future evolutions of the digital I and C system. (author)

  4. Consistency of plant-specific n-alkane patterns in plaggen ecosystems: a review

    NARCIS (Netherlands)

    Kirkels, F.M.S.A.; Jansen, B.; Kalbitz, K.

    2013-01-01

    Plaggen soils, formed by various vegetational inputs during century-long plaggen (i.e. sod) application, comprise remarkably stable organic matter. Source identification could contribute to a better understanding of carbon stabilization mechanisms in soils and reconstruction of Holocene vegetation

  5. GABA signalling modulates plant growth by directly regulating the activity of plant-specific anion transporters.

    Science.gov (United States)

    Ramesh, Sunita A; Tyerman, Stephen D; Xu, Bo; Bose, Jayakumar; Kaur, Satwinder; Conn, Vanessa; Domingos, Patricia; Ullah, Sana; Wege, Stefanie; Shabala, Sergey; Feijó, José A; Ryan, Peter R; Gilliham, Matthew; Gillham, Matthew

    2015-07-29

    The non-protein amino acid, gamma-aminobutyric acid (GABA) rapidly accumulates in plant tissues in response to biotic and abiotic stress, and regulates plant growth. Until now it was not known whether GABA exerts its effects in plants through the regulation of carbon metabolism or via an unidentified signalling pathway. Here, we demonstrate that anion flux through plant aluminium-activated malate transporter (ALMT) proteins is activated by anions and negatively regulated by GABA. Site-directed mutagenesis of selected amino acids within ALMT proteins abolishes GABA efficacy but does not alter other transport properties. GABA modulation of ALMT activity results in altered root growth and altered root tolerance to alkaline pH, acid pH and aluminium ions. We propose that GABA exerts its multiple physiological effects in plants via ALMT, including the regulation of pollen tube and root growth, and that GABA can finally be considered a legitimate signalling molecule in both the plant and animal kingdoms.

  6. Chemical and radiochemical specifications - PWR power plants; Specifications chimiques et radiochimiques - Centrales REP

    Energy Technology Data Exchange (ETDEWEB)

    Stutzmann, A [Electricite de France (EDF), 93 - Saint-Denis (France)

    1997-07-01

    Published by EDF this document gives the chemical specifications of the PWR (Pressurized Water Reactor) nuclear power plants. Among the chemical parameters, some have to be respected for the safety. These parameters are listed in the STE (Technical Specifications of Exploitation). The values to respect, the analysis frequencies and the time states of possible drops are noticed in this document with the motion STE under the concerned parameter. (A.L.B.)

  7. Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide

    International Nuclear Information System (INIS)

    2011-01-01

    This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances

  8. STUDY OF SERUM ELECTROLYTES IN FEMALE THYROID PATIENTS : A CASE CONTROL STUDY

    Directory of Open Access Journals (Sweden)

    Neela Mannangi

    2015-02-01

    women suggests that estrogen might be involved in the pathophysiology of thyroid dysfunction. In our study the serum sodium levels were markedly decreased as compared to healthy controls. According to Saruta T et al Plasma Renin Activity (PRA and Plasma Aldosterone (PA may be suppressed in hypothyroidism probably due to dysfunction of juxtaglomerular cells and glomerul osa cells respectively. The suppression of PRA and PA in patients with hypothyroidism is related to exaggerated sodium excretion and decrease in potassium excretion. CONCLUSION : We conclude that significant decreased Na + and increased K + levels were seen in female hypothyroid patients compared to controls. Hence monitoring of serum levels of these electrolytes will be helpful during the management of hypothyroid patient

  9. Application of a simplified seismic risk methodology to the La Salle County Station Unit 2 BWR

    International Nuclear Information System (INIS)

    Lappa, D.A.; Wells, J.E.

    1986-01-01

    It is important to bear in mind that no risk assessment of any U.S. nuclear power plant can be interpreted to be generally representative of more than a handful of other U.S. plants. Variations in factors ranging from plant age and operating experience to NRC licensing requirements and design guidelines have led to a wide diversity of power plants in the United States. Except for a few combinations of plants of comparable design and vintage, the extension of plant-specific results to other nuclear power plants should only be done with considerable trepidation. This situation is worsened for a seismic PRA because of the variability in the seismic hazard from site to site. In the case of this study, it would be a mistake to infer that all BWRs are sufficiently resistant to earthquakes because of the generally low seismic failure probabilities at La Salle. Unless those BWRs had similar site characteristics and were of a similar design and vintage as La Salle, no immediate extension of this study's results would be appropriate. With these thoughts in mind, we turn our attention to one of the questions which the La Salle seismic PRA is supposed to address, namely, the comparable seismic vulnerability of BWRs and PWRs. The La Salle study has provided us with some insight to the seismic risk at a particular BWR. This information may or may not be useful to understanding the seismic vulnerability of other BWRs

  10. Development of fragility descriptions of equipment for seismic risk assessment of nuclear power plants

    International Nuclear Information System (INIS)

    Hardy, G.S.; Campbell, R.D.

    1983-01-01

    Probabilistic risk assessment (PRA) of a nuclear power plant for postulated hazard requires the development of fragility relationships for the plants' safety related equipment. The objective of this paper is to present some general results and conclusions concerning the development of these seismic fragility levels. Participation in fragility-related research and experience gained from the completion of several PRA studies of a variety of nuclear power plants have provided much insight as to the most vulnerable equipment and the most efficient use of resources for development of fragilities. Plants studied had seismic design bases ranging from very simple equivalent static analysis for some of the earlier plants to state-of-the-art complex multimode dyanamic analyses for plants currently under construction. Increased sophistication and rigor in seismic qualification of equipment has resulted for the most part in increased seismic resistance. The majority of equipment has been found, however, to possess more than adequate resistance to seismic loading regardless of the degree of sophistication utilized in design as long as seismic loading was included in the design process. This paper presents conclusions of the authors as to which items of equipment typically require an individual ''plant-specific'' fragility analysis and which can be treated in a generic fashion. In addition, general conclusions on the relative seismic capacity levels and most frequent failure modes are summarized for generic equipment groups

  11. A study of relay, breaker, instrumentation and control failures during an earthquake, and their effect on nuclear power plant safety

    International Nuclear Information System (INIS)

    Lambert, H.E.; Budnitz, R.J.

    1987-01-01

    In this project, an improved PRA systems analysis methodology for post-earthquake relay-chatter analysis is developed, and its use is demonstrated through analysis of the Zion-1 and LaSalle-2 reactors as case studies. For both Zion-1 and LaSalle-2, assuming that loss of offsite power (LOSP) occurs after a large earthquake and that there are no operator recovery actions, the analysis finds very many combinations (Boolean minimal cut sets) involving chatter of three or four relays and/or pressure switch contacts. The number is so large that there is a very high likelihood (of the order of unity) that at least one combination will occur after earthquake-caused LOSP. This conclusion depends in detail on the fragility curves and response assumptions used for chatter. (orig.)

  12. Constrained optimization of test intervals using a steady-state genetic algorithm

    International Nuclear Information System (INIS)

    Martorell, S.; Carlos, S.; Sanchez, A.; Serradell, V.

    2000-01-01

    There is a growing interest from both the regulatory authorities and the nuclear industry to stimulate the use of Probabilistic Risk Analysis (PRA) for risk-informed applications at Nuclear Power Plants (NPPs). Nowadays, special attention is being paid on analyzing plant-specific changes to Test Intervals (TIs) within the Technical Specifications (TSs) of NPPs and it seems to be a consensus on the need of making these requirements more risk-effective and less costly. Resource versus risk-control effectiveness principles formally enters in optimization problems. This paper presents an approach for using the PRA models in conducting the constrained optimization of TIs based on a steady-state genetic algorithm (SSGA) where the cost or the burden is to be minimized while the risk or performance is constrained to be at a given level, or vice versa. The paper encompasses first with the problem formulation, where the objective function and constraints that apply in the constrained optimization of TIs based on risk and cost models at system level are derived. Next, the foundation of the optimizer is given, which is derived by customizing a SSGA in order to allow optimizing TIs under constraints. Also, a case study is performed using this approach, which shows the benefits of adopting both PRA models and genetic algorithms, in particular for the constrained optimization of TIs, although it is also expected a great benefit of using this approach to solve other engineering optimization problems. However, care must be taken in using genetic algorithms in constrained optimization problems as it is concluded in this paper

  13. German precursor study: methods and results

    International Nuclear Information System (INIS)

    Hoertner, H.; Frey, W.; von Linden, J.; Reichart, G.

    1985-01-01

    This study has been prepared by the GRS by contract of the Federal Minister of Interior. The purpose of the study is to show how the application of system-analytic tools and especially of probabilistic methods on the Licensee Event Reports (LERs) and on other operating experience can support a deeper understanding of the safety-related importance of the events reported in reactor operation, the identification of possible weak points, and further conclusions to be drawn from the events. Additionally, the study aimed at a comparison of its results for the severe core damage frequency with those of the German Risk Study as far as this is possible and useful. The German Precursor Study is a plant-specific study. The reference plant is Biblis NPP with its very similar Units A and B, whereby the latter was also the reference plant for the German Risk Study

  14. CANDU 6 probabilistic safety study summary

    International Nuclear Information System (INIS)

    1988-07-01

    This report summarizes the methodology, phenomenology and results relevent to the assessment of severe events in a CANDU 6 (formerly designated CANDU 600) station. The station design being analysed is based on a CANDU 6 Mark I currently operating in Canada. This evaluation includes event frequency and fission product release assessments but does not include assessment of radiation dose to the public, so that the information is equivalent to a level 2 Probabilistic Risk Assessment (PRA). The study has shown that the predicted overall average frequency for core melt in a CANDU 6 Mark I is 4.4 x 10 -6 events/year. This low frequency is, in large part due to the heavy water moderator which acts as a heat sink, prevents UO 2 melting and maintains core geometry for many events which could otherwise result in a core melt. The consequences for most core melts will be limited to the release of a fraction of noble gases and organic iodides. Other isotopes will be condensed or dissolved in the containment atmosphere and are ultimately retained in the pool of water in the basement where they are unavailable for release. Most core melts (∼ 90%) can be mitigated by operator action so that there is no danger of consequential damage to the containment structure and leak tightness. The frequency and consequences of less likely, more severe core melt sequences are also discussed in this report and shown to be small contributors to public risk

  15. Application Study of Fire Severity Classification

    International Nuclear Information System (INIS)

    Kim, In Hwan; Kim, Hyeong Taek; Jee, Moon Hak; Kim, Yun Jung

    2013-01-01

    This paper introduces the Fire Incidents Severity Classification Method for Korean NPPs that may be derived directly from the data fields and feasibility study for domestic uses. FEDB was characterized in more detail and assessed based on the significance of fire incidents in the updated database and five fire severity categories were defined. The logical approach to determine the fire severity starts from the most severe characteristics, namely challenging fires, and continues to define the less challenging and undetermined categories in progress. If the FEDB is utilized for Korean NPPs, the ways of Fire Severity Classification suggested in 2.4 above can be utilized for the quantitative fire risk analysis in future. The Fire Events Database (FEDB) is the primary source of fire data which are used for fire frequency in Fire PSA (Probabilistic Safety Assessment). The purpose of its development is to calculate the quantitative fire frequency at the comprehensive and consolidated source derived from the fire incident information available for Nuclear Power Plants (NPPs). Recently, the Fire Events Database (FEDB) was updated by Electric Power Research Institute (EPRI) and Nuclear Regulatory Commission (NRC) in U. S. The FEDB is intended to update the fire event history up to 2009. A significant enhancement to it is the reorganization and refinement of the database structure and data fields. It has been expanded and improved data fields, coding consistency, incident detail, data review fields, and reference data source traceability. It has been designed to better support several Fire PRA uses as well

  16. Survival and bioactivities of selected probiotic lactobacilli in yogurt fermentation and cold storage: New insights for developing a bi-functional dairy food.

    Science.gov (United States)

    Rutella, Giuseppina Sefora; Tagliazucchi, Davide; Solieri, Lisa

    2016-12-01

    In previous work, we demonstrated that two probiotic strains, namely Lactobacillus casei PRA205 and Lactobacillus rhamnosus PRA331, produce fermented milks with potent angiotensin-converting enzyme (ACE)-inhibitory and antioxidant activities. Here, we tested these strains for the survivability and the release of antihypertensive and antioxidant peptides in yogurt fermentation and cold storage. For these purposes three yogurt batches were compared: one prepared using yogurt starters alone (Lactobacillus delbrueckii subspecies bulgaricus 1932 and Streptococcus thermophilus 99), and the remaining two containing either PRA205 or PRA331 in addition to yogurt starters. Despite the lower viable counts at the fermentation end compared to PRA331, PRA205 overcame PRA331 in survivability during refrigerated storage for 28 days, leading to viable counts (>10(8) CFU/g) higher than the minimum therapeutic threshold (10(6) CFU/g). Analyses of in vitro ACE-inhibitory and antioxidant activities of peptide fractions revealed that yogurt supplemented with PRA205 displays higher amounts of antihypertensive and antioxidant peptides than that produced with PRA331 at the end of fermentation and over storage. Two ACE-inhibitory peptides, Valine-Proline-Proline (VPP) and Isoleucine-Proline-Proline (IPP), were identified and quantified. This study demonstrated that L. casei PRA205 could be used as adjunct culture for producing bi-functional yogurt enriched in bioactive peptides and in viable cells, which bring health benefits to the host as probiotics. Copyright © 2016 Elsevier Ltd. All rights reserved.

  17. Control plasma renin activity and changes in sympathetic tone as determinants of minoxidil-induced increase in plasma renin activity.

    Science.gov (United States)

    O'Malley, K; Velasco, M; Wells, J; McNay, J L

    1975-01-01

    A study was made of the possible mechanism(s) underlying minoxidil-induced increase in plasma renin activity (PRA). 10 patients with essential hypertension were treated with minoxidil and subsequently with a combination of minoxidil plus propranolol. Minoxidil lowered mean arterial pressure 31.6 plus or minus 3.3 mm Hg, mean plus or minus SEM. There was an associated increase in both PRA, 6.26 plus or minus 2.43 NG/ML/H, and heart rate, 21.4 plus or minus 2.7 beats/min. The changes in PRA and heart rate were positively correlated, r, 0.79. Addition of propranolol reduced mean arterial pressure by a further 10.1 plus or minus 1.5 mm Hg and returned heart rate to control levels. Propranolol reduced PRA significantly but not to control levels. Control PRA positively correlated with PRA on minoxidil, r, 0.97, and with PRA on minoxidil plus propranolol, r, 0.98. We conclude that control PRA is a major determinant of change in PRA with minoxidil. Minoxidil increased PRA by at least two mechanisms: (a) an adrenergic mechanism closely related to change in heart rate and blocked by propranolol, and (b) a mechanism(s) not sensitive to propranolol and possibly related to decrease in renal perfusion pressure. PMID:1127099

  18. Exercise induced renal dysfunction demonstrated both in hypertensives and normotensive controls studies by Tc-99m-DTPA

    International Nuclear Information System (INIS)

    Mizuiri, S.; Hayashi, I.; Ohara, T.; Hirata, K.; Sasaki, Y.

    1985-01-01

    It was previously reported that the hippurate transport disturbance after exercise is a specific phenomenon to patients with hypertension. The authors' study with Tc-99m-DTPA revealed exercise induced renal dysfunction not only in hypertensives (H) but also in normotensive controls (N). The details of the investigation is presented. Tc-99m-DTPA was intravenously injected at rest and during bicycle ergometric stress to 14 H and 14 N in sitting position. Serial dynamic renal images were taken, of which data were simultaneously stored in a data processor for later analysis. The renogram was drawn setting ROI on each kidney. Peak counts (PC) of vascular phase, peak time (PT) of secretory phase and radioisotope retention rate (RR) at 10 minutes were the parameters being compared between at rest and at exercise. GFR of each kidney was determined. Blood samples were obtained at rest and at the end of exercise for the measurement of aldosterone (ALD), plasma renin activity (PRA) and catecholamines (A, NA). Exercise caused significant lowering of PC, prolongation of PT and increase in RR (10 min. counts/peak counts) both in H and N. GFR (miota/min.) during exercise was significantly lower than at rest in both H (80 +- 22 vs 93.8 +- 16.9, p<0.02) and N (84 +- 17 vs 102 +- 15, p<0.01). ALD, PRA, A and NA are all elevated during exercise both in H and N. None of the rest-exercise differences significantly differed between H and N. The data indicate the exercise induced renal dysfunction demonstrated by Tc-99m-DTPA renograms is not specified to H but can also be observed in N, which may be resulted from the common changes in H and N of GFR and humoral factors

  19. Report on a study of the feasibility of use of the COLUMN2 computer program in a probabilistic risk assessment code

    International Nuclear Information System (INIS)

    Hall, R.C.; Liew, S.K.

    1986-10-01

    This report contains the results of a feasibility study carried out on the COLUMN2 computer program to assess its potential for use in time-dependent probabilistic risk assessment code for radiological assessment purposes. COLUMN2 is a program which provides predictions of nuclide transport in a one-dimensional geosphere configuration using a simple Ksub(d) approach for sorption. A moving grid numerical solver is used and the program is therefore potentially capable of handling time-dependent parameters. The reported work covers aspects of code acquisition, loading, theory and structure, necessary code modifications and testing, the last aspect including two documented test cases from the COLUMN2 manual and verification tests derived from international comparison exercises. Recommendations are made as to the required code development of COLUMN2 in order that the code is capable of fulfilling its prime role as defined by the System Design Working Group in a pra code. (author)

  20. Survey of Swiss nuclear's cost study 2016

    International Nuclear Information System (INIS)

    Alt, Stefan; Ustohalova, Veronika

    2017-01-01

    The report discusses the Swiss nuclear cost study 2016 concerning the following issues: evaluation of the aspects of the cost study: cost structure, cost classification and risk provision, additional payment liability, option of lifetime extension for Swiss nuclear power plants; specific indications on the report ''cost study 2016 (KS16) - estimation of the decommissioning cost of Swiss nuclear power plants'': decommissioning costs in Germany, France and the USA, indexing the Swiss cost estimation for decommissioning cost, impact factors on the decommissioning costs; specific indications on the report ''cost study 2016 (KS16) - estimation of the disposal cost - interim storage, transport, containers and reprocessing''; specific indications on the report ''cost studies (KS16) - estimation of disposal costs - geological deep disposal'': time scale and costs incurred, political/social risks, retrievability, comparison with other mining costs.

  1. Linezolid-resistant clinical isolates of enterococci and Staphylococcus cohnii from a multicentre study in China: molecular epidemiology and resistance mechanisms.

    Science.gov (United States)

    Chen, Hongbin; Wu, Weiyuan; Ni, Ming; Liu, Yingmei; Zhang, Jixia; Xia, Fei; He, Wenqiang; Wang, Qi; Wang, Zhanwei; Cao, Bin; Wang, Hui

    2013-10-01

    Genetic characterisation of linezolid-resistant Gram-positive cocci in a multicentre study in China has not been reported previously. To study the mechanism underlying the resistance of linezolid-resistant isolates, nine Enterococcus faecalis, one Enterococcus faecium and three Staphylococcus cohnii isolates with various levels of resistance were collected from five hospitals across China in 2009-2012. The nine E. faecalis isolates were classified into seven sequence types, indicating that these linezolid-resistant E. faecalis isolates were polyclonal. Enterococci isolates had reduced susceptibility to linezolid (MICs of 4-8 mg/L) and had mutation of ribosomal protein L3, with three also having mutation of L4, but without the multidrug resistance gene cfr or the 23S rRNA mutation G2576T. The three S. cohnii isolates were highly resistant to linezolid (MICs of 64 mg/L to >256 mg/L), harboured the cfr gene and had the 23S rRNA mutation G2576T. Southern blotting indicated that the cfr gene of these three isolates resided on different plasmids (pHK01, pRM01 and pRA01). In plasmid pHK01, IS21-558 and the cfr gene were integrated into transposon Tn558. In plasmids pRM01 and pRA01, the cfr gene was flanked by two copies of an IS256-like insertion sequence, indicating that the transferable form of linezolid resistance is conferred by the cfr gene. In conclusion, the emergence of linezolid-resistant Gram-positive cocci in different regions of China is of concern. The cfr gene and the 23S rRNA mutation contribute to high-level linezolid resistance in S. cohnii, and the L3 and L4 mutations are associated with low-level linezolid resistance in enterococci. Copyright © 2013 Elsevier B.V. and the International Society of Chemotherapy. All rights reserved.

  2. Probabilistic safety assessment applications and insights

    International Nuclear Information System (INIS)

    Hitchler, M.J.; Burns, N.L.; Liparulo, N.J.; Mink, F.J.

    1987-01-01

    The insights gained through a comparison of seven PRA studies (Italian PUN, Sizewell B, Ringhals 2, Millstone 3, Zion 1 and 2, Oconee 3, and Seabrook) included insights regarding the adequacy of the PRA technology utilized in the studies and the potential areas for improvement and insights regarding the adequacy of plant designs and how PRA has been utilized to enhance the design and operation of nuclear power plants. (orig.)

  3. Insights gained through probabilistic risk assessments

    International Nuclear Information System (INIS)

    Hitchler, M.J.; Burns, N.L.; Liparulo, N.J.; Mink, F.J.

    1987-01-01

    The insights gained through a comparison of seven probabilistic risk assessments (PRA) studies (Italian PUN, Sizewell B, Ringhals 2, Millstone 3, Zion 1 and 2, Oconee 3, and Seabrook) included insights regarding the adequacy of the PRA technology utilized in the studies and the potential areas for improvement and insights regarding the adequacy of plant designs and how PRA has been utilized to enhance the design and operation of nuclear power plants

  4. K otázce datování počátků kultury s keramikou pražského typu na Moravě. Příspěvek pro 15. mezinárodní sjezd slavistů v Minsku

    Czech Academy of Sciences Publication Activity Database

    Jelínková, Dagmar

    2012-01-01

    Roč. 53, č. 2 (2012), s. 7-21 ISSN 1211-7250 R&D Projects: GA ČR GA404/07/1629 Institutional support: RVO:68081758 Keywords : Prague-type-pottery culture * Southern Moravia * inhumation grave * sax * settlement * dating C14 Subject RIV: AC - Archeology, Anthropology, Ethnology http://dino.iabrno.cz/dokumenty/pv/PV53_2_studie/PV53_2_studie_1.pdf

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

    International Nuclear Information System (INIS)

    Ohlmeier, H.

    1989-01-01

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

  6. A Study on Plasma Renin Activity in Essential Hypertension

    International Nuclear Information System (INIS)

    Choe, Kang Won; Lee, Jung Sang; Cho, Bo Yeon; Koh, Chang Soon; Lee, Mun Ho

    1975-01-01

    Radioimmunoassay for the measurement of plasma renin activity (PRA) was performed in 43 normal Koreans and 45 patients with essential hypertension. Plasma samples were drawn in supine position in the morning and after upright posture for 4 hours. Urinary sodium excretion rates were measured in the concurrent 24 hour urine samples, an index of their sodium balance. The results were as follows: 1) There was an inverse correlation between 24 hr sodium excretion and PRA. The normal values of PRA in supine position ranged from 1.0 to 7.0 ng/ml/hr. when 24 hour sodium excretion were between 50 to 150 mEq. PRA in elderly tended to be low. 2) When stimulated by 4 hour upright posture, PRA increased by 2.6 times from the baseline value. 3) Of the 45 patients with essential hypertension, PRA was low in 10 cases (22.2%), normal in 28 cases (62.2%), and high in 7 cases (15.6%). 4) In the normal and high renin groups, who tended to be younger in ages, mean diastolic blood pressure and BUN were higher than in low renin group. Though hypertensive retinopathy and left ventricular hypertrophy in ECG were more prevalent in the former, no significant differences were noted as in the case of serum cholesterol. 5) There were 8 cases of cardiovascular complications (7 with cerebral vascular accident, 1 with myocardial infarction); 3 in low renin group (30%), 2 in normal renin (7.1%) and 3 in higher renin group (42.9%). This figure indicated higher rate of cardiovascular complications in higher renin groups, and lower rate in normal renin group. But the incidence of the complication was not significantly low in low renin group.

  7. Risk-informed design of IRIS using a level-1 probabilistic risk assessment from its conceptual design phase

    International Nuclear Information System (INIS)

    Mizuno, Yuko; Ninokata, Hisashi; Finnicum, David J.

    2005-01-01

    In this study, a probabilistic risk assessment (PRA) for the International Reactor Innovative and Secure (IRIS) has been generated to address two key areas as a part of the effort for the pre-application licensing of the IRIS design. First, the IRIS PRA is supporting the evaluation of IRIS design by providing design insights as well as a solid risk basis for the pre-licensing evaluation of the IRIS design. Second, the current PRA task is beginning the preparation of the more complete PRA analyses and documentation that will be required for Design Certification. The initial IRIS PRA is an at-power, Level-1 PRA for internal events that focuses on the evaluation of the IRIS design features to support the risk-informed design of IRIS by application of the PRA insights and the risk information to the design. To accomplish the evaluation, a reasonably complete Level-1 PRA model has been developed. The use of PRA in the early stages of the design has allowed a selection of design and performance features and an optimization of the design of several systems to reduce the potential for events that could lead to core damage via both enhanced prevention and mitigation of challenges. As a result, the total core damage frequency for internal events for the IRIS design has been calculated as 1.2x10 -8 per year

  8. Overview of methods for uncertainty analysis and sensitivity analysis in probabilistic risk assessment

    International Nuclear Information System (INIS)

    Iman, R.L.; Helton, J.C.

    1985-01-01

    Probabilistic Risk Assessment (PRA) is playing an increasingly important role in the nuclear reactor regulatory process. The assessment of uncertainties associated with PRA results is widely recognized as an important part of the analysis process. One of the major criticisms of the Reactor Safety Study was that its representation of uncertainty was inadequate. The desire for the capability to treat uncertainties with the MELCOR risk code being developed at Sandia National Laboratories is indicative of the current interest in this topic. However, as yet, uncertainty analysis and sensitivity analysis in the context of PRA is a relatively immature field. In this paper, available methods for uncertainty analysis and sensitivity analysis in a PRA are reviewed. This review first treats methods for use with individual components of a PRA and then considers how these methods could be combined in the performance of a complete PRA. In the context of this paper, the goal of uncertainty analysis is to measure the imprecision in PRA outcomes of interest, and the goal of sensitivity analysis is to identify the major contributors to this imprecision. There are a number of areas that must be considered in uncertainty analysis and sensitivity analysis for a PRA: (1) information, (2) systems analysis, (3) thermal-hydraulic phenomena/fission product behavior, (4) health and economic consequences, and (5) display of results. Each of these areas and the synthesis of them into a complete PRA are discussed

  9. Evaluation of operating experience: The precursor study (GPS) performed in the Federal Republic of Germany. Working material

    International Nuclear Information System (INIS)

    1991-01-01

    Probabilistic Safety Assessments (PSAs) are systematic and quantitative predictions of possible accident scenarios at technical installations on the basis of data gained from the past experience on similar technical installations. For supporting PSAs by operational experience as far as possible Precursor studies are performed. An Accident Sequence Precursor is defined as an observed event which could results, in coincidence with additional postulated events, in a potential severe core damage accident. In the presented case study the procedure of such Precursor studies is explained. Particularly, the methodology and the results of the plant-specific Precursor (GPS) performed in the Federal Republic of Germany are shown in detail. 26 refs, 13 figs, 8 tabs

  10. Evaluation of operating experience: The precursor study (GPS) performed in the Federal Republic of Germany. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-31

    Probabilistic Safety Assessments (PSAs) are systematic and quantitative predictions of possible accident scenarios at technical installations on the basis of data gained from the past experience on similar technical installations. For supporting PSAs by operational experience as far as possible Precursor studies are performed. An Accident Sequence Precursor is defined as an observed event which could results, in coincidence with additional postulated events, in a potential severe core damage accident. In the presented case study the procedure of such Precursor studies is explained. Particularly, the methodology and the results of the plant-specific Precursor (GPS) performed in the Federal Republic of Germany are shown in detail. 26 refs, 13 figs, 8 tabs.

  11. Considerations on a regulatory framework for environmental management of produced water resulting from the extraction of petroleum in the state of Bahia; Consideracoes acerca de um modelo regulatorio pra o gerenciamento ambiental da agua produzida resultante da extracao de petroleo do estado da Bahia

    Energy Technology Data Exchange (ETDEWEB)

    Fraser, Roberta Tourinho Dantas [Instituto do Meio Ambiente e Recursos Hidricos (INEMA), Salvador, BA (Brazil); Vieira, Victor Menezes [Geo Innova Ltda., Lauro de Freitas, BA (Brazil); Ferreira, Doneivan Fernandes [Universidade Federal da Bahia (UFBA), Salvador, BA (Brazil)

    2012-07-01

    Produced water is the main byproduct associated to oil and gas extraction process. This water, considered by regulation as a residue, has the potential to cause adverse impact on environment. As extraction progresses and reservoirs mature increasing volumes of water are produced and need to be wisely managed. Due to Reconcavo Basin advanced stage of maturity, the state of Bahia has become a very large producer of water in the country. Remarkably, no state environmental regulation is in place to provide management guidelines and proper disposal rules for this waste. The present study intends to argue the need for a regulatory framework involving the management of water produced in state onshore sedimentary basins, identifying and discussing critical variables involved in this process. The following methodological instruments were used in the study: literature and normative survey, interaction with key stakeholders and field work. Environmental regulation has, as its main purpose, protection and preservation of the environment against potential polluting activities, while recognizing the importance of socioeconomic development. In this sense, implementing specific rules for management of produced water not only serves to harmonize productive activities such as oil and gas extraction with protective policies, but also brings institutional benefits that could represent a significant reduction in operating costs associated with inadequate management of this waste. It also tends to improve industry image as perceived by society. However, success of regulatory compliance is dependent of a number of variables, which, in the case of produced water management includes: physicochemical characterization; establishment of benchmark studies to guide application of proper techniques for injection and disposal; the choice of efficient regulatory instruments; expertise and experienced human resources within regulatory agencies responsible for monitoring activities and enforcing

  12. A gente vive pra cuidar da população: estratégias de cuidado e sentidos para a saúde, doença e cura em terreiros de candomblé We live to take care of the population: health care strategies and meanings for health, disease and healing in candomblé temples

    Directory of Open Access Journals (Sweden)

    Clarice Santos Mota

    2011-06-01

    Full Text Available Os estudos que exploram a interface entre religião e saúde demonstram que, entre as motivações que orientam a filiação religiosa, figura de modo destacado a busca de soluções para aflições e enfermidades. A terapêutica religiosa constitui assim uma das alternativas de cura, cuja adesão por parte de seus seguidores é influenciada, entre outros fatores, por experiências individuais ou coletivas de sua eficácia e/ou pela fidelidade a uma religião que regulam a vida em geral, incluindo as condutas relativas ao cuidado com o corpo, com a saúde etc. Este estudo explora as inter-relações entre saúde, religiosidade e identidade étnica em um bairro popular de Salvador, marcado pelo pluralismo religioso. Ao investigar as narrativas de famílias afrodescendentes membros do candomblé, busca-se compreender a relação entre a cosmologia religiosa do candomblé e as concepções e práticas de saúde e doença e cuidado. Para atingir essa compreensão, é preciso também apreender modos de organização social, crenças, visão de mundo e práticas no universo do candomblé, detendo-se especialmente nos aspectos associados com o complexo saúde-doença-cuidado. Trata-se de um estudo etnográfico desenvolvido através da observação participante e de entrevistas semi-estruturadas.Studies which explore the relations between religion and health have been showing that one of the main reasons for joining a religious institution is the quest for health care. Therefore, the choice of religious healing is influenced by previous experiences of success or by the bond with a system of beliefs that regulates social life, including health care practices. This study explores the connections between religiousness and ethnic identity in a popular neighborhood in Salvador that is characterized by its religious plurality. The main goal of the research was to investigate the relations between the cosmology of Candomblé and the conceptions and practices

  13. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment ampersand storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage ampersand treatment facilities

    International Nuclear Information System (INIS)

    Sasser, K.

    1994-06-01

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory's storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations

  14. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sasser, K.

    1994-06-01

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

  15. Study for Relation of Pressure and Aging Degradation during LOCA Test

    International Nuclear Information System (INIS)

    Kim, Jong Seog

    2013-01-01

    As result of this test, it was found that low pressure effect in aging was not significant compared with that of temperature. If temperature profile in LOCA test can satisfy the plant LOCA profile, no further analysis of pressure profile for aging degradation is necessary. For environmental qualification of electric equipment in containment building of nuclear power plant, LOCA test should be applied. During the LOCA test, temperature and pressure of LOCA chamber shall be controlled to meet a requirement of plant specific LOCA profile. It is general to keep LOCA test temperature and pressure above the plant specific LOCA profile. If the test temperature is lower than required profile in some time zone while it is higher in other time zone, calculation of total cumulated test temperature is required to compare with that of plant profile. Arrhenius equation can be applied for calculation of total temperature accumulation. If there is a deviation of pressure between test profile and plant specific profile, can we still use the same rule of temperature? Since the Arrhenius equation can't be applied to pressure, analysis of pressure effect to aging degradation is not easy. Study for relation of pressure and aging degradation during LOCA condition is described herein. To Study an aging degradation effect of pressure during LOCA test, comparison of IR during high LOCA pressure and low LOCA pressure were implemented. We expected low IR in high pressure because it contained a high concentration of oxygen which induces high aging degradation. Contrary to our expectation, IR of low pressure was lower than that of high pressure. It is assumed that high vibration of temperature profile to maintain the low pressure at high temperature induced supply of high enthalpy steam into LOCA chamber

  16. Study

    Directory of Open Access Journals (Sweden)

    Erum Zahir

    2017-05-01

    Full Text Available Physicochemical properties like density, viscosity, boiling point, saponification value (SV, iodine value (IV,and peroxide value (PV of Corn and Mustard oils were studied to evaluate the compositional quality of oils and also to investigate the effect on the use of same oil for repeated frying as it ultimately changes the physicochemical, nutritional and sensory properties of the oil. FT-IR spectroscopy was used to evaluate the degree of oxidation after heating and frying processes. Results revealed that due to the temperature change in the oil there is a notable difference in the spectral band which showed that the proportions of the fatty acids were changed. The spectra of Corn oil at the boiling point and at multiple frying times with a piece of potato showed frequencies in range of 2852.7–2926.0 cm−1 while in Mustard oil an additional peak was observed at 3633.8 cm−1 which exhibits the secondary oxidized product formation.

  17. International status of application of probabilistic risk analysis

    International Nuclear Information System (INIS)

    Cullingford, M.C.

    1984-01-01

    Probabilistic Risk Assessment (PRA) having been practised for about ten years and with more than twenty studies completed has reached a level of maturity such that the insights and other products derived from specific studies may be assessed. The first full-scale PRA studies were designed to develop the methodology and assess the overall risk from nuclear power. At present PRA is performed mostly for individual plants to identify core damage accident sequences and significant contributors to such sequences. More than 25 countries are utilizing insights from PRA, some from full-scale PRA studies and other countries by performing reliability analyses on safety systems identified as important contributors to one or more core melt sequences. Many Member States of the IAEA fall into one of three groups: those having (a) a large, (b) a medium number of reactor-years of operating experience and (c) those countries in the planning or feasibility study stages of a nuclear power programme. Of the many potential uses of PRA the decision areas of safety improvement by backfitting, development of operating procedures and as the basis of standards are felt to be important by countries of all three groups. The use of PRA in showing compliance with safety goals and for plant availability studies is held to be important only by those countries which have operating experience. The evolution of the PRA methodology has led to increased attention to quantification of uncertainties both in the probabilities and consequences. Although many products from performing a PRA do not rely upon overall risk numbers, increasing emphasis is being placed on the interpretation of uncertainties in risk numbers for use in decisions. International co-operation through exchange of information regarding experience with PRA methodology and its application to nuclear safety decisions will greatly enhance the widespread use of PRA. (author)

  18. Direct renin inhibition in addition to or as an alternative to angiotensin converting enzyme inhibition in patients with chronic systolic heart failure: rationale and design of the Aliskiren Trial to Minimize OutcomeS in Patients with HEart failuRE (ATMOSPHERE) study

    DEFF Research Database (Denmark)

    Krum, Henry; Massie, Barry; Abraham, William T

    2011-01-01

    AIMS: The renin-angiotensin-aldosterone system (RAAS) represents a key therapeutic target in heart failure (HF) management. However, conventional agents that block this system induce a reflex increase in plasma renin activity (PRA), which may lead to RAAS 'escape'. Direct renin inhibitors (DRIs......S for Patients with HEart failuRE (ATMOSPHERE) study is to evaluate the effect of both aliskiren and enalapril monotherapy and aliskiren/enalapril combination therapy on cardiovascular death and HF hospitalization in patients with chronic systolic HF, NYHA functional class II-IV symptoms, and elevated plasma...... levels of BNP. Methods Patients tolerant to at least 10 mg or equivalent of enalapril will undergo an open-label run-in period where they receive enalapril then aliskiren. Approximately 7000 patients tolerating this run-in period will then be randomized 1:1:1 to aliskiren monotherapy, enalapril...

  19. Comparison of risk sensitivity to human errors in the Oconee and LaSalle PRAs

    International Nuclear Information System (INIS)

    Wong, S.; Higgins, J.

    1991-01-01

    This paper describes the comparative analyses of plant risk sensitivity to human errors in the Oconee and La Salle Probabilistic Risk Assessment (PRAs). These analyses were performed to determine the reasons for the observed differences in the sensitivity of core melt frequency (CMF) to changes in human error probabilities (HEPs). Plant-specific design features, PRA methods, and the level of detail and assumptions in the human error modeling were evaluated to assess their influence risk estimates and sensitivities

  20. Long-Term Effects of Antibodies Against Human Leukocyte Antigens Detected by Flow Cytometry in the First Year After Renal Transplantation

    Directory of Open Access Journals (Sweden)

    Tülay Kılıçaslan Ayna

    2013-03-01

    Full Text Available Objective: In this study, we aimed to investigate the incidence, dynamics and profiles of human leukocyte antigen (HLA-directed antibodies developed after transplantation and their impact on graft rejection and outcome in kidney recipients. Study Design: Prospective follow-up study. Material and Methods: A total of 56 kidney recipients were monitored at 1st, 6th and 12th months for the development of anti-HLA antibodies using bead based flow-cytometry assays (Flow PRA tests. Results: In 21 (37.5% patients, panel reactive antibodies (PRA was positive after transplantation, however, in 35 (62.5% patients PRA was found negative. Twelve (57.1% patients with post-transplantation HLA-reactive antibodies [PRA (+] and 8 (22.9% patients with no detectable alloantibodies [PRA (-] were developed allograft rejection (p=0.010. In the PRA positive patient group the rates of early period infection and delayed graft function (DGF were higher than the PRA negative patient group. Serum creatinine levels of PRA positive group at 6. and 12. months after transplantation were significantly higher than the PRA negative group (p=0.015 and p=0.048, respectively. The rejection rates of patients who had class I and II HLA antibodies were significantly higher than the patients who had either class I or II HLA antibodies (p=0.011. Acute rejection rates were significantly higher in patients who had class I and II HLA antibodies at the first month (p=0.007. Conclusion: Higher occurrence of rejection episodes in PRA positive group may show the importance of anti-HLA antibody monitoring using Flow-PRA after renal transplantation as a prognostic marker in terms of graft survival.

  1. A Study on Renin-Angiotensin System and Total Exchangeable Sodium in Hypertension

    International Nuclear Information System (INIS)

    Choe, Kang Won; Park, Jung Sik; Lee, Jung Sang; Koh, Chang Soon

    1976-01-01

    The etiologic role of renin-angiotensin system and sodium-volume status in the pathophysiology of various forms of hypertension was investigated. Plasma renin activity (PRA) was measured by radioimmunoassay, while sodium-volume status was evaluated by the determination of total exchangeable sodium(NaE) using isotope dilution method. The subjects consisted of 25 controls, 24 patients with essential hypertension, 22 patients with chronic renal failure (13 with hypertension, 9 without hypertension) and 14 patients with malignant hypertension. The results were as follows: 1) An inverse correlation between NaE and PRA was noted in control subjects (r=-0.598, p 0.1) 3) Absolute value of PRA was not deviated significantly from control group (2.53±1.416 ng/ml/hr) except in malignant hypertension (6.09±2.042, p 0.1). It is suggested that renin-angiotensin system plays a predominant role in the pathogenesis of malignant hypertension and in hypertension of chronic renal failure, though sodium retention is also contributing factor. PRA variation in essential hypertension does not appear to be associated with any consistent change in Na-volume status, suggesting the existence of another mechanism in the genesis of hypertension and PRA variation.

  2. Astronomický ciferník pražského orloje

    Czech Academy of Sciences Publication Activity Database

    Křížek, Filip; Křížek, Michal

    2011-01-01

    Roč. 86, č. 1 (2011), s. 1-6 ISSN 0035-9343 Institutional research plan: CEZ:AV0Z10190503; CEZ:AV0Z10480505 Keywords : great circle * Ptolemy theorem * stereographic projection Subject RIV: BA - General Mathematics

  3. Status of efforts to evaluate LOCA frequency estimates using combined PRA and PFM approaches

    International Nuclear Information System (INIS)

    Wilkowski, G.; Rudland, D.; Tregoning, R.; Scott, P.

    2002-01-01

    The risk-informed reevaluation of 10 CFR 50.46 (along with Appendix K and GDC 35), the emergency core cooling system (ECCS) requirements, utilizes loss of coolant accident (LOCA) initiating event frequencies to evaluate the technical basis for potential related rule changes. A longer-term effort is considering redefining the maximum design basis pipe break size for sizing the ECCS system. In the past few years, the U.S. Nuclear Regulatory Commission (NRC) has utilized NUREG/CR-5750 pipe-break LOCA estimated for initiating event frequencies. However, several failure mechanisms have recently emerged at plants which have not been evident within the service period covered by the NUREG/CR-5750 estimates. The concern is that these and other potential aging-related mechanisms may not be adequately represented within the NUREG/CR-5750 LOCA estimates. Additionally, LOCAs can occur from failure of active components (e.g. safety relief valves, reactor coolant pump seals, etc.) and other non-pipe break passive failures (e.g. steam generator tubes). The LOCA contributions from these additional sources must also be considered in deciding the design basis break size. The LOCA estimates must also attempt to capture expected future changes in the LOCA frequencies so that the estimates are pertinent up through the end of the license renewal period. (orig.)

  4. Verification and validation of the SAPHIRE Version 4.0 PRA software package

    International Nuclear Information System (INIS)

    Bolander, T.W.; Calley, M.B.; Capps, E.L.

    1994-02-01

    A verification and validation (V ampersand V) process has been performed for the System Analysis Programs for Hands-on Integrated Reliability Evaluation (SAPHIRE). SAPHIRE is a set of four computer programs that the Nuclear Regulatory Commission (NRC) developed to perform probabilistic risk assessments (PRAs). These programs allow an analyst to create, quantify, and evaluate the risk associated with a facility or process being analyzed. The programs included in this set are Integrated Reliability and Risk Analysis System (IRRAS), System Analysis and Risk Assessment (SARA), Models and Results Database (MAR-D), and Fault Tree/Event Tree/Piping and Instrumentation Diagram (FEP) graphical editor. The V ampersand V steps included a V ampersand V plan to describe the process and criteria by which the V ampersand V would be performed; a software requirements documentation review to determine the correctness, completeness, and traceability of the requirements; a user survey to determine the usefulness of the user documentation, identification and testing of vital and non-vital features, and documentation of the test results

  5. An evaluation of internal event Level 1 PRA methods used in NUREG-1150

    International Nuclear Information System (INIS)

    Camp, A.L.; Cramond, W.R.

    1989-01-01

    As part of the effort to support NUREG-1150, Sandia National Laboratories and its subcontractors have developed innovative techniques for efficiently performing internal event Level I probabilistic risk assessments. This methodology is one of the alternatives for industry to use in performing individual plant evaluations in the future. While this new methodology was very successful, there are some areas where improvements can be made. This paper evaluates the strengths and weaknesses of the methodology and makes some important recommendations for modifications in order to provide insights to future users

  6. Diablo Canyon internal events PRA [Probabilistic Risk Assessment] review: Methodology and findings

    International Nuclear Information System (INIS)

    Fitzpatrick, R.G.; Bozoki, G.; Sabek, M.

    1990-01-01

    The review of the Diablo Canyon Probabilistic Risk Assessment (DCRPA) incorporated some new and innovative approaches. These were necessitated by the unprecedented size, scope and level of detail of the DCRPA, which was submitted to the NRC for licensing purposes. This paper outlines the elements of the internal events portion of the review citing selected findings to illustrate the various approaches employed. The paper also provides a description of the extensive and comprehensive importance analysis applied by BNL to the DCRPA model. Importance calculations included: top event/function level; individual split fractions; pair importances between frontline-support and support-support systems; system importance by initiator; and others. The paper concludes with a brief discussion of the effectiveness of the applied methodology. 3 refs., 5 tabs

  7. External hazards in the PRA of Olkiluoto 1 and 2 NPP units - Accidental oil spills

    International Nuclear Information System (INIS)

    Tunturivuori, Lasse

    2014-01-01

    Oil transports in Finnish territorial waters have increased significantly during the last 10 years. The Gulf of Finland is at this moment a very important route of oil being transported from Russia to the Western Europe. Although the number of accidental oil spills is decreasing in amount and in size, there is a growing concern of their effects to nuclear power plants (NPPs). The amounts of oil transported on the Gulf of Bothnia are much smaller than on the Gulf of Finland. However, accidental oil spills have occurred also there, the size and amount of which are smaller, though. Accidental oil spills are often a result of grounding of a ship or collision of two ships, and often occur during harsh weather conditions like storm or dense fog. However, also coastal oil depots may break, the oil of which may spread over wide distances on the sea. The modelling of initiating events resulting from accidental oil spills includes oil spill response actions performed by the regional rescue services, alarming of the oil spill by the emergency response centre to the NPP rescue services and spill response by the NPPs rescue services. It is unclear what the consequences are if drifted oil would enter the coolant water tunnels. The effect of different oil types to the operation of the safety-related service water systems and components are being assessed. In the ultimate case, an oil spill would clog the inlet channels thus failing the ultimate heat sink of the NPP units. The licensee is evaluating what is the optimal way to operate the NPP units in the case that an oil slick is threatening the plant to ensure reactor core cooling and RHR. The continued operation of, and especially the cooling of, at least one auxiliary feedwater pump is critical in the mitigation of the initiating event. Strategies, like reversing the water flow of the cooling water channels or closing of the cooling water channels, are being evaluated. (authors)

  8. Bohemicalia Zachiana II. Pražské období Jana Zacha

    Czech Academy of Sciences Publication Activity Database

    Slavický, Tomáš

    2002-01-01

    Roč. 39, č. 1 (2002), s. 3-23 ISSN 0018-7003 Institutional research plan: CEZ:AV0Z8059909 Keywords : Jan Zach * Music in Prague in the 18th Century Subject RIV: AL - Art, Architecture, Cultural Heritage

  9. PRA has many faces - can the safety goal be well-posed

    International Nuclear Information System (INIS)

    Bargmann, H.

    1983-01-01

    The question is discussed whether probabilistic reliability problems can, principally, be well-posed in practical situations. The problem is reduced to the question whether an underlying probabilistic experiment which is, essentially, the set of outcomes can be precisely specified such that the solution of the problem is unique. Upon reexamination of a classical paradox due to Bertrand and consideration of a typical problem of structural reliability we conclude that the possibility of well-posing a reliability problem should be considered illusory, for fundamental reasons which are inherent in practical situations. In particular, it should not be assumed that a quantitative safety goal could be verified. Generally, a probabilistic assessment should be considered as a quantitative method for establishing rational results which should, however, not be viewed as quantitative measures but as qualitative guides

  10. Proračun produktivnosti zaposlenika na osnovi podataka praćenja proizvodnje

    OpenAIRE

    Dolenc, Filip

    2017-01-01

    U ovom radu analizirala se važnost upravljanja bazama podataka u teorijskom smislu te se na primjeru stvarne tvrtke analizirao proces upravljanja bazama podataka od strane asistenta voditelja odjela. Da bi poduzeće bilo produktivno, odnosno da bi ostvarivalo pozitivne poslovne rezultate, asistent voditelja odjela mora prije konačnog obračuna i analize produktivnosti provjeriti i editirati eventualne greške te pratiti i ažurirati niz drugih datoteka i aktivnosti koje su prikazane u ovom ra...

  11. Identification and analysis of external event combinations for Hanhikivi 1PRA

    Energy Technology Data Exchange (ETDEWEB)

    Helander, Juho [Fennovoima Oy, Helsinki (Finland)

    2017-03-15

    Fennovoima's nuclear power plant, Hanhikivi 1, Pyhäjoki, Finland, is currently in design phase, and its construction is scheduled to begin in 2018 and electricity production in 2024. The objective of this paper is to produce a preliminary list of safety-significant external event combinations including preliminary probability estimates, to be used in the probabilistic risk assessment of Hanhikivi 1 plant. Starting from the list of relevant single events, the relevant event combinations are identified based on seasonal variation, preconditions related to different events, and dependencies (fundamental and cascade type) between events. Using this method yields 30 relevant event combinations of two events for the Hanhikivi site. The preliminary probability of each combination is evaluated, and event combinations with extremely low probability are excluded from further analysis. Event combinations of three or more events are identified by adding possible events to the remaining combinations of two events. Finally, 10 relevant combinations of two events and three relevant combinations of three events remain. The results shall be considered preliminary and will be updated after evaluating more detailed effects of different events on plant safety.

  12. Nirmal Varma o Pražském jaru a srpnu 1968

    Czech Academy of Sciences Publication Activity Database

    Marková, Dagmar

    2008-01-01

    Roč. 63, č. 2 (2008), s. 42-45 ISSN 0029-5302 Institutional research plan: CEZ:AV0Z90210515 Keywords : Nirmal Varma * Prague Spring * Hindi literature Subject RIV: AJ - Letters, Mass-media, Audiovision

  13. 78 FR 77597 - Safety Zone; Allied PRA-Solid Works, San Diego Bay; San Diego, CA

    Science.gov (United States)

    2013-12-24

    ... authority under section 4(a) of the Administrative Procedure Act (APA) (5 U.S.C. 553(b)). This provision... M16475.lD, which guide the Coast Guard in complying with the National Environmental Policy Act of 1969...

  14. Experience in integrating the operator contributions in the PRA of actual operating plants

    International Nuclear Information System (INIS)

    Potash, L.M.; Stewart, M.; Dietz, P.E.; Lewis, C.M.; Dougherty, E.M. Jr.

    1982-01-01

    While working on the human factors' portion of the Oconee Probabilistic Risk Assessment, we identified several major problems that inhibit any effort to handle operator error in PRAs. The approaches we developed should help to direct future efforts in dealing with these problems

  15. Pra Desain Pabrik Substitute Natural Gas (SNG dari Low Rank Coal

    Directory of Open Access Journals (Sweden)

    Asti Permatasari

    2014-09-01

    Full Text Available Substitute Natural Gas (SNG merupakan campuran gas hidrokarbon dengan sifat mirip seperti gas alam yang dapat diproduksi dari gasifikasi dengan bahan baku berupa batubara atau biomassa. Gasifikasi adalah proses perubahan bahan baku padat menjadi gas. Dengan mengubah bahan baku padat menjadi gas, maka material yang tidak diinginkan yang terkandung di dalam bahan baku tersebut seperti senyawa sulfur, karbon dioksida dan abu dapat dihilangkan dengan menggunakan metode tertentu sehingga dapat dihasilkan gas bersih yang disebut dengan syngas. Syngas yang memiliki kandungan utama CO dan H2 kemudian dikonfersi menjadi SNG yang berupa metana (CH4 melalui proses metanasi sehingga menghasilkan produk utama berupa CH4. SNG merupakan suatu bahan bakar baru yang dapat digunakan industri untuk menggantikan gas alam. Permintaan gas alam masa mendatang diperkirakan akan tumbuh cukup pesat terkait dengan upaya industri untuk beralih ke gas untuk mengurangi ketergantungan terhadap BBM. Gas alam dan minyak bumi sebagai salah satu sumber daya alam memiliki manfaat yang sangat banyak dalam menunjang berbagai sektor kehidupan manusia. Banyaknya manfaat dari sumber daya alam gas alam menyebabkan banyaknya kebutuhan akan gas alam di dunia, dimana kebutuhan tersebut terus bertambah setiap tahunnya. Padahal gas alam yang selama ini banyak dimanfaatkan berbagai sektor di Indonesia sifatnya tidak terbarukan (non renewable serta cadangannya diperkirakan akan menurun. Pemerintah harus menggalakkan pengembangan sumber energy alternative pengganti gas alam dan minyak bumi sesuai dengan Peraturan Presiden nomor 5 tahun 2006. Salah satu energi potensial yang dapat menggantikannya adalah SNG dari batubara. Indonesia memiliki cadangan batubara dalam jumlah yang sangat banyak. Wilayah Indonesia diketahui memiliki potensi endapan batubara yang sangat luas. Data dari Pusat Sumber Daya Geologi (2006 menyebutkan bahwa wilayah Sumatera Selatan memiliki jumlah cadangan batubara kualitas rendah dan sedang yang sangat banyak, yaitu masing-masing sebesar 2.426,00 juta ton dan 186,00 juta ton. Maka dari itu, pabrik SNG dari low rank coal ini akan didirikan di Kecamatan Ilir Timur, Sumatera Selatan. Rencananya pabrik ini akan didirikan pada tahun 2016 dan siap beroperasi pada tahun 2018. Diperkirakan konsumsi gas alam pada tahun 2018 sebesar 906.599,3 MMSCF sehingga pendirian pabrik yang baru diharapkan dapat menggantikan kebutuhan gas alam sebesar 4% di Indonesia, yaitu sebanyak 36.295,502 MMSCF per tahun atau sebesar 109.986 MMSCFD. Proses pembuatan SNG dari low rank coal terdiri dari empat proses utama, yaitu coal preparation, gasifikasi, gas cleaning, dan metanasi. Dari analisa perhitungan ekonomi didapat Investasi 823.947.924 USD, IRR sebesar 13,12%, POT selama 5 tahun, dan BEP sebesar 68,55%.

  16. Pražskij lingvističeskij kružok i jevrazijstika

    Czech Academy of Sciences Publication Activity Database

    Savický, Nikolaj

    2011-01-01

    Roč. 80, 2/3 (2011), s. 171-173 ISSN 0037-6736 Institutional research plan: CEZ:AV0Z90920516 Keywords : linguistic geography * physical geograpfy * language union * interdisciplinarity Subject RIV: AI - Linguistics

  17. Risk-based configuration control: Application of PRA in improving technical specifications and operational safety

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Vesely, W.E.

    1991-01-01

    The objective of risk-based configuration control is to detect and control plant configurations form a risk perspective. The configurations of particular interest involve components which are down during power operation. Controlling plant configurations from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser control in areas unimportant to risk

  18. RABIES, PENYEBAB DAN MANAJEMEN PRA-PAJANAN SERTA PASCA-PAJANAN

    Directory of Open Access Journals (Sweden)

    Hemavalli Ragunathan

    2016-03-01

    Full Text Available RABIES, ETIOLOGY,PRE-EXPOSURE AND POST-EXPOSURE MANAGEMENT ABSTRACT Rabies is an acute viral disease that causes fatal encephalomyelitis in virtually all the warm-blooded animals including man. The virus is found in wild and some domestic animals, and is transmitted to other animals and to humans through their saliva (i.e. following bites, scratches, licks on broken skin and mucous membrane. Guidelines throughout worldwide quote that dogs are responsible for about 97% of human rabies, followed by cats (2%, jackals, mongoose and others (1%. The disease is mainly transmitted by the bite of a rabid dog. Keyword: Rabies, Epidemiology, Causes, Management

  19. PRA (probabilistic risk analysis) in the nuclear sector. Quantifying human error and human malice

    International Nuclear Information System (INIS)

    Heyes, A.G.

    1995-01-01

    Regardless of the regulatory style chosen ('command and control' or 'functional') a vital prerequisite for coherent safety regulations in the nuclear power industry is the ability to assess accident risk. In this paper we present a critical analysis of current techniques of probabilistic risk analysis applied in the industry, with particular regard to the problems of quantifying risks arising from, or exacerbated by, human risk and/or human error. (Author)

  20. René Wellek a Pražská škola

    Czech Academy of Sciences Publication Activity Database

    Sládek, Ondřej

    2016-01-01

    Roč. 1, č. 1 (2016), s. 19-30 ISSN 2453-8507 Institutional support: RVO:68378068 Keywords : literary theory ; structuralism ; poetics ; Wellek, René ; Prague School * structuralism * poetics * Wellek, René * Prague School * Prague linguistic circle * Mukařovský, Jan Subject RIV: AJ - Letters, Mass-media, Audiovision

  1. Archeologie na pražském pracovišti NPÚ

    Czech Academy of Sciences Publication Activity Database

    Sommer, Petr

    2015-01-01

    Roč. 31, č. 2 (2015), s. 115-117 ISSN 0231-6056 Institutional support: RVO:67985912 Keywords : cultural heritage * National Institute * archaeological monuments Subject RIV: AC - Archeology, Anthropology, Ethnology

  2. Pengaruh Penerapan Experiential Marketing terhadap Loyalitas Konsumen Kartu PRA Bayar Simpati Telkomsel

    OpenAIRE

    SE, MM, Mareta Kemala Sari

    2012-01-01

    This research aims to analyze influences of experiential marketing variable as dependent variable and provides consumer experiences in getting benefit from communication services to simPATI consumer loyalty. This research is descriptive research with non probability sampling technique – convenience sampling method. Sample size is Hair income that is 20 times of variable, number of respondent is 100 people. The data is analyzed by using multiple regressions with SPSS program, test, F test, alp...

  3. Imigrantes bolivianos em São Paulo : a Praça Kantuta e o futebol

    OpenAIRE

    Ubiratan Silva Alves

    2011-01-01

    Resumo: A migração para o Brasil tem um marco nos anos 50 quando os bolivianos vieram para estudar através de um intercâmbio Brasil-Bolívia ou ainda por fuga política. Mas a relevância dos movimentos migratórios da América Latina se destaca a partir da década de 70 devido ao processo de industrialização de países como o Brasil, a Argentina e a Venezuela além da fuga de suas respectivas pátrias por divergências políticas. A partir da década de 1980, houve um grande aumento de bolivianos que vi...

  4. KONTINUITAS DAN DISKONTINUITAS AL-QUR'AN TERHADAP TRADISI ARAB PRA-ISLAM

    Directory of Open Access Journals (Sweden)

    Kurdi Kurdi

    2015-05-01

    Full Text Available This article discusses on continuity and discontinuity of the Qur'an to Arabs traditions before revelation provided from either doctrine of prior religions or native agreements of society. The Qur'an has given response on many aspects of rituals, economy, family, law and punishments. Many of such traditions become as Islamic doctrine and others are rejected. The steps of the continuity are total acceptance, distinctive way, conditional limitation and corrective response, while the styles of the discontinuity are total, gradual and continuous liberations.

  5. Assessing Sediment and Nutrient Transport in the Pra Basin of Ghana

    African Journals Online (AJOL)

    Regression analysis was used to establish relationships between suspended sediment yield and nutrient export coefficient as the dependent variable, and runoff and catchment area as the independent variables. The established regression equation can be used to estimate suspended sediment or nutrient yield at any ...

  6. Novinky pražského mozartovského výzkumu

    Czech Academy of Sciences Publication Activity Database

    Jonášová, Milada

    2016-01-01

    Roč. 24, č. 4 (2016), s. 20-22 ISSN 1210-9525 R&D Projects: GA ČR GAP409/12/2563 Institutional support: RVO:68378076 Keywords : copyists research * autograph * operas Subject RIV: AL - Art, Architecture, Cultural Heritage

  7. PENGARUH PENERAPAN EXPERIENTIAL MARKETING TERHADAP LOYALITAS KONSUMEN KARTU PRA BAYAR SIMPATI TELKOMSEL

    Directory of Open Access Journals (Sweden)

    mareta kemala sari

    2012-10-01

    Full Text Available This research aims to analyze influences of experiential marketing variable as dependent variable and provides consumer experiences in getting benefit from communication services to simPATI consumer loyalty. This research is descriptive research with non probability sampling technique – convenience sampling method. Sample size is Hair income that is 20 times of variable, number of respondent is 100 people. The data is analyzed by using multiple regressions with SPSS program, test, F test, alpha 0.05. The research shows, (1. No significant influences between sense marketing and customer loyalty (sig=0.166. (2. There is significant influences between feel marketing and customer loyalty (Sig = 0.029. (3. No significant influences between feel marketing and customer loyalty (Sig = 0,689. (4. There is a significant influence between act marketing and customer loyalty. (5. No significant influences between relate marketing and customer loyalty (Sig = 0,572. (6. There is a significant influence between all variables experiential marketing and customer loyalty (Sig = 0,000. Researcher suggests company to review sense marketing, act marketing and relate marketing strategy that has applied and consider other factors that influences consumer loyalty and also increase feel marketing and think marketing strategies.

  8. Olha pra mim: encontro de gerações intermediado pela escrita de cartas

    OpenAIRE

    Santos, Divina de Fátima dos

    2015-01-01

    Esta tese analisou os benefícios da troca de cartas entre gerações muito distintas, investigando o quanto o ato de escrever sobre acontecimentos da vida cotidiana pode estar associado a uma melhor autopercepção dos participantes do processo. Procurou-se compreender o significado de uma troca de correspondências ocorrida entre crianças e idosos, residentes na cidade de Caraguatatuba, no litoral norte de São Paulo, e os seus efeitos sobre suas subjetividades. O trabalho analisou a participação ...

  9. Em busca do tempo nas ruas e praças de São Paulo

    OpenAIRE

    Frehse, Fraya

    2016-01-01

    Como será que o cotidiano de nós, pesquisadores urbanos, nas cidades em que vivemos, repercute em nossa trajetória investigativa sobre tais cidades? Argumento neste estudo que há inquietações intelectuais derivadas de nossa condição urbana, por assim dizer. Basta assumir o urbano em termos lefebvrianos; isto é, como referência metodológica para refletir sobre as contradições históricas que impregnam a vida cotidiana na cidade como espaço que simultaneamente favorece e dificulta, de modo privi...

  10. Upaya Peningkatan Tingkat Pengetahuan Siswi MAN 2 Palembang Mengenai Sindrom Pra Menstruasi

    Directory of Open Access Journals (Sweden)

    Muhammad Aditya Alfarizki

    2017-03-01

    Full Text Available Premenstrual syndrome characterized by affective, physical, and behavior symptoms with moderate to severe grade, that usually recurrent every luteal phase of menstrual cycle and disappear within menstruation. The frequency of premenstrual syndrome is still high, in Indonesia and all over the world. To overcome this situation, there should be a health promotion. The aim of this community service was to increase the girl’s knowledge of premenstrual syndrome. This community service was held in one day on November 2016 in public islamic high school MAN 2 Palembang. The schedule was start with pre test consist of 15 questions, counseling sesssion using power point media, discussion session, and post test consist of the same questions to measure the knowledge after counseling. Pre test score showed that 13.9% students had good knowledge and post test score showed an increase of good knowledge (66.7%. Conclusion, heatlh education through counseling method bring a change of knowledge.

  11. Popularita e-sportu u pražské mládeže

    OpenAIRE

    Inneman, Martin

    2017-01-01

    Title: Popularity of e-sports among Prague's youth Objectives: The main objective of this thesis is to determine popularity of e-sports among Prague's youth and the associated marketing potential of this industry. The thesis also tests the depth of knowledge, so that it is possible to create an overall opinion on the current state of e-sports among Prague's youth. Methods: The method used in this thesis is marketing research. Due to the lack of secondary data it was necessary to obtain primar...

  12. Overview of results and perspectives from the Shoreham major common-cause initiating events study

    International Nuclear Information System (INIS)

    Joksimovich, V.; Orvis, D.D.; Paccione, R.J.

    1986-01-01

    This study represents the continuation of a large effort by LILCO to fully understand the potential hazards posed by future operation of the Shoreham Nuclear Power Stations (SNPS). The Shoreham Probabilistic Risk Assessment, a level 3 PRA without external events, provided a characterization of the accident sequences that could leave the core in a condition in which it would be vulnerable to severe damage if further mitigating actions were not taken. It estimated the frequency and magnitude of the potential radioactivity releases associated with such sequences. The study was limited to accident sequences initiated by so called internal events to the plant including a loss of offsite power. It also characterized the public risk associated with those accident sequences. The ''Major Common-Cause Initiating Events Study'' (MCCI) for the Shoreham plant was performed to obtain insights into the plant's susceptibility to, and inherent defenses against, certain MCCIs. Major common-cause initiating events are occurrences which have the potential to initiate a plant transient or LOCA and, also, damage one or more plant systems needed to mitigate the effects of a transient or LOCA. The scope of the MCCI study included detailed analyses of seismic events and fires through the severe core damage and bounding analyses of aircraft crashes, windstorms, turbine missiles and release of hazardous materials near the plant

  13. 77 FR 16869 - Proposed Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF...

    Science.gov (United States)

    2012-03-22

    ... system. This TS improvement is part of the consolidated line item improvement process (CLIIP). Additional... NRC-2012-0071. NRC's Agencywide Documents Access and Management System (ADAMS): You may access... continuous hours every 31 days, would be changed to require at least 15 continuous minutes of heater...

  14. 75 FR 75705 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2010-12-06

    ..., Rockville, Maryland. NRC's Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received at the NRC are available electronically at the NRC's Electronic Reading Room... and Management System (ADAMS) under Accession Number ML093570241. The proposed changes revise the...

  15. Plant specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events

    International Nuclear Information System (INIS)

    2011-01-01

    The German Parliament requested (17 March 2011) a comprehensive inspection of German nuclear power plants. For this purpose independent expert commissions should perform a new risk analysis of all German NPPS and nuclear installations with respect to the lessons learned from the Fukushima (Japan) events and other extraordinary damage scenarios. The Reactor safety commission (RSK) was assigned by the German Bundesamt fuer Strahlenschutz to develop a catalogue of requirements for this safety inspection. The contribution summarizes the required inspection volume (status 30.03.2011) including the following events: natural events like earth quakes, floods, weather-based consequences and possible superposition. Additionally the following assumptions have to be considered: event independent postulated common failures or systematic faults, station blackout larger than 2 hours, long-term failure of the auxiliary cooling water supply; aggravating boundary conditions for the performance of emergency measures (non-availability of power supply), hydrogen generation and detonation hazard, restricted personnel availability, non-accessibility due to high radiation levels, impeded technical support from outside. (orig.)

  16. Plant-specific Histone Deacetylases HDT½ Regulate GIBBERELLIN 2-OXIDASE 2 Expression to Control Arabidopsis Root Meristem Cell Number

    KAUST Repository

    Li, Huchen; Torres-Garcia, Jesus; latrasse, David; Benhamed, Moussa; Schilderink, Stefan; Zhou, Wenkun; Kulikova, Olga; Hirt, Heribert; Bisseling, Ton

    2017-01-01

    Root growth is modulated by environmental factors and depends on cell production in the root meristem (RM). New cells in the meristem are generated by stem cells and transit-amplifying cells, which together determine RM cell number. Transcription

  17. Seedling lethality in Nicotiana plumbaginifolia conferred by Ds transposable element insertion into a plant-specific gene.

    Science.gov (United States)

    Majira, Amel; Domin, Monique; Grandjean, Olivier; Gofron, Krystyna; Houba-Hérin, Nicole

    2002-10-01

    A seedling lethal mutant of Nicotiana plumbaginifolia (sdl-1) was isolated by transposon tagging using a maize Dissociation (Ds) element. The insertion mutation was produced by direct co-transformation of protoplasts with two plasmids: one containing Ds and a second with an Ac transposase gene. sdl-1 seedlings exhibit several phenotypes: swollen organs, short hypocotyls in light and dark conditions, and enlarged and multinucleated cells, that altogether suggest cell growth defects. Mutant cells are able to proliferate under in vitro culture conditions. Genomic DNA sequences bordering the transposon were used to recover cDNA from the normal allele. Complementation of the mutant phenotype with the cDNA confirmed that the transposon had caused the mutation. The Ds element was inserted into the first exon of the open reading frame and the homozygous mutant lacked detectable transcript. Phenocopies of the mutant were obtained by an antisense approach. SDL-1 encodes a novel protein found in several plant genomes but apparently missingfrom animal and fungal genomes; the protein is highly conserved and has a potential plastid targeting motif.

  18. 78 FR 13100 - Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-535...

    Science.gov (United States)

    2013-02-26

    ... Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0280. Address..., select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems with... calculation of SDM at the reactor moderator temperature corresponding to the most reactive state throughout...

  19. 76 FR 189 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2011-01-03

    ... [pressurized water reactor] Operability Requirements and Actions for RCS [reactor coolant system] Leakage... Specifications (STS) to define a new time limit for restoring inoperable RCS leakage detection instrumentation to... operability of the RCS leakage detection instrumentation. The CLIIP model SE will facilitate expedited...

  20. 75 FR 79048 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2010-12-17

    ... [boiling water reactor] Operability Requirements and Actions for RCS [reactor coolant system] Leakage... Specifications (STS) to define a new time limit for restoring inoperable RCS leakage detection instrumentation to... operability of the RCS leakage detection instrumentation. The CLIIP model SE will facilitate expedited...

  1. 76 FR 19510 - Notice of Availability (NOA) of the Models For Plant-Specific Adoption of Technical...

    Science.gov (United States)

    2011-04-07

    ... the addition of a Note to prohibit the use of the provisions of Limiting Condition for Operation 3.0.4... in the Federal Register on May 4, 2005 (70 FR 23238). Federal Rulemaking Web site: Supporting...

  2. 76 FR 66763 - Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-510...

    Science.gov (United States)

    2011-10-27

    ....'' TSTF-510, Revision 2, is available in the Agencywide Documents Access and Management System (ADAMS... SG Tube Integrity specification (Limiting Condition for Operation (LCO) 3.4.17, LCO 3.4.20, and LCO 3... address implementation issues associated with the inspection periods, and address other administrative...

  3. Root isolations of Metarhizium spp. from crops reflect diversity in the soil and indicate no plant specificity

    DEFF Research Database (Denmark)

    Steinwender, Bernhardt M.; Enkerli, Jürg; Widmer, Franco

    2015-01-01

    elongation factor 1-alpha and characterized by simple sequence repeat (SSR) analysis of 14 different loci. Metarhizium brunneum was the most common species isolated from plant roots (84.1% of all isolates), while M. robertsii (11.1%) and M. majus (4.8%) comprised the remainder. The SSR analysis revealed...

  4. Uncertainty estimation in nuclear power plant probabilistic safety assessment

    International Nuclear Information System (INIS)

    Guarro, S.B.; Cummings, G.E.

    1989-01-01

    Probabilistic Risk Assessment (PRA) was introduced in the nuclear industry and the nuclear regulatory process in 1975 with the publication of the Reactor Safety Study by the U.S. Nuclear Regulatory Commission. Almost fifteen years later, the state-of-the-art in this field has been expanded and sharpened in many areas, and about thirty-five plant-specific PRAs (Probabilistic Risk Assessments) have been performed by the nuclear utility companies or by the U.S. Nuclear Regulatory commission. Among the areas where the most evident progress has been made in PRA and PSA (Probabilistic Safety Assessment, as these studies are more commonly referred to in the international community outside the U.S.) is the development of a consistent framework for the identification of sources of uncertainty and the estimation of their magnitude as it impacts various risk measures. Techniques to propagate uncertainty in reliability data through the risk models and display its effect on the top level risk estimates were developed in the early PRAs. The Seismic Safety Margin Research Program (SSMRP) study was the first major risk study to develop an approach to deal explicitly with uncertainty in risk estimates introduced not only by uncertainty in component reliability data, but by the incomplete state of knowledge of the assessor(s) with regard to basic phenomena that may trigger and drive a severe accident. More recently NUREG-1150, another major study of reactor risk sponsored by the NRC, has expanded risk uncertainty estimation and analysis into the realm of model uncertainty related to the relatively poorly known post-core-melt phenomena which determine the behavior of the molten core and of the rector containment structures

  5. Participatory Rural Appraisal as an Approach to Environmental Education in Urban Community Gardens.

    Science.gov (United States)

    Doyle, Rebekah; Krasny, Marianne

    2003-01-01

    Describes the Cornell University Garden Mosaics program in which youth learn about ethnic gardening practices in urban community gardens using research methods adapted from the Participatory Rural Appraisal (PRA). Conducts a study to determine whether youth could effectively facilitate PRA activities with gardeners and to document any social and…

  6. Probabilistic Reversible Automata and Quantum Automata

    OpenAIRE

    Golovkins, Marats; Kravtsev, Maksim

    2002-01-01

    To study relationship between quantum finite automata and probabilistic finite automata, we introduce a notion of probabilistic reversible automata (PRA, or doubly stochastic automata). We find that there is a strong relationship between different possible models of PRA and corresponding models of quantum finite automata. We also propose a classification of reversible finite 1-way automata.

  7. A comparative study on the reliability criteria determination

    International Nuclear Information System (INIS)

    Jerng, Dong Wook; Ju, Tae Young

    2009-01-01

    There are two methods to determine the reliability criteria for maintenance effectiveness monitoring; using the failure probability, and the importance from PRA. Comparisons of the results from these two methods provides an insight on the relevancy of setting the reliability criteria to improve the maintenance effectiveness. (author)

  8. Sensitivity study of state-of-the-art common cause failure analysis

    International Nuclear Information System (INIS)

    Guey, Ching

    2004-01-01

    Common cause failures (CCFs) have been touted as one of the major contributors of plant risk due to its pervasive nature and somewhat conservative approaches taken in most Probabilistic Risk Assessment (PRA) studies. The objectives of this study are twofold: First, to gain a better understanding on the impact of various CCF failure probability on the overall plant risk. Secondly, to appreciate the state-of-the-art CCF modelling and data limitations for applications to a full-scale plant risk assessment. The sensitivity study of varying the CCF parameters for different cases indicates that CCF data differences based on the various cases commonly adopted in the PRAs yield core damage frequency variations between 8.5% to -25.6% of the baseline case. It appears that only if CCFs are guaranteed to occur, the core damage frequency would change significantly, by approximately a factor of 5. This suggests that prevention of CCFs is more important than dwelling on the analytical differences in the finer interpretation of the operating experience to develop the CCF parameters. (author)

  9. Indigenous environmental indicators for malaria: A district study in Zimbabwe.

    Science.gov (United States)

    Macherera, Margaret; Chimbari, Moses J; Mukaratirwa, Samson

    2017-11-01

    This paper discusses indigenous environmental indicators for the occurrence of malaria in ward 11, 15 and 18 of Gwanda district, Zimbabwe. The study was inspired by the successes of use of indigenous knowledge systems in community based early warning systems for natural disasters. To our knowledge, no study has examined the relationship between malaria epidemics and climatic factors in Gwanda district. The aim of the study was to determine the environmental indicators for the occurrence of malaria. Twenty eight key informants from the 3 wards were studied. Questionnaires, focus group discussions and PRA sessions were used to collect data. Content analysis was used to analyse the data. The local name for malaria was 'uqhuqho' literally meaning a fever. The disease is also called, "umkhuhlane wemiyane" and is derived from the association between malaria and mosquitoes. The findings of our study reveal that trends in malaria incidence are perceived to positively correlate with variations in both temperature and rainfall, although factors other than climate seem to play an important role too. Plant phenology and insects are the commonly used indicators in malaria prediction in the study villages. Other indicators for malaria prediction included the perceived noise emanating from mountains, referred to as "roaring of mountains" and certain behaviours exhibited by ostriches. The results of the present study highlight the importance of using climatic information in the analysis of malaria surveillance data, and this knowledge can be integrated into the conventional health system to develop a community based malaria forecasting system. Copyright © 2016 The Authors. Published by Elsevier B.V. All rights reserved.

  10. Comparative study of approaches to estimate pipe break frequencies

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K.; Pulkkinen, U.; Talja, H.; Saarenheimo, A.; Karjalainen-Roikonen, P. [VTT Industrial Systems (Finland)

    2002-12-01

    The report describes the comparative study of two approaches to estimate pipe leak and rupture frequencies for piping. One method is based on a probabilistic fracture mechanistic (PFM) model while the other one is based on statistical estimation of rupture frequencies from a large database. In order to be able to compare the approaches and their results, the rupture frequencies of some selected welds have been estimated using both of these methods. This paper highlights the differences both in methods, input data, need and use of plant specific information and need of expert judgement. The study focuses on one specific degradation mechanism, namely the intergranular stress corrosion cracking (IGSCC). This is the major degradation mechanism in old stainless steel piping in BWR environment, and its growth is influenced by material properties, stresses and water chemistry. (au)

  11. Shutdown decay heat removal analysis of a Babcock and Wilcox pressurized water reactor: Case study

    International Nuclear Information System (INIS)

    Cramond, W.R.; Ericson, D.M. Jr.; Sanders, G.A.

    1987-03-01

    This is one of six case studies for USI A-45 Decay Heat Removal (DHR) Requirements. The purpose of this study is to identify any potential vulnerabilities in the DHR systems of a typical Babcock and Wilcox PWR, to suggest possible modifications to improve the DHR capability, and to assess the value and impact of the most promising alternatives to the existing DHR systems. The systems analysis considered small LOCAs and transient internal initiating events, and seismic, fire, extreme wind, internal and external flood, and lightning external events. A full-scale systems analysis was performed with detailed fault trees and event trees including support system dependencies. The system analysis results were extrapolated into release categories using applicable past PRA phenomenological results and improved containment failure mode probabilities. Public consequences were estimated using site specific CRAC2 calculations. The Value-Impact (VI) analysis of possible alternatives considered both onsite and offsite impacts arriving at several risk measures such as averted population dose out to a 50-mile radius and dollars per person rem averted. Uncertainties in the VI analysis are discussed and the issues of feed and bleed and secondary blowdown are analyzed

  12. Sensitivity studies on the approaches for addressing multiple initiating events in fire events PSA

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dae Il; Lim, Ho Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    A single fire event within a fire compartment or a fire scenario can cause multiple initiating events (IEs). As an example, a fire in a turbine building fire area can cause a loss of the main feed-water (LOMF) and loss of off-site power (LOOP) IEs. Previous domestic fire events PSA had considered only the most severe initiating event among multiple initiating events. NUREG/CR-6850 and ANS/ASME PRA Standard require that multiple IEs are to be addressed in fire events PSA. In this paper, sensitivity studies on the approaches for addressing multiple IEs in fire events PSA for Hanul Unit 3 were performed and their results were presented. In this paper, sensitivity studies on the approaches for addressing multiple IEs in fire events PSA are performed and their results were presented. From the sensitivity analysis results, we can find that the incorporations of multiple IEs into fire events PSA model result in the core damage frequency (CDF) increase and may lead to the generation of the duplicate cutsets. Multiple IEs also can occur at internal flooding event or other external events such as seismic event. They should be considered in the constructions of PSA models in order to realistically estimate risk due to flooding or seismic events.

  13. The effect of postural changes on plasma renin activity during normal and pathologic pregnancies.

    Science.gov (United States)

    Brandes, J M; Abramovici, H; Katz, M; Diengott, D; Spindel, A; Kahana, L

    1978-11-01

    A study of the effect of posture on plasma renin activity (PRA) in the third trimester in 27 gravidas revealed a significantly greater increase in PRA in the supine position, compared to the left lateral. The women were classified into 3 groups: normal pregnancy, preeclampsia, intrauterine fetal death. There was no statistical difference in PRA among the 3 groups. It is assumed that the increase of PRA in the supine position was due mainly to mechanical pressure by the gravid uterus on the great vessels (regardless of whether the fetus was dead or alive) and that effective circulatory volume was thus reduced. However, low PRA in the left lateral position in women with preeclampsia seemed to correlate with more severe disease in these women.

  14. Use of a probabilistic safety study in the design of the Italian reference PWR

    International Nuclear Information System (INIS)

    Richardson, D.C.; Russino, G.; Valentini, V.

    1985-01-01

    The intent of this paper is to provide a description of the experience gained in having performed a Probabilistic Safety Study (PSS) on the proposed Italian reference pressurized water reactor. The experience revealed that through careful application of probabilistic techniques, Probabilistic Risk Assessment (PRA) can be used as a tool to develop an optimum plant design in terms of safety and cost. Furthermore, the PSS can also be maintained as a living document and a tool to assess additional regulatory requirements that may be imposed during the construction and operational life of the plant. Through the use of flexible probabilistic techniques, the probabilistic safety model can provide a living safety assessment starting from the conceptual design and continuing through the construction, testing and operational phases. Moreover, the probabilistic safety model can be used during the operational phase of the plant as a method to evaluate the operational experience and identify potential problems before they occur. The experience, overall, provided additional insights into the various aspects of the plants design and operation that would not have been identified through the use of traditional safety evaluation techniques

  15. Survey of Swiss nuclear's cost study 2016; Pruefung der Kostenstudie 2016 von swissnuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alt, Stefan; Ustohalova, Veronika [Oeko-Institut e.V. - Institut fuer Angewandte Oekologie, Freiburg im Breisgau (Germany)

    2017-04-26

    The report discusses the Swiss nuclear cost study 2016 concerning the following issues: evaluation of the aspects of the cost study: cost structure, cost classification and risk provision, additional payment liability, option of lifetime extension for Swiss nuclear power plants; specific indications on the report ''cost study 2016 (KS16) - estimation of the decommissioning cost of Swiss nuclear power plants'': decommissioning costs in Germany, France and the USA, indexing the Swiss cost estimation for decommissioning cost, impact factors on the decommissioning costs; specific indications on the report ''cost study 2016 (KS16) - estimation of the disposal cost - interim storage, transport, containers and reprocessing''; specific indications on the report ''cost studies (KS16) - estimation of disposal costs - geological deep disposal'': time scale and costs incurred, political/social risks, retrievability, comparison with other mining costs.

  16. Study of a Station Blackout Event in the PWR Plant

    International Nuclear Information System (INIS)

    Ching-Hui Wu; Tsu-Jen Lin; Tsu-Mu Kao

    2002-01-01

    On March 18, 2001, a PWR nuclear power plant located in the Southern Taiwan occurred a Station Blackout (SBO) event. Monsoon seawater mist caused the instability of offsite power grids. High salt-contained mist caused offsite power supply to the nuclear power plant very unstable, and forced the plant to be shutdown. Around 24 hours later, when both units in the plant were shutdown, several inadequate high cycles of bus transfer between 345 kV and 161 kV startup transformers degraded the emergency 4.16 kV switchgears. Then, in the Train-A switchgear room of Unit 1 occurred a fire explosion, when the degraded switchgear was hot shorted at the in-coming 345 kV breaker. Inadequate configuration arrangement of the offsite power supply to the emergency 4.16 kV switchgears led to loss of offsite power (LOOP) events to both units in the plant. Both emergency diesel generators (EDG) of Unit 1 could not be in service in time, but those of Unit 2 were running well. The SBO event of Unit 1 lasted for about two hours till the fifth EDG (DG-5) was lined-up to the Train-B switchgear. This study investigated the scenario of the SBO event and evaluated a risk profile for the SBO period. Guidelines in the SBO event, suggested by probabilistic risk assessment (PRA) procedures were also reviewed. Many related topics such as the re-configuration of offsite power supply, the addition of isolation breakers of the emergency 4.16 kV switchgears, the betterment of DG-5 lineup design, and enhancement of the reliability of offsite power supply to the PWR plant, etc., will be in further studies. (authors)

  17. Risk evaluations of aging: Procedures guide for an age-dependent PSA with emphasis on prioritization and sensitivity studies

    International Nuclear Information System (INIS)

    Vesely, W.E.

    1991-01-01

    Based on the previous work which has been performed in the project, a procedures guide is being developed for carrying out an age-dependent probabilistic safety assessment (PSA) for evaluating the core damage frequency with aging effects explicitly treated. A PSA is basically a Level 1 Probabilistic Risk Assessment (PRA). The emphasis of the guide is on prioritization and sensitivity studies. Focus is also on active components although consideration of aging effects in passive components is also treated. The guide is intended to become a NUREG/CR and is the first of three volumes which are being developed. The following topics with demonstrations and applications are described in the presentation: (1) the age-dependent PSA versus the standard PSA; (2) component reliability models used in an age-dependent PSA; (3) approaches for transforming a PSA into an age-dependent PSA; (4) application of an age-dependent PSA; (5) using a PSA to evaluate the risk effects from aging passive components; (6) evaluation of the risk importance of passive components; (7) prioritizations of aging contributors; (8) evaluations of test and maintenance effectiveness; and (9) sensitivity studies and uncertainty analyses of aging effects

  18. SEPRA - shutdown PSA for the OLKILUOTO nuclear power plant

    International Nuclear Information System (INIS)

    Himanen, R.

    1995-01-01

    The utility TVO has extended the PSA study to the analysis of refueling, shutdown and startup. The Shutdown Event PRA (SEPRA) was reported to the authority in September 1992. The study consists of the analysis of leaks and loss of decay heat removal in the planned shutdown conditions. Special studies were performed for the cold pressurization, for local criticality events, for heavy load transport and for the transients during startup and shutdown. A remarkable effort was put to identify risks, i.e. to the qualitative analysis. The regular preventive maintenance tasks in the refueling outages were analyzed and the important tasks were selected for further studies. Besides the severe core damage risk the utility was interested in less grave consequences, e.g. the economic risks, causing significant extension of outages. The plant specific screening of initiators consisted of a study on the incident history and of interviewing the plant personnel on selected tasks. A number of thermohydraulic calculations were carried out to support the analysis of accident sequences. The operator actions after an initiating event were verified with the operating staff. The annual core damage risk from the refueling outage is about one forth of the total annual risk. The modifications decreased significantly the core damage frequency. It is foreseen that the SEPRA will form a basis of the procedure enhancement for the low power states. (author) 5 figs., 1 tab., 10 refs

  19. Insights of PSA studies made for operating nuclear power stations in Finland

    International Nuclear Information System (INIS)

    Laaksonen, J.; Virolainen, R.

    1991-01-01

    In 1984 the Finnish regulatory authority (STUK) required the utilities to make plant specific probabilistic safety assessment (PSA) studies for each plant. It was also strongly recommended that most of the work be made by plant personnel. This advice was well observed by both utilities. Results of level 1 PSA studies were submitted for regulatory review in June 1989. Only internal initiating events, including loss-of-offsite power and human errors, were considered at this stage. Each study took an effort of 12 to 20 man years. A thorough regulatory review, about two man years per plant, is currently underway, and will cause some changes in the initial results of the studies. The utilities are continuing their PSA work with the fire and flood analysis, and then with the analysis of risks during start-up and shutdown conditions. As soon as a level 1 PSA study has been reviewed, and a common understanding of the models and data has been reached between the utility and the STUK, this basic PSA version will be the first element of a living PSA. The second element is a user friendly PSA code that can rapidly run through the quantitative part of the study and thus easily indicate the influence of any deviation from the basic version. The third element is plant specific data collection and processing system. The living PSA for the first plant is expected to be fully operational sometime next year. The first use of the living PSA will be the safety assessment of proposed plant modifications and a systematic re-evaluation of technical specifications

  20. Proposal of methodology of tsunami accident sequence analysis induced by earthquake using DQFM methodology

    International Nuclear Information System (INIS)

    Muta, Hitoshi; Muramatsu, Ken

    2017-01-01

    Since the Fukushima-Daiichi nuclear power station accident, the Japanese regulatory body has improved and upgraded the regulation of nuclear power plants, and continuous effort is required to enhance risk management in the mid- to long term. Earthquakes and tsunamis are considered as the most important risks, and the establishment of probabilistic risk assessment (PRA) methodologies for these events is a major issue of current PRA. The Nuclear Regulation Authority (NRA) addressed the PRA methodology for tsunamis induced by earthquakes, which is one of the methodologies that should be enhanced step by step for the improvement and maturity of PRA techniques. The AESJ standard for the procedure of seismic PRA for nuclear power plants in 2015 provides the basic concept of the methodology; however, details of the application to the actual plant PRA model have not been sufficiently provided. This study proposes a detailed PRA methodology for tsunamis induced by earthquakes using the DQFM methodology, which contributes to improving the safety of nuclear power plants. Furthermore, this study also states the issues which need more research. (author)

  1. Pressurized thermal shock re-evaluation studies for Korean PWR plant

    International Nuclear Information System (INIS)

    Jung, Sung Gyu; Kim, Hyun Su; Jin, Tae Eun; Jang, Chang Hee

    2001-01-01

    The PTS reference temperature of reactor pressure vessel for one of the Korean NPPs has been predicted to exceed the screening criteria before it reaches it's design life. To cope with this issue, a plant-specific PTS analysis had been performed in accordance with the Regulatory Guide 1.154 in 1999. As a result of that analysis, it was found that current methodology of RG. 1.154 was very conservative. The objective of this study is to examine the effects of changing various input parameters and to determine the amount of conservatism of the current PTS analysis method. To do this, based on the past PTS analysis experience, parametric study were performed for various models using modified VISA-II code. This paper discusses the analysis results and recommendations to reduce the conservatism of current analysis method

  2. Studies on renin stimulation in normal controls and in patients with essential hypertension

    International Nuclear Information System (INIS)

    Koh, C.S.; Choe, K.W.; Lee, H.K.; Lee, J.S.

    1978-01-01

    To find out a convenient and reliable method of detecting low renin status, we employed intravenous furosemine injection as a stimulatory maneuver. The results thus obtained were compared with those from the postural stimuli and basal plasma renin activity (PRA) in relation to sodium excretion. Intravenous furosemide test was performed in 66 control subjects and 44 patients with essential hypertension. The results were as follow; 1) Mean PRA in control subjects rose from 2.5+-1.95 ng/ml/hr (basal) to 4.5+-2.51, 5.2+-2.49 and 4.2+-2.44 ng/ml/hr at 1, 2 and 3hrs after IV injection. One-hour response is more convenient in clinical practice. 2) Postural stimuli by assuming an upright posture for 3hrs gave rise to considerable increase in PRA (4.0+-2.92 from 2.4+-1.85), but we found it less convenient than stimulation with furosemide. 3) The increase in PRA was much less marked in patients with essential hypertension as a whole (2.9+-2.75). Hyporesponsiveness to furosemide stimuli was found in 34.1%. Of these hyporesponders, a third had a normal basal PRA, indicating the need for this kind stimulatory procedure. 4) Younger age group showed greater renin responsiveness than older age group after furosemide stimuli. Likewise mean age of low renin patients (52.9+-5.38 years old) was significantly higher than that of high and normal renin patients (44.1+-13.78 years old). (author)

  3. Studies on Renin Stimulation in Normal Controls and in Patients with Essential Hypertension

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Chang Soon; Choe, Kang Won; Lee, Hong Kyu; Lee, Jung Sang [Seoul National University College of Medicine, Seoul (Korea, Republic of)

    1978-03-15

    To find out a convenient and reliable method of detecting low renin status, we employed intravenous furosemide injection as a stimulatory maneuver. The results thus obtained were compared with those from the postural stimuli and basal plasma renin activity (PRA) in relation to sodium excretion. Intravenous furosemide test was performed in 66 control subjects and 44 patients with essential hypertension. The results were as follow; 1) Mean PRA in control subjects rose from 2.5+-1.95 ng/ml/hr (basal) to 4.5+-2.51, 5.2+-2.49 and 4.2+-2.44 ng/ml/hr at 1, 2 and 3 hrs after IV injection. One-hour response is more convenient in clinical practice. 2) Postural stimuli by assuming an upright posture for 3 hrs gave rise to considerable increase in PRA (4.0+-2.92 from 2.4+-1.85), but we found it less convenient than stimulation with furosemide. 3) The increase in PRA was much less marked in patients with essential hypertension as a whole (2.9+-2.75). Hyporesponsiveness to furosemide stimuli was found in 34.1%. Of these hyporesponders, a third had a normal basal PRA, indicating the need for this kind stimulatory procedure. 4) Younger age group showed greater renin responsiveness than older age group after furosemide stimuli. Likewise mean age of low renin patients (52.9+-5.38 years old) was significantly higher than that of high and normal renin patients (44.1+-13.78 years old).

  4. Studies on Renin Stimulation in Normal Controls and in Patients with Essential Hypertension

    International Nuclear Information System (INIS)

    Koh, Chang Soon; Choe, Kang Won; Lee, Hong Kyu; Lee, Jung Sang

    1978-01-01

    To find out a convenient and reliable method of detecting low renin status, we employed intravenous furosemide injection as a stimulatory maneuver. The results thus obtained were compared with those from the postural stimuli and basal plasma renin activity (PRA) in relation to sodium excretion. Intravenous furosemide test was performed in 66 control subjects and 44 patients with essential hypertension. The results were as follow; 1) Mean PRA in control subjects rose from 2.5±1.95 ng/ml/hr (basal) to 4.5±2.51, 5.2±2.49 and 4.2±2.44 ng/ml/hr at 1, 2 and 3 hrs after IV injection. One-hour response is more convenient in clinical practice. 2) Postural stimuli by assuming an upright posture for 3 hrs gave rise to considerable increase in PRA (4.0±2.92 from 2.4±1.85), but we found it less convenient than stimulation with furosemide. 3) The increase in PRA was much less marked in patients with essential hypertension as a whole (2.9±2.75). Hyporesponsiveness to furosemide stimuli was found in 34.1%. Of these hyporesponders, a third had a normal basal PRA, indicating the need for this kind stimulatory procedure. 4) Younger age group showed greater renin responsiveness than older age group after furosemide stimuli. Likewise mean age of low renin patients (52.9±5.38 years old) was significantly higher than that of high and normal renin patients (44.1±13.78 years old).

  5. Effect of implementing anti-HLA antibody detection by Luminex in the kidney transplant program in Chile.

    Science.gov (United States)

    Elgueta, S; Fuentes, C; López, M; Hernández, J; Arenas, A; Jiménez, M; Gajardo, J G; Rodríguez, H; Labraña, C

    2011-11-01

    The development of new highly sensitive, specific technologies to detect HLA antibodies has allowed a better definition of the profile of non-permitted antigens for patients awaiting kidney transplantation. The use of calculated or virtual panel reactive antibodies (CPRA or vPRA) seeks to improve the prediction of positive crossmatches (XM), but increases the proportion of sensitized patients on the waiting list. In 2008-2009, we implemented detection of antibodies using Luminex technology and applied vPRA since 2009. The objective of this study was to evaluate the impact of these innovations in defecting patient sensitization on kidney transplant waiting lists for deceased donors and among transplanted patients. We analyzed the waiting list for 2007 through 2009 and the first semester of 2010, including the patients transplanted in these periods and the XM with deceased donors. We observed an increase in the mean peak PRA of transplanted patients from 7.2% in 2007 to 17.1% in 2010 (P = .001), and in the proportion of patients transplanted with a peak PRA > 50% from 2.8% in 2007 to 15.7% in 2010 (P = .0001), with no increase in the proportion of this population on the waiting lists. There was a concurrent decrease in positive XM among patients with a peak PRA > 50%. The use of vPRA and Luminex permitted a greater number of transplants of patients with peak PRA > 50% and was a good predictor of a positive XM. Published by Elsevier Inc.

  6. STUDI EKSPLORATORI HUBUNGAN ANTARA KONVERGENSI IFRS DENGAN BIAYA AUDIT

    OpenAIRE

    Cahyonowati, Nur

    2016-01-01

    Penelitian ini menguji konsekuensi ekonomi dari adopsi IFRS di Indonesia. IFRS adopsi diprediksi akan meningkatkan biaya audit. Penelitian ini menemukan bahwa biaya audit telah meningkat secara signifikan pada pra dan pasca adopsi IFRS. Selain itu, penelitian ini menyarankan bahwa kompleksitas audit lebih mungkin dianggap sebagai prediktor biaya audit dibandingkan dengan risiko litigasi. Ukuran perusahaan, proksi untuk kompleksitas audit, ditemukan menjadi prediktor yang signifikan untuk laya...

  7. Relationship between mechanical properties and crystal structure in cocrystals and salt of paracetamol.

    Science.gov (United States)

    Ahmed, Hamzah; Shimpi, Manishkumar R; Velaga, Sitaram P

    2017-01-01

    Objectives were to study mechanical properties of various solid forms of paracetamol and relate to their crystal structures. Paracetamol form I (PRA), its cocrystals with oxalic acid (PRA-OXA) and 4,4-bipyridine (PRA-BPY) and hydrochloride salt (PRA-HCL) were selected. Cocrystals and salt were scaled-up using rational crystallization methods. The resulting materials were subjected to different solid-state characterizations. The powders were sieved and 90-360 µm sieve fraction was considered. These powders were examined by scanning electron microscopy (SEM) and densities were determined. Tablets were made at applied pressures of 35-180 MPa under controlled conditions and the tablet height, diameter and hardness were measured. Tensile strength and porosity of the tablets were estimated using well known models. Crystal structures of these systems were visualized and slip planes were identified. Cocrystal and salt of PRA were physically pure. Sieved powders had comparable morphologies and particle size. The apparent and theoretical densities of powders were similar, but no clear trends were observed. The tensile strengths of these compacts were increased with increasing pressure whereas tabletability decreased in the order oxalic acid > PRA-HCL ≈ PRA-OXA > BPY > PRA-BPY. Tablet tensile strength decreases exponentially with increasing porosity with the exception of PRY-BPY and BPY. Slip plane prediction based on attachment energies may not be independently considered. However, it was possible to explain the improved mechanical properties of powders based on the crystal structure. Cocrystallization and salt formation have introduced structural features that are responsible for improved tableting properties of PRA.

  8. Loss of co-ordinate expression of progesterone receptors A and B is an early event in breast carcinogenesis.

    Science.gov (United States)

    Mote, P A; Bartow, S; Tran, N; Clarke, C L

    2002-03-01

    Progesterone receptor (PR) mediates the effects of progesterone in mammary tissues and plays a crucial role in normal breast development and in breast cancer. PR proteins are expressed as two isoforms, PRA and PRB, that have different capacities to activate target genes, yet it is unknown whether progesterone action in normal and malignant breast is mediated by PRA and/or PRB. This study determines the relative expression of PRA and PRB in normal breast and in benign, premalignant and malignant archival breast lesions by dual immunofluorescent histochemistry. In normal breast and in proliferative disease without atypia (PDWA) PRA and PRB were co-expressed within the same cells in comparable amounts, implicating both isoforms in progesterone action. In atypical lesions, however, there was a significant increase in predominant expression of PRA or PRB, with lesion progression from the normal state to malignancy. PR isoform predominance, especially PRA predominance, was evident in a high proportion of ductal carcinomas in situ (DCIS) and invasive breast lesions. In the normal breast and in PDWA, the relative expression of PRA and PRB in adjacent cells was homogenous. There was a significant increase in cell-to-cell heterogeneity of PR isoform expression in ADH and DCIS lesions and in the majority of breast cancers. Heterogeneous cell-to-cell expression of PR isoforms occurred prior to overall predominant expression of one isoform in premalignant breast lesions, demonstrating that loss of control of relative PRA:PRB expression is an early event in the development of breast cancer. PRA:PRB ratios within a breast lesion are likely to be important as both markers and effectors of tumor growth and development, and progressively aberrant PR isoform expression may play a role in the etiology of breast cancer.

  9. Patient safety improvement programmes for primary care. Review of a Delphi procedure and pilot studies by the LINNEAUS collaboration on patient safety in primary care

    Science.gov (United States)

    Verstappen, Wim; Gaal, Sander; Esmail, Aneez; Wensing, Michel

    2015-01-01

    ABSTRACT Background: To improve patient safety it is necessary to identify the causes of patient safety incidents, devise solutions and measure the (cost-) effectiveness of improvement efforts. Objective: This paper provides a broad overview with practical guidance on how to improve patient safety. Methods: We used modified online Delphi procedures to reach consensus on methods to improve patient safety and to identify important features of patient safety management in primary care. Two pilot studies were carried out to assess the value of prospective risk analysis (PRA), as a means of identifying the causes of a patient safety incident. Results: A range of different methods can be used to improve patient safety but they have to be contextually specific. Practice organization, culture, diagnostic errors and medication safety were found to be important domains for further improvement. Improvement strategies for patient safety could benefit from insights gained from research on implementation of evidence-based practice. Patient involvement and prospective risk analysis are two promising and innovative strategies for improving patient safety in primary care. Conclusion: A range of methods is available to improve patient safety, but there is no ‘magic bullet.’ Besides better use of the available methods, it is important to use new and potentially more effective strategies, such as prospective risk analysis. PMID:26339837

  10. High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

    International Nuclear Information System (INIS)

    Wong, S.; DiBiasio, A.; Gunther, W.

    1993-09-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant

  11. High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Wong, S.; DiBiasio, A.; Gunther, W. [Brookhaven National Lab., Upton, NY (United States)

    1993-09-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant.

  12. Risk-based Inspection Guide for the Susquehanna Station HPCI system

    International Nuclear Information System (INIS)

    Travis, R.; Higgins, J.; Gunther, W.; Shier, W.

    1992-11-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A system Risk-based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Susquehanna Steam Electric Station (SSES) which is operated by Pennsylvania Power ampersand Light (PP ampersand L). Included in this S-RIG is a discussion of the role of HPCI in mitigating accidents and a presentation of PRA-based failure modes which could prevent proper operation of the system. The S-RIG uses industry operating experience, including plant-specific illustrative examples, to augment the basic PRA failure modes. It is designed to be used as a reference for both routine inspections and the evaluation of the significance of component failures

  13. System safety and reliability using object-oriented programming techniques

    International Nuclear Information System (INIS)

    Patterson-Hine, F.A.; Koen, B.V.

    1987-01-01

    Direct evaluation fault tree codes have been written in recursive, list-processing computer languages such as PL/1 (PATREC-I) and LISP (PATREC-L). The pattern-matching strategy implemented in these codes has been used extensively in France to evaluate system reliability. Recent reviews of the risk management process suggest that a data base containing plant-specific information be integrated with a package of codes used for probabilistic risk assessment (PRA) to alleviate some of the difficulties that make a PRA so costly and time-intensive. A new programming paradigm, object-oriented programming, is uniquely suited for the development of such a software system. A knowledge base and fault tree evaluation algorithm, based on previous experience with PATREC-L, have been implemented using object-oriented techniques, resulting in a reliability assessment environment that is easy to develop, modify, and extend

  14. Neuropsychological Assessment of Children With Reading Disabilities From 8 to 10 Years Old: An Exploratory Portuguese Study.

    Science.gov (United States)

    da Rocha e Silva, Cláudia Susana Rosa Correia; Glória e Silva, Filipe Miguel; Martins, Maria Isabel Pavão

    2015-01-01

    Reading disabilities are one of the most significant causes of school failure and may result from different causes and cognitive processes. A comprehensive battery of neuropsychological tests was applied to a control group of 102 children (46 girls, 56 boys) with no history of learning disabilities and 32 children (13 girls, 19 boys) with poor reading achievement (PRA) to characterize their cognitive profile. A principal component analysis of the cognitive measures was undertaken to identify cognitive domains. Age-adjusted normative data were computed from controls for verbal and visuospatial abilities, psychomotor skills, executive functions, and a total score. Significant differences were found between the 2 groups. Although single tests could not identify children with PRA, measures of oral and written language, immediate and working memory, calculation, and verbal learning discriminated the 2 groups. A logistic regression model using these factors allowed us to identify 91.2% of healthy children and 96.9% of children with PRA. PRA may result from different patterns of cognitive difficulties, and it is more common in children with oral language and working-memory deficits. Wide-range cognitive testing is necessary to identify strong and weak areas to plan personalized intervention programs.

  15. Unilateral adrenal hyperplasia is a usual cause of primary hyperaldosteronism. Results from a Swedish screening study

    Directory of Open Access Journals (Sweden)

    Sigurjonsdottir Helga

    2012-09-01

    Full Text Available Abstract Background The existence of unilateral adrenal hyperplasia (AH has been considered a rare cause of primary hyperaldosteronism (PA. Methods In a prospective study we screened for PA in a non-selected (NSP and selected hypertensive population (SP, to define the cause of PA. We included 353 consecutive patients with hypertension; age 20 to 88 years, 165 women and 188 men, from a university-based Hypertension and Nephrology Outpatient clinics (123 SP and two primary care centres, (230 NSP from the same catch-up area. Serum aldosterone and plasma renin activity (PRA were measured and the ARR calculated. Verifying diagnostic procedure was performed in patients with both elevated aldosterone and ARR. Patients diagnosed with PA were invited for adrenal venous sampling (AVS and offered laparoscopic adrenalectomy when AVS found the disease to be unilateral. Results After screening, 46 patients, 13% of the whole population (22.8% SP and 7.8% NSP had aldosterone and ARR above the locally defined cut-off limits (0.43 nmol/l and 1.28 respectively. After diagnostic verification, 20 patients (6% had PA, (14.5% SP and 1.4% NSP. Imaging diagnostic procedures with CT-scans and scintigraphy were inconclusive. AVS, performed in 15 patients verified bilateral disease in 4 and unilateral in 10 patients. One AVS failed. After laparoscopic adrenalectomy, 4 patients were found to have adenoma and 5 unilateral AH. One patient denied operation. Conclusion The prevalence of PA was in agreement with previous studies. The study finds unilateral PA common and unilateral AH as half of those cases. As may be suspected PA is found in much higher frequency in specialised hypertensive units compared to primary care centers. AVS was mandatory in diagnosis of unilateral PA.

  16. Insights from an overview of four PRAs

    International Nuclear Information System (INIS)

    Fitzpatrick, R.; Arrieta, L.; Teichmann, T.; Davis, P.

    1987-01-01

    This paper summarizes the findings of an investigation of four probabilistic risk assessments (PRAs), those for Millstone 3 Seabrook, Shoreham, and Oconee 3, performed by Brookhaven National Laboratory (BNL) for the Reliability and Risk Assessment branch of the U.S. Nuclear Regulatory Commission (NRC). This group of four PRAs was subjected to an overview process with the basic goal of ascertaining what insights might be gained (beyond those already documented within the individual PRAs) by an independent evaluation of the group with respect to nuclear plant safety and vulnerability. Specifically, the objectives of the study were 1) to identify and rank initiators, systems, components, and failure modes from dominant accident sequences according to their contribution to core melt probability and public risk; and 2) to derive from this process plant-specific and generic insights. The effort was not intended to verify the specific details and results of each PRA but rather - having accepted the results - to see what they might mean in a more global context. This paper also presents some comments and insights into the amenability of certain features of these PRAs to this type of overview process

  17. Summary of PWR leak detection studies

    International Nuclear Information System (INIS)

    Cho, J.H.; Elia, F.A. Jr.

    1986-01-01

    Thermal-hydraulic analysis can be used to determine the location and magnitude of leaks inside and location of leaks outside a pressurized water reactor (PWR) containment as required by plant technical specifications. The major advantage of this detection method is that it minimizes radiation exposure of maintenance personnel because most of the leak detection process is performed from the control room outside containment. Plant-specific analyses are utilized to predict change in parameters such as local dew point temperature, relative humidity, dry bulb temperature, and flow rate to sump for various leak rates and enthalpies. These parameter responses are then programmed into the plant computer and instrumentation is provided for area monitoring. The actual inputs are continuously monitored and compared to the predicted plant responses to identify the leak location and quantify the leak. This study concludes that a system that monitors dew point (or relative humidity) and dry bulb temperature changes together with the flow rate to the sump will provide the capability to both locate and quantify a leak inside a containment, while a system that monitors dew point temperature (or relative humidity) changes will provide the capability to locate a leak outside a containment

  18. PROGRAM PPG UNTUK MEMBANGUN KOMPETENSI GURU GEOGRAFI (STUDI KASUS DI UNIVERSITAS NEGERI MALANG

    Directory of Open Access Journals (Sweden)

    Mega Prani Ningsih

    2016-10-01

    menjelaskan bentuk implementasi Program PPG SM3T dalam membangun kompetensi guru geografi alumni program SM3T. Bentuk implementasi Program PPG SM3T meliputi proses pengembangan kurikulum hingga penilaian kompetensi guru geografi. Kompetensi yang dimaksud adalah kompetensi pedagogik, kompetensi kepribadian, kompetensi sosial, dan kompetensi profesional. Penelitian ini merupakan penelitian studi kasus di Universitas Negeri Malang. Teknik pengumpulan data dilakukan melalui wawancara mendalam dan dokumentasi. Analisis data menggunakan model interaktif Miles dan Huberman. Hasil penelitian ini menunjukkan bahwa bentuk implementasi Program PPG meliputi beberapa tahapan, yaitu (1 tahap pengembangan silabus oleh pihak terkait sesuai kebijakan universitas; (2 tahap pra kondisi sebagai gabungan tahap pra kondisi dan pleno 1; (3 tahap sistem pembelajaran yang terdiri dari beberapa tahapan dan kegiatan pembelajaran, yaitu (a tahap workshop SSP terdiri atas tahapan kegiatan pleno 2, yaitu pendalaman materi kurikulum 2013, pre-test, diskusi kelompok yaitu diskusi materi geografi dan pedagogik yang belum dipahami, kerja kelompok mandiri yaitu menyusun perangkat pembelajaran, gabungan tahap pleno 3, revisi dan persetujuan RPP, yaitu peer teaching, tes formatif, KKL dan melakukan kegiatan insidental seperti menulis jurnal dan artikel ilmiah; (b tahap PPL terdiri dari tahapan prosesi penyerahan mahasiswa PPL ke sekolah, pelatihan KMD oleh pihak PPG, melakukan kegiatan mengajar dan non mengajar, penelitian PTK, dan uji kinerja berupa Lesson Study; dan (c tahap uji kompetensi terdiri dari, pendalaman materi subtansial geografi, Ujian Tulis Lokal, dan Ujian Tulis Nasional. Tahapan implementasi diarahkan dalam membangun kompetensi guru geografi, yaitu pedagogik, kepribadian, sosial, dan profesional.

  19. El Pràcticum al grau de Pedagogia de la Universitat de Barcelona: el mapa de la professió, la pràctica simulada i la immersió en una organització

    Directory of Open Access Journals (Sweden)

    Ruth Vilà Baños

    2014-01-01

    Full Text Available Es presenta el treball innovador que l’equip de coordinació del Pràcticum del grau de Pedagogia de la Universitat de Barcelona ha elaborat per organitzar les assignatures vinculades a la pràctica dels professionals de la pedagogia. Amb la finalitat de preparar els futurs professionals en els aspectes més pràctics de la seva formació, s’estructuren tres assignatures: Professionalització i Sortides Laborals, Pràctiques d’Iniciació Professional i Pràctiques Externes. En aquestes assignatures es treballa de forma innovadora el perfil del pedagog i el mapa de la professió, a primer curs del grau; la pràctica simulada a través de casos, a tercer, i la immersió en una organització, com a pràctica externa, acompanyada dels seminaris de pràctica reflexiva.

  20. The effect of low capacity injection systems on transient initiated loss of vessel water injection at Browns Ferry unit one

    International Nuclear Information System (INIS)

    Ott, L.T.

    1983-01-01

    Probabilistic risk assessment (PRA) analyses have indicated the transient initiated loss of vessel water injection (TQUV sequence) to be a dominant accident scenario for BWR plants. The PRA studies assumed the low capacity injection systems to be unimportant in severe accidents. The results of a Severe Accident Sequence Analysis (SASA) Program study have shown that these systems are capable of preventing or significantly delaying core damage in a TQUV sequence