Containment leak-tightness enhancement at VVER 440 NPPs

International Nuclear Information System (INIS)

Prandorfy, M.

2000-01-01

The hermetic compartments of WWER 440 NPPs fulfil the function of the containment used at NPPs all over the world. The purpose of the containment is to protect the NPP personnel against radioactive impact as well as to prevent radioactive leakage to the. environ ent during a lost of coolant accident. Leak-tightness enhancement in NPPs with WWER 440/213 and WWER 440/230 reactors is an important safety issue. New procedures, measures and methods were adopted at NPPs in Mochovce, Jaslovske Bohunice, Dukovany and PAKS for leak identification and sealing works performed by VUEZ Levice. (authors)

Causes of fires at NPPs and ways for their prevention

International Nuclear Information System (INIS)

Denisov, V.A.

1992-01-01

Causes of fires at different NPPs are analyzed. The schemes for classification of causes and after-effects of fires at NPPs are suggested. The structure of database on fires at NPPs suggested by IAEA is considered. The conclusion on applicability of the suggested general approaches to fire causes analysis at NPPs for preventive methods development is made

Current status of generation III nuclear power and assessment of AP1000 developed by Westinghouse

International Nuclear Information System (INIS)

Zhang Mingchang

2005-01-01

In order to make greater contributions to the environment, new nuclear power systems will be needed to meet the increase of electricity demand and to replace plants to be decommissioned. A series of new designs, so called Generation III and Generation III +, are being developed to ensure their deployment in a Near-Term Deployment Road-map in US by 2010 and in Europe by 2015. The AP1000, developed by Westinghouse, is a two-loop 1000 MWe PWR with passive safety features and extensive simplifications to enhance its competitiveness in cost and tariff. It is the first Generation III + plant receiving the Final Design Approval by the US NRC. This paper briefly describes AP1000 design features and technical specifications, and presents a more detailed design evaluation with reference to relevant literatures. Both the opportunity and challenges for nuclear power development in China during the first decade of the 21 st century in a historic transition from Gen II to Gen III are analyzed. The key is to balance risks and benefits if the first AP1000 to be settled down in China. (author)

Proceedings (slides) of the OECD/NEA Workshop on Innovations in Water-cooled Reactor Technologies

International Nuclear Information System (INIS)

Spiler, Joze; Kim, Sang-Baik; ); Feron, Fabien; Jaervinen, Marja-Leena; Husse, Julien; ); Ferraro, Giovanni; Bertels, Frank; Denk, Wolfgang; Tuomisto, Harri; Golay, Michael; Buongiorno, J.; Todreas, N.; Adams, E.; Briccetti, A.; Jurewicz, J.; Kindfuller, V.; Srinivasan, G.; Strother, M.; Minelli, P.; Fasil, E.; Zhang, J.; Genzman, G.; Epinois, Bertrand de l'; Kim, Shin Whan; Laaksonen, Jukka; Maltsev, Mikhail; Yu, CHongxing; Powell, David; Gorgemans, Julie; Hopwood, Jerry; Bylov, Igor; Bakhmetyev, Alexander M.; Lepekhin, Andrey N.; Fadeev, Yuriy P.; Bruna, Giovanni; Gulliford, Jim; ); Ham-Su, Rosaura; Thevenot, Caroline; GAUTIER, Guy-Marie; MARSAULT, Philippe; PIGNATEL, Jean-Francois; White, Andrew; )

2015-02-01

New technologies and solutions have been developed over more than thirty years to improve the safety, performance and economics of nuclear power plants. Particular efforts were made in designing systems to prevent or mitigate nuclear accidents and, greatly limit or even avoid any offsite release of radioactivity. Reactor designs developed in the 1980's and later are often referred to as Generation III (Gen III) reactors. They offer enhanced safety compared to earlier Generation II (Gen II) designs, as well as improved performance and economics. Examples of Gen III safety design features include solutions for corium localisation, advanced containment structures, improved emergency core-cooling systems, filtered venting systems, hydrogen risk management solutions, etc. Some of these solutions have also been back-fitted or partially adapted to existing reactors, based on recommendations from regulators or modernisation efforts by the utilities operating these reactors, to bring their level of safety to levels approaching those of the more modern designs. Other innovations found in the latest water-cooled reactor designs include the use of passive safety systems, and often associated with those, a simplification in the design of the reactor. Gen III reactors also feature better economics, for example increased design lifetime up to 60 years, ability to use 100% MOX fuel and operate with higher flexibility, higher thermal efficiencies and reduced staff requirements. Modularity is often quoted as a feature of some Gen III designs as a way of reducing the construction times and simplifying the decommissioning of the plant. The scope of the Workshop includes, inter alia: - Evolution of regulatory and design requirements for commercial water-cooled reactors; - Innovations in water-cooled reactor technologies that allowed significant improvement in the level of safety, with a discussion on advantages and challenges of active vs. passive safety systems; - Innovations under

Protective capping and surface passivation of III-V nanowires by atomic layer deposition

Energy Technology Data Exchange (ETDEWEB)

Dhaka, Veer, E-mail: veer.dhaka@aalto.fi; Perros, Alexander; Kakko, Joona-Pekko; Haggren, Tuomas; Lipsanen, Harri [Department of Micro- and Nanosciences, Micronova, Aalto University, P.O. Box 13500, FI-00076 (Finland); Naureen, Shagufta; Shahid, Naeem [Research School of Physics & Engineering, Department of Electronic Materials Engineering, Australian National University, Canberra ACT 2601 (Australia); Jiang, Hua; Kauppinen, Esko [Department of Applied Physics and Nanomicroscopy Center, Aalto University, P.O. Box 15100, FI-00076 (Finland); Srinivasan, Anand [School of Information and Communication Technology, KTH Royal Institute of Technology, Electrum 229, S-164 40 Kista (Sweden)

2016-01-15

Low temperature (∼200 °C) grown atomic layer deposition (ALD) films of AlN, TiN, Al{sub 2}O{sub 3}, GaN, and TiO{sub 2} were tested for protective capping and surface passivation of bottom-up grown III-V (GaAs and InP) nanowires (NWs), and top-down fabricated InP nanopillars. For as-grown GaAs NWs, only the AlN material passivated the GaAs surface as measured by photoluminescence (PL) at low temperatures (15K), and the best passivation was achieved with a few monolayer thick (2Å) film. For InP NWs, the best passivation (∼2x enhancement in room-temperature PL) was achieved with a capping of 2nm thick Al{sub 2}O{sub 3}. All other ALD capping layers resulted in a de-passivation effect and possible damage to the InP surface. Top-down fabricated InP nanopillars show similar passivation effects as InP NWs. In particular, capping with a 2 nm thick Al{sub 2}O{sub 3} layer increased the carrier decay time from 251 ps (as-etched nanopillars) to about 525 ps. Tests after six months ageing reveal that the capped nanostructures retain their optical properties. Overall, capping of GaAs and InP NWs with high-k dielectrics AlN and Al{sub 2}O{sub 3} provides moderate surface passivation as well as long term protection from oxidation and environmental attack.

Protective capping and surface passivation of III-V nanowires by atomic layer deposition

Directory of Open Access Journals (Sweden)

Veer Dhaka

2016-01-01

Full Text Available Low temperature (∼200 °C grown atomic layer deposition (ALD films of AlN, TiN, Al2O3, GaN, and TiO2 were tested for protective capping and surface passivation of bottom-up grown III-V (GaAs and InP nanowires (NWs, and top-down fabricated InP nanopillars. For as-grown GaAs NWs, only the AlN material passivated the GaAs surface as measured by photoluminescence (PL at low temperatures (15K, and the best passivation was achieved with a few monolayer thick (2Å film. For InP NWs, the best passivation (∼2x enhancement in room-temperature PL was achieved with a capping of 2nm thick Al2O3. All other ALD capping layers resulted in a de-passivation effect and possible damage to the InP surface. Top-down fabricated InP nanopillars show similar passivation effects as InP NWs. In particular, capping with a 2 nm thick Al2O3 layer increased the carrier decay time from 251 ps (as-etched nanopillars to about 525 ps. Tests after six months ageing reveal that the capped nanostructures retain their optical properties. Overall, capping of GaAs and InP NWs with high-k dielectrics AlN and Al2O3 provides moderate surface passivation as well as long term protection from oxidation and environmental attack.

Internal communication at Bohunice NPPs

International Nuclear Information System (INIS)

Dobdk, Dobroslav

1999-01-01

Communication is the base of everyday existence of a modern person and every company. It is not easy to work in this area in a changing 'eastern' country. Many tools, which are used are in the mind of people connected with 'propaganda'. I would like to share our experience with you. The goal of an internal communication is to spread and provide continuous current of objective information between the management of Bohunice NPPs and its personnel and between the personnel itself. Communication with the Bohunice NPPs employees helps to get acquainted with their opinions and ideas concerning the subsidiary and nuclear power industry

Optical absorption and oxygen passivation of surface states in III-nitride photonic devices

Science.gov (United States)

Rousseau, Ian; Callsen, Gordon; Jacopin, Gwénolé; Carlin, Jean-François; Butté, Raphaël; Grandjean, Nicolas

2018-03-01

III-nitride surface states are expected to impact high surface-to-volume ratio devices, such as nano- and micro-wire light-emitting diodes, transistors, and photonic integrated circuits. In this work, reversible photoinduced oxygen desorption from III-nitride microdisk resonator surfaces is shown to increase optical attenuation of whispering gallery modes by 100 cm-1 at λ = 450 nm. Comparison of photoinduced oxygen desorption in unintentionally and n+-doped microdisks suggests that the spectral changes originate from the unpinning of the surface Fermi level, likely taking place at etched nonpolar III-nitride sidewalls. An oxygen-rich surface prepared by thermal annealing results in a broadband Q improvement to state-of-the-art values exceeding 1 × 104 at 2.6 eV. Such findings emphasize the importance of optically active surface states and their passivation for future nanoscale III-nitride optoelectronic and photonic devices.

Operational safety performance of Slovak NPPs in 2005

International Nuclear Information System (INIS)

Tomek, J.

2006-01-01

In this presentation author presents operational safety performance of Slovak NPPs in 2005. Operation of Slovak NPPs in 2005 was safe and reliable, with: - high level of performance low risk; - minimal impact on the personnel, environment and public; - positive attitude to safety.

Current activities on safety improvement at Ukrainian NPPs

International Nuclear Information System (INIS)

Stovbun, V.V.

2000-01-01

This report describes general development status of the national programs on safety improvement of the Ukrainian NPPs, basic approaches adopted for planning and implementation of safety improvement works, and state of implementation of principal technical activities aimed at safety improvement of Ukrainian NPPs. (author)

Seleção de genótipos parentais de acerola com base na divergência genética multivariada

Directory of Open Access Journals (Sweden)

CARPENTIERI-PÍPOLO VALÉRIA

2000-01-01

Full Text Available Este trabalho teve por objetivo identificar e selecionar genótipos parentais de acerola (Malpighia emarginata L. adequadas a programas de melhoramento genético. Nove caracteres quantitativos de maior importância agronômica foram usados para determinação da distância genética e formação de grupos similares de acessos. O agrupamento pelo método de Tocher, a partir das distâncias generalizadas de Mahalanobis, possibilitou a divisão de 14 genótipos em três grupos. Com base na divergência genética e no caráter agronômico-chave (teor de vitamina C, destacaram-se como mais promissores os cruzamentos dos genótipos: AM Mole pertencente ao grupo III, com os genótipos PR AM, N° 18, PR 17, PR 16, Eclipse, AM 22 e Dominga, todos pertencentes ao grupo I.

Psychological health of operators in NPPs and accident prevention

International Nuclear Information System (INIS)

Zhou Huayun

2004-01-01

Mental and physical health of operators of nuclear power plants (NPPs) is directly related to normal and safe operation of NPPs. The cognitive process, volitional character, attention, emotion, feeling and personality are important factors that affect operators' safe behavior. Alcohol, medical drugs and operators' biological rhythm are can also make great effects on their psychological health. By means of job-fitness psychological test, better candidates for operators could be primarily selected from point of psychological view. Psychological follow-up of post skill training, simulator training and practical work of operators can make NPPs prevent from operational accidents due to human errors to the greatest extent. It is helpful for NPPs to find and solve some psychological problems by means of psychological counseling, regulation or psychotherapy. (author)

Progress of steam generator ageing management of Chinese NPPs

International Nuclear Information System (INIS)

Hongyun, L.; Chun, G.; Jun, T.; Zhigang, W.

2012-01-01

In China, the first two NPPs have operated over 15 years (QNPC) and 13 years (Dayabay). Now, most of Chinese NPPs have started their ageing management project. Steam generator (SG) is one of key safety important components for PWR and CANDU, which is selected as the first group of components to develop component ageing management system. QNPC and TQNPC have made some progress in this area. The basic SG ageing management system has been set up, and some application has been under way. To set up SG basic ageing management system, we start with (1) SG ageing mechanism analysis (2) Developing SG ageing management programme (3) Developing SG ageing management information system, SGAMDB (4) Ageing degradation assessment and remained life evaluation SG ageing mechanisms are classified as function degradation and material/structure degradation. The specific tables with unified format are used to analyze the ageing mechanism. The numbering requirements for ageing mechanism are developed to manage them in ageing information system. All ageing mechanisms are graded I and II and III based on its feasibility, impact on safety and operation experience, so that the key mechanisms are managed more strictly. SG ageing management programme (SGAMP), which is fundamental document for ageing management, provides the requirements for working process, what to do and when to do. SGAMP reviewing and improving requirements are as well included. SG ageing management database (SGAMDB) is the first component ageing management database for Chinese NPP, which have been installed and are in operation in QNPC and TQNPC. SG ageing degradation assessment and remained life evaluation are based on ageing mechanism, which includes integrity of tube bundle, integrity and remained fatigue life of key assemblies, and heat transfer capability degradation. Most NPPs at Chinese mainland have started their plant ageing and life management projects. Steam generator (SG), which is one of safety important

EPCGen2 Pseudorandom Number Generators: Analysis of J3Gen

Directory of Open Access Journals (Sweden)

Alberto Peinado

2014-04-01

Full Text Available This paper analyzes the cryptographic security of J3Gen, a promising pseudo random number generator for low-cost passive Radio Frequency Identification (RFID tags. Although J3Gen has been shown to fulfill the randomness criteria set by the EPCglobal Gen2 standard and is intended for security applications, we describe here two cryptanalytic attacks that question its security claims: (i a probabilistic attack based on solving linear equation systems; and (ii a deterministic attack based on the decimation of the output sequence. Numerical results, supported by simulations, show that for the specific recommended values of the configurable parameters, a low number of intercepted output bits are enough to break J3Gen. We then make some recommendations that address these issues.

Description of Guyruita gen. nov. and two new species (Ischnocolinae, Theraphosidae Descrição de Guyruita gen. nov. e duas novas espécies (Ischnocolinae, Theraphosidae

Directory of Open Access Journals (Sweden)

José P.L. Guadanucci

2007-12-01

Full Text Available The genus Guyruita gen. nov. and two new species from Brazil are described. Holothele waikoshiemi (Bertani & Araújo, 2005 from Venezuela is transferred here to the new genus. Guyruita gen. nov. differs from the remaining Ischnocolinae by the following features: labium densely occupied by a lot of cuspules (more than 100, intercheliceral intumescence absent, posterior sternal sigilla remote from margin, tarsal claws without teeth, tarsal scopula I-II undivided (tarsus II with a line of sparse setae, which does not divide the scopula, III-IV divided.É descrito o gênero Guyruita gen. nov. e duas espécies novas do Brasil. Holothele waikoshiemi (Bertani & Araújo, 2005 da Venezuela é transferido para o novo gênero. Guyruita gen. nov. difere dos outros Ischnocolinae pelas seguintes caracterísicas: lábio densamente ocupado por muitas cúspides (mais de 100, tumescência interqueliceral ausente, sigilla esternal posterior distante da margem, unhas tarsais sem dentes, escópula tarsal I e II inteiras (tarso II com uma fileira de cerdas esparsas, as quais não dividem a escópula, III e IV divididas.

Generation IV nuclear reactors: Current status and future prospects

International Nuclear Information System (INIS)

Locatelli, Giorgio; Mancini, Mauro; Todeschini, Nicola

2013-01-01

Generation IV nuclear power plants (GEN IV NPPs) are supposed to become, in many countries, an important source of base load power in the middle–long term (2030–2050). Nowadays there are many designs of these NPPs but for political, strategic and economic reasons only few of them will be deployed. International literature proposes many papers and reports dealing with GEN IV NPPs, but there is an evident difference in the types and structures of the information and a general unbiased overview is missing. This paper fills the gap, presenting the state-of-the-art for GEN IV NPPs technologies (VHTR, SFR, SCWR, GFR, LFR and MSR) providing a comprehensive literature review of the different designs, discussing the major R and D challenges and comparing them with other advanced technologies available for the middle- and long-term energy market. The result of this research shows that the possible applications for GEN IV technologies are wider than current NPPs. The economics of some GEN IV NPPs is similar to actual NPPs but the “carbon cost” for fossil-fired power plants would increase the relative valuation. However, GEN IV NPPs still require substantial R and D effort, preventing short-term commercial adoption. - Highlights: • Generation IV reactors are the middle–long term technology for nuclear energy. • This paper provides an overview and a taxonomy for the designs under consideration. • R and D efforts are in the material, heat exchangers, power conversion unit and fuel. • The life cycle costs are competitive with other innovative technologies. • The hydrogen economy will foster the development of Generation IV reactors

External events analysis in PSA studies for Czech NPPs

International Nuclear Information System (INIS)

Holy, J.; Hustak, S.; Kolar, L.; Jaros, M.; Hladky, M.; Mlady, O.

2014-01-01

The purpose of the paper is to summarize current status of natural external hazards analysis in the PSA projects maintained in Czech Republic for both Czech NPPs - Dukovany and Temelin. The focus of the presentation is put upon the basic milestones in external event analysis effort - identification of external hazards important for Czech NPPs sites, screening out of the irrelevant hazards, modeling of plant response to the initiating events, including the basic activities regarding vulnerability and fragility analysis (supported with on-site analysis), quantification of accident sequences, interpretation of results and development of measures decreasing external events risk. The following external hazards are discussed in the paper, which have been addressed during several last years in PSA projects for Czech NPPs: 1)seismicity, 2)extremely low temperature 3)extremely high temperature 4)extreme wind 5)extreme precipitation (water, snow) 6)transport of dangerous substances (as an example of man-made hazard with some differences identified in comparison with natural hazards) 7)other hazards, which are not considered as very important for Czech NPPs, were screened out in the initial phase of the analysis, but are known as potential problem areas abroad. The paper is a result of coordinated effort with participation of experts and staff from engineering support organization UJV Rez, a.s. and NPPs located in Czech Republic - Dukovany and Temelin. (authors)

Regulatory challenges faced first Indonesia NPPs by independent TSOs

International Nuclear Information System (INIS)

Sri Budi Utami

2010-01-01

Technical and scientific support organizations (TSOs) dedicated to supporting national regulatory authorities. At present BAPETEN has internal TSOs. Pertaining to the regulatory control of nuclear safety, security, and safeguards for nuclear power plants (NPPs), independent TSOs providing support to the safety regulatory bodies are facing a number of technical challenges to ensuring the safety of NPPs. It is essential that BAPETEN need independent TSOs in order to warrant a sufficient level of safety, security and non proliferation in building and operating of first NPP. It is essential that BAPETEN need independent TSOs in order to warrant a sufficient level of safety, security and non proliferation in building and operating of first NPPs. (author)

The status of nuclear safety of Ukrainian NPPS and evaluations by ASSET methodology

International Nuclear Information System (INIS)

Koltakov, V.

1997-01-01

The presentation discusses the following issues: nuclear power plants and research reactors; electricity production and operating personnel; status of nuclear safety at NPPs of Ukraine; operation of Ukrainian NPPs; violations of NPPs operation; short review of ASSET missions; experience of feedback process. Figs, tabs

The status of nuclear safety of Ukrainian NPPS and evaluations by ASSET methodology

Energy Technology Data Exchange (ETDEWEB)

Koltakov, V [State Scientific and Technical Center on Nuclear and Radiational Safety, Kiev (Ukraine)

1997-10-01

The presentation discusses the following issues: nuclear power plants and research reactors; electricity production and operating personnel; status of nuclear safety at NPPs of Ukraine; operation of Ukrainian NPPs; violations of NPPs operation; short review of ASSET missions; experience of feedback process. Figs, tabs.

The ways to increase the Ukrainian NPPs ecological safety

International Nuclear Information System (INIS)

Barbashev, S.V.

2005-01-01

The analysis of the approaches to achieve the basic goals of radiation and ecological safety at Ukrainian NPPs has been made. The problems, solution of which will allow to speak of a realization at NPPs of a cardinally other than now ecological approach to the estimation of nuclear energy's influence on the environment and ecological safety maintenance, has been numbered

A Virtual Reality Framework to Optimize Design, Operation and Refueling of GEN-IV Reactors

International Nuclear Information System (INIS)

Rizwan-uddin; Nick Karancevic; Stefano Markidis; Joel Dixon; Cheng Luo; Jared Reynolds

2008-01-01

Many GEN-IV candidate designs are currently under investigation. Technical issues related to material, safety and economics are being addressed at research laboratories, industry and in academia. After safety, economic feasibility is likely to be the most important criterion in the success of GEN-IV design(s). Lessons learned from the designers and operators of GEN-II (and GEN-III) reactors must play a vital role in achieving both safety and economic feasibility goals

A Virtual Reality Framework to Optimize Design, Operation and Refueling of GEN-IV Reactors.

Energy Technology Data Exchange (ETDEWEB)

Rizwan-uddin; Nick Karancevic; Stefano Markidis; Joel Dixon; Cheng Luo; Jared Reynolds

2008-04-23

many GEN-IV candidate designs are currently under investigation. Technical issues related to material, safety and economics are being addressed at research laboratories, industry and in academia. After safety, economic feasibility is likely to be the most important crterion in the success of GEN-IV design(s). Lessons learned from the designers and operators of GEN-II (and GEN-III) reactors must play a vital role in achieving both safety and economic feasibility goals.

Internal flooding analyses results of Slovak NPPs

International Nuclear Information System (INIS)

Sopira, Vladimir

2000-01-01

The assessment of the flood risk was the objective of the internal flooding analysis for NPPs Bohunice V1, V2 and Mochovce. All important flooding sources were identified. The rooms containing safety important components were analyzed from the point of view of: Integrity of flood boundaries; Capability for drainage; Flood signalisation; Flood localization and liquidation; Vulnerability of safety system component. The redundancies of safety systems are located mostly separately and no flood can endanger more than single train. It can be concluded that NPPs with WWER-440 are very safe against the flooding initiating event

Study on the Post-Fire Safe-Shutdown Analysis for CANDU NPPs

Energy Technology Data Exchange (ETDEWEB)

Kim, In Hwan; Kim, Yun Jung; Park, Mun Hee [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The purpose of this paper is to study a method of the Post-Fire Safe-Shutdown Analysis in order to apply to CANDU NPPs when one group of the Safety Structures, Systems and Components(SCCs) is failed by Fire. The purpose of Fire Protection is prevention, suppression of the fire and mitigation of the effect on the Nuclear Safety. When fire takes place at the Nuclear Power Plants(NPPs), the reactor should achieve and maintain safe shut-down condition and minimize radioactive material release to an environment. The purpose of the Post-Fire SSA process is an evaluation process during a fire at NPPs. At this study, the process was conceptually adopted for control room complex of CANDU NPPs. The Core Damage Frequency of the Reactor will be evaluated more accurately if the SSA is adopted adequately at a fire.

Decommissioning of Ukrainian NPPs

International Nuclear Information System (INIS)

Skripov, A.E.

2002-01-01

The decision about the development of 'Decommissioning Concept of Ukrainian NPPs' being on commercial operational stage was approved by NAEK 'Energoatom' Board of Administration by way of the decommissioning activity effective planning. The Concept will be the branch document, containing common approaches formulations on problem decisions according to the units decommissioning with generated resources, and RAW and SNF management strategy during decommissioning

Organizational factors in Korean NPPs

International Nuclear Information System (INIS)

Jang, D. J.; Kim, Y. I.; Jeong, C. H.; Kim, J. W.

2003-01-01

Organizational factors are referred to as the factors that influence the achievement of a goal of an organization. Latent problems of an organization could contribute to causing human errors in such stages as design, operation and maintenance, and furthermore, leading to an severe accident. In order to evaluate an organization from the safety viewpoint, it is necessary to identify the organizational factors in a systematic fashion. In this paper, some efforts to identify the organizational factors in Korean NPPs are presented. The study was performed in the following steps: 1) Reviewing the definitions and range of the organizational factors used by the previous 13 researches, 2) Structuring the organizational factors by screening and collating factors, 3) Analysing the organizational factors that is considered to have contributed to the trip events based on the trip report of Korean NPPs, 4) Suggesting a more reliable taxonomy of organizational factors for event analysis by applying the Onion Structure Model to the selected factors

Perinatal exposure to genistein, a soy phytoestrogen, improves spatial learning and memory but impairs passive avoidance learning and memory in offspring.

Science.gov (United States)

Kohara, Yumi; Kuwahara, Rika; Kawaguchi, Shinichiro; Jojima, Takeshi; Yamashita, Kimihiro

2014-05-10

This study investigated the effects of perinatal genistein (GEN) exposure on the central nervous system of rat offspring. Pregnant dams orally received GEN (1 or 10 mg/kg/day) or vehicle (1 ml/kg/day) from gestation day 10 to postnatal day 14. In order to assess the effects of GEN on rat offspring, we used a battery of behavioral tests, including the open-field, elevated plus-maze, MAZE and step-through passive avoidance tests. MAZE test is an appetite-motivation test, and we used this mainly for assessing spatial learning and memory. In the MAZE test, GEN groups exhibited shorter latency from start to goal than the vehicle-treated group in both sexes. On the other hand, performances in the step-through passive avoidance test were non-monotonically inhibited by GEN in both sexes, and a significant difference was observed in low dose of the GEN-treated group compared to the vehicle-treated group in female rats. Furthermore, we found that perinatal exposure to GEN did not significantly alter locomotor activity or emotionality as assessed by the open-field and elevated-plus maze tests. These results suggest that perinatal exposure to GEN improved spatial learning and memory of rat offspring, but impaired their passive avoidance learning and memory. Copyright © 2014 Elsevier Inc. All rights reserved.

EDF analysis of hydrogen problem on present NPPs

International Nuclear Information System (INIS)

Guieu, S.

1997-01-01

By letter dated March 1995, Electricite de France (EDF) has sent to the French Safety Authority (called DSIN, depending jointly from Industry and Environment Ministries) its position, for Present NPPs, regarding three main topics concerning severe accidents pointed by DSIN: hydrogen problem; high pressure core melt risk; and instrumentation. Concerning 'hydrogen problem', EDF answer is not only a state-of-the art analysis but intend to answer the question of the need (or not) for implementation of countermeasures in Present French NPPs. This position is presently under review by DSIN and its Technical Supports. (author)

Finite mixture models for sensitivity analysis of thermal hydraulic codes for passive safety systems analysis

Energy Technology Data Exchange (ETDEWEB)

Di Maio, Francesco, E-mail: francesco.dimaio@polimi.it [Energy Department, Politecnico di Milano, Via La Masa 34, 20156 Milano (Italy); Nicola, Giancarlo [Energy Department, Politecnico di Milano, Via La Masa 34, 20156 Milano (Italy); Zio, Enrico [Energy Department, Politecnico di Milano, Via La Masa 34, 20156 Milano (Italy); Chair on System Science and Energetic Challenge Fondation EDF, Ecole Centrale Paris and Supelec, Paris (France); Yu, Yu [School of Nuclear Science and Engineering, North China Electric Power University, 102206 Beijing (China)

2015-08-15

Highlights: • Uncertainties of TH codes affect the system failure probability quantification. • We present Finite Mixture Models (FMMs) for sensitivity analysis of TH codes. • FMMs approximate the pdf of the output of a TH code with a limited number of simulations. • The approach is tested on a Passive Containment Cooling System of an AP1000 reactor. • The novel approach overcomes the results of a standard variance decomposition method. - Abstract: For safety analysis of Nuclear Power Plants (NPPs), Best Estimate (BE) Thermal Hydraulic (TH) codes are used to predict system response in normal and accidental conditions. The assessment of the uncertainties of TH codes is a critical issue for system failure probability quantification. In this paper, we consider passive safety systems of advanced NPPs and present a novel approach of Sensitivity Analysis (SA). The approach is based on Finite Mixture Models (FMMs) to approximate the probability density function (i.e., the uncertainty) of the output of the passive safety system TH code with a limited number of simulations. We propose a novel Sensitivity Analysis (SA) method for keeping the computational cost low: an Expectation Maximization (EM) algorithm is used to calculate the saliency of the TH code input variables for identifying those that most affect the system functional failure. The novel approach is compared with a standard variance decomposition method on a case study considering a Passive Containment Cooling System (PCCS) of an Advanced Pressurized reactor AP1000.

Environmental monitoring around the Nuclear Power Plants (NPPs) in India

International Nuclear Information System (INIS)

Ravi, P.M.

2014-01-01

Environmental Survey Laboratories (ESLs) are established at all major nuclear installations before the commissioning of an installation. As per the lndian regulations, the environmental monitoring around NPPs are carried out by an independent body. Accordingly, Environmental Survey Laboratories (ESLs) under Health Physics Division, Bhabha Atomic Research Centre is entrusted with the responsibility. This paper presents the various aspects of environmental monitoring programmes being pursued around Indian NPPs

Trends in development of new generation of NPPs with increased safety

International Nuclear Information System (INIS)

Rumyantsev, V.V.

1992-01-01

The main requirements for designing, construction and operation of NPPs with advanced water cooled ALWR and SBWR reactors being under development in the USA are discussed. The trends in modernization of control systems at NPPs of new generation based on wide introduction of digital computers and visualization of technological parameter measurements are considered

An Approach for Effect Analysis of Electromagnetic Pulse in Operating NPPs

International Nuclear Information System (INIS)

Ryu, Ho Sun; Ye, Song Hae; Kim, Minyi; Lee, Euijong

2016-01-01

Recently, there is a growing Electromagnetic Pulse (EMP) threat caused by North Korea’s nuclear weapons and unmanned aerial vehicles (UAVs). KHNP CRI is currently conducting a research project that will evaluate the safety of domestic nuclear power plants (NPPs) against EMP effects and prepare safety measures to counter vulnerable points. We will instead use simulation tools to evaluate the electromagnetic shielding ability and the conductivity of cables through vulnerable points in NPPs. Through a study of electromagnetic simulation techniques and tools, this paper suggests a simulation method for analysis of EMP effects in operating NPPs. Although 3D tools are relatively accurate, is difficult to use only 3D tools to simulate EMP effects for huge and complex structures such as NPPs. It is more efficient in terms of cost and time to use a 3D tool and an EMT tool for the simulation of such structures. We have compared the advantages and disadvantages of various methods and have selected the most appropriate tools; we will proceed in our next paper with the simulation of EMP effects

An Approach for Effect Analysis of Electromagnetic Pulse in Operating NPPs

Energy Technology Data Exchange (ETDEWEB)

Ryu, Ho Sun; Ye, Song Hae; Kim, Minyi; Lee, Euijong [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

Recently, there is a growing Electromagnetic Pulse (EMP) threat caused by North Korea’s nuclear weapons and unmanned aerial vehicles (UAVs). KHNP CRI is currently conducting a research project that will evaluate the safety of domestic nuclear power plants (NPPs) against EMP effects and prepare safety measures to counter vulnerable points. We will instead use simulation tools to evaluate the electromagnetic shielding ability and the conductivity of cables through vulnerable points in NPPs. Through a study of electromagnetic simulation techniques and tools, this paper suggests a simulation method for analysis of EMP effects in operating NPPs. Although 3D tools are relatively accurate, is difficult to use only 3D tools to simulate EMP effects for huge and complex structures such as NPPs. It is more efficient in terms of cost and time to use a 3D tool and an EMT tool for the simulation of such structures. We have compared the advantages and disadvantages of various methods and have selected the most appropriate tools; we will proceed in our next paper with the simulation of EMP effects.

Passive safety systems for integral reactors

International Nuclear Information System (INIS)

Kuul, V.S.; Samoilov, O.B.

1996-01-01

In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs

Passive safety systems for integral reactors

Energy Technology Data Exchange (ETDEWEB)

Kuul, V S; Samoilov, O B [OKB Mechanical Engineering (Russian Federation)

1996-12-01

In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs.

Radiation supervision - NPPs A-1, V-1, V-2

International Nuclear Information System (INIS)

2000-01-01

In this leaflet the radiation supervision of the nuclear power plants A-1, V-1, V-2 is presented. Off-site radiation supervision laboratory is a part of monitoring scheme of the NPPs. More than 1150 samples are taken from the environment annually. The tele-dosimetric system was constructed to improve the quality of the Bohunice NPPs operation impacts supervision. It has been running in a continuous operation from 1992 and providing supervision of the nuclear power plant off-site area within 25 kilometres. The tele-dosimetric system is described

Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

Energy Technology Data Exchange (ETDEWEB)

Woo, Tae Ho, E-mail: thw@snu.ac.kr

2013-12-15

Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs.

Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

International Nuclear Information System (INIS)

Woo, Tae Ho

2013-01-01

Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs

The 1st reveal of Gen-V nuclear energy. Prospecting investigation of nuclear power 2050 (A2050) for energy innovation in the nuclear industry

International Nuclear Information System (INIS)

Woo, Tae Ho; Lee, Soon Ho

2012-01-01

The proposed strategy for the future nuclear energy is analyzed. The conventional nuclear power plants (NPPs) are investigated by the 21 st style interdisciplinary research as the information technology (IT), nanotechnology (NT), and biological technology (BT). New kinds of energy production methods as spherical isotropic power reactor (SIPR) and nano lattice power (NLP) are introduced. In addition, the problems of Gen-IV technologies are challenged to be solved, which is the matters of the mechanical and thermal controls of several coolants cases. The simulation result shows the increasing for the usefulness of the business. The core and vessel are very tractable due to moving core vessel (SIPR). The concept of safety system is changed to be submerged into coolant instead of injection concept (SIPR). The commercial fusion energy is realized for mass energy productions (NLP). Eventually, the safety as well as economical status is increased comparing to previous NPPs. (orig.)

Opportunities and supporting activities to promote preventive maintenance of NPPs in Japan

International Nuclear Information System (INIS)

Sanada, A.; Shinkawa, T.; Sakurada, M.

1998-01-01

With increase of the number of NPPs and operation history, enhancement of the safety regulation is becoming important for such long-operated NPPs. Centering on the comprehensive preventive maintenance, periodic safety reviews by utilities and its review and evaluation by MITI are in progress. The first reviews have not revealed essential and critical indications to be newly implemented. This means that the most of activities to secure reliability and safety have been done steadily. The present paper addresses the mechanism of on-going preventive maintenance and its essential elements: opportunities to identify issues and problems, and supporting activities to promote decision-makings on feedback, upgrading and modernization of NPPs. (author)

Safety upgrading activities against tsunami, earthquake, and severe accident at Hamaoka NPPs

International Nuclear Information System (INIS)

Watanabe, Tetsuya; Wakunaga, Takao; Ishida, Takahisa

2013-01-01

As the lessons learned by the Fukushima Daiichi NPPs accident, Chubu Electric Power carried out the Emergency Safety Measures at Hamaoka NPPs immediately, and announced the plan for tsunami countermeasures including the construction of 18m-height tsunami protection wall in July 2011. Furthermore, the company announced the additional severe accident and tsunami countermeasures, and etc. in December 2012 and in April 2013, such as the installation of Filtered Containment Venting System and increasing the height of the tsunami protection wall from 18m to 22m. In this paper, we present major safety upgrading activities against tsunami, earthquake and severe accident at Hamaoka NPPs. (author)

Operating experiences with passive systems and components in German nuclear power plants

International Nuclear Information System (INIS)

Maqua, M.

1996-01-01

Operating experience with passive systems and components is limited to the equipment installed in existing NPPs. In German power plants, this experience is available for equipment of the IAEA categories A, C and D. The presentation is focused on typical examples out of these three categories. An overview is given on the number of reported events and typical failure modes. Selected failures are discussed in detail. 1 ref., 6 figs, 7 tabs

Operating experiences with passive systems and components in German nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Maqua, M [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany)

1996-12-01

Operating experience with passive systems and components is limited to the equipment installed in existing NPPs. In German power plants, this experience is available for equipment of the IAEA categories A, C and D. The presentation is focused on typical examples out of these three categories. An overview is given on the number of reported events and typical failure modes. Selected failures are discussed in detail. 1 ref., 6 figs, 7 tabs.

Best-practices guidelines for L2PSA development and applications. Volume 2 - Best practices for the Gen II PWR, Gen II BWR L2PSAs. Extension to Gen III reactors

International Nuclear Information System (INIS)

Raimond, E.; Durin, T.; Rahni, N.; Meignen, R.; Cranga, M.; Pichereau, F.; Bentaib, A.; Guigueno, Y.; Loeffler, H.; Mildenberger, O.; Lajtha, G.; Santamaria, C.S.; Dienstbier, J.; Rydl, A.; Holmberg, J.E.; Lindholm, I.; Maennistoe, I.; Pauli, E.M.; Dirksen, G.; Grindon, L.; Peers, K.; Hulqvist, G.; Parozzi, F.; Polidoro, F.; Cazzoli, E.; Vitazkova, J.; Burgazzi, L.; Oury, L.; Ngatchou, C.; Siltanen, S.; Niemela, I.; Routamo, T.; Helstroem, P.; Bassi, C.; Brinkman, H.; Seidel, A.; Schubert, B.; Wohlstein, R.; Guentay, S.; Vincon, L.

2010-01-01

The objective of this coordinated action was to develop best practice guidelines for the performance of Level 2 PSA methodologies with a view of harmonisation at EU level and to allow meaningful and practical uncertainty evaluations in a Level 2 PSA. Specific relationships with community in charge of nuclear reactor safety (utilities, safety authorities, vendors, and research or services companies) have been established in order to define the current needs in terms of guidelines for level 2 PSA development and applications. An international workshop was organised in Hamburg, with the support of VATTENFALL, in November 2008. The level 2 PSA experts from the ASAMPSA2 project partners have proposed some guidelines for the development and application of L2PSA based on their experience and on information available from international cooperation (EC Severe Accident network of Excellence - SARNET, IAEA standards, OECD-NEA publications and workshop) or open literature. The number of technical issues addressed in the guideline is very large and all are not covered with the same relevancy in the first version of the guideline. This version is submitted for external review in November 2010 by severe accident experts and PSA, especially, from SARNET and OECD-NEA members. The feedback of the external review will be dis cussed during an international open works hop planned in March 2011 and all outcomes will be taken into consideration in the final version of this guideline (June 2011). The guideline includes 3 volumes: - Volume 1 - General considerations on L2PSA. - Volume 2 - Technical recommendations for Gen II and III reactors. - Volume 3 - Specific considerations for future reactor (Gen IV). The recommendations formulated in the guideline should not be considered as 'mandatory' but should help the L2PSA developers to achieve high quality studies with limited time and resources. It may also help the L2PSA reviewers by positioning one specific study in comparison with some

The 1{sup st} reveal of Gen-V nuclear energy. Prospecting investigation of nuclear power 2050 (A2050) for energy innovation in the nuclear industry

Energy Technology Data Exchange (ETDEWEB)

Woo, Tae Ho [Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering; Lee, Seok Jong [POSCO Engineering and Construction Co., Ltd., Incheon (Korea, Republic of); Lee, Soon Ho [SK Engineering and Construction Co., Ltd., Seoul (Korea, Republic of)

2012-11-15

The proposed strategy for the future nuclear energy is analyzed. The conventional nuclear power plants (NPPs) are investigated by the 21{sup st} style interdisciplinary research as the information technology (IT), nanotechnology (NT), and biological technology (BT). New kinds of energy production methods as spherical isotropic power reactor (SIPR) and nano lattice power (NLP) are introduced. In addition, the problems of Gen-IV technologies are challenged to be solved, which is the matters of the mechanical and thermal controls of several coolants cases. The simulation result shows the increasing for the usefulness of the business. The core and vessel are very tractable due to moving core vessel (SIPR). The concept of safety system is changed to be submerged into coolant instead of injection concept (SIPR). The commercial fusion energy is realized for mass energy productions (NLP). Eventually, the safety as well as economical status is increased comparing to previous NPPs. (orig.)

Spectroscopic evidence for a porphobilinogen deaminase-tetrapyrrole complex that is an intermediate in the biosynthesis of uroporphyrinogen III

International Nuclear Information System (INIS)

Rose, S.; Frydman, R.B.; de los Santos, C.; Sburlati, A.; Valasinas, A.; Frydman, B.

1988-01-01

Incubation of porphobilinogen (PBG) with PBG deaminase from Rhodopseudomonas sphaeroides in carbonate buffer to total PBG consumption resulted in low yields of uroporphyrinogen I(uro'gen I). In the reaction mixture a pyrrylmethane accumulated, which at longer incubation periods was transformed into uro'gen I. The accumulated pyrrylmethane gave an Ehrlich reaction which was different from that of a 2-(aminomethyl)dipyrrylmethane or 2-(aminomethyl)tripyrrane. It resembled that of a bilane but was different from that of a 2-(hydroxymethyl)bilane. The 13 C NMR spectra of incubations carried out with [11- 13 C]PBG indicated that the pyrrylmethane was a tetrapyrrole with methylene resonances at 22.35-22.50 ppm. It was loosely bound to the deaminase, and when separated from the enzyme by gel filtration or gel electrophoresis, it immediately cyclized to uro'gen I. No enzyme-bound methylene could be detected by its chemical shift, suggesting that its line width must be very broad. When uro'gen III-cosynthase was added to the deaminase-tetrapyrrole complex, uro'gen III was formed at the expense of the latter in about 75% yield. A protonated uro'gen I structure for this intermediate was ruled out by incubations using [2,11- 13 C]PBG. Uro'gen III formation from 2-(hydroxymethyl)bilane (HMB) and from the deaminase-tetrapyrrole intermediate was compared by using deaminase-cosynthase and cosynthase from several sources. It was found that while the HMB inhibited uro'gen III formation at higher concentrations and longer incubation times, uro'gen III formation from the complex did not decrease with time

A Cyber Security Risk Assessment Procedure for Digital I and C Systems in NPPs

International Nuclear Information System (INIS)

Song, J. G.; Lee, J. W.; Lee, C. K.; Kwon, K. C.; Lee, D. Y.

2011-01-01

Digital Instrumentation and Control (I and C) systems in nuclear power plants (NPPs) use general digital technologies similar to those used in IT systems. However, one of significant differences between the two systems resides in the duration of their service life. The I and C systems in NPPs operate for more than 20 years. IT systems, on the other hand, are in service for about 3 to 5 years. Hence, a one-time risk assessment for IT systems is normally acceptable. In contrast, the risk assessment for the I and C systems in NPPs should be recursively performed during their longer operation life. A recursive procedure for cyber security risk assessment of the I and C systems in NPPs is studied and proposed in this paper

A Cyber Security Risk Assessment Procedure for Digital I and C Systems in NPPs

Energy Technology Data Exchange (ETDEWEB)

Song, J. G.; Lee, J. W.; Lee, C. K.; Kwon, K. C.; Lee, D. Y. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-10-15

Digital Instrumentation and Control (I and C) systems in nuclear power plants (NPPs) use general digital technologies similar to those used in IT systems. However, one of significant differences between the two systems resides in the duration of their service life. The I and C systems in NPPs operate for more than 20 years. IT systems, on the other hand, are in service for about 3 to 5 years. Hence, a one-time risk assessment for IT systems is normally acceptable. In contrast, the risk assessment for the I and C systems in NPPs should be recursively performed during their longer operation life. A recursive procedure for cyber security risk assessment of the I and C systems in NPPs is studied and proposed in this paper

Analysis of 'human element related trip case book in Korean NPPs' using organizational factors

International Nuclear Information System (INIS)

Kim, S. Y.; Kim, Y. I.; Lee, Y. S.; Kim, C. S.; Jung, C. H.; Jung, W. D.

2002-01-01

There have been no studies appling organizational factors to data analysis in Korean NPPs. In this paper, data in 'human element related trip case book in Korean NPPs' are analyzed and categorized by the 20 organizational factors of NRC-BNL according to the cause of reactor trip. These inform us how organizational factors affected on the safety of Korean NPPs. Consequently important organizational factor are identified through which it is known that NPP organization would have a tendency

Ergonomic (human factors) problems in design of NPPs. A review of TMI and Chernobyl accidents

International Nuclear Information System (INIS)

Huang Xiangrui; Zheng Fuyu; Gao Jia

1994-01-01

The general principle of ergonomic in design of NPPs is given and some causes of TMI and Chernobyl accidents from the view point of human factor engineering are reviewed. The paper also introduces some Ergonomic problems in design, operation and management of earlier NPPs. Some ergonomic principles of man-machine systems design have been described. Some proposals have been suggested for improving human reliability in NPPs

Cyber security in nuclear industry – Analytic study from the terror incident in nuclear power plants (NPPs)

International Nuclear Information System (INIS)

Cho, Hyo Sung; Woo, Tae Ho

2017-01-01

Highlights: • The cyber terrorism in NPPs of South Korea shows the study motivations. • Analyses of the cyber terrorism in NPPs are investigated. • Designed solutions for the cyber terrorism in NPPs are discussed. • South Korean case is considered as the cyber terrorism in NPPs. - Abstract: The cyber terrorism for nuclear power plants (NPPs) is investigated for the analytic study following the South Korean case on December 2014. There are several possible cyber terror attacks in which the twelve cases are studied for the nuclear terror cases including the computer hacking and data stealing. The defense-in-depth concept is compared for cyber terrorism, which was imported from the physical terror analysis. The conventional three conditions of the physical protection system (PPS) are modified as prevention, detection, and response. The six cases are introduced for the solutions of the facility against the possible cyber terrorism in NPPs. The computer hacking methods and related solutions are analyzed for the applications in the nuclear industry. The nuclear security in the NPPs could be an extremely serious condition and the remedies are very important in the safe plant operations. In addition, the quantitative modeling study is performed.

Safeguard assessment for life extension in nuclear power plants (NPPs) using a production function

International Nuclear Information System (INIS)

Woo, Tae-Ho; Lee, Un-Chul

2011-01-01

Research highlights: → The numerical value is constructed for the secure operation. → As the power increases, the NSEF increases. → Specific month could be indicated by the relative value of NSEF. → It is suggested for the better power in NPPs. → There is another possibility for the secure operation factors. - Abstract: Life extension is investigated as a safeguard assessment for the stability on the operation of the nuclear power plants (NPPs). The Cobb-Douglas function, one of the production functions, is modified for the nuclear safeguard in NPPs, which was developed for the life quality of the social and natural objects. Nuclear Safeguard Estimator Function (NSEF) is developed for the application in NPPs. The cases of NPPs are compared with each other in the aspect of the secure performance. The results are obtained by the standard productivity comparisons with the designed power operations. The range of secure life extension is between 1.008 and 5.353 in 2000 MW e and the range is between 0.302 and 0.994 in 600 MW e . So, the successfulness of the power operation increases about 5 times higher than that of the interested power in this study, which means that the safeguard assessment has been performed in the life extension of the NPPs. The technology assessment (TA) is suggested for the safe operation which is an advanced method comparing conventional probabilistic safety assessment (PSA).

Passive cooling applications for nuclear power plants using pulsating steam-water heat pipes

International Nuclear Information System (INIS)

Aparna, J.; Chandraker, D.K.

2015-01-01

Gen IV reactors incorporate passive principles in their system design as an important safety philosophy. Passive safety systems use inherent physical phenomena for delivering the desired safe action without any external inputs or intrusion. The accidents in Fukushima have renewed the focus on passive self-manageable systems capable of unattended operation, for long hours even in extended station blackout (SBO) and severe accident conditions. Generally, advanced reactors use water or atmospheric air as their ultimate heat sink and employ passive principles in design for enhanced safety. This paper would be discussing the experimental results on pulsating steam water heat-pipe devices and their applications in passive cooling. (author)

DETEKSI GEN-GEN PENYANDI FAKTOR VIRULENSI PADA BAKTERI VIBRIO

Directory of Open Access Journals (Sweden)

Ince Ayu Khairani Kadriah

2011-04-01

menggunakan isolat bakteri yang diisolasi dari budidaya udang windu di berbagai daerah di Sulawesi Selatan dan Jawa. Pada penelitian ini digunakan primer spesifik untuk mendeteksi gen-gen virulen toxR gene, hemolysin (vvh gene, dan GyrB gene dengan metode PCR. Dari 35 isolat yang diisolasi, 20 isolat terdeteksi memiliki gen virulensi dan 8 di antaranya memiliki dua gen virulen. Spesies bakteri yang memiliki gen virulen adalah: V.harveyi, V. parahaemolyticus, V. mimicus, dan V. campbelli

Overview of human performance improvement initiatives in Nuclear Power Plants (NPPs )

International Nuclear Information System (INIS)

Sharma, Ashok Kumar

2006-01-01

Nuclear Power Plants (NPPs) are very complex systems. Diverse, multiple and redundant technological systems are used for effective control and safety of the NPPs. The increased numbers of such systems require increased operator attention. Additionally, the control stations (man-machine interfaces) are to be kept manageable in size. This sometimes reduces the scope for truly ergonomic design. These limitations, coupled with the shortcomings of human nature, led to unintended human performance problems and errors resulting into poor plant performance worldwide. Some organisational weaknesses, managerial decisions and latent errors also aided and abetted human errors. In view of this, a need was felt for development of performance culture at all levels in NPP organisations. Towards this end, ready-to-use performance improvement tools were developed and used for individual performers, supervisors and managers in the NPPs. This paper describes the experiences of the global nuclear electricity generating industry towards human performance improvement and error reduction. (author)

Our consistent countermeasure following up with lesson from Fukushima NPPs accident

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Rok [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of); Ro, Seung Gy [Sung woo E and T, Kyeonggi (Korea, Republic of); Kim, Si Hwan [UNIST, Ulsan (Korea, Republic of); Nam, Jang Soo [Korean Nuclear Society, Daejeon (Korea, Republic of); Yoo, Guk Hee [Nuclear Safety and Security Commission, Seoul (Korea, Republic of); Kim, Soong Pyung [Chosun Univ., Gwangju (Korea, Republic of)

2012-10-15

Fukushima NPPs accident has not only resulted in driving out the nuclear Renaissance which is about to revive after several lean years, but also given humankind a very rigorous lessons in nuclear safety. Recently administrative systems were reorganized for stepping up further nuclear safety. Nuclear Safety and Security Commission(NSSC) as a governmental organization, directly under the jurisdiction of the president, which is responsible for a nuclear safety mission separated from Ministry of Education, Science and Technology. A beef up work of 50 safety related items for Korean NPPs identified after Fukushima NPPs accident has been implemented under the supervision of the commission. It has also been emphasized that sincere communications between the nuclear society and the people at large are essential for obtaining public acceptance of nuclear energy by ensuring the credibility of nuclear safety. The main points of lecture materials presented in the nuclear senior members' forum have been reviewed to derive invaluable guidelines.

Next generation of human resources for GEN (Generation) III+ new build projects

International Nuclear Information System (INIS)

Baltin, Goerge; Glaubrecht, Stefan; Schoenfelder, Christian

2014-01-01

requires a wide spread approach, involving important stakeholders in this field, such as nuclear operators, nuclear suppliers, academic institutions and political institutions. The specific approach will vary from one country to another and will depend on various factors, e.g. the objectives of the national nuclear program, the existing nuclear infrastructure (if any, e.g. legal framework, educational institutions), the existence (and possibly maturity) of a nuclear industry, the selected GEN III+ technology and the related local supply chain, as well as the integration of national institutions into international networks. The paper provides a systematic overview of the dimensions to be considered as well as the various options and development paths available, and the factors determining the selection process for a specific national approach fusing the efforts of authorities, utilities, education providers and industry. The commitment of industry is illustrated by presenting some examples from recent activities in which AREVA is involved, such as partnerships with academic institutions in Germany, Poland, or Slovakia. Furthermore, as international networks will play an increasingly important role for human resources development, AREVA's participation in international educational associations like ENEN (European Nuclear Education Network), or in international projects, e.g. those funded by the European Commission, is covered. This is assisted by AREVA's involvement in implementing a new methodology for training and job taxonomy (ECVET), supporting life-long learning and international mobility. Finally the paper draws some conclusions on different approaches, and provides some recommendations for future human resources development activities. (authors)

Principal regulations of the Decommissioning Conception of the operating NPPs in Ukraine

International Nuclear Information System (INIS)

Litvins'kij, L.L.; Lobach, Yu.M.; Rusyinko, P.M.

2004-01-01

The paper contains the review of principal regulations of the Decommissioning Conception of the operating NPPs in Ukraine. There are presented the results of analysis based on the consideration of three possible scenarios of the nuclear power complex development corresponding to the different terms of the unit's lifetime extension. Concept decommissioning decisions are established; the results of strategic planning and long-term forecast of decommissioning activity on the operating NPPs in Ukraine are presented too

Availability and its correlation with the cost situation of NPPs and an advanced reactor as a possible future solution

International Nuclear Information System (INIS)

Fuchs, M.

1998-01-01

The availability depends from a lot of factors, especially from design approaches. The way for the development of design approaches for attaining the safety requirements with more redundancy and without diversity of the systems, especially of safety systems, in NPPs in the past is not acceptable for the future because of cost reasons. It is necessary to find new technical ways to achieve a better availability, reliability and safety by lower costs. The simplification of safety systems by using passive systems may be a solution in the future. The development of a new boiling water reactor BWR 1000 in Germany by Siemens which is sponsored by German utilities and supported by various European partners can be named as such example. (author)

Mound technology for isolation of decommissioned NPPs

International Nuclear Information System (INIS)

Korovkin, S.V.; Tutunina, E.V.

2012-01-01

The problem of NPPs' decommissioning calls for immediate attention. Today the most socially acceptable solution is green lawn, but due to the difficulty of this option, alternative solutions are being developed as well. The authors believe that the option is isolation of shut-down NPPs in-situ by covering them with layers of inert materials, resulting in the formation of a mound. In this case the reactor building itself becomes a repository that holds solid radioactive wastes generated over the time of unit operation. Spent fuel is to be shipped out of the site. A layer of inert materials several meters thick guarantees secure protection against ionising radiation and unauthorised access to the structures in isolation. The structures inside the mound are also inaccessible to ground waters. The green mound concept is considered as well as the mound backfilling technology which excludes collapse under the weight of inert materials that form the mound. It is pointed out that never-completed Voronezh nuclear heating plant is the optimal object for field-testing of the suggested technology [ru

Risk based definition of TS requirements for NPPs with WWER-1000 type reactor

International Nuclear Information System (INIS)

Morozov, V.; Tokmachev, G.

2000-01-01

The main regulations in safety related maintenance for NPPs in Russia are defined as a part of Technical Specifications (TSs). It includes limiting conditions for operation (surveillance requirements, allowed outage time, et.). In Russian practice the two levels of TSs are presented: general TSs that have been established as a master documents for similar designed NPPs and plant specific based on operation practice of each NPP unit. This paper presents a brief review of submissions to TS changes for NPPs with WWER type reactor were issued by AEP PSA team since 1988 year. Besides it provides an approach allows to estimate the complex affect on plant risk for both Limiting Conditions of Operation (LCO) and Surveillance Test Intervals (STI) based on relevant probabilistic tool (Minimal Cut Sets method and Marcov Chains methods). (author)

An Attentional Resources-effectiveness Measure in Complex Diagnostic Tasks in NPPs

Energy Technology Data Exchange (ETDEWEB)

Ha, Jun Su; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

2007-07-01

The main role of the human operators in main control rooms (MCRs) of nuclear power plants (NPPs) is generally to supervise and operate the system. The operator's tasks in NPPs are performed through a series of cognitive activities: monitoring the environment, detecting data or information, understanding and assessing the situation, diagnosing the symptoms, decision-making, planning responses, and implementing the responses. In NPPs, there are a lot of information sources that should be monitored but the operators have only limited capacity of attention and memory. Because it is impossible to monitor all information sources, the operators continuously decide where to allocate their attentional resources. This kind of cognitive skill is called selective attention. In order for operators to effectively monitor, detect, and thus understand the state of a system, the operator should allocate their attentional resources to valuable information sources. Hence, the effectiveness of selective attention is expected to be able to reflect the effectiveness of monitoring, detection, and eventually understanding. In this study, an attentional resources effectiveness measure is proposed which based on cost benefit (or resource-effectiveness) principle.

An Attentional Resources-effectiveness Measure in Complex Diagnostic Tasks in NPPs

International Nuclear Information System (INIS)

Ha, Jun Su; Seong, Poong Hyun

2007-01-01

The main role of the human operators in main control rooms (MCRs) of nuclear power plants (NPPs) is generally to supervise and operate the system. The operator's tasks in NPPs are performed through a series of cognitive activities: monitoring the environment, detecting data or information, understanding and assessing the situation, diagnosing the symptoms, decision-making, planning responses, and implementing the responses. In NPPs, there are a lot of information sources that should be monitored but the operators have only limited capacity of attention and memory. Because it is impossible to monitor all information sources, the operators continuously decide where to allocate their attentional resources. This kind of cognitive skill is called selective attention. In order for operators to effectively monitor, detect, and thus understand the state of a system, the operator should allocate their attentional resources to valuable information sources. Hence, the effectiveness of selective attention is expected to be able to reflect the effectiveness of monitoring, detection, and eventually understanding. In this study, an attentional resources effectiveness measure is proposed which based on cost benefit (or resource-effectiveness) principle

Application of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors

Energy Technology Data Exchange (ETDEWEB)

Shvyryaev, Yu. V.; Morozov, V. B.; Kuchumov, A.Yu., E-mail: morozov@aep.ru [JSC Atomenergoproekt, Moscow (Russian Federation)

2014-10-15

The projects of new-generation NPPs equipped with VVER reactors are developed as projects the safety level of which is superior to that of NPPs that are currently in operation. The main design solutions adopted for implementing the defence-in-depth (DiD) concept in the projects of new-generation NPPs equipped with VVER reactors are briefly characterized in the paper. (author)

Seismic verification methods for structures and equipment of VVER-type and RBMK-type NPPs (summary of experiences)

International Nuclear Information System (INIS)

Masopust, R.

2003-01-01

The main verification methods for structures and equipment of already existing VVER-type and RBMK-type NPPs are briefly described. The following aspects are discussed: fundamental seismic safety assessment principles for VVER/RBMK-type NPPs (seismic safety assessment procedure, typical work plan for seismic safety assessment of existing NPPs, SMA (HCLPF) calculations, modified GIP (GIP-VVER) procedure, similarity of VVER/RBMK equipment to that included in the SQUG databases and seismic interactions

From AWE-GEN to AWE-GEN-2d: a high spatial and temporal resolution weather generator

Science.gov (United States)

Peleg, Nadav; Fatichi, Simone; Paschalis, Athanasios; Molnar, Peter; Burlando, Paolo

2016-04-01

A new weather generator, AWE-GEN-2d (Advanced WEather GENerator for 2-Dimension grid) is developed following the philosophy of combining physical and stochastic approaches to simulate meteorological variables at high spatial and temporal resolution (e.g. 2 km x 2 km and 5 min for precipitation and cloud cover and 100 m x 100 m and 1 h for other variables variable (temperature, solar radiation, vapor pressure, atmospheric pressure and near-surface wind). The model is suitable to investigate the impacts of climate variability, temporal and spatial resolutions of forcing on hydrological, ecological, agricultural and geomorphological impacts studies. Using appropriate parameterization the model can be used in the context of climate change. Here we present the model technical structure of AWE-GEN-2d, which is a substantial evolution of four preceding models (i) the hourly-point scale Advanced WEather GENerator (AWE-GEN) presented by Fatichi et al. (2011, Adv. Water Resour.) (ii) the Space-Time Realizations of Areal Precipitation (STREAP) model introduced by Paschalis et al. (2013, Water Resour. Res.), (iii) the High-Resolution Synoptically conditioned Weather Generator developed by Peleg and Morin (2014, Water Resour. Res.), and (iv) the Wind-field Interpolation by Non Divergent Schemes presented by Burlando et al. (2007, Boundary-Layer Meteorol.). The AWE-GEN-2d is relatively parsimonious in terms of computational demand and allows generating many stochastic realizations of current and projected climates in an efficient way. An example of model application and testing is presented with reference to a case study in the Wallis region, a complex orography terrain in the Swiss Alps.

Taxonomic dissection of the genus Micrococcus: Kocuria gen. nov., Nesterenkonia gen. nov., Kytococcus gen. nov., Dermacoccus gen. nov., and Micrococcus Cohn 1872 gen. emend.

Science.gov (United States)

Stackebrandt, E; Koch, C; Gvozdiak, O; Schumann, P

1995-10-01

The results of a phylogenetic and chemotaxonomic analysis of the genus Micrococcus indicated that it is significantly heterogeneous. Except for Micrococcus lylae, no species groups phylogenetically with the type species of the genus, Micrococcus luteus. The other members of the genus form three separate phylogenetic lines which on the basis of chemotaxonomic properties can be assigned to four genera. These genera are the genus Kocuria gen. nov. for Micrococcus roseus, Micrococcus varians, and Micrococcus kristinae, described as Kocuria rosea comb. nov., Kocuria varians comb. nov., and Kocuria kristinae comb. nov., respectively; the genus Nesterenkonia gen. nov. for Micrococcus halobius, described as Nesterenkonia halobia comb. nov.; the genus Nesterenkonia gen. nov. for Micrococcus halobius, described as Nesterenkonia halobia comb. nov.; the genus Dermacoccus gen. nov. for Micrococcus nishinomiyaensis, described as Dermacoccus nishinomiyaensis comb. nov.; and the genus Kytocossus gen. nov. for Micrococcus sedentarius, described as Kytococcus sedentarius comb. nov. M. luteus and M. lylae, which are closely related phylogenetically but differ in some chemotaxonomic properties, are the only species that remain in the genus Micrococcus Cohn 1872. An emended description of the genus Micrococcus is given [corrected].

Advantages of viscodampers for NPPs upgrading

International Nuclear Information System (INIS)

Reinsch, K.H.; Schwahn, K.J.; Podrouzek, J.

1993-01-01

Viscodampers GERB are the ideal components for seismic upgrading of flexible pipework systems of the existing operating NPPs, of WWER-440 type, namely in primary reactor part. There are cheap, maintenance-free, simple and their installation minimizes the support forces to the structures. The quoted attests are enclosed in this paper. The references for application on Bohunice NPP upgrading are positive, and they are used in Mochovce and Temelin NPP as well

Economic Evaluation of Long-term Operation of NPPs in Korea

International Nuclear Information System (INIS)

Lee, Kihyun; Kim, Taeryong; Jeong, Cheolwook

2015-01-01

It is inevitable for Korean government to establish the energy policy which can support the energy security and independence since Korea depends on approximately 97% of energy resources from abroad. We selected nuclear power plant to overcome the problem. Since Kori unit 1 began operating as a first nuclear power plant, nuclear power generation has been played a big role in providing about 30% of total electricity supply in Korea. Many researchers and economists have already assessed about safety and economic aspects of the nuclear power generation. This paper will deal with the economic benefits for the contribution of nuclear power generation especially long-term operation of NPPs to the Korean society. In this paper, the economic analysis of the LTO for the existing power plant less than and equal to 1,000MW compared to no extension was investigated. The selected durations of LTO are 10 years, 20 years, and 30 years beyond design life. The result from the analysis is that LTO of NPPs is more beneficial than observance of its design life. In the aspects of utility's electricity sales increase and reducing the new construction of APR1400 NPPs with cost savings, LTO is one of the best option in order to provide electric energy with Korean society

Safeguard management for operation security in nuclear power plants (NPPs)

International Nuclear Information System (INIS)

Woo, Tae-Ho; Lee, Un-Chul

2011-01-01

Safeguard modeling is conducted for the successful operations in the nuclear power plants (NPPs). The characteristics of the secure operation in NPPs are investigated using the network effect method which is quantified by the Monte-Carlo algorithm. Fundamentally, it is impossible to predict the exact time of a terror incident. So, the random sampling for the event frequency is a reasonable method, including the characteristics of network effect method such as the zero-sum quantification. The performance of operation with safeguard is the major concern of this study. There are three kinds of considerations as the neutronics, thermo-hydraulics, and safeguard properties which are organized as an aspect of safeguard considerations. The result, therefore, can give the stability of the operations when the power is decided. The maximum value of secure operation is 12.0 in the third month and the minimum value is 1.0 in the 18th and 54th months, in a 10 years period. Thus, the stability of the secure power operation increases 12 times higher than the lowest value according to this study. This means that the secure operation is changeable in the designed NPPs and the dynamical situation of the secure operation can be shown to the operator.

Servicing NPPs in Japan, Korea and Taiwan

International Nuclear Information System (INIS)

Bohmann, W.; Poetz, F.

1991-01-01

More than 45 comparable orders (for equipment or services ) have been carried out in Japan, Korea and Taiwan by ABB Reaktor since 1982. Recently contracts to deliver inspection and repair equipment for the core baffle former bolts of Japanese NPPs, and in 1990, a contract to clean two steam generators in Korea, together with Pacific Nuclear Services, USA, were won. 2 figs

Organisational factors important to the safe operation of NPPs

International Nuclear Information System (INIS)

Frischknecht, Albert; Baumont, Genevieve

2000-01-01

The purpose of this paper is to present the achievements of a group of human factor specialists known as Expanded Task Force on Human Factors (ETF). ETF is part of the Principal Working Group No.1 (PWG1) on 'Operating Experience and Human Factors' of the Committee on Nuclear Safety Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). Today, as shown by incident analysis, technology is so far developed that human behaviour and organisational deficiencies can contribute to a major part of the root causes of incidents in nuclear power plants. The influence of the organisation on the safe behaviour and performance of individuals is recognised as a relevant issue for the safety of nuclear power plants (NPPs). The need for an up-to-date basis of knowledge in this area was recognised by CSNI and therefore the ETF organised a workshop, in Switzerland, in 1998, on Organisational Factors. During the workshop, different aspects of organisational influences on the safe operation of NPPs were discussed and twelve important organisational factors concerning safety related activities in a NPP were identified. The result of the workshop is summarised in a state-of-the-art Report (SOAR) 'Identification and Assessment of Organisational Factors Related to the Safety of NPPs' issued by the OECD/NEA. The present paper gives an overview on the main findings of the workshop and conclusions concerning the evaluation of organisational factors. (author)

Ageing of instrumentation and control cables in NPPs

International Nuclear Information System (INIS)

Santhosh; Ghosh, A.K.; Fernandes, B.G.

2011-01-01

Cables are vital components of instrumentation and control (I and C) systems in nuclear power plants (NPPs). The polymer materials used for insulation and jacket materials for electric cables are susceptible to ageing and degradation mechanisms caused by exposure to many of the stressors encountered in NPP service conditions. Ageing of components in NPP is an important concern since the degradation caused by ageing can impact the performance of susceptible equipment. This is of particular concern for safety-related equipment since the failure due to ageing can compromise the continued safe operation of the plant. The state-of-the art for incorporating cable ageing effects into probabilistic safety assessment (PSA) is still evolving and in the reliability assessment of NPP systems, the ageing effect of electrical cable is generally not considered and also, there is no standard method exists for incorporating such ageing effects into the system reliability. Therefore, identification and quantification of ageing of electrical cables is very much essential for an accurate prediction of system reliability for PSA applications. The objective of this study is to develop a methodology to assess the susceptibility of polymeric cable insulation to various ageing mechanisms; and the state of the insulation at any chosen time in order to evaluate the remaining life-time of operating cables in NPPs. This paper presents the state-of-the-art tools and techniques for insulation condition assessment, insulation life prediction methodologies, equipment qualification guidelines, and ageing management programs relating to I and C cables in NPPs. An approach to calculate the insulation resistance subjecting to different stressors has also been presented in this paper. (author)

Design and development of innovative passive valves for Nuclear Power Plant applications

Energy Technology Data Exchange (ETDEWEB)

Sapra, M.K., E-mail: sapramk@barc.gov.in; Kundu, S.; Pal, A.K.; Vijayan, P.K.; Vaze, K.K.; Sinha, R.K.

2015-05-15

Highlights: • Passive valves are self-acting valves requiring no external energy to function. • These valves have been developed for Advanced Heavy Water Reactor (AHWR) of India. • Passive valves are core components of passive safety systems of the reactor. • Accumulator Isolation Passive Valve (AIPV) has been developed and tested for ECSS. • AIPV provided passive isolation and flow regulation in ECCS of Integral Test Loop. - Abstract: The recent Fukushima accident has resulted in an increased need for passive safety systems in upcoming advanced reactors. In order to enhance the global contribution and acceptability of nuclear energy, proven evidence is required to show that it is not only green but also safe, in case of extreme natural events. To achieve and establish this fact, we need to design, demonstrate and incorporate reliable ‘passive safety systems’ in our advanced reactor designs. In Nuclear Power Plants (NPPs), the use of passive safety systems such as accumulators, condensing and evaporative heat exchangers and gravity driven cooling systems provide enhanced safety and reliability. In addition, they eliminate the huge costs associated with the installation, maintenance and operation of active safety systems that require multiple pumps with independent and redundant electric power supplies. As a result, passive safety systems are preferred for numerous advanced reactor concepts. In current NPPs, passive safety systems which are not participating in day to day operation, are kept isolated, and require a signal and external energy source to open the valve. It is proposed to replace these valves by passive components and devices such as self-acting valves, rupture disks, etc. Some of these innovative passive valves, which do not require external power, have been recently designed, developed and tested at rated conditions. These valves are proposed to be used for various passive safety systems of an upcoming Nuclear Power Plant being designed

A Proposal for a Methodology to Develop a Cyber-Attack Penetration Test Scenario Including NPPs Safety

Energy Technology Data Exchange (ETDEWEB)

Lee, In Hyo [KAIST, Daejeon (Korea, Republic of); Son, Han Seong [Joongbu Univ., Geumsan (Korea, Republic of); Kim, Si Won [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of); Kang, Hyun Gook [Rensselaer Polytechnic Institute, Troy (United States)

2016-10-15

Penetration test is a method to evaluate the cyber security of NPPs; so, this approach was performed in some studies. Because they focused on vulnerability finding or test bed construction, scenario based approach was not performed. However, to test the cyber security of NPPs, a proper test scenario should be needed. Ahn et al. developed cyber-attack scenarios but those scenarios couldn't be applied in penetration test because they developed the scenarios based on past incidents of NPPs induced by cyber-attack. That is, those scenarios only covered scenarios which were happened before; so, they couldn't cover other various scenarios and couldn't reflect them into a penetration test. In this study, a method to develop a cyber-attack penetration test scenario of NPPs especially focused on safety point of view is suggested. To evaluate the cyber security of NPPs, penetration test can be a possible way. In this study, a method to develop a penetration test scenario was explained. Especially, the goal of hacker was focused on nuclear fuel integrity deterioration. So, in the methodology, Level 1 PSA results were utilized to reflect plant safety into the security. From the PSA results, basic event was post processed and possible cyber-attacks were reviewed with vulnerabilities of digital control system.

A Proposal for a Methodology to Develop a Cyber-Attack Penetration Test Scenario Including NPPs Safety

International Nuclear Information System (INIS)

Lee, In Hyo; Son, Han Seong; Kim, Si Won; Kang, Hyun Gook

2016-01-01

Penetration test is a method to evaluate the cyber security of NPPs; so, this approach was performed in some studies. Because they focused on vulnerability finding or test bed construction, scenario based approach was not performed. However, to test the cyber security of NPPs, a proper test scenario should be needed. Ahn et al. developed cyber-attack scenarios but those scenarios couldn't be applied in penetration test because they developed the scenarios based on past incidents of NPPs induced by cyber-attack. That is, those scenarios only covered scenarios which were happened before; so, they couldn't cover other various scenarios and couldn't reflect them into a penetration test. In this study, a method to develop a cyber-attack penetration test scenario of NPPs especially focused on safety point of view is suggested. To evaluate the cyber security of NPPs, penetration test can be a possible way. In this study, a method to develop a penetration test scenario was explained. Especially, the goal of hacker was focused on nuclear fuel integrity deterioration. So, in the methodology, Level 1 PSA results were utilized to reflect plant safety into the security. From the PSA results, basic event was post processed and possible cyber-attacks were reviewed with vulnerabilities of digital control system

Analytical and Experimental Feasibility Study of Combined OTEC on NPPs

Energy Technology Data Exchange (ETDEWEB)

Cho, Jeongtae; Oh, Kyemin; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of); Jung, Hoon [KEPCO Research Institute, Daejeon (Korea, Republic of)

2013-05-15

The concept of the Combined Ocean Thermal Energy Conversion (Combined OTEC) needs to study. Combined OTEC uses exhausted steam on Nuclear Power Plants (NPPs) as heat source instead surface water. Exhausted steam extracted from condenser evaporates working fluid of Combined OTEC at heat exchanger (Hx-W). Essential calculation for conceptual design of Combined OTEC was already performed and presented before. However, the technical issue whether sufficient extraction of exhausted steam from high degree of vacuum of condenser to Hx-W can be supplied or not was unclear, which is significant to continue a demonstration program. In this study, so, we calculated the rate of extracted steam to evaluate whether sufficient steam can be extracted using RELAP code. In aspect of implementation of Combined OTEC, confirmation of sufficient flow of exhausted steam into Hx-W is the starting point of research. As the result of RELAP calculation, we confirmed that exhausted steam would flow into Hx-W. Considering the amount of exhausted steam in NPPs which is 1000 MWe and has 36 % of efficiency, 9 % of flow rate to Hx-W is means that 160 MWt of heat can be available as heat source of Combined OTEC. Using this, it can be possible to improve efficiency of aged NPPs and can compensate power loss caused by increase of circulation water temperature particularly in summer season.

NPPs of CEZ in 2005 year of CEZ group improvement

International Nuclear Information System (INIS)

Linhart, Z.

2006-01-01

In this presentation author deals with NPPs of CEZ, a.s. group in 2005 year. Structure of the CEZ, a.s., electricity production in NPP Temelin and NPP Dukovany and other exploitation data are presented.

GenBank

OpenAIRE

Benson, Dennis A.; Karsch-Mizrachi, Ilene; Lipman, David J.; Ostell, James; Rapp, Barbara A.; Wheeler, David L.

2002-01-01

The GenBank sequence database incorporates publicly available DNA sequences of more than 105 000 different organisms, primarily through direct submission of sequence data from individual laboratories and large-scale sequencing projects. Most submissions are made using the BankIt (web) or Sequin programs and accession numbers are assigned by GenBank staff upon receipt. Data exchange with the EMBL Data Library and the DNA Data Bank of Japan helps ensure comprehensive worldwide coverage. GenBank...

Development project for a residual life evaluation system in LWR NPPs

International Nuclear Information System (INIS)

Hervia, F.; Francia, L.

1995-01-01

Economic and safety factors have stimulated the interest of Spanish NPPs towards the optimisation of NPP Residual Life Management, and consequently the need to have access to tools to support such management. This requirement has been the subject of a project, the main objectives of which are the identification of the most significant ageing factors in NPPs and their corresponding parameters, and the development of an associated integrated monitoring system. Work on the project was started by UNESA in September 1992 and is partly financed from PIE funds. This paper gives a general description of the objectives and activities of Phase 1, the Definition of the Core Project, which is nearing completion, and Phase 2, the Application of the Integrated System in a Pilot Plant. Phase 1 has confirmed the technical feasibility of the system and its suitability as a tool for the continuous evaluation of the plant condition. Furthermore, it has raised issues of great interest to NPPs. The results and conclusions of Phase 1 are currently being used to define the most suitable scope for the development and implementation of the system in the pilot plant (Phase 2), so that all the main functions of the system are tested without incurring unnecessary costs

Osmanlı’da Bir Darbe ve Tahlili: Genç Osman Örneği A Coup in Ottoman Empire And Its Analysis: Genç Osman Example

Directory of Open Access Journals (Sweden)

Hasan YAŞAROĞLU

2013-09-01

Full Text Available The New Order (Nizam-ı Cedit movements started in period of Selim The third (III. Selim of Otttoman sultans, is an important step taken toward westernization. Some sultans in last period of Ottoman Empire have also strived to take similar steps. There are records of initiation for reform movements even during period of Mustafa The Third (III. Mustafa, father of Selim The Third (III. Selim. When we went back to more in time, The Lale Devri (The Tulip Period emerges. The Tulip Period (Lale Devri despite the term being at the forefront of pleasure and deligth, some steps have been taken at this time in the direction of the westernization/renewal. The period of Sultan Osman The Second (II Osman forms the first steps taken toward renewal. Unfortunately, an uprising movement has ended the mentioned period above. Both this first Ottoman innovation movement and the first Ottoman insurrection that terminated the innovation are of importance in terms of being sample for the next ones. After these events, most of the reform movements, which emerged in the Ottoman Empire, have shared the same fate as Genç Osman reform movement.Upon his uncle Mustafa The First (I. Mustafa being jailed, Genç Osman (Young Othman became the Ottoman Sultan, but Othman has soon attracted the wrath of Janissaries and the Ulema due to his tough attitude. This hatred increased in time when Sultan Othman personally assumed the supreme commander in chief of army and decided to go to Mecca for pilgimage and eventually turned into a rebellion. The coup that was started under the leadership of Janissary and Sipahi units, and the rebels, strengthened the next day with the participation of scholars, relied on the Palace’s door to inform their demands. Genç Osman (Young Othman initially rejected the demands of the rebels, but he but was unable to sustain his attitude over the time. The rebels, at the end, entered the Palace, and have taken the Sultan’s uncle Mustafa The first (I

GenBank

Data.gov (United States)

U.S. Department of Health & Human Services — GenBank is the NIH genetic sequence database, an annotated collection of all publicly available DNA sequences. GenBank is designed to provide and encourage access...

Component reliability analysis for development of component reliability DB of Korean standard NPPs

International Nuclear Information System (INIS)

Choi, S. Y.; Han, S. H.; Kim, S. H.

2002-01-01

The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA and Risk Informed Application. We have performed a project to develop the component reliability DB and calculate the component reliability such as failure rate and unavailability. We have collected the component operation data and failure/repair data of Korean standard NPPs. We have analyzed failure data by developing a data analysis method which incorporates the domestic data situation. And then we have compared the reliability results with the generic data for the foreign NPPs

The passive system for reflooding of the VVER reactor core from the second-stage hydro-accumulators: design and basic design solutions

International Nuclear Information System (INIS)

Alexandr D Efanov; Sergey G Kalyakin; Andrey V Morozov; Oleg V Remizov; Vladimir M Berkovich; Victor N Krushelnitskiy; Vladimir G Peresadko; Yuri G Dragunov; Alexey K Podshibyakin; Sergey I Zaitcev

2005-01-01

Full text of publication follows: The fundamental difference in the safety assurance of the operating NPPs and those under design implies that the safety in the existing NPPs is achieved by energy-dependent (active) systems and depends on the proficiency of attending personnel. To provide safety, the new NPP designs use the physical processes proceeding in the facility without power supply; and they are unaffected by human errors. As to the safety level, the design of the new generation nuclear power plant NPP-92 relates to the class of the improved NPPs; and it applies a principle of diversity in the structure of systems responsible for critical safety functions. In accordance with the above-mentioned safety concept, the design development required a complex of experimental investigations and numerical modeling to be conducted. Among the passive safety systems of the NPP with RP-392 is the system of the second stage hydro-accumulators (GE-2). The system of the second-stage hydro-accumulators consists of four groups of hydro-accumulating tanks with a total coolant volume of 960 m 3 . The system is intended for the core flooding with coolant during 24 hours. In each group of the hydro-accumulators, the graded coolant flowrate is provided, which depends on residual heat in the reactor. The special check valves are tuned to open at the pressure drop in the circuit below 1.5 MPa. The paper presents the thermalhydraulic substantiation of the serviceability of the second-stage hydro-accumulators system for passive heat removal from the VVER reactor core and the basic design solutions on the GE-2 system. (authors)

Seismic stability of NPPs in Eastern Europe. Final report from June 1993 - June 1994

International Nuclear Information System (INIS)

Ambriashvili, Y.K.

1995-01-01

The present work was fulfilled within the contract between IAEA and 'Atomenegroproject' Institute of the Russian Federation. The program of the work fulfilled within the period from June 1993 till June 1994 was as follows: review and comments of the standards related to aseismic design of the structure and components; aseismic classification of main safety systems and components by function of WWER NPPs; response spectrum which was developed for design of WWER NPPs; comparison of Western and the Russian standards and codes related to aseismic design of NPPs. The general requirements for aseismic designed constructions, comments on the main important points of seismic loads, calculation of the seismic loads, methodology of design and test of the equipment and electrical systems are presented in the work. The main constructions and equipment for NPP WWER-440 provided the functions of plant during and after the earthquakes are also listed. Methodology of calculation and selection of response spectrum for design of WWER NPPs. The comparative analysis of the Western and the Russian Norms are reviewed. The main conclusions of the present work are as follows: General principal stages of the methods and approaches of the design, investigations and testing are almost identified with IAEA and Western approaches. Recommendations corresponding with the IAEA and Western standards should be consumed in a new version of codes of aseismic design of NPPs that are working out now in the Russian Federation. It is connected with maximum acceleration, response spectra, time histories, damping factor and etc. Meanwhile 'Atomenergoproject' now has possibility to fulfil calculations of soil- structure-equipment systems and carry out full scale tests of the equipment on the components seismic platform in accordance with the high level of the technical requirements

Seismic stability of NPPs in Eastern Europe. Final report from June 1993 - June 1994

Energy Technology Data Exchange (ETDEWEB)

Ambriashvili, Y K [Atomenergoproject, Moscow (Russian Federation)

1995-07-01

The present work was fulfilled within the contract between IAEA and 'Atomenegroproject' Institute of the Russian Federation. The program of the work fulfilled within the period from June 1993 till June 1994 was as follows: review and comments of the standards related to aseismic design of the structure and components; aseismic classification of main safety systems and components by function of WWER NPPs; response spectrum which was developed for design of WWER NPPs; comparison of Western and the Russian standards and codes related to aseismic design of NPPs. The general requirements for aseismic designed constructions, comments on the main important points of seismic loads, calculation of the seismic loads, methodology of design and test of the equipment and electrical systems are presented in the work. The main constructions and equipment for NPP WWER-440 provided the functions of plant during and after the earthquakes are also listed. Methodology of calculation and selection of response spectrum for design of WWER NPPs. The comparative analysis of the Western and the Russian Norms are reviewed. The main conclusions of the present work are as follows: General principal stages of the methods and approaches of the design, investigations and testing are almost identified with IAEA and Western approaches. Recommendations corresponding with the IAEA and Western standards should be consumed in a new version of codes of aseismic design of NPPs that are working out now in the Russian Federation. It is connected with maximum acceleration, response spectra, time histories, damping factor and etc. Meanwhile 'Atomenergoproject' now has possibility to fulfil calculations of soil- structure-equipment systems and carry out full scale tests of the equipment on the components seismic platform in accordance with the high level of the technical requirements.

NPPs Secondary Circuit Piping Wall-Thinning Management in China

International Nuclear Information System (INIS)

Zhong Zhimin; Li Jinsong; Zheng Hui

2012-01-01

Since 1980s, secondary circuit piping wall-thinning incidents happened in nuclear power plants (NPPs) worldwide. Particularly Surry 2 and Mihama 3 accidents resulted from flow-accelerated corrosion (FAC), unplanned outage, huge fatalities and economic loss pushed whole industry to pay more attention on the wall-thinning problem.

Development of source term PIRT of Fukushima Daiichi NPPs accident

International Nuclear Information System (INIS)

Suehiro, S.; Okamoto, K.

2017-01-01

The severe accident evaluation committee of AESJ (Atomic Energy Society of Japan) developed the thermal hydraulic PIRT (Phenomena Identification and Ranking Table) and the source term PIRT based on findings during the Fukushima Daiichi NPPs accident. These PIRTs aimed to explore the debris distribution and the current condition in the NPPs with high accuracy and to extract higher priority from the aspect of the sophistication of the analytical technology to predict the severe accident phenomena by the code. The source term PIRT was divided into 3 phases for the time domain and 9 categories for the spatial domain. The 68 phenomena were extracted and the importance from viewpoint of the source term was ranked through brainstorming and discussion. This paper describes the developed source term PIRT list and summarized the high ranked phenomena in each phase. (author)

Radiological Consequences Analysis for Abnormal Condition on NPPs 1000 MWe by Using Radcon Model

International Nuclear Information System (INIS)

Pande Mande Udiyani; Sri Kuntjoro

2009-01-01

The operation of NPPs (Nuclear Power Plants) in Indonesia to anticipates rare of energy will generate various challenges, especially about NPPs safety. So installation organizer of nuclear must provide scientific argument to safety NPPs, one of them is by providing document of safety analysis. Calculation of radiological consequences after abnormal condition applies on generic PWR-1000 power reactor. Calculation is done by using program package RadCon (Radiological Consequences Model), with postulate condition is based on DBA (Design Basis Accident). Calculation of dispersion of radionuclide concentration is using PC-COSYMA as input data for RadCon. Simulation for radiological consequences analysis uses by site data sample. Analysis result shows that maximum receiving of internal - externals radiological consequence for short term and long-term below 1 km radius area is below the limit acceptably effective dose for a member of the public as a result of an accident which should not exceed 5 mSv (ICRP 1990). (author)

Coordinated research programme on safety of RBMK type NPPs in relation to external events. V. 1. Working material

International Nuclear Information System (INIS)

1999-01-01

The present volume is a collection of progress reports which have been submitted within the scope of the CRP on safety of RBMK type NPPs in relation to external events including seismic related papers and man-induced events (explosions and airplane crash). It includes papers concerned with experience related to RBMK equipment testing and calculations of seismic resistance, soil-structure interactions analysis, safety assurance, aircraft impact qualification and other external events for RBMK type NPP, seismic stability of NPPs in Eastern Europe, probabilistic assessment of NPP safety under aircraft impact, dynamic analysis of NPPs, screening of external hazards for NPP

An Approach to Human Error Hazard Detection of Unexpected Situations in NPPs

Energy Technology Data Exchange (ETDEWEB)

Park, Sangjun; Oh, Yeonju; Shin, Youmin; Lee, Yong-Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Fukushima accident is a typical complex event including the extreme situations induced by the succeeding earthquake, tsunami, explosion, and human errors. And it is judged with incomplete cause of system build-up same manner, procedure as a deficiency of response manual, education and training, team capability and the discharge of operator from human engineering point of view. Especially, the guidelines of current operating NPPs are not enough including countermeasures to the human errors at the extreme situations. Therefore, this paper describes a trial to detect the hazards of human errors at extreme situation, and to define the countermeasures that can properly response to the human error hazards when an individual, team, organization, and working entities that encounter the extreme situation in NPPs. In this paper we try to propose an approach to analyzing and extracting human error hazards for suggesting additional countermeasures to the human errors in unexpected situations. They might be utilized to develop contingency guidelines, especially for reducing the human error accident in NPPs. But the trial application in this study is currently limited since it is not easy to find accidents cases in detail enough to enumerate the proposed steps. Therefore, we will try to analyze as more cases as possible, and consider other environmental factors and human error conditions.

An Approach to Human Error Hazard Detection of Unexpected Situations in NPPs

International Nuclear Information System (INIS)

Park, Sangjun; Oh, Yeonju; Shin, Youmin; Lee, Yong-Hee

2015-01-01

Fukushima accident is a typical complex event including the extreme situations induced by the succeeding earthquake, tsunami, explosion, and human errors. And it is judged with incomplete cause of system build-up same manner, procedure as a deficiency of response manual, education and training, team capability and the discharge of operator from human engineering point of view. Especially, the guidelines of current operating NPPs are not enough including countermeasures to the human errors at the extreme situations. Therefore, this paper describes a trial to detect the hazards of human errors at extreme situation, and to define the countermeasures that can properly response to the human error hazards when an individual, team, organization, and working entities that encounter the extreme situation in NPPs. In this paper we try to propose an approach to analyzing and extracting human error hazards for suggesting additional countermeasures to the human errors in unexpected situations. They might be utilized to develop contingency guidelines, especially for reducing the human error accident in NPPs. But the trial application in this study is currently limited since it is not easy to find accidents cases in detail enough to enumerate the proposed steps. Therefore, we will try to analyze as more cases as possible, and consider other environmental factors and human error conditions

Highly Reliable Power and Communication System for Essential Instruments under a Severe Accident of NPPs

Energy Technology Data Exchange (ETDEWEB)

Yoo, S. J.; Choi, B. H.; Jung, S. Y.; Rim, Chun T. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2013-10-15

In this paper, three survivable strategies to overcome the problems listed above are proposed for the essential instruments under the severe accident of NPPs. First, wire/wireless multi power systems are adopted to the essential instruments for continuous power supply. Second, wire/wireless communication systems are proposed for reliable transmission of measuring information among instruments and operators. Third, a physical protection system such as a harness and a heat isolation box is introduced to ensure operable conditions for the proposed systems. In this paper, a highly reliable strategy, which consists of wire/wireless multi power and communication systems and physical protection system is proposed to ensure the survival of the essential instruments under harsh external conditions. The wire/wireless multi power and communication systems are designed to transfer power and data in spite of the failure of conventional wired systems. The physical protection system provides operable environments to the instruments. Therefore, the proposed system can be considered as a candidate of practical and urgent remedy for NPPs under the severe accident. After the Fukushima nuclear accident, survivability of essential instruments has been emphasized for immediate and accurate response. The essential instruments can measure environment conditions such as temperature, pressure, radioactivity and corium behavior inside nuclear power plants (NPPs) under a severe accident. Access to the inside of NPPs is restricted to human beings because of hazardous environment such as high radioactivity, high temperature and high pressure. Thus, monitoring the inside of NPPs is necessary for avoiding damage from the severe accident. Even though there were a number of instruments in Fukushima Daiichi NPP, they failed to obtain exact monitoring information. According to the details of the Fukushima nuclear accident, following problems can be counted as strong candidates of this instruments

Highly Reliable Power and Communication System for Essential Instruments under a Severe Accident of NPPs

International Nuclear Information System (INIS)

Yoo, S. J.; Choi, B. H.; Jung, S. Y.; Rim, Chun T.

2013-01-01

In this paper, three survivable strategies to overcome the problems listed above are proposed for the essential instruments under the severe accident of NPPs. First, wire/wireless multi power systems are adopted to the essential instruments for continuous power supply. Second, wire/wireless communication systems are proposed for reliable transmission of measuring information among instruments and operators. Third, a physical protection system such as a harness and a heat isolation box is introduced to ensure operable conditions for the proposed systems. In this paper, a highly reliable strategy, which consists of wire/wireless multi power and communication systems and physical protection system is proposed to ensure the survival of the essential instruments under harsh external conditions. The wire/wireless multi power and communication systems are designed to transfer power and data in spite of the failure of conventional wired systems. The physical protection system provides operable environments to the instruments. Therefore, the proposed system can be considered as a candidate of practical and urgent remedy for NPPs under the severe accident. After the Fukushima nuclear accident, survivability of essential instruments has been emphasized for immediate and accurate response. The essential instruments can measure environment conditions such as temperature, pressure, radioactivity and corium behavior inside nuclear power plants (NPPs) under a severe accident. Access to the inside of NPPs is restricted to human beings because of hazardous environment such as high radioactivity, high temperature and high pressure. Thus, monitoring the inside of NPPs is necessary for avoiding damage from the severe accident. Even though there were a number of instruments in Fukushima Daiichi NPP, they failed to obtain exact monitoring information. According to the details of the Fukushima nuclear accident, following problems can be counted as strong candidates of this instruments

Quantitative evaluation of fault coverage for digitalized systems in NPPs using simulated fault injection method

International Nuclear Information System (INIS)

Kim, Suk Joon

2004-02-01

Even though digital systems have numerous advantages such as precise processing of data, enhanced calculation capability over the conventional analog systems, there is a strong restriction on the application of digital systems to the safety systems in nuclear power plants (NPPs). This is because we do not fully understand the reliability of digital systems, and therefore we cannot guarantee the safety of digital systems. But, as the need for introduction of digital systems to safety systems in NPPs increasing, the need for the quantitative analysis on the safety of digital systems is also increasing. NPPs, which are quite conservative in terms of safety, require proving the reliability of digital systems when applied them to the NPPs. Moreover, digital systems which are applied to the NPPs are required to increase the overall safety of NPPs. however, it is very difficult to evaluate the reliability of digital systems because they include the complex fault processing mechanisms at various levels of the systems. Software is another obstacle in reliability assessment of the systems that requires ultra-high reliability. In this work, the fault detection coverage for the digital system is evaluated using simulated fault injection method. The target system is the Local Coincidence Logic (LCL) processor in Digital Plant Protection System (DPPS). However, as the LCL processor is difficult to design equally for evaluating the fault detection coverage, the LCL system has to be simplified. The simulations for evaluating the fault detection coverage of components are performed by dividing into two cases and the failure rates of components are evaluated using MIL-HDBK-217F. Using these results, the fault detection coverage of simplified LCL system is evaluated. In the experiments, heartbeat signals were just emitted at regular interval after executing logic without self-checking algorithm. When faults are injected into the simplified system, fault occurrence can be detected by

Specific features of auxiliary water supply at underground NPPs

International Nuclear Information System (INIS)

Pergamenshchik, B.K.; Pavlov, A.S.

1991-01-01

Specific features of auxiliary water supply systems for underground NPPs related to peculiarities of NPP basis equipment arrangement, are considered. Circulation water supply scheme, in which water cooling storage basin (cooling towers) with operational area corresponding to NPP power is on the surface and has traditional design, is proposed. Sufficiently high efficiency of the arrangement proposed is proved

Accident transient processes at NPPs with the WWER type reactors

International Nuclear Information System (INIS)

Bukrinskij, A.M.

1982-01-01

Thermal-physical and nuclear-physical transient processes at NPPs with the WWER type reactors during accidents with the main technological equipment failures and the accidents with loss of coolant in the primary and secondary coolant circuits are considered. Mathematical methods used for these processes modelling is described. Examples of concrete calculations for accidents with different failures are given. Comparative analysis of the results of dynamic tests at the Novo-Voronezh-3 reactor is presented. It is concluded that the modern NPP design is impossible without application of mathematical modelling methods. The mathematical modelling of transients is also necessary for proper and safe NPP operation. Mathematical modelling of accidents at NPPs is a comparatively new method of investigation. Its success and development are completely based on the progress in modern computer development. With their improvement the mathematical models will become more complicate and adequacy of real physical process representation by their means will increase

Economic evaluation of I and C modernization approach in NPPs

International Nuclear Information System (INIS)

Kang, Hyeon Tae; Sung, Chan Ho; Lee, Jae Ki

2009-01-01

Utilities have recently been debating the respective pros and cons of implementation of a multi-phase modernization during several normal outages versus a single major modernization implementation during a prolonged outage. We have studied these approaches and have been developing the basic design of NPPs I and C modernization since early 2008. As part of this study, analyses of the NPPs I and C systems were conducted and the need for upgrading the systems was raised. One of the primary concerns regarding the system modernization is a cost-benefit implementation, which will influence the modernization approach. From this viewpoint, the I and C modernization must consider economic factors such as I and C vendor cost, architecture engineering cost, installation cost, utility cost, and other transition costs such as training and procedure development. This paper presents a comparison study of economical aspects including cost evaluation between the aforementioned modernization implementations and suggests a solution for the I and C modernization approach. (author)

Continued efforts to improve the robustness of the French Gen II PWRs with respect to the risk of severe accidents. Safety assessment and research activities

International Nuclear Information System (INIS)

Raimond, E.; Bonnet, J.M.; Generino, G.; Dubreuil, M.; Pichereau, F.; Van Dorsselaere, J.P.

2012-01-01

In the context of post Fukushima accident, the paper presents the continuous efforts performed in France to upgrade progressively the French Gen II pressurised water reactors safety features in order to face the risks of any severe accident. It reminds some decisions taken after the TMI2 and the Chernobyl accidents and describes the situation in France before the Fukushima accident: -) progress done on severe accident consequences analysis thanks to recent research activities, -) improvement of Gen II PWRs safety features, in relation with the periodic safety review process, -) definition of higher safety levels requirement directly linked to the protection of population in the framework of Gen II PWRs long term operation. The last part of the paper comments carefully how the Fukushima accident will interfere on all these previous efforts to increase the Gen II PWRs robustness. The Fukushima accident clearly highlights a need of additional efforts to identify possible cliff edge effect in case of beyond design events (especially external events). The definition of additional accident management procedures and means to secure a reactor (or a site) whatever the conditions will be a major consequence for the French NPPs. In a second step, some complements on the existing defense-in-depth approach are now expected: additional requirements to define line of defense against adverse consequences of beyond design situations. The need for specific additional research activities after the Fukushima accident seems to be limited to some specific issues (for example spent fuel pool behaviour in case of long term loss of cooling). This paper is followed by the slides of the presentation

Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors

International Nuclear Information System (INIS)

Lap-Yan, C.; Wie, T. Y. C.

2009-01-01

The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a GEN IV direct-cycle gas-cooled fast reactor (GFR) which is based on the technology developments of the HTRs. Given the different criteria and design characteristics of the GFR, an approach different from that taken for the HTRs for passive DHR would have to be explored. Different design options based on maintaining core flow were evaluated by performing transient analysis of a depressurization accident using the system code RELAP5-3D. The study also reviewed the conceptual design of autonomous systems for shutdown decay heat removal and recommends that future work in this area should be focused on the potential for Brayton cycle DHRs.

Core Management of NPPs in China and Experience of Tianwan NPP

International Nuclear Information System (INIS)

Guohan, G.

2006-01-01

The Current Status of the NPPs in China; the Nuclear Power Development Plan till 2020; the Fuel Management and the Core Management Strategy of NPPs are briefly presented in this paper. The gained experience during construction of Taiwan NPP, new design features and major construction milestones of Taiwan NPP are also discussed. The full list of 21 non-conformance reports (NCR) submitted by Jiangsu Nuclear Power Company to NNSA during construction of Taiwan NPP is given. The main issues raised during FSAR review like: RP operation with incomplete number of primary loops; Sedimentation in the construction and piping of service water system; Location of postulated pipe break; Stratification analysis for surge line of pressurizer; Safety classification of equipment in primary circuit; Fire resistant capability of cable insulation; Fire Hazard Analysis; Optimization of protection against ionizing radiation ect. are also listed

Algoritmos genéticos locales

OpenAIRE

García-Martínez, Carlos; Lozano, Manuel

2007-01-01

Los Algoritmos Genéticos Locales son procedimientos que iterativamente re nan soluciones dadas. Su diferencia con procedimientos de mejora iterativa clásicos reside en el uso de operadores genéticos para realizar el re namiento. En este estudio presentamos un nuevo Algoritmo Genético Local Binario basado en un Algoritmo Genético Estacionario. Hemos comparado el Algoritmo Genético Local Binario con otros procedimientos de mejora iterativa de la literatura. Los res...

Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method

International Nuclear Information System (INIS)

Woo, Tae Ho

2012-01-01

It has been proposed to extend the life of nuclear power plants (NPPs) for the economic purpose. Especially, the primary systems in reactor are considered in the thermohydraulic and neutronic aspect, which is related to the safety system. The electric power and the lifespan of components are expressed as economic situation. In addition, political considerations are given by the presidential change and the nuclear non-proliferation characteristics. The dynamical investigation using system dynamics (SD) shows the effective time for the life extension of the NPPs by Monte-Carlo simulations. This non-linear algorithm is incorporated with the feedback loop of the event sequences. The expected event is related to the past event, which affects to the dynamical simulations of lifetime in the NPPs. In the conclusions, the safety guarantee as well as the economic profit in the re-use of long term operated power plants is presented, which is mentioned as the transient time between 2019 and 2021 in this paper. (orig.)

Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method

Energy Technology Data Exchange (ETDEWEB)

Woo, Tae Ho [Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering

2012-12-15

It has been proposed to extend the life of nuclear power plants (NPPs) for the economic purpose. Especially, the primary systems in reactor are considered in the thermohydraulic and neutronic aspect, which is related to the safety system. The electric power and the lifespan of components are expressed as economic situation. In addition, political considerations are given by the presidential change and the nuclear non-proliferation characteristics. The dynamical investigation using system dynamics (SD) shows the effective time for the life extension of the NPPs by Monte-Carlo simulations. This non-linear algorithm is incorporated with the feedback loop of the event sequences. The expected event is related to the past event, which affects to the dynamical simulations of lifetime in the NPPs. In the conclusions, the safety guarantee as well as the economic profit in the re-use of long term operated power plants is presented, which is mentioned as the transient time between 2019 and 2021 in this paper. (orig.)

New Solutions For Increasing Environmental Protection During Severe Accidents At Nuclear Power Plants

International Nuclear Information System (INIS)

Kulyukhin, Sergei A.; Mikheev, Nikolai B.; Falkovskii, Leo N.; Reshetov, Leo A.; Zvetkova, Marianna Ya.; Yagodkin, Ivan V.; Osipov, Viktor P.; Skvortsov, Sergei S.; Berkovich, Viktor M.; Taranov, Gennadii S.; Grigor'ev, Mikhail M.; Meshkov, Vladimir M.; Noskov, Andrei A.; Mitrofanov, Mikhail I.

2008-01-01

This paper reports new solutions for increasing environmental protection during severe accidents at NPPs. For NPPs with two protective shells and pressure release system such as WWER-1000 we suggest a new comprehensive, passive-mode environmental protection system of decontamination of the radioactive air-steam mixture from the containment and the inter-containment area, which includes the 'wet' stage (scrubbers, etc.), the 'dry' stage (sorption module), and also an ejector, which in a passive mode is capable of solving the multi-purpose task of decontamination of the air-steam mixture. For Russian WWER-440/230 NPPs we suggest three protection levels: 1) a jet-vortex condenser; 2) the spray system; 3) a sorption module. For modern designs of new generation NPPs, which do not provide for pressure release systems, we proposed a new passive filtering system together with the passive heat-removal system, which can be used during severe accidents in case all power supply units become unavailable. (authors)

New Solutions For Increasing Environmental Protection During Severe Accidents At Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kulyukhin, Sergei A.; Mikheev, Nikolai B. [Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Moscow (Russian Federation); Falkovskii, Leo N.; Reshetov, Leo A.; Zvetkova, Marianna Ya. [All-Russian Research Institute of Atomic Machine-Building, Moscow, Russia (Russian Federation); Yagodkin, Ivan V.; Osipov, Viktor P.; Skvortsov, Sergei S. [Institute of Physics and Power Engineering, Obninsk (Russian Federation); Berkovich, Viktor M.; Taranov, Gennadii S.; Grigor' ev, Mikhail M. [Institute ' Atomenergoproekt' , Moscow (Russian Federation); Meshkov, Vladimir M.; Noskov, Andrei A.; Mitrofanov, Mikhail I. [ROSENERGOATOM Concern, Moscow (Russian Federation)

2008-07-01

This paper reports new solutions for increasing environmental protection during severe accidents at NPPs. For NPPs with two protective shells and pressure release system such as WWER-1000 we suggest a new comprehensive, passive-mode environmental protection system of decontamination of the radioactive air-steam mixture from the containment and the inter-containment area, which includes the 'wet' stage (scrubbers, etc.), the 'dry' stage (sorption module), and also an ejector, which in a passive mode is capable of solving the multi-purpose task of decontamination of the air-steam mixture. For Russian WWER-440/230 NPPs we suggest three protection levels: 1) a jet-vortex condenser; 2) the spray system; 3) a sorption module. For modern designs of new generation NPPs, which do not provide for pressure release systems, we proposed a new passive filtering system together with the passive heat-removal system, which can be used during severe accidents in case all power supply units become unavailable. (authors)

Typical design/qualification acceptance criteria for newly installed pipelines and equipment components of VVER-type NPPs

International Nuclear Information System (INIS)

Masopust, R.

2003-01-01

This paper describes in general the typical design/qualification acceptance criteria and seismic acceptance criteria in particular that are applicable for important to safety newly installed pipelines and equipment components of VVER-type already existing NPPs, specifically during the design verification phase of this newly installed equipment. These criteria are currently used for VVER 440-213 and VVER 1000 NPPs in Czech Republic and in Slovakia. The similar criteria are also used in Hungary. (author)

Comparative evaluation of three cognitive error analysis methods through an application to accident management tasks in NPPs

International Nuclear Information System (INIS)

Jung, Won Dea; Kim, Jae Whan; Ha, Jae Joo; Yoon, Wan C.

1999-01-01

This study was performed to comparatively evaluate selected Human Reliability Analysis (HRA) methods which mainly focus on cognitive error analysis, and to derive the requirement of a new human error analysis (HEA) framework for Accident Management (AM) in nuclear power plants(NPPs). In order to achieve this goal, we carried out a case study of human error analysis on an AM task in NPPs. In the study we evaluated three cognitive HEA methods, HRMS, CREAM and PHECA, which were selected through the review of the currently available seven cognitive HEA methods. The task of reactor cavity flooding was chosen for the application study as one of typical tasks of AM in NPPs. From the study, we derived seven requirement items for a new HEA method of AM in NPPs. We could also evaluate the applicability of three cognitive HEA methods to AM tasks. CREAM is considered to be more appropriate than others for the analysis of AM tasks. But, PHECA is regarded less appropriate for the predictive HEA technique as well as for the analysis of AM tasks. In addition to these, the advantages and disadvantages of each method are described. (author)

Programming guidelines for computer systems of NPPs

International Nuclear Information System (INIS)

Suresh babu, R.M.; Mahapatra, U.

1999-09-01

Software quality is assured by systematic development and adherence to established standards. All national and international software quality standards have made it mandatory for the software development organisation to produce programming guidelines as part of software documentation. This document contains a set of programming guidelines for detailed design and coding phases of software development cycle. These guidelines help to improve software quality by increasing visibility, verifiability, testability and maintainability. This can be used organisation-wide for various computer systems being developed for our NPPs. This also serves as a guide for reviewers. (author)

Divergência genética entre genótipos de frangos tipo caipira

Directory of Open Access Journals (Sweden)

R. C. Veloso

2015-10-01

Full Text Available RESUMOObjetivou-se com este trabalho verificar a divergência genética entre sete genótipos de frangos tipo caipira da linhagem Redbro utilizando as características de desempenho por meio de técnicas de análise multivariada. Foram utilizados 840 pintos de um dia, machos, distribuídos em delineamento inteiramente ao acaso, dos seguintes genótipos: Caboclo, Carijó, Colorpak, Gigante Negro, Pesadão Vermelho, Pescoço Pelado e Tricolor. Após a consistência dos dados, foram avaliadas as seguintes variáveis: ganho em peso médio diário, consumo de ração médio diário e conversão alimentar, para os períodos: 1 a 28, 1 a 56, 1 a 70 e 1 a 84 dias de idade; peso corporal ao nascimento, aos 28, 56, 70 e aos 84 dias de idade. O desempenho dos genótipos foi avaliado por meio da análise de variância multivariada e da função discriminante linear de Fisher, usando os testes do maior autovalor de Roy e da união-interseção de Roy para as comparações múltiplas. O estudo da divergência genética foi feito por meio da análise por variáveis canônicas e pelo método de otimização de Tocher. Os genótipos Caboclo e Gigante Negro apresentaram médias canônicas diferentes dos demais genótipos. As duas primeiras variáveis canônicas explicaram 97,41% da variação entre os genótipos. A divergência genética entre os genótipos avaliados permitiu a formação de quatro grupos com os seguintes genótipos: grupo 1 - Colorpak; grupo 2 - Pesadão Vermelho e Pescoço Pelado; grupo 3 - Carijó e Tricolor; e grupo 4 - Caboclo e Gigante Negro.

Regulatory Analysis on the Safety Assessment of NPPs against Aircraft Crash

International Nuclear Information System (INIS)

Kim, Sang Yun; Park, Jong Seuk; Chung, Yun Suk; Jung, Rae Young

2011-01-01

Following the 9/11 terror, a new regulation (10CFR 50.150) was enacted in June 2009 in the United States mandating the assessment of new nuclear power plants (NPPs) against intentional aircraft crashes, along with a regulation (10CFR 50.54 (h)(h)) in March 2009 that requires the establishment of accident mitigation measures for NPPs in operation. The UAE requested that the Korean NPP (APR 1400) design meet the U.S.'s new requirements related to the intentional aircraft crash. During the UAE NPP contract bidding process, France claimed that the Korean NPP is vulnerable to aircraft crashes comparing with the French NPP (EPR). Under these international and domestic environments, the necessity to establish a domestic regulation concerning the intentional aircraft crash was raised. This paper proposes a draft regulatory position on this issue through a comprehensive analysis of various influencing factors

The Initial Test Programme Features for the Advanced Korean NPPs (Shin–Kori NPP Units 3&4)

International Nuclear Information System (INIS)

Sul, Y.S.

2015-01-01

Korea has developed the Advanced Power Reactor 1400 (APR1400), an evolutionary pressurised water reactor and has obtained the standard design approval in 2002. As of 2014, eight nuclear power plants (NPPs) are in preparation for operation or under construction, four in Korea (SKN 3&4, SUN 1&2) and four in UAE (BNPP 1, 2, 3&4), and four NPPs are in planning in Korea (SKN 5&6, SUN 3&4). Especially, SKN Units 3&4 are the first construction NPPs for the APR1400 and are currently in the final stage to get Operating Licence (OL). The initial test programme for NPPs begins as systems and components are turned over to the startup organization and ends with completion of the Power Ascension Tests (PATs). For SKN Unit 3, the Pre-core Hot Functional Testing has been successfully completed and the initial fuel loading would proceed after getting OL. The SKN Unit 4 is preparing for the CHT (Cold Hydrostatic Test). The SKN 3&4 has many new and advanced design features and so has developed the test programmes to demonstrate that those advanced design features can be safely operated and the performance levels can be maintained in accordance with approved safety requirements. Among those test programs, the examples of test programs, newly introduced ones compared to the previous NPPs are as follows; – SIT (Safety Injection Tank) Blowdown Test with FD (Fluidic Device) – IRWST (In-Containment Refueling Water Storage Tank) In-Plant Test – POSRV (Pilot Operated Safety Relief Valve) Test – Low Power Physics Testing and PAT considering FOAK (First Of A Kind) unit – Safe Shutdown Test with DCS (Distrubuted Control System) Fail and CMF (Common Mode Failure) for Safety Instrumentation and Control System. (author)

Activation scheme to use performance indicators for the graded regulation on Korean NPPs

International Nuclear Information System (INIS)

Hwang, M. J.; Kang, D. I.; Kim, G. R.; Sung, G. Y.

2003-01-01

In this paper, we will provide an activation scheme of using performance indicators for graded regulation on Korean Nuclear Power Plants (NPPs). The safe operation of NPPs is the basic objective of nuclear society. To achieve the object, the direction of the regulation is established to regulate the risk of public health and safety. Therefore, it's essential to keep the safety of plants. However, it's not easy to define the appropriate safety level. So, the requirement of performance indicator establishment and framework establishment for safety management has been increased. Performance indicators can provide quantified safety value numerically. Therefore, we can increase the acceptance and trust of the public for safety of NPPs. Also, it helps pridictive regulation through the objective comparison of safety. Moreover, according to the importance of safety, we can allocate the resources effectively and lead an effort for the improvement of safety by comparison among nations and plants. The safety of a plant is affected by not only design but also the quality of operators, appropriate operation, maintenance and test. So, in this paper, we reviewed the application of performance indicators in domestic and foreign countries, and groped for a method to activate the use of performance indicators

Development of requirements for seismic upgrading of equipment of existing WWER-440 and WWER-1000 type NPPs

International Nuclear Information System (INIS)

Kaznovsky, S.; Ostretsov, I.

1993-01-01

The change in seismology data and safety demands a necessity arose for seismic upgrading of the existing operating NPPs of WWER type which have been originally designed and built without or with simplifies calculations of seismic influences. The paper describes the traditional methods and approaches and calculation-experimental method for examining and ensuring of equipment seismic resistance at the NPPs directly. Method of ground explosions is included as well

A methodology for a quantitative assessment of safety culture in NPPs based on Bayesian networks

International Nuclear Information System (INIS)

Kim, Young Gab; Lee, Seung Min; Seong, Poong Hyun

2017-01-01

Highlights: • A safety culture framework and a quantitative methodology to assess safety culture were proposed. • The relation among Norm system, Safety Management System and worker's awareness was established. • Safety culture probability at NPPs was updated by collecting actual organizational data. • Vulnerable areas and the relationship between safety culture and human error were confirmed. - Abstract: For a long time, safety has been recognized as a top priority in high-reliability industries such as aviation and nuclear power plants (NPPs). Establishing a safety culture requires a number of actions to enhance safety, one of which is changing the safety culture awareness of workers. The concept of safety culture in the nuclear power domain was established in the International Atomic Energy Agency (IAEA) safety series, wherein the importance of employee attitudes for maintaining organizational safety was emphasized. Safety culture assessment is a critical step in the process of enhancing safety culture. In this respect, assessment is focused on measuring the level of safety culture in an organization, and improving any weakness in the organization. However, many continue to think that the concept of safety culture is abstract and unclear. In addition, the results of safety culture assessments are mostly subjective and qualitative. Given the current situation, this paper suggests a quantitative methodology for safety culture assessments based on a Bayesian network. A proposed safety culture framework for NPPs would include the following: (1) a norm system, (2) a safety management system, (3) safety culture awareness of worker, and (4) Worker behavior. The level of safety culture awareness of workers at NPPs was reasoned through the proposed methodology. Then, areas of the organization that were vulnerable in terms of safety culture were derived by analyzing observational evidence. We also confirmed that the frequency of events involving human error

Structural seismic upgrading of NPPs in Czech and Slovak republics

Energy Technology Data Exchange (ETDEWEB)

David, M [DAVID Consulting, Engineering and Design Office, Prague (Czech Republic)

1997-03-01

Several Nuclear Power Plants of the VVER type has been constructed during the past years in former Czechoslovak Republic. Some of them has been already put in operation and some of them are under construction. Nuclear Power Plants V1(2 units of VVER 440/230), V2(2 units of VVER 440/213) in Slovak and NPP Dukovany (4 units of VVER 440/213) in Czech republic are in operation. NPP Mochovce (4 units of VVER 440/213) in Slovak and NPP Temelin (4 units reduced now to 2 units VVER 1000) have been already almost completed, but still under construction. All above cited NPPs have not been either explicitly designed against earthquake or the design against earthquake or its input data must be upgraded to be compatible with present requirements. The upgrading of seismic input as well the seismic upgrading of all structures and technological equipments for so many NPPs has involved a lot of comprehensive work in Czech as well as in Slovak republics. The upgrading cannot be completed in a short time and as a rule the seismic upgrading has been usually performed in several steps, beginning with the most important arrangements against seismic hazard. The basic principles and requirements for seismic upgrading has been defined in accordance with the international and particularly with the IAEA recommendations. About the requirements for seismic upgrading of NPPs in Czech and Slovak republics will be reported in other contribution. This contribution is dealing with the problems of seismic upgrading of NNPs civil engineering structures. The aim of this contribution is to point out some specific problems connected firstly with very complicated concept of Versa structures and secondly with the difficult task to increase the structural capacity to the required seismic level. (J.P.N.)

Structural seismic upgrading of NPPs in Czech and Slovak republics

International Nuclear Information System (INIS)

David, M.

1997-01-01

Several Nuclear Power Plants of the VVER type has been constructed during the past years in former Czechoslovak Republic. Some of them has been already put in operation and some of them are under construction. Nuclear Power Plants V1(2 units of VVER 440/230), V2(2 units of VVER 440/213) in Slovak and NPP Dukovany (4 units of VVER 440/213) in Czech republic are in operation. NPP Mochovce (4 units of VVER 440/213) in Slovak and NPP Temelin (4 units reduced now to 2 units VVER 1000) have been already almost completed, but still under construction. All above cited NPPs have not been either explicitly designed against earthquake or the design against earthquake or its input data must be upgraded to be compatible with present requirements. The upgrading of seismic input as well the seismic upgrading of all structures and technological equipments for so many NPPs has involved a lot of comprehensive work in Czech as well as in Slovak republics. The upgrading cannot be completed in a short time and as a rule the seismic upgrading has been usually performed in several steps, beginning with the most important arrangements against seismic hazard. The basic principles and requirements for seismic upgrading has been defined in accordance with the international and particularly with the IAEA recommendations. About the requirements for seismic upgrading of NPPs in Czech and Slovak republics will be reported in other contribution. This contribution is dealing with the problems of seismic upgrading of NNPs civil engineering structures. The aim of this contribution is to point out some specific problems connected firstly with very complicated concept of Versa structures and secondly with the difficult task to increase the structural capacity to the required seismic level. (J.P.N.)

Indicative value of non-pollen palynomorphs (NPPs) and palynofacies for palaeoreconstructions: Holocene Peat, Brazil

International Nuclear Information System (INIS)

Medeanic, Svetlana; Silva, Maristela Bagatin

2010-01-01

The results of the palynological study of the samples from the core, performed in the Aguas Claras peatland, RS, Brazil (50 45'00''W, 30 00'15''S), focus on detailed taxonomic analysis of non-pollen palynomorphs (NPPs) and palynofacies from the Holocene peat and underline the Late Pleistocene mud and sandy mud that were represented. NPPs from the samples revealed taxonomic variety of fungal palynomorphs, presented by Brachysporium, Clastesporium, Dicellaesporites, Dicellaeporisporites, Gelasinospora, Glomus, Sordaria, Helicoon, and others. The habitats of above mentioned taxa are varied: aquatic, mycorrhizal, parasitic, organic matter decaying, and dung-coprophilous. Freshwater algal palynomorphs were composed of Botryococcus, Closterium, Debarya, Mougeotia, Pseudoschizaea, Spirogyra, and Zygnema. The percentage ratio between algal and fungal palynomorphs was changed from the different samples of the core, reflecting climatic oscillations (more humid-dryer). Prevalence of fungal palynomorphs was connected with dryer climate, and on the contrary, freshwater algal palynomorph predominance was related with increasing humidity. The six palynomorph zones that corresponded to the six principal phases of environmental and climatic changes were determined. The zone from the uppermost part of peat was characterized by relatively frequent dung-coprophilous and parasitic fungi, as a result of agricultural and domestic activities. Palynofacies analysis combined to NPPs was used for palaeoenvironmental and paleoclimatic reconstructions. Palynofacies from the samples were characterized by evident changes in relationship (%) between the different types of organic matter, their quality, and quantity and fluorescence index. The obtained data contribute to the understanding of the peat deposition. The combined use of NPPs and palynofacies analyses provided a valuable approach for the paleoenvironmental and paleoclimatic reconstructions. (author)

Indicative value of non-pollen palynomorphs (NPPs) and palynofacies for palaeoreconstructions: Holocene Peat, Brazil

Energy Technology Data Exchange (ETDEWEB)

Medeanic, Svetlana; Silva, Maristela Bagatin [LOG, IO, FURG, Rio Grande (Brazil)

2010-12-01

The results of the palynological study of the samples from the core, performed in the Aguas Claras peatland, RS, Brazil (50 45'00''W, 30 00'15''S), focus on detailed taxonomic analysis of non-pollen palynomorphs (NPPs) and palynofacies from the Holocene peat and underline the Late Pleistocene mud and sandy mud that were represented. NPPs from the samples revealed taxonomic variety of fungal palynomorphs, presented by Brachysporium, Clastesporium, Dicellaesporites, Dicellaeporisporites, Gelasinospora, Glomus, Sordaria, Helicoon, and others. The habitats of above mentioned taxa are varied: aquatic, mycorrhizal, parasitic, organic matter decaying, and dung-coprophilous. Freshwater algal palynomorphs were composed of Botryococcus, Closterium, Debarya, Mougeotia, Pseudoschizaea, Spirogyra, and Zygnema. The percentage ratio between algal and fungal palynomorphs was changed from the different samples of the core, reflecting climatic oscillations (more humid-dryer). Prevalence of fungal palynomorphs was connected with dryer climate, and on the contrary, freshwater algal palynomorph predominance was related with increasing humidity. The six palynomorph zones that corresponded to the six principal phases of environmental and climatic changes were determined. The zone from the uppermost part of peat was characterized by relatively frequent dung-coprophilous and parasitic fungi, as a result of agricultural and domestic activities. Palynofacies analysis combined to NPPs was used for palaeoenvironmental and paleoclimatic reconstructions. Palynofacies from the samples were characterized by evident changes in relationship (%) between the different types of organic matter, their quality, and quantity and fluorescence index. The obtained data contribute to the understanding of the peat deposition. The combined use of NPPs and palynofacies analyses provided a valuable approach for the paleoenvironmental and paleoclimatic reconstructions. (author)

Functional verification of a safety class controller for NPPs using a UVM register Model

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyu Chull [Dept. of Applied Computer Engineering, Dankook University, Cheonan (Korea, Republic of)

2014-06-15

A highly reliable safety class controller for NPPs (Nuclear Power Plants) is mandatory as even a minor malfunction can lead to disastrous consequences for people, the environment or the facility. In order to enhance the reliability of a safety class digital controller for NPPs, we employed a diversity approach, in which a PLC-type controller and a PLD-type controller are to be operated in parallel. We built and used structured testbenches based on the classes supported by UVM for functional verification of the PLD-type controller designed for NPPs. We incorporated a UVM register model into the testbenches in order to increase the controllability and the observability of the DUT(Device Under Test). With the increased testability, we could easily verify the datapaths between I/O ports and the register sets of the DUT, otherwise we had to perform black box tests for the datapaths, which is very cumbersome and time consuming. We were also able to perform constrained random verification very easily and systematically. From the study, we confirmed the various advantages of using the UVM register model in verification such as scalability, reusability and interoperability, and set some design guidelines for verification of the NPP controllers.

A Classification Method of Technical Security Controls for Digital I and C Systems in NPPs

International Nuclear Information System (INIS)

Song, J. G.; Lee, J. W.; Park, G. Y.; Kwon, K. C.; Lee, D. Y.; Lee, C. K.

2012-01-01

The instrumentation and control (I and C) systems in nuclear power plants (NPPs) are a key facility to monitor plant state, control plant devices, and prevent accidents. Recent I and C systems have been composed of digital systems in order to enhance the effectiveness of operation and maintenance of NPPs. An assessment method for the analysis of security controls is needed to respond to potential cyber attacks against digital I and C systems. RG 5.71 'Cyber Security Programs for Nuclear Facilities' published by U.S.NRC in 2010 presents a comprehensive set of security controls for NPPs. Although this document provides the requirements of security controls, a guidance describing which security controls should be applied to specific digital assets and how to implement them is still needed for the I and C system design and development. In this paper, a classification method of the technical security controls listed in RG 5.71 is proposed to provide a guide useful for the application of the controls during the design and implementation phases of I and C systems

A Classification Method of Technical Security Controls for Digital I and C Systems in NPPs

Energy Technology Data Exchange (ETDEWEB)

Song, J. G.; Lee, J. W.; Park, G. Y.; Kwon, K. C.; Lee, D. Y.; Lee, C. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

The instrumentation and control (I and C) systems in nuclear power plants (NPPs) are a key facility to monitor plant state, control plant devices, and prevent accidents. Recent I and C systems have been composed of digital systems in order to enhance the effectiveness of operation and maintenance of NPPs. An assessment method for the analysis of security controls is needed to respond to potential cyber attacks against digital I and C systems. RG 5.71 'Cyber Security Programs for Nuclear Facilities' published by U.S.NRC in 2010 presents a comprehensive set of security controls for NPPs. Although this document provides the requirements of security controls, a guidance describing which security controls should be applied to specific digital assets and how to implement them is still needed for the I and C system design and development. In this paper, a classification method of the technical security controls listed in RG 5.71 is proposed to provide a guide useful for the application of the controls during the design and implementation phases of I and C systems

Comparison of Domestic Safety Review and European Union(EU) Stress Test After Nuclear Accident in Fukushima Daiichi NPPs

Energy Technology Data Exchange (ETDEWEB)

Kang, Hwa Sung; Kim, Jin Weon [Chosun University, Gwangju (Korea, Republic of)

2016-05-15

The European Union(EU) nuclear regulators group established stress test criteria and procedures, and utilities performed a self-review in accordance with those criteria and procedures. For Wolsung nuclear unit-1,the stress test was additionally conducted for deciding the continued operation of NPP, even though the safety review had been conducted after Fukushima NPP accident. Thus, this study is to compares the process, criteria, and results of the safety review performed in domestic NPPs and EU stress test performed in Cernavoda NPP. From the comparisons, the effectiveness and necessity of the stress test to decide the continued operation of NPPs is discussed. and the improvement items for safety enhancement are derived. The comparison showed that the process and review criteria of EU stress test was more systematic and specific than those used in domestic NPPs. But it was indicated that the improvement items resulted from the safety review performed in domestic NPPs are more comprehensive and powerful than EU stress tests (Cernavoda NPP) results. EU stress test for Cernavoda NPP evaluated in 3 fieldsand derived 13 design change items. The 50 improvement items derived from domestic safety review were including the contents of these 13 items.

GenBank

OpenAIRE

Benson, Dennis A.; Cavanaugh, Mark; Clark, Karen; Karsch-Mizrachi, Ilene; Lipman, David J.; Ostell, James; Sayers, Eric W.

2012-01-01

GenBank? (http://www.ncbi.nlm.nih.gov) is a comprehensive database that contains publicly available nucleotide sequences for almost 260 000 formally described species. These sequences are obtained primarily through submissions from individual laboratories and batch submissions from large-scale sequencing projects, including whole-genome shotgun (WGS) and environmental sampling projects. Most submissions are made using the web-based BankIt or standalone Sequin programs, and GenBank staff assig...

Review of the generic aging lessons learned (GALL) report for U.S. NPPs

International Nuclear Information System (INIS)

Gong Yi; Dou Yikang

2014-01-01

Generic aging lessons learned (GALL) report is a technical basis document issued by U.S. nuclear regulatory commission (NRC) for guiding the review of license renewal application (LRA) of its domestic nuclear power plants (NPPs). By form of tabulations, GALL report addresses the correlation among materials, environments, aging effects/mechanisms, and aging management programs (AMPs) from the level of specific structures and/or components. Based on literature investigation and analysis, the essential information of GALL report in the aspects of background, development history, content framework, and application was reviewed in this paper, which should be the first time in China and would have reference value for establishment of both the AMPs and the nuclear safety regulations of extending the lifetime of its NPPs. (authors)

Preliminary Assessment for the Effects of the External Hazard Factors on the Safety of NPPs

International Nuclear Information System (INIS)

Jin, So Beom; Hyun, Seung Gyu; Kim, Sang Yun; Lee, Sung Kyu; Hur, Youl

2010-01-01

The Ch.etsu Offshore Earthquake(2007.7.16) in Japan caused damage to the Kashiwazaki-Kariwa(K-K) Nuclear Power Plants (NPPs) with seismic ground motion that exceeded the design level. This incident drew the interest of the safety evaluation studies for NPPs subjected to earthquakes exceeding the design basis around the world. Also, the Indian Ocean Tsunami(2004.12.26) tripped the Madras NPP by reason of flooding of the intake pump house and inundated the construction site of a fast breeder reactor site in India. In addition, from the various man-made and natural hazards such as the oil spill accident near Mallipo, Taean, Chungnam (2007.12), the forest fire near the Ulchin NPP site, the several inflows of marine organism into the intake of the Ulchin NPP, it was confirmed that the safety of NPPs may be affected by natural and human induced disasters. Intergovernmental Panel on Climate Change (IPCC) has been warned about global warming; the average temperature rose about 1.5 .deg. C during the 20th century and the damages caused by typhoons and heavy rains have also increased in Korea. Accordingly, a natural disaster prevention research team(hereafter team) ,which have been organized and operated since 2009, has assessed the impact of various hazards such as earthquakes and environmental changes due to global warming on the safety of NPP and has discussed to establish countermeasures. This paper introduces that the preliminary assessment for the effects of the external hazard factors on the safety of NPPs was conducted by the team

A fuzzy controller for NPPs

International Nuclear Information System (INIS)

Schildt, G.H.

1997-01-01

A fuzzy controller for safety related process control is presented for applications in the field of NPPs. The size of necessary rules is relatively small. Thus, there exists a real chance for verification and validation of software due to the fact that the whole software can be structured into standard fuzzy software (like fuzzyfication, inference algorithms, and defuzzyfication), real-time operating system software, and the contents of the rule base. Furthermore, there is an excellent advantage fuel to real-time behaviour, because program execution time is much more predictable than for conventional PID-controller software. Additionally, up to now special know-how does exist to prove stability of fuzzy controller. Hardware design has been done due to fundamental principles of safety technique like watch dog function, dynamization principles, and quiescent current principle. (author). 3 refs, 5 figs

A fuzzy controller for NPPs

Energy Technology Data Exchange (ETDEWEB)

Schildt, G H [Technische Univ., Vienna (Austria)

1997-07-01

A fuzzy controller for safety related process control is presented for applications in the field of NPPs. The size of necessary rules is relatively small. Thus, there exists a real chance for verification and validation of software due to the fact that the whole software can be structured into standard fuzzy software (like fuzzyfication, inference algorithms, and defuzzyfication), real-time operating system software, and the contents of the rule base. Furthermore, there is an excellent advantage fuel to real-time behaviour, because program execution time is much more predictable than for conventional PID-controller software. Additionally, up to now special know-how does exist to prove stability of fuzzy controller. Hardware design has been done due to fundamental principles of safety technique like watch dog function, dynamization principles, and quiescent current principle. (author). 3 refs, 5 figs.

Some remarks on the specification of seismic conditions for NPPs, based on the Romanian experience

Energy Technology Data Exchange (ETDEWEB)

Sandi, H [INCERC Building Research Inst., Bucharest (Romania)

1993-07-01

Some introductory remarks are devoted to the importance of revising the level of earthquake protection of NPPs, given the new knowledge at hand. Some summary data on the seismicity of Romania are given, with emphasis on the implications of instrumental data obtained during the recent strong intermediate depth earthquake of 1986 and 1990. Some problems raised by the new data in connection with the Cernavoda NPP (currently under construction), from the viewpoint of ground and floor design conditions, are discussed. Some proposals are then presented in connection with the future activities related to the verification of NPPs of the region. (author)

Some remarks on the specification of seismic conditions for NPPs, based on the Romanian experience

International Nuclear Information System (INIS)

Sandi, H.

1993-01-01

Some introductory remarks are devoted to the importance of revising the level of earthquake protection of NPPs, given the new knowledge at hand. Some summary data on the seismicity of Romania are given, with emphasis on the implications of instrumental data obtained during the recent strong intermediate depth earthquake of 1986 and 1990. Some problems raised by the new data in connection with the Cernavoda NPP (currently under construction), from the viewpoint of ground and floor design conditions, are discussed. Some proposals are then presented in connection with the future activities related to the verification of NPPs of the region. (author)

GenBank

OpenAIRE

Benson, Dennis A.; Karsch-Mizrachi, Ilene; Lipman, David J.; Ostell, James; Sayers, Eric W.

2008-01-01

GenBank? is a comprehensive database that contains publicly available nucleotide sequences for more than 300 000 organisms named at the genus level or lower, obtained primarily through submissions from individual laboratories and batch submissions from large-scale sequencing projects. Most submissions are made using the web-based BankIt or standalone Sequin programs, and accession numbers are assigned by GenBank? staff upon receipt. Daily data exchange with the European Molecular Biology Labo...

GenBank

OpenAIRE

Benson, Dennis A.; Karsch-Mizrachi, Ilene; Lipman, David J.; Ostell, James; Wheeler, David L.

2006-01-01

GenBank (R) is a comprehensive database that contains publicly available nucleotide sequences for more than 240 000 named organisms, obtained primarily through submissions from individual laboratories and batch submissions from large-scale sequencing projects. Most submissions are made using the web-based BankIt or standalone Sequin programs and accession numbers are assigned by GenBank staff upon receipt. Daily data exchange with the EMBL Data Library in Europe and the DNA Data Bank of Japan...

The application of workflow technology in the development of management procedures in NPPs

International Nuclear Information System (INIS)

Fang Zhaoxia; Huang Fang

2012-01-01

According to the national nuclear safety standards and guides, operating organizations of NPPs should document management programs against all safety related activities. One of the preconditions for the implementation of these programs is to setup a comprehensive instructions and procedures. The workflow technology which is a concept originally from computer technology can help in analysing work processes of different working areas in NPP, designing and developing management procedures hierarchy and requirements. The application of the workflow can not only comprehensively analyse the work process but also analyse the requirements for personnel which are related to the work process, therefore the procedures and programs developed could meet the requirements of national nuclear safety standards and guides. This paper also covers the application of workflow in other areas in NPPs. (authors)

European project SARGEN IV: safety approach and assessment of GEN IV reactors

International Nuclear Information System (INIS)

Ammirabile, L.

2013-01-01

• SARGEN I V has elaborated a proposal for the harmonization of safety assessment practices for GEN IV NPP. • An overall reinforcement of DiD is expected for GEN I V NPP, including improved independence between all levels of DiD. • An inherent approach should reinforce the fulfillment of fundamental safety functions e.g. the consequences for some situations should be reduced and the grace periods should be extended. For the same reason, the use of passive systems can be envisaged. • The need of complementary and integrated deterministic and probabilistic approaches is reiterated. • Methodologies: Some of them are not yet applied. • Assessment of hazards would be a challenging aspect of next generation of NPP safety assessment and should be improved, which is confirmed by the first insights of Fukushima Daiichi TEPCO reactors accidents. • Provisions to cope with extreme events notably to improve the grace period before cliff-edge effects and thus allowing back-up measures to be implemented have to be defined and should be considered as hardened equipments

Recent events in NPPs and incident reporting system (IRS) activity. Working material

International Nuclear Information System (INIS)

1996-01-01

The IAEA convened the 1996 Joint Meeting to Exchange Information on Recent Events in Nuclear Power Plants and the Technical Committee-Annual Meeting of the Incident Reporting System (IRS) national co-ordinators, organized jointly with the Nuclear Energy Agency (NEA) of the OECD in Paris, France from 22-26 April 1996. These consecutive meetings took place at the OECD Headquarters, 2 rue Andre Pascal. The main objective of the first meeting (22-24 April 1996) was to exchange and discuss information on recent events which occurred in NPPs. The second meeting (25-26 April 1996) was devoted to the IAEA and NEA activity in the framework of the IRS. The main issues of the programme at the meetings were as follows: in-depth discussion on NPP recent events, presented by the participants; panel discussion on operational safety experience issues identified by the participants; IAEA and NEA activities on IRS subjects in 1995-1996 and plans for the future; issues from the inter-agency's IRS Advisory Committee. Annexes I and II provide more information on the programme at the meetings. A list of participants is given in Annex III (50 participants from 22 countries and 3 international organization). Annexes IV and V provide information on national presentations on recent events. Figs, tabs

The history of NATO TNF policy: The role of studies, analysis and exercises conference proceedings. Volume 3: Papers by Gen. Robert C. Richardson III (Ret.)

Energy Technology Data Exchange (ETDEWEB)

Rinne, R.L. [ed.

1994-02-01

This conference was organized to study and analyze the role of simulation, analysis, modeling, and exercises in the history of NATO policy. The premise was not that the results of past studies will apply to future policy, but rather that understanding what influenced the decision process-and how-would be of value. The structure of the conference was built around discussion panels. The panels were augmented by a series of papers and presentations focusing on particular TNF events, issues, studies, or exercises. The conference proceedings consist of three volumes. Volume 1 contains the conference introduction, agenda, biographical sketches of principal participants, and analytical summary of the presentations and discussion panels. Volume 2 contains a short introduction and the papers and presentations from the conference. This volume contains selected papers by Brig. Gen. Robert C. Richardson III (Ret.).

Republic of Korea: Design Study for Passive Shutdown System of the PGSFR

International Nuclear Information System (INIS)

Lee, J.H.

2015-01-01

There have been no experiences of implementing a passive shutdown system in operating or operated SFRs around the world. However, new SFRs are considered to adopt a self-actuated shutdown system (SASS) in the future to provide an alternate means of passively shutting down the reactor. The Prototype Gen-IV SFR (PGSFR) developed by KAERI also adopts this system for the same reason. This passive shutdown design concept is combined with a group of secondary control rod drive mechanisms (SCRDM). The system automatically releases the control rod assembly (CRA) around the set temperature, and then drops the CRA by gravity without any external control signals and any actuating power in an emergency of the reactor. This paper describes the parametric design study of a passive shutdown system, which consists of a thermal expansion device, an electromagnet, and a secondary control rod assembly head. The conceptual design values of each component are also suggested. Parametric calculations are performed to check the suitability of the performance requirements of the thermal expansion device and electromagnets

A fuzzy controller for NPPs

International Nuclear Information System (INIS)

Schildt, G.H.

1996-01-01

After an introduction into safety terms a fuzzy controller for safety related process control will be presented, especially for applications in the field of NPPs. One can show that the size of necessary rules is relatively small. Thus, there exists a real chance for verification and validation of software due to the fact that the whole software can be structured into standard fuzzy software (like fuzzyfication, inference algorithms, and defuzzyfication), real-time operating system software, and the contents of the rule base. Furthermore, there is an excellent advantage due to real-time behaviour, because program execution time can be much more planned than for conventional PID-controller software. Additionally, up to now special know-how does exist to prove stability of fuzzy controller. Hardware design has been done due to fundamental principles of safety technique like watch dog function, dynamization principle, and quiescent current principle

Considerations in the evaluation of concrete structures for continued service in aged Nuclear Power Plants (NPPs)

International Nuclear Information System (INIS)

Naus, D.; Marchbanks, M.; Oland, B.; Arndt, G.; Brown, T.

1989-01-01

Currently, there are /approximately/119 commercial nuclear power plants (NPPs) in the US either under construction, operating at low-to-full power, or awaiting an operating license. Together, these units have a net generating capacity of /approximately/110 GW(e). Assuming no life extension of present facilities, the operating licenses for these plants will start to expire in the middle of the next decade with Yankee Rowe being the first plant to attain this status. Where it is noted that with no life extension of facilities, a potential loss of electrical generating capacity in excess of 75 GW(e) could occur during the time period 2006 to 2020 when the operating licenses of 80 to 90 NPPs are scheduled to expire. A potential timely and cost-effective solution to meeting future electricity demand, which has worked well for non-nuclear generating plants, is to extend the service life (operating licenses) of existing NPPs. Since the concrete components in these plants provide a vital safety function, any continued service considerations must include an in-depth assessment of the safety-related concrete structures. 7 refs

Analysis of human performance in KHNP NPPs

International Nuclear Information System (INIS)

Tae, Sung Eun

2004-01-01

The most important thing in the management of nuclear power plant is safety. One of the key factors to enhance the safety is to analyze human performance and to reflect the results on the practical plant operation. KHNP NPPs experienced human errors in the fields of operation and maintenance. The human errors need to be analyzed and, necessary corrective actions according to the causes should be made to prevent the same event or similar events. Therefore we'd like to introduce the procedure of K-HPES(KHNP-Human Performance Enhancement System) and the results of analysis of HPES reports produced in 2002 and 2003

Reduction of waste arising as an option for improvement of waste management systems at NPPs with WWER type reactors

International Nuclear Information System (INIS)

Dultchenko, A.; Mikolaitchouk, H.

1995-01-01

After the USSR breakdown Ukraine inherited five NPPs with 12 WWER type reactor units and 4 RBMK type reactor units and no selected disposal site for NPP operational waste and just a few waste treatment facilities which had not been licensed or certified and could not be considered as complying safety requirements and NPP needs. At the same time the lack of competent designer organizations in Ukraine and the overall economical situation including the payment crisis resulted in significant delays in the development of radioactive waste management infrastructure and brought to the foreground a reduction of waste arisings and implementation of waste recycling technologies. In order to evaluate efficiency of waste management systems at Ukrainian NPPs in comparison with current practices at western NPPs and fix main deficiencies and optimum upgrading measures the comparative analyses of waste management systems at Ukrainian NPPs was initiated within the R and D program supported by the Ukrainian State Committee for Nuclear and Radiation Safety (UkrSCNRS). In carrying out the analyses the results of IAEA Technical Assistance Regional project on Advice on Waste Management at WWER type Reactors were used. Taking into account an influence of the Chernobyl accident consequences on the waste management system of Chernobyl NPP the case of Chernobyl NPP was set apart and cannot be considered typical so the authors confine their analysis to the WWER type reactors. For the purposes of comparison the related information about Kozlodui, Paks, Loviisa and Russian NPPs provided under the above-mentioned IAEA Regional Project was used

Enhanced non-radiative energy transfer in hybrid III-nitride structures

International Nuclear Information System (INIS)

Smith, R. M.; Athanasiou, M.; Bai, J.; Liu, B.; Wang, T.

2015-01-01

The effect of surface states has been investigated in hybrid organic/inorganic white light emitting structures that employ high efficiency, nearfield non-radiative energy transfer (NRET) coupling. The structures utilize blue emitting InGaN/GaN multiple quantum well (MQW) nanorod arrays to minimize the separation with a yellow emitting F8BT coating. Surface states due to the exposed III-nitride surfaces of the nanostructures are found to reduce the NRET coupling rate. The surface states are passivated by deposition of a silicon nitride layer on the III-nitride nanorod surface leading to reduced surface recombination. A low thickness surface passivation is shown to increase the NRET coupling rate by 4 times compared to an un-passivated hybrid structure. A model is proposed to explain the increased NRET rate for the passivated hybrid structures based on the reduction in surface electron depletion of the passivated InGaN/GaN MQW nanorods surfaces

Guidelines for evaluation of anchorage adequacy for safety-related equipment typically used on WWER-type NPPs

International Nuclear Information System (INIS)

Masopust, R.

1999-01-01

This report describes the criteria which should be met when the capacity evaluation of anchorage of safety related equipment is performed for the WWER type NPPs. It should be noted that these criteria were developed specifically for anchorage of WWER type equipment and components to the concrete or steel building structures and they cover different types of anchor bolts and other anchorage details which are typical just for the existing, constructed or reconstructed WWER type NPPs. The screening approach for verifying of equipment anchorage presented in this report is based on a combination of inspections, calculations, and engineering judgement

Safety Aspects of Ageing Management throughout the Full Life Cycle of NPPs

International Nuclear Information System (INIS)

Dou, Yikang

2012-01-01

Most component failures stem from effects of one or multiple ageing mechanism(s). Ageing management is one of the most robust measures to prevent failure and to maintain and increase safety of nuclear power plants. Based on Nuclear Safety Guideline on Ageing Management (NS-G-2.12) published by IAEA in 2009, the paper summarizes main ageing management activities required for all stages of life cycle of NPPs, including design, construction/manufacture, commissioning, operation, life extension for long-term operation and decommissioning. Interactive relations of ageing management in successive stages are analyzed. Implementation of the IAEA Guideline in comprehensive way will bring new challenges to design conception, modes of construction, manufacture, commissioning, equipment qualification, O and M, licensing, life extension and decommissioning for NPPs, however, it will be beneficial to enhance nuclear safety level, especially to promote development of nuclear power in China in a safe, reliable, profitable and sustainable way. (author)

Characterization of Radiation Fields for Assessing Concrete Degradation in Biological Shields of NPPs

Science.gov (United States)

Remec, Igor; Rosseel, Thomas M.; Field, Kevin G.; Pape, Yann Le

2017-09-01

Life extensions of nuclear power plants (NPPs) to 60 years of operation and the possibility of subsequent license renewal to 80 years have renewed interest in long-term material degradation in NPPs. Large irreplaceable sections of most nuclear generating stations are constructed from concrete, including safety-related structures such as biological shields and containment buildings; therefore, concrete degradation is being considered with particular focus on radiation-induced effects. Based on the projected neutron fluence values (E > 0.1 MeV) in the concrete biological shields of the US pressurized water reactor fleet and the currently available data on radiation effects on concrete, some decrease in mechanical properties of concrete cannot be ruled out during extended operation beyond 60 years. An expansion of the irradiated concrete database is desirable to ensure reliable risk assessment for extended operation of nuclear power plants.

Divergência, variabilidade genética e desempenho agronômico em genótipos de couve.

OpenAIRE

Azevedo, Alcinei Mistico

2012-01-01

Embora haja grande variabilidade genética para a couve, são poucos trabalhos no Brasil que visão obter informações para programas de melhoramento genético nesta cultura. Assim, objetivou-se neste trabalho caracterizar 30 genótipos de couve a partir de caracteres morfo-agronômicos para estimar a divergência genética, a importância dos caracteres para a divergência, o desempenho agronômico, os parâmetros genéticos e a correlação entre as características avaliadas. O experimento foi conduzido na...

Condition Based Prognostics of Passive Components - A New Era for Nuclear Power Plant Life Management

International Nuclear Information System (INIS)

Bakhtiari, S.; Mohanty, S.; Prokofiev, I.; Tregoning, R.

2012-01-01

As part of a research project sponsored by the U.S. NRC, Argonne National Laboratory (ANL) conducted scoping studies to identify viable and promising sensors and techniques for in-situ inspection and real-time monitoring of degradation in nuclear power plant (NPP) systems, structures, and components (SSC). Significant advances have been made over the past two decades toward development of online monitoring (OLM) techniques for detection, diagnostics, and prognostics of degradation in active nuclear power plant (NPP) components (e.g., pumps, valves). However, early detection of damage and degradation in safety-critical passive components, (e.g. piping, tubing pressure vessel), is challenging, and will likely remain so for the foreseeable future. Ensuring the structural integrity of the reactor pressure vessel (RPV) and piping systems in particular is a prerequisite to long term safe operation of NPPs. The current practice is to implement inservice inspection (ISI) and preventive maintenance programs. While these programs have generally been successful, they are limited in that information is only obtained during plant outages. Additionally, these inspections, often the critical path in the outage schedule, are costly, time consuming, and involve potentially high dose to nondestructive examination/evaluation (NDE) personnel. A viable plant-wide on-line structural health monitoring program for continuous and automatic monitoring of critical SSCs could be a more effective approach for guarding against unexpected failures. Specifically, OLM information about the current condition of the SSCs could be input to an online prognostics (OLP) system to forecast their remaining useful life in real time. This paper provides an overview of scoping studies performed at ANL on assessing the viability of OLM and OLP systems for real time and automated monitoring and remaining of condition and the remaining useful life of passive components in NPPs. (author)

Transitioning Resolution Responsibility between the Controller and Automation Team in Simulated NextGen Separation Assurance

Science.gov (United States)

Cabrall, C.; Gomez, A.; Homola, J.; Hunt, S..; Martin, L.; Merccer, J.; Prevott, T.

2013-01-01

As part of an ongoing research effort on separation assurance and functional allocation in NextGen, a controller- in-the-loop study with ground-based automation was conducted at NASA Ames' Airspace Operations Laboratory in August 2012 to investigate the potential impact of introducing self-separating aircraft in progressively advanced NextGen timeframes. From this larger study, the current exploratory analysis of controller-automation interaction styles focuses on the last and most far-term time frame. Measurements were recorded that firstly verified the continued operational validity of this iteration of the ground-based functional allocation automation concept in forecast traffic densities up to 2x that of current day high altitude en-route sectors. Additionally, with greater levels of fully automated conflict detection and resolution as well as the introduction of intervention functionality, objective and subjective analyses showed a range of passive to active controller- automation interaction styles between the participants. Not only did the controllers work with the automation to meet their safety and capacity goals in the simulated future NextGen timeframe, they did so in different ways and with different attitudes of trust/use of the automation. Taken as a whole, the results showed that the prototyped controller-automation functional allocation framework was very flexible and successful overall.

Application of the integral code MELCOR for German NPPs and use within accident management and PSA projects

International Nuclear Information System (INIS)

Sonnenkalb, Martin

2006-01-01

The paper summarizes the application of MELCOR to German NPPS with PWR and BWR. A development of different code systems like ATHLET/ATHLET-CD, COCOSYS and ASTEC is done as well at GRS but it is not discussed in this paper. GRS has been using MELCOR since 1990 for real plant calculations. The results of MELCOR analyses are used mainly in PSA level 2 studies and in Accident Management projects for both types of NPPs. MELCOR has been a very useful and robust tool for these analyses. The calculations performed within the PSA level 2 studies for both types of German NPPs have shown that typical severe accident scenarios are characterized by several phases and that the consideration of plant specifics are important not only for realistic source term calculations. An overview of typically severe accident phases together with main accident management measures installed in German NPPs is presented in the paper. Several severe accident sequences have been calculated for both reactor types and some detailed nodalisation studies and code to code comparisons have been prepared in the past, to prove the developed core, reactor circuit and containment/building nodalisation schemes. Together with the compilation of the MELCOR data set, the qualification of the nodalisation schemes has been pursued with comparative calculations with detailed GRS codes for selected phases of severe accidents. The results of these comparative analyses showed in most of the areas a good agreement of essential parameters and of the general description of the plant behaviour during the accident progression. The in general detail of the German plant nodalisation schemes developed for MELCOR contributes significantly to this good agreement between integral and detailed code results. The implementation of MELCOR into the GRS simulator ATLAS was very important for the assessment of the results, not only due to the great detail of the nodalisation schemes used. It is used for training of severe accident

Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, In Kil; Kim, Min Kyu; Hofmayer, Charles; Braverman, Joseph; Nie, Jinsuo

2009-03-01

This report describes the research effort performed by BNL for the Year 2 scope of work. This research focused on methods that could be used to represent the long-term behavior of materials used at NPPs. To achieve this BNL reviewed time-dependent models which can approximate the degradation effects of the key materials used in the construction of structures and passive components determined to be of interest in the Year 1 effort. The intent was to review the degradation models that would cover the most common time-dependent changes in material properties for concrete and steel components

Development of Probabilistic Performance Evaluation Procedure for Umbilical Lines of Seismically Isolated NPPs

International Nuclear Information System (INIS)

Hahm, Daegi; Park, Junhee; Choi, Inkil

2013-01-01

In this study, we proposed a procedure to perform the probabilistic performance evaluation of interface piping system for seismically isolated NPPs, and carried out the preliminary performance evaluation of the target example umbilical line. For EDB level earthquakes, the target performance goal cannot be fulfilled, but we also find out that the result can be changed with respect to the variation of the assumed values, i. e., the distribution of response, and the limit state of piping system. Recently, to design the nuclear power plants (NPPs) more efficiently and safely against the strong seismic load, many researchers focus on the seismic isolation system. For the adoption of seismic isolation system to the NPPs, the seismic performance of isolation devices, structures, and components should be guaranteed firstly. Hence, some researches were performed to determine the seismic performance of such items. For the interface piping system between isolated structure and non-isolated structure, the seismic capacity should be carefully estimated since that the required displacement absorption capacity will be increased significantly by the adoption of the seismic isolation system. Nowadays, in NUREG report, the probabilistic performance criteria for isolated NPP structures and components are proposed. Hence, in this study, we developed the probabilistic performance evaluation method and procedure for interface piping system, and applied the method to an example pipe. The detailed procedure and main results are summarized in next section. For the interface piping system, the seismic capacity should be carefully estimated since that the required displacement absorption capacity will be increased significantly by the adoption of the seismic isolation system

Progress of experimental research on nuclear safety in NPIC

Energy Technology Data Exchange (ETDEWEB)

Gong, Houjun; Zan, Yuanfeng; Peng, Chuanxin; Xi, Zhao; Zhang, Zhen; Wang, Ying; He, Yanqiu; Huang, Yanping [Nuclear Power Institute of China, Chengdu (China)

2016-05-15

Two kinds of Generation III commercial nuclear power plants have been developed in CNNC (China National Nuclear Corporation), one is a small modular reactor ACP100 having an equivalent electric power 100 MW, and the other is HPR1000 (once named ACP1000) having an equivalent electric power 1 000 MW. Both NPPs widely adopted the design philosophy of advanced passive safety systems and considered the lessons from Fukushima Daichi nuclear accident. As the backbone of the R and D of ACP100 and HPR1000, NPIC (Nuclear power Institute of China) has finished the engineering verification test of main safety systems, including passive residual heat removal experiments, reactor cavity injection experiments, hydrogen combustion experiments, and passive autocatalytic recombiner experiments. Above experimental work conducted in NPIC and further research plan of nuclear safety are introduced in this paper.

A study on maintenance rule program and its application at Korean NPPs

International Nuclear Information System (INIS)

Hwang, Mee Jeong; Kim, Kil Yoo; Kang, Dae Il; Yang, Joon Eon; Ha, Jae Joo

2000-11-01

The objective of the Maintenance Rule is to require monitoring of the overall continuing effectiveness of licensee maintenance programs to ensure that safety related and certain nonsafety-related SSCs are capable of performing their intended functions and, for nonsafety-related equipment failures will not occur that prevent the fulfillment of safety-related functions, and failures resulting in scrams and unnecessary actuations of safety-related systems are minimized. That is, proper maintenance is essential to plant safety. U.S. Maintenance Rule, which was effective July 1996 in USA., was not officially adopted in Korea by Korean regulatory body. However, since many PSA and IPE have been performed for NPPs, the philosophy and usefulness of the Maintenance Rule as well as performance-based regulation are being acceptable. We survey the Maintenance Rule program and applications in the USA, and also developed the Maintenance Rule program to apply to Korean NPPs. In addition, we applied the Maintenance Rule Program apply to Ulchin 3,4 Units roughly with the Maintenance Rule Program developed in this project

A study on maintenance rule program and its application at Korean NPPs

Energy Technology Data Exchange (ETDEWEB)

Hwang, Mee Jeong; Kim, Kil Yoo; Kang, Dae Il; Yang, Joon Eon; Ha, Jae Joo

2000-11-01

The objective of the Maintenance Rule is to require monitoring of the overall continuing effectiveness of licensee maintenance programs to ensure that safety related and certain nonsafety-related SSCs are capable of performing their intended functions and, for nonsafety-related equipment failures will not occur that prevent the fulfillment of safety-related functions, and failures resulting in scrams and unnecessary actuations of safety-related systems are minimized. That is, proper maintenance is essential to plant safety. U.S. Maintenance Rule, which was effective July 1996 in USA., was not officially adopted in Korea by Korean regulatory body. However, since many PSA and IPE have been performed for NPPs, the philosophy and usefulness of the Maintenance Rule as well as performance-based regulation are being acceptable. We survey the Maintenance Rule program and applications in the USA, and also developed the Maintenance Rule program to apply to Korean NPPs. In addition, we applied the Maintenance Rule Program apply to Ulchin 3,4 Units roughly with the Maintenance Rule Program developed in this project.

Notes on some Indo-Pacific Pontoniinae III-IX descriptions of some new genera and species from the Western Indian Ocean and the South China Sea

NARCIS (Netherlands)

Bruce, A.J.

1967-01-01

CONTENTS Introduction................... 1 III. Anapontonia denticauda Bruce, 1966, from the western Indian Ocean . . 2 IV. Mesopontonia gorgoniophila gen. nov., sp. nov., from the South China Sea 13 V. Metapontonia fungiacola gen. nov., sp. nov., from the western Indian Ocean 23 VI. The genus

Output signal analysis for a variation of the R-C passive elements in a 4-2 mA R-L-C equivalent circuit modeling under a high temperature accident condition in NPPs

International Nuclear Information System (INIS)

Kil-Mo, Koo; Sang-Baik, Kim; Hee-Dong, Kim; Gyu-Tae, Kim

2007-01-01

An electrical signal should be checked to see whether it lies within its expected electrical range when there is a doubtful condition. The normal signal level for pressure, flow, level and resistance temperature detector sensors is 4-20 mA in most industrial process controls. In the case of an abnormal signal level from an instrument under a severe accident condition, it is necessary to obtain a more accurate signal validation to operate a system in a control room in NPPs. Diagnostics and analysis for some abnormal signals have been performed through an important equivalent circuits modeling for passive elements under severe accident conditions. Unlike the design basis accidents, there are some inherent uncertainties for the instrumentation capabilities under severe accident conditions. In this paper, to implement a diagnostic analysis for an equivalent circuits modeling, a kind of linked LabVIEW program for each PSpice and MULTI-SIM code is introduced as a one body order system, which can obtain some abnormal signal patterns by a special function such as an advanced simulation tool for each PSpice and Multi-SIM code as a means of a function for a PC based ASSA (Abnormal Signal Simulation Analyzer) module. The output signal can be analyzed by a comparative analysis of each PSpice and Multi-SIM code for a 4-20 mA circuit modeling which is by a composition of an R-L-C passive circuit as an alternating range of the elements for the temperature accident condition. In this simulation, a new simulator through an analysis of the important equivalent circuits modeling has been designed, the designed simulator is composed of the LabVIEW code as a main tool and the out-put file of each PSpice code and a Multi-SIM engine code as an engine tool is exported to the in-put file of the LabVIEW code. There are 3 main function units of the ASSA module, the first one is individual PSpice and Multi-SIM engine code units to comprise an equivalent circuit element, the second one is the

IAEA-NULIFE VERLIFE - Procedure for integrity and lifetime assessment of components and piping in WWER NPPs during operation - Tool for LTO

International Nuclear Information System (INIS)

Brumovsky, M.

2012-01-01

VERLIFE - 'Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs during Operation' was developed within the 5th Framework Programme of the European Union in 2003 and later upgraded within the 6th Framework Programme 'COVERS - Safety of WWER NPPs' of the European Union in 2008. This Procedure had to fill the gap in original Soviet/Russian Codes and Rules for WWER type NPPs, as these codes were developed only for design and manufacture and were not changed since their second edition in 1989. VERLIFE Procedure is based on these Russian codes but incorporates also new developments in research, mainly in fracture mechanics, and also some principal approaches used in PWR codes. To assure that VERLIFE Procedure will remain a living document, new 3-years IAEA project (in close cooperation with another project of the 6th Framework Programme of the European Union 'NULIFE - Plant Life Management of NPPs') has started in 2009. Final document, was approved by expert groups of the IAEA and NULIFE in June 28-30, 2011, and will be issued as 'IAEA/NULIFE Guidelines for Integrity and Lifetime Assessment of Components and Piping in WWER NPPs during Operation'. This document represents a necessary part for any integrity and lifetime assessment during operation that is a bases for further decision about safe and potential long term operation. To prepare documents like TLAA, it is necessary to have a tool that is able to evaluate lifetime of the main NPP components taking into account existing past operation as well as proposal for the future. (author)

pGenN, a Gene Normalization Tool for Plant Genes and Proteins in Scientific Literature

Science.gov (United States)

Ding, Ruoyao; Arighi, Cecilia N.; Lee, Jung-Youn; Wu, Cathy H.; Vijay-Shanker, K.

2015-01-01

Background Automatically detecting gene/protein names in the literature and connecting them to databases records, also known as gene normalization, provides a means to structure the information buried in free-text literature. Gene normalization is critical for improving the coverage of annotation in the databases, and is an essential component of many text mining systems and database curation pipelines. Methods In this manuscript, we describe a gene normalization system specifically tailored for plant species, called pGenN (pivot-based Gene Normalization). The system consists of three steps: dictionary-based gene mention detection, species assignment, and intra species normalization. We have developed new heuristics to improve each of these phases. Results We evaluated the performance of pGenN on an in-house expertly annotated corpus consisting of 104 plant relevant abstracts. Our system achieved an F-value of 88.9% (Precision 90.9% and Recall 87.2%) on this corpus, outperforming state-of-art systems presented in BioCreative III. We have processed over 440,000 plant-related Medline abstracts using pGenN. The gene normalization results are stored in a local database for direct query from the pGenN web interface (proteininformationresource.org/pgenn/). The annotated literature corpus is also publicly available through the PIR text mining portal (proteininformationresource.org/iprolink/). PMID:26258475

A Regulatory Perspective on the Performance and Reliability of Nuclear Passive Safety Systems

International Nuclear Information System (INIS)

Quan, Pham Trung; Lee, Sukho

2016-01-01

Passive safety systems have been proven to enhance the safety of NPPs. When an accident such as station blackout occurs, these systems can perform the following functions: the decay heat removal, passive safety injection, containment cooling, and the retention of radioactive materials. Following the IAEA definitions, using passive safety systems reduces reliance on active components to achieve proper actuation and not requiring operator intervention in accident conditions. That leads to the deviations in boundary conditions of the critical process or geometric parameters, which activate and operate the system to perform accident prevention and mitigation functions. The main difficulties in evaluation of functional failure of passive systems arise because of (a) lack of plant operational experience; (b) scarcity of adequate experimental data from integral test facilities or from separate effect tests in order to understand the performance characteristics of these passive systems, not only at normal operation but also during accidents and transients; (c) lack of accepted definitions of failure modes for these systems; and (d) difficulty in modeling certain physical behavior of these systems. Reliability assessment of the PSS is still one of the important issues. Several reliability methodologies such as REPAS, RMPS and ASPRA have been applied to the reliability assessments. However, some issues are remained unresolved due to lack of understanding of the treatment of dynamic failure characteristics of components of the PSS, the treatment of dynamic variation of independence process parameters such as ambient temperature and the functional failure criteria of the PSS. Dynamic reliability methodologies should be integrated in the PSS reliability analysis to have a true estimate of system failure probability. The methodology should estimate the physical variation of the parameters and the frequency of the accident sequences when the dynamic effects are considered

Development of Human-level Decision Making Algorithm for NPPs through Deep Neural Networks : Conceptual Approach

International Nuclear Information System (INIS)

Kim, Seung Geun; Seong, Poong Hyun

2017-01-01

Development of operation support systems and automation systems are closely related to machine learning field. However, since it is hard to achieve human-level delicacy and flexibility for complex tasks with conventional machine learning technologies, only operation support systems with simple purposes were developed and high-level automation related studies were not actively conducted. As one of the efforts for reducing human error in NPPs and technical advance toward automation, the ultimate goal of this research is to develop human-level decision making algorithm for NPPs during emergency situations. The concepts of SL, RL, policy network, value network, and MCTS, which were applied to decision making algorithm for other fields are introduced and combined with nuclear field specifications. Since the research is currently at the conceptual stage, more research is warranted.

Seleção preliminar de genótipos de pinheira em Bom Jesus-PI Preliminary selection of sugar apple genotypes in Bom Jesus county, Piauí state, Brazil

Directory of Open Access Journals (Sweden)

Ítalo Herbert Lucena Cavalcante

2011-01-01

Full Text Available A pinheira (Annona squamosa L. ocorre espontaneamente no Nordeste Brasileiro, onde é explorada de forma extrativista, caracterizando-se pela falta de manejo adequado e material genético selecionado. Nesse sentido, foi realizado um experimento com objetivo de avaliar a produtividade, as características físicas e químicas de frutos de dez genótipos de pinheira no município de Bom Jesus, PI. Adotou-se delineamento inteiramente casualizado, com tratamentos representados por dez genótipos de pinheira e três repetições. Foram avaliadas as seguintes variáveis: vitamina C, acidez titulável, sólidos solúveis, relação SS/AT "ratio", diâmetros longitudinal e transversal, relação DL/DT, número se sementes por fruto, massa dos frutos e produção por planta. Os genótipos apresentam diferenças quanto às características químicas, físicas e produtivas dos frutos. Os genótipos foram agrupados em sete grupos, com destaque para o grupo III (Gen-02 e grupo IV (Gen-05, fato que explicitou as diferenças entre os genótipos de pinheira quanto às características produtivas e químicas e físicas dos frutos. Genótipos Gen-01 e Gen-02 apresentam potencial para instalação em plantios comerciais, pela produtividade, formato do fruto ou por caracterizarem fontes naturais de vitamina C.The sugar apple (Annona squamosa L. is native to tropical America, occurring spontaneously in Northeastern Brazil, where it is exploited mainly as subsistence without adequate management and without genetic material selection. An experiment was developed aiming to evaluate yield, physical and chemical characteristics of the fruits of ten sugar apple genotypes in Bom Jesus, Piauí State, Brazil. A completely randomized design with treatments represented by ten genotypes and three replications was adopted. The following variables were evaluated: vitamin C, titratable acidity, soluble solids, SS/TA ratio, longitudinal diameter and transverse, LD/TD, number of

WWER NPPs fuel handling machine control system

International Nuclear Information System (INIS)

Mini, G.; Rossi, G.; Barabino, M.; Casalini, M.

2001-01-01

In order to increase the safety level of the fuel handling machine on WWER NPPs, Ansaldo Nucleare was asked to design and supply a new Control System. Two FHM Control System units have been already supplied for Temelin NPP and others supplies are in process for the Atommash company, which has in charge the supply of FHMs for NPPs located in Russia, Ukraine and China. The Fuel Handling Machine (FHM) Control System is an integrated system capable of a complete management of nuclear fuel assemblies. The computer-based system takes into account all the operational safety interlocks so that it is able to avoid incorrect and dangerous manoeuvres in the case of operator error. Control system design criteria, hardware and software architecture, and quality assurance control, are in accordance with the most recent international requirements and standards, and in particular for electromagnetic disturbance immunity demands and seismic compatibility. The hardware architecture of the control system is based on ABB INFI 90 system. The microprocessor-based ABB INFI 90 system incorporates and improves upon many of the time proven control capabilities of Bailey Network 90, validated over 14,000 installations world-wide. The control system complies all the former designed sensors and devices of the machine and markedly the angular position measurement sensors named 'selsyn' of Russian design. Nevertheless it is fully compatible with all the most recent sensors and devices currently available on the market (for ex. Multiturn absolute encoders). All control logic components were developed using standard INFI 90 Engineering Work Station, interconnecting blocks extracted from an extensive SAMA library by using a graphical approach (CAD) and allowing an easier intelligibility, more flexibility and updated and coherent documentation. The data acquisition system and the Man Machine Interface are implemented by ABB in co-operation with Ansaldo. The flexible and powerful software structure

VVER NPPs fuel handling machine control system

International Nuclear Information System (INIS)

Mini, G.; Rossi, G.; Barabino, M.; Casalini, M.

2002-01-01

In order to increase the safety level of the fuel handling machine on WWER NPPs, Ansaldo Nucleare was asked to design and supply a new Control System. Two Fuel Handling Machine (FHM) Control System units have been already supplied for Temelin NPP and others supply are in process for the Atommash company, which has in charge the supply of FHMs for NPPs located in Russia, Ukraine and China.The computer-based system takes into account all the operational safety interlocks so that it is able to avoid incorrect and dangerous manoeuvres in the case of operator error. Control system design criteria, hardware and software architecture, and quality assurance control, are in accordance with the most recent international requirements and standards, and in particular for electromagnetic disturbance immunity demands and seismic compatibility. The hardware architecture of the control system is based on ABB INFI 90 system. The microprocessor-based ABB INFI 90 system incorporates and improves upon many of the time proven control capabilities of Bailey Network 90, validated over 14,000 installations world-wide.The control system complies all the former designed sensors and devices of the machine and markedly the angular position measurement sensors named 'selsyn' of Russian design. Nevertheless it is fully compatible with all the most recent sensors and devices currently available on the market (for ex. Multiturn absolute encoders).All control logic were developed using standard INFI 90 Engineering Work Station, interconnecting blocks extracted from an extensive SAMA library by using a graphical approach (CAD) and allowing and easier intelligibility, more flexibility and updated and coherent documentation. The data acquisition system and the Man Machine Interface are implemented by ABB in co-operation with Ansaldo. The flexible and powerful software structure of 1090 Work-stations (APMS - Advanced Plant Monitoring System, or Tenore NT) has been successfully used to interface the

GenLab, Laboratorio Virtual de Genética

Directory of Open Access Journals (Sweden)

Fidel Ramírez

2000-07-01

Full Text Available GenLab es el nombre que tiene el software diseñado por nosotros, en el cual se modela el proceso meiótico y la fecundación en organismos diploides. El objetivo de esta aplicación es ilustrar el resultado de un cruce determinado, tratando de ser lo más ajustados a la realidad. La modelación de la reproducción sexual se realiza internamente y el GenLab se limita a presentar los resultados según el número de descendencia seleccionado para un cruce específico, esto significa que se puede escoger una gran cantidad de características para los parentales y se puede estudiar la frecuencia de estos en la descendencia. El modelo cuenta con base de datos donde están almacenados algunos de los locus de Drosophila melanogaster junto con su ubicación en centimorgans 1. EI propósito de este modelo es servir como herramienta pedagógica  y didáctica tanto en universidades como en colegios, facilitando el aprendizaje de algunos principios básicos de la genética, por lo cual puede ser usado si se cuenta con una conexión a Internet y un navegador visitando http://biologia.unal.edu.co/fidel.

Monitoring of coolant temperature stratification on piping components in WWER-440 NPPs

International Nuclear Information System (INIS)

Hudcovsky, S.; Slanina, M.; Badiar, S.

2001-01-01

The presentation deals with the aims of non-standard temperature measurements installed on primary and secondary circuit in WWER-440 NPPs, explains reasons of coolant temperature stratification on the piping components. It describes methods of the measurements on pipings, range of installation of the temperature measurements in EBO and EMO units and illustrates results of measurements of coolant temperature stratification. (Authors)

Scaling for Mixed Convection Heat Transfer in Passive Containments and Experiment Design

International Nuclear Information System (INIS)

Wang, Shengfei; Yu, Yu; Lv, Xuefeng; Niu, Fenglei; Yan, Xiuping

2012-01-01

Most of the advanced nuclear reactor design utilizes passive systems to remove heat from the core by natural circulation. The passive systems will be widely used in generation III pressurized water reactor. One of the typical passive systems is passive containment cooling system (PCCS), which is a passive condenser system designed to remove heat from the containment for long term cooling after a postulated reactor accident. In order to establish empirical correlations and develop simulation models, a scaling analysis is performed in designing an experiment for the prototype PCCS. This paper presents a scaling method and the design of the experimental facility. The key dimensionless parameters governing the dominant processes are given at last

Technique for calculating the requirements for housing when designing workers' towns for NPPs

International Nuclear Information System (INIS)

Vorob'ev, I.E.; Gavrilko, A.P.

1989-01-01

Problem of determining housing requirements when constructing and operating NPPs is considered. Concrete variants of ratio of apartments of different types (hotel-type, one-,two, three-and four-room ones) for operating and auxiliary personnel as well as for construction and mounting staff and auxiliary services related to NPP construction, are proposed

A analysis of cementation technology for liquid radioactive-waste in PWR NPPs

International Nuclear Information System (INIS)

Chen Liang; Chen Li; Li Junhua

2009-01-01

Cementation is one of the most popular solidification technology for the low-and-intermediate level liquid radioactive waste. It has been applied in all of domestic PWR NPPs. The process characteristics and operation of the cementations in the different NPPs are introduced,and the advantage and disadvantage of the cementation are analyzed in this paper. A drum and a cask are compared as a package of the solidified waste, the drum can decrease over 50% final volume of the waste, furthermore the cost for manufacture and transportation for this drum is more cheaper than the cask, but an additional shielding may be necessary for the waste with higher level radioactivity that is packed in drum. More waste can be contained if an appropriate in-drum mixer is used while secondary waste will be unavoidable if the out-drum mixing is adopted. A carriage can make it easier to decontaminate on the surface of equipment and on the floor, furthermore the carriage is more economical than a roller conveyor in manufacture and maintenance. The cementation recipe for the waste should be optimized and additive material should be as less as possible to increase the containing rate of the waste. (authors)

Large-scale experimental facility for emergency condition investigation of a new generation NPP WWER-640 reactor with passive safety systems

Energy Technology Data Exchange (ETDEWEB)

Aniskevich, Y.N.; Vasilenko, V.A.; Zasukha, V.K.; Migrov, Y.A.; Khabensky, V.B. [Research Inst. of Technology NITI (Russian Federation)

1997-12-31

The creation of the large-scale integral experimental facility (KMS) is specified by the programme of the experimental investigations to justify the engineering decisions on the safety of the design of the new generation NPP with the reactor WWER-640. The construction of KMS in a full volume will allow to conduct experimental investigations of all physical phenomena and processes, practically, occurring during the accidents on the NPPs with the reactor of WWER type and including the heat - mass exchange processes with low rates of the coolant, which is typical during the utilization of the passive safety systems, process during the accidents with a large leak, and also the complex intercommunicated processes in the reactor unit, passive safety systems and in the containment with the condition of long-term heat removal to the final absorber. KMS is being constructed at the Research Institute of Technology (NITI), Sosnovy Bor, Leningrad region, Russia. (orig.). 5 refs.

Large-scale experimental facility for emergency condition investigation of a new generation NPP WWER-640 reactor with passive safety systems

International Nuclear Information System (INIS)

Aniskevich, Y.N.; Vasilenko, V.A.; Zasukha, V.K.; Migrov, Y.A.; Khabensky, V.B.

1997-01-01

The creation of the large-scale integral experimental facility (KMS) is specified by the programme of the experimental investigations to justify the engineering decisions on the safety of the design of the new generation NPP with the reactor WWER-640. The construction of KMS in a full volume will allow to conduct experimental investigations of all physical phenomena and processes, practically, occurring during the accidents on the NPPs with the reactor of WWER type and including the heat - mass exchange processes with low rates of the coolant, which is typical during the utilization of the passive safety systems, process during the accidents with a large leak, and also the complex intercommunicated processes in the reactor unit, passive safety systems and in the containment with the condition of long-term heat removal to the final absorber. KMS is being constructed at the Research Institute of Technology (NITI), Sosnovy Bor, Leningrad region, Russia. (orig.)

Large-scale experimental facility for emergency condition investigation of a new generation NPP WWER-640 reactor with passive safety systems

Energy Technology Data Exchange (ETDEWEB)

Aniskevich, Y N; Vasilenko, V A; Zasukha, V K; Migrov, Y A; Khabensky, V B [Research Inst. of Technology NITI (Russian Federation)

1998-12-31

The creation of the large-scale integral experimental facility (KMS) is specified by the programme of the experimental investigations to justify the engineering decisions on the safety of the design of the new generation NPP with the reactor WWER-640. The construction of KMS in a full volume will allow to conduct experimental investigations of all physical phenomena and processes, practically, occurring during the accidents on the NPPs with the reactor of WWER type and including the heat - mass exchange processes with low rates of the coolant, which is typical during the utilization of the passive safety systems, process during the accidents with a large leak, and also the complex intercommunicated processes in the reactor unit, passive safety systems and in the containment with the condition of long-term heat removal to the final absorber. KMS is being constructed at the Research Institute of Technology (NITI), Sosnovy Bor, Leningrad region, Russia. (orig.). 5 refs.

In situ passivation of GaAsP nanowires.

Science.gov (United States)

Himwas, C; Collin, S; Rale, P; Chauvin, N; Patriarche, G; Oehler, F; Julien, F H; Travers, L; Harmand, J-C; Tchernycheva, M

2017-12-08

We report on the structural and optical properties of GaAsP nanowires (NWs) grown by molecular-beam epitaxy. By adjusting the alloy composition in the NWs, the transition energy was tuned to the optimal value required for tandem III-V/silicon solar cells. We discovered that an unintentional shell was also formed during the GaAsP NW growth. The NW surface was passivated by an in situ deposition of a radial Ga(As)P shell. Different shell compositions and thicknesses were investigated. We demonstrate that the optimal passivation conditions for GaAsP NWs (with a gap of 1.78 eV) are obtained with a 5 nm thick GaP shell. This passivation enhances the luminescence intensity of the NWs by 2 orders of magnitude and yields a longer luminescence decay. The luminescence dynamics changes from single exponential decay with a 4 ps characteristic time in non-passivated NWs to a bi-exponential decay with characteristic times of 85 and 540 ps in NWs with GaP shell passivation.

In situ passivation of GaAsP nanowires

Science.gov (United States)

Himwas, C.; Collin, S.; Rale, P.; Chauvin, N.; Patriarche, G.; Oehler, F.; Julien, F. H.; Travers, L.; Harmand, J.-C.; Tchernycheva, M.

2017-12-01

We report on the structural and optical properties of GaAsP nanowires (NWs) grown by molecular-beam epitaxy. By adjusting the alloy composition in the NWs, the transition energy was tuned to the optimal value required for tandem III-V/silicon solar cells. We discovered that an unintentional shell was also formed during the GaAsP NW growth. The NW surface was passivated by an in situ deposition of a radial Ga(As)P shell. Different shell compositions and thicknesses were investigated. We demonstrate that the optimal passivation conditions for GaAsP NWs (with a gap of 1.78 eV) are obtained with a 5 nm thick GaP shell. This passivation enhances the luminescence intensity of the NWs by 2 orders of magnitude and yields a longer luminescence decay. The luminescence dynamics changes from single exponential decay with a 4 ps characteristic time in non-passivated NWs to a bi-exponential decay with characteristic times of 85 and 540 ps in NWs with GaP shell passivation.

Organization and mechanization of maintenance operations at NPPs with the WWER type reactors

International Nuclear Information System (INIS)

Titov, A.A.

1983-01-01

The structure of capital investments defining organization and mechanization of maintepance operations at NPPs with the WWER type reactors is analyzed. The trends in development of optimum decisions for organization and mechanization of repair obs at NPPs being designed taking into account the prospects of nuclear powep enginerning development, the system of NPP maintenance servicing, as well as the structure of repair-productive capacities are discussed. On the basis of the analysis of the data obtained in designing the Zaporozhskaya NPP it is shown that the capital investments for organizing and mechanization of maintenance operations at the unified NPP site with four WWER-1000 reactors reach nearly 18 roubles/kW. A conclusion is drawn that at present the design of an NPP with the WWER-1000 reactor totally meets the requirements of realization of periodic maintenance operations. It is advisable to cooperate the NPP management with that of a thermal power station from the viewpoint of using manpower, which would improve the operating conditions and labour productivity of workers engaged in repair and, consequently, reduce the capital investments and repair expenditures

Development status of component reliability database for Korean NPPs and a case study

International Nuclear Information System (INIS)

Choi, S. Y.; Yang, S. H.; Lee, S. C.; Kim, S. H.; Han, S. H.

1999-01-01

We have applied a generic database to the PSA (Probabilistic Safety Assessment) for the Korean Standard NPPs (Nuclear Power Plant) since there is no specific component reliability database. However generic data is not enough to reflect the specific characteristics of domestic plants since it is collected by foreign plants. Therefore we are developing the plant-specific component reliability database for domestic NPPs. In this paper, we describe the development status of the component reliability database and the approach method of data collection and component failure analysis. We also summarize a case study of component failure analysis. We first collect the failure and repair data from the TR (Trouble Report) electronic database and the daily operation report sheet. Now we add a data collection method that checks the original TR sheet to improve the data quality. We input the component failure and repair data of principal components of about 30 systems into the component reliability database. Now, we are analyzing the component failure data of 11 safety systems among the systems to calculate component failure rate and unavailability etc

An Enhancement of Campaign Posters for Human Error Prevention in NPPs

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Yong Hee; Kwon, Soon Il

2010-01-01

Accidents in high reliability systems such as nuclear power plants (NPPs) give rise to not only a loss of property and life, but also social problems. One of the most frequently used techniques to grasp the current situation for hazard factors in the NPPs is an event investigation analysis based on the INPO's Human Performance Enhancement System (HPES), and the Korean Human Performance Enhancement System (K-HPES) in Korea, respectively. There are many methods and approaches for an HE assessment that is valuable for investigating the causes of undesirable events and counter-plans to prevent their recurrence in the NPPs. They differ from each other according to the objectives of the analysis; the explanation of the event, the investigation of the causes, the allocation of the responsibility, and the establishment of the counter-plan. Event databases include their own events and information from various sources such as the IAEA, regulatory bodies, and also from the INPO and WANO. As many as 111 reactor trips have occurred in the past 5 years ('01∼'05), and 26 cases of them have occurred due to HE. The trend of human error rate didn't decrease in 2004, so the KHNP started to make efforts to decrease HEs. The KHNP created as many as 40 posters for human performance improvement in 2006. The INPO has been using a traditional form of poster; additionally, the Central Research Institute of Electric Power Industry (CRIEPI) developed a type of caution report. The caution report is comprised of a poster name, a serial number, a figure, work situations, the point at issue, and a countermeasure. The preceding posters which KHNP developed in 2006 give a message about specific information related to HE events. However, it is not enough to arouse interest in the effectiveness of the posters because most people are favorably disposed toward a simple poster with many illustrations. Therefore, we stressed the need for worker's receptiveness rather than notification of information

The passivation of calcite by acid mine water. Column experiments with ferric sulfate and ferric chloride solutions at pH 2

Energy Technology Data Exchange (ETDEWEB)

Soler, Josep M. [Institute of Earth Sciences ' Jaume Almera' (CSIC), Lluis Sole i Sabaris s/n, 08028 Barcelona, Catalonia (Spain); Institute of Environmental Assessment and Water Research (CSIC), Jordi Girona 18, 08034 Barcelona, Catalonia (Spain)], E-mail: jsoler@ija.csic.es; Boi, Marco [Institute of Earth Sciences ' Jaume Almera' (CSIC), Lluis Sole i Sabaris s/n, 08028 Barcelona, Catalonia (Spain); Institute of Environmental Assessment and Water Research (CSIC), Jordi Girona 18, 08034 Barcelona, Catalonia (Spain); Mogollon, Jose Luis [Institute of Earth Sciences ' Jaume Almera' (CSIC), Lluis Sole i Sabaris s/n, 08028 Barcelona, Catalonia (Spain); Instituto de Ciencias de la Tierra, Universidad Central de Venezuela, Caracas 1020-A (Venezuela, Bolivarian Republic of); Cama, Jordi; Ayora, Carlos [Institute of Earth Sciences ' Jaume Almera' (CSIC), Lluis Sole i Sabaris s/n, 08028 Barcelona, Catalonia (Spain); Institute of Environmental Assessment and Water Research (CSIC), Jordi Girona 18, 08034 Barcelona, Catalonia (Spain); Nico, Peter S.; Tamura, Nobumichi; Kunz, Martin [Lawrence Berkeley National Laboratory, 1 Cyclotron Road, Berkeley, CA 94720 (United States)

2008-12-15

Column experiments, simulating the behavior of passive treatment systems for acid mine drainage, have been performed. Acid solutions (HCl or H{sub 2}SO{sub 4}, pH 2), with initial concentrations of Fe(III) ranging from 250 to 1500 mg L{sup -1}, were injected into column reactors packed with calcite grains at a constant flow rate. The composition of the solutions was monitored during the experiments. At the end of the experiments (passivation of the columns), the composition and structure of the solids were measured. The dissolution of calcite in the columns caused an increase in pH and the release of Ca into the solution, leading to the precipitation of gypsum and Fe-oxyhydroxysulfates (Fe(III)-SO{sub 4}-H{sup +} solutions) or Fe-oxyhydroxychlorides (Fe(III)-Cl-H{sup +} solutions). The columns worked as an efficient barrier for some time, increasing the pH of the circulating solutions from 2 to {approx}6-7 and removing its metal content. However, after some time (several weeks, depending on the conditions), the columns became chemically inert. The results showed that passivation time increased with decreasing anion and metal content of the solutions. Gypsum was the phase responsible for the passivation of calcite in the experiments with Fe(III)-SO{sub 4}-H{sup +} solutions. Schwertmannite and goethite appeared as the Fe(III) secondary phases in those experiments. Akaganeite was the phase responsible for the passivation of the system in the experiments with Fe(III)-Cl-H{sup +} solutions.

The ENEN-III project: Technical Training on the Concepts and Design of GEN IV nuclear reactors

International Nuclear Information System (INIS)

Berkvens, T.; Renault, C.; Alonso, M.; Salomaa, R.; Schönfelder, C.

2013-01-01

Some conclusions: • Not enough training courses to cover the LO’s: – Especially GEN IV; – Many introductory courses, little specific courses; – Reach out to other partners for more courses. • Skills and Attitudes: – Much more difficult to train/measure; – To be treated in a separate project. • Use of Learning Outcomes must be promoted; • Involvement of human resources necessary for the successful implementation of the schemes: – End of project workshop

Automatic accounting of nuclear materials at WWER type reactor NPPs

International Nuclear Information System (INIS)

Babaev, N.S.; Poznyakov, N.L.; Strelkov, D.F.

1978-01-01

The possibilities of automatic accounting of nuclear materials at NPPs based on WWER reactors are considered. Organizational and technical principles of an automated system of accounting that takes into consideration IAEA requirements in conducting accounting documentation are proposed. A program is described for accounting materials using a BESM-6 computer. Operation of the program requires that all accounting data be recorded on conventional carriers of computer information (magnetic tapes, discs, perforated cards), which constitute the basic NPP accounting documents and may be directly used as initial data for a corresponding information program

Chemical technologies and life management of Ukrainian NPPs

International Nuclear Information System (INIS)

Arkhipenko, A.V.; Barbashev, S.V.; Litvinskij, L.L.; Masko, A.N.

2000-01-01

Now 11 units with WWER-1000 reactors, 2 units with WWER-440 and 1 unit with RBMK-1000 are operated in Ukraine. State of chemical technologies of NPPs essentially influences on unit operating resource by the next ways: decreasing of corrosion intensity of equipment metal; decreasing of contamination on thermal exchanged surfaces of equipment; decreasing of amounts of radioactive waste. Improvement of these parameters can be achieved by the next measures: improvement of purification schemes for feed water of main systems; introduction of more effective water-chemical regimes (WCR); implementation of new methods and instruments of chemical monitoring for WCR; providing of without-scale regime of thermal-exchanged equipment operating by reactor division users through optimisation of the WCR of the NPP spray pool. (author)

Variabilidad genética de Plasmodium falciparum en pacientes con malaria grave y malaria no complicada en Iquitos - Perú

Directory of Open Access Journals (Sweden)

Gisely Hijar G

2002-07-01

Full Text Available Objetivo: Determinar la diversidad genética del gen que codifica la proteína rica en glutamato (GLURP de Plasmodium falciparum en pacientes con malaria complicada y no complicada circulante en un área del departamento de Loreto, distrito de Maynas. Materiales y métodos: La diversidad genética fue analizada usando reacción en cadena de la polimerasa (PCR en 30 muestras sanguíneas de pacientes con malaria no complicada (MNC y 46 con malaria grave complicada (MGC. Resultados: Ocho genotipos fueron detectados en pacientes con MNC (Genotipo I,II,III, IV,V, VI,VII y VIII y cuatro genotipos en los pacientes con MGC (Genotipo V,VI,VII,VIII. Asimismo, en 50% de las muestras con MNC fueron detectadas infecciones múltiples, a diferencia de las muestras de MGC en donde no se detectó infecciones múltiples. Conclusión: Existe una diversidad genética en esta región del gen GLURP de P. falciparum, para esa época (marzo 1998 - abril 1999 y esa área del país. En tal sentido, nuestros resultados podrían servir de base para llevar a cabo estudios epidemiológicos posteriores, ya que permitiría conocer la distribución de las cepas circulantes en nuestro país.

FutureGen Project Report

Energy Technology Data Exchange (ETDEWEB)

Cabe, Jim; Elliott, Mike

2010-09-30

This report summarizes the comprehensive siting, permitting, engineering, design, and costing activities completed by the FutureGen Industrial Alliance, the Department of Energy, and associated supporting subcontractors to develop a first of a kind near zero emissions integrated gasification combined cycle power plant and carbon capture and storage project (IGCC-CCS). With the goal to design, build, and reliably operate the first IGCC-CCS facility, FutureGen would have been the lowest emitting pulverized coal power plant in the world, while providing a timely and relevant basis for coal combustion power plants deploying carbon capture in the future. The content of this report summarizes key findings and results of applicable project evaluations; modeling, design, and engineering assessments; cost estimate reports; and schedule and risk mitigation from initiation of the FutureGen project through final flow sheet analyses including capital and operating reports completed under DOE award DE-FE0000587. This project report necessarily builds upon previously completed siting, design, and development work executed under DOE award DE-FC26- 06NT4207 which included the siting process; environmental permitting, compliance, and mitigation under the National Environmental Policy Act; and development of conceptual and design basis documentation for the FutureGen plant. For completeness, the report includes as attachments the siting and design basis documents, as well as the source documentation for the following: • Site evaluation and selection process and environmental characterization • Underground Injection Control (UIC) Permit Application including well design and subsurface modeling • FutureGen IGCC-CCS Design Basis Document • Process evaluations and technology selection via Illinois Clean Coal Review Board Technical Report • Process flow diagrams and heat/material balance for slurry-fed gasifier configuration • Process flow diagrams and heat/material balance

Significant events during the year 2000 for French NPPs. Emphasis on reinforced regulatory supervision of Dampierre NPP

International Nuclear Information System (INIS)

Amri, A.

2001-01-01

Under DSIN request, since 1999 the French utility EDF started a programme to check the compliance of the current safety provisions with those expected at the design stage. 469 significant incidents for the French NPPs are declared. Two incidents, classified at INES 2 have occurred in 2000: errors in the operating procedures in Dampierre, Bugey and Tricastin NPPs which led to an anticipated unavailability of the safety injection system, while its availability is still required, and accumulation at the site of Tricastin of organizational and human malfunctions during a short time, revealing a lack of rigour. Results of the reinforced DSIN supervision like: effective management implication on the site, building of better human and social relationships, operating rigour still insufficient are presented

Analysis of the events on the operating of the wrong compartment of NPPs

International Nuclear Information System (INIS)

Zheng Lixin; Zhou Hong; Zhang Hao; Che Shuwei; Zhang Jiajun

2013-01-01

In this paper, an operational event that unit trip caused by the operating of the wrong compartment, due to the personnel error is introduced. Through in-depth research on this kind of events the causes of the events are found, some suggestions are put forward. It can provide a reference for preventing the similar events from recurring to other NPPs. (authors)

Collections and Analyses of Common Cause Failure Data for the Korea Standard and Westinghouse Type NPPs

International Nuclear Information System (INIS)

Kang, Dae Il; Han, S. H.

2007-04-01

The analyses of the CCF events for domestic NPPs were performed to establish the domestic database for the CCF events and to deliver supply them to the operation office of the international common cause failure data exchange (ICDE) project. We collected and analyzed the CCF events of emergency diesel generators, centrifugal pumps, motor-operated valves, check valves, circuit breakers for the Korean Standard Type nuclear power plants (NPPs), Yonggwang Units 3 and 4 and Ulchin Units 3 and 4, and the Westinghouse type NPPs, Kori Unit 3 and 4 and Yonggwang Units 1 and 2. First, the components to be collected and analyzed were classified into the common cause component groups (CCCGs) according to the ICDE coding guidelines. Next, the CCF events were identified based on reviews of the component database for the PSA and its related documents, and consultations with NPP staff. Fourteen CCF events were identified. The ratio of the number of CCF events to that of individual failure events was identified as approximately 10 percentages. However, an in depth review of the CCF events showed that most failure severities of them were identified as partial CCF events, which can be interpreted as some component failures within the CCCGs. Root causes of the CCF events were identified as 9 internal part failures, 2 human errors, 2 design deficiencies, 1 procedure inadequacy. It could be concluded that the major root causes of the CCF events were internal piece part failures

Current status and future expectation concerning probabilistic risk assessment of NPPs. 1. Features and issues of probabilistic risk assessment methodology

International Nuclear Information System (INIS)

Yamashita, Masahiro

2012-01-01

Probabilistic risk assessment (PRA) of Nuclear Power Plants (NPPs) could play an important role in assuring safety of NPPs. However PRA had not always effectively used, which was indicated in Japanese government's report on Fukushima Daiichi NPP accident. At the Risk Technical Committee (RTC) of Standards Committee of Atomic Energy Society of Japan, preparation of standards (implementing criteria) focusing on PRA methodology and investigation on basic philosophy for use of PRA had been in progress. Based on activities of RTC, a serial in three articles including this described current status and future expectation concerning probabilistic risk assessment of NPPs. This article introduced features and issues of PRA methodology related to the use of PRA. Features of PRA methodology could be shown as (1) systematic and comprehensive understanding of risk, (2) support of grading approach, (3) identification of effective safety upgrade measures and (4) quantitative understanding of effects of uncertainty. Issues of PRA methodology were (1) extension of PRA application area, (2) upgrade of PRA methodology, (3) quality assurance of PRA, (4) treatment of uncertainty and (5) quantitative evaluation criteria. (T. Tanaka)

Operating Experience of Digital, Software-based Components Used in I and C and Electrical Systems in German NPPs

International Nuclear Information System (INIS)

Blum, Stefanie; Lochthofen, Andre; Quester, Claudia; Arians, Robert

2015-01-01

In recent years, many components in instrumentation and control (I and C) and electrical systems of nuclear power plants (NPPs) were replaced by digital, software-based components. Due to the more complex structure, software-based I and C and electrical components show the potential for new failure mechanisms and an increasing number of failure possibilities, including the potential for common cause failures. An evaluation of the operating experience of digital, software-based components may help to determine new failure modes of these components. In this paper, we give an overview over the results of the evaluation of the operating experience of digital, software-based components used in I and C and electrical systems in NPPs in Germany. (authors)

Evaluation of communication characteristics of operating teams in NPPs using SNA technique

Energy Technology Data Exchange (ETDEWEB)

Kim, H. J.; Lee, S. W.; Kang, H. G.; Seong, P. H. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Park, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kang, H. G. [Khalifa Univ. of Science, Abu Dhabi (United Arab Emirates)

2012-03-15

Inappropriate communications within operational teams can lead to serious consequences of a system since it can cause lack of exchange of important information to perform the task to secure the safety of the system in nuclear power plants (NPPs). For that reason, we studied the communication characteristics However, existing studies on the communication characteristics seem to have problem since they have characterized team communications from a single perspective. According that, we have developed an evaluation method to characterize team communications using social network techniques which can evaluate them from various perspectives which are group cohesiveness, frequency of communications, degree of hierarchy, and communication contents. In addition, we suggested some kids of specific communication characteristics of operating teams that can reduce the occurrence of inappropriate communications. Eight verbal protocol data which are audio-visual recorded under emergency training sessions by main control room (MCR) operating teams are used. As a result of the study, there was negative relationship between group cohesiveness and the ratio of inappropriate communications. Moreover, some kinds of specific communication contents are related to the ratio of inappropriate communications. Consequently, we can evaluate communications characteristics of operating teams in NPPs and suggest specific characteristics to provide useful insights to prevent inappropriate communications.

Evaluation of communication characteristics of operating teams in NPPs using SNA technique

International Nuclear Information System (INIS)

Kim, H. J.; Lee, S. W.; Kang, H. G.; Seong, P. H.; Park, J. K.; Kang, H. G.

2012-01-01

Inappropriate communications within operational teams can lead to serious consequences of a system since it can cause lack of exchange of important information to perform the task to secure the safety of the system in nuclear power plants (NPPs). For that reason, we studied the communication characteristics However, existing studies on the communication characteristics seem to have problem since they have characterized team communications from a single perspective. According that, we have developed an evaluation method to characterize team communications using social network techniques which can evaluate them from various perspectives which are group cohesiveness, frequency of communications, degree of hierarchy, and communication contents. In addition, we suggested some kids of specific communication characteristics of operating teams that can reduce the occurrence of inappropriate communications. Eight verbal protocol data which are audio-visual recorded under emergency training sessions by main control room (MCR) operating teams are used. As a result of the study, there was negative relationship between group cohesiveness and the ratio of inappropriate communications. Moreover, some kinds of specific communication contents are related to the ratio of inappropriate communications. Consequently, we can evaluate communications characteristics of operating teams in NPPs and suggest specific characteristics to provide useful insights to prevent inappropriate communications

ADVANCED MMIS TOWARD SUBSTANTIAL REDUCTION IN HUMAN ERRORS IN NPPS

Directory of Open Access Journals (Sweden)

POONG HYUN SEONG

2013-04-01

Full Text Available This paper aims to give an overview of the methods to inherently prevent human errors and to effectively mitigate the consequences of such errors by securing defense-in-depth during plant management through the advanced man-machine interface system (MMIS. It is needless to stress the significance of human error reduction during an accident in nuclear power plants (NPPs. Unexpected shutdowns caused by human errors not only threaten nuclear safety but also make public acceptance of nuclear power extremely lower. We have to recognize there must be the possibility of human errors occurring since humans are not essentially perfect particularly under stressful conditions. However, we have the opportunity to improve such a situation through advanced information and communication technologies on the basis of lessons learned from our experiences. As important lessons, authors explained key issues associated with automation, man-machine interface, operator support systems, and procedures. Upon this investigation, we outlined the concept and technical factors to develop advanced automation, operation and maintenance support systems, and computer-based procedures using wired/wireless technology. It should be noted that the ultimate responsibility of nuclear safety obviously belongs to humans not to machines. Therefore, safety culture including education and training, which is a kind of organizational factor, should be emphasized as well. In regard to safety culture for human error reduction, several issues that we are facing these days were described. We expect the ideas of the advanced MMIS proposed in this paper to lead in the future direction of related researches and finally supplement the safety of NPPs.

Advanced MMIS Toward Substantial Reduction in Human Errors in NPPs

Energy Technology Data Exchange (ETDEWEB)

Seong, Poong Hyun; Kang, Hyun Gook [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Na, Man Gyun [Chosun Univ., Gwangju (Korea, Republic of); Kim, Jong Hyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of); Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of); Jung, Yoensub [Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of)

2013-04-15

This paper aims to give an overview of the methods to inherently prevent human errors and to effectively mitigate the consequences of such errors by securing defense-in-depth during plant management through the advanced man-machine interface system (MMIS). It is needless to stress the significance of human error reduction during an accident in nuclear power plants (NPPs). Unexpected shutdowns caused by human errors not only threaten nuclear safety but also make public acceptance of nuclear power extremely lower. We have to recognize there must be the possibility of human errors occurring since humans are not essentially perfect particularly under stressful conditions. However, we have the opportunity to improve such a situation through advanced information and communication technologies on the basis of lessons learned from our experiences. As important lessons, authors explained key issues associated with automation, man-machine interface, operator support systems, and procedures. Upon this investigation, we outlined the concept and technical factors to develop advanced automation, operation and maintenance support systems, and computer-based procedures using wired/wireless technology. It should be noted that the ultimate responsibility of nuclear safety obviously belongs to humans not to machines. Therefore, safety culture including education and training, which is a kind of organizational factor, should be emphasized as well. In regard to safety culture for human error reduction, several issues that we are facing these days were described. We expect the ideas of the advanced MMIS proposed in this paper to lead in the future direction of related researches and finally supplement the safety of NPPs.

Advanced MMIS Toward Substantial Reduction in Human Errors in NPPs

International Nuclear Information System (INIS)

Seong, Poong Hyun; Kang, Hyun Gook; Na, Man Gyun; Kim, Jong Hyun; Heo, Gyunyoung; Jung, Yoensub

2013-01-01

This paper aims to give an overview of the methods to inherently prevent human errors and to effectively mitigate the consequences of such errors by securing defense-in-depth during plant management through the advanced man-machine interface system (MMIS). It is needless to stress the significance of human error reduction during an accident in nuclear power plants (NPPs). Unexpected shutdowns caused by human errors not only threaten nuclear safety but also make public acceptance of nuclear power extremely lower. We have to recognize there must be the possibility of human errors occurring since humans are not essentially perfect particularly under stressful conditions. However, we have the opportunity to improve such a situation through advanced information and communication technologies on the basis of lessons learned from our experiences. As important lessons, authors explained key issues associated with automation, man-machine interface, operator support systems, and procedures. Upon this investigation, we outlined the concept and technical factors to develop advanced automation, operation and maintenance support systems, and computer-based procedures using wired/wireless technology. It should be noted that the ultimate responsibility of nuclear safety obviously belongs to humans not to machines. Therefore, safety culture including education and training, which is a kind of organizational factor, should be emphasized as well. In regard to safety culture for human error reduction, several issues that we are facing these days were described. We expect the ideas of the advanced MMIS proposed in this paper to lead in the future direction of related researches and finally supplement the safety of NPPs

The European gen-set market: growth and consolidation mean joy and pain

International Nuclear Information System (INIS)

French, Ian

2000-01-01

The changes in the European gen-set market are discussed. In recent years the market has undergone a period of increasing consolidation: prices fell and some companies folded. However, the market is not dead and continued growth is expected over the next five years although the compound rate is forecast to be only 1.5%. The article is presented under the sub-headings of (i) current market situation; (ii) product lifecycle; (iii) shipments by technology; (iv) market deregulation; (v) technology overview (spark ignition, compression ignition and gas turbines) (vi) European market: national overview and (vii) key market challenges (competition, emissions and over capacity)

Ion temperatures in TORTUR III

International Nuclear Information System (INIS)

Hendriks, F.B.

1985-12-01

Spatially resolved ion-energy distributions are presented for discharges in the TORTUR III tokamak. The measurements are performed in an active method, using a neutral hydrogen probing beam of 20-30 keV, to enhance charge-exchange processes along its path, as well as by the usual passive method. Ion temperatures can amount up to 1 keV

A Study on OBE Exceedance Criteria Using the CAV Concept for NPPs in Korea

International Nuclear Information System (INIS)

Park, Se Moon; Cho, Sung Il; Yun, Kwan Hee

2009-01-01

NPPs in Korea have so far complied with the US Regulatory Guide 1.12 Rev.1 (1974) for the seismic monitoring systems. However, researchers in Korea have been considering attempting to comply with Regulatory Guide 1.12 rev.2 (1997) when implementing all future seismic monitoring systems. To comply with the new regulations, Operating Basis Earthquake (OBE) Exceedance Criteria applied with the Cumulative Absolute Velocity (CAV) has to be developed for local use. The CAV was developed in the USA as one reasonable OBE exceedance criterion for NPPs; however, it has not been widely used outside the USA, not-withstanding its solid technical basis. It is, however, expected that the worldwide NPP construction boom will necessitate development and more frequent use of reasonable OBE exceedance criteria. As multi-units (four or more) are situated in one site in Korea, prevention of simultaneous shutdown of multi-unit caused by non damaging earthquakes is very important; otherwise, a serious economic loss could occur, and there could also be a great impact on the stability of the power grid that would arise due to the unnecessary shutdown. Actually, we have had the experience of observing a Peak Ground Acceleration (PGA)-value greater than 0.1g (the current OBE level for Korean NPPs) due to an M=4.8 earthquake (20 th Jan. '07) that did not even cause any damage to the poorly-designed structures nearby. This experience gave a motivation to the KHNP should concern the needs of study on OBE exceedance criteria in view of application of the CAV to Korean seismic situation, which will be more practical. The present paper is intended to show the intermediate result of the research on Operating Basis Earthquake (OBE) exceedance criteria in Korea

ON-POWER DETECTION OF PIPE WALL-THINNED DEFECTS USING IR THERMOGRAPHY IN NPPS

Directory of Open Access Journals (Sweden)

JU HYUN KIM

2014-04-01

Full Text Available Wall-thinned defects caused by accelerated corrosion due to fluid flow in the inner pipe appear in many structures of the secondary systems in nuclear power plants (NPPs and are a major factor in degrading the integrity of pipes. Wall-thinned defects need to be managed not only when the NPP is under maintenance but also when the NPP is in normal operation. To this end, a test technique was developed in this study to detect such wall-thinned defects based on the temperature difference on the surface of a hot pipe using infrared (IR thermography and a cooling device. Finite element analysis (FEA was conducted to examine the tendency and experimental conditions for the cooling experiment. Based on the FEA results, the equipment was configured before the cooling experiment was conducted. The IR camera was then used to detect defects in the inner pipe of the pipe specimen that had artificially induced defects. The IR thermography developed in this study is expected to help resolve the issues related to the limitations of non-destructive inspection techniques that are currently conducted for NPP secondary systems and is expected to be very useful on the NPPs site.

Mitigation of severe accidents in AREVA's Gen 3+ nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fischer, M., E-mail: manfred.fischer@areva.com; Henning, A.; Surmann, R.

2014-04-01

The current AREVA Gen 3+ PWR designs (EPR™ and ATMEA1) are based on the proven defense-in-depth safety concepts inherited from their predecessors, the French “N4” and the German “Konvoi” reactors. Complemented by specific enhancements, including higher redundancy and diversity as well as the use of passive systems, this leads to very low values of the core damage frequency (CDF). Notwithstanding this very low probability, dedicated design measures have been implemented to improve the response of the plant in case of a postulated severe accident (SA) with core melting. This way not only the frequency of large-early-releases (LERF) but also the related radiological consequences are drastically reduced. Situations that potentially lead to high loads that can challenge the short-term integrity of the containment, like RPV melt-through under high pressure, energetic hydrogen/steam explosions, as well as long-term containment failure caused by internal over-pressure are avoided by a combination of preventive measures and dedicated systems. At the example of the EPR{sup TM}, the paper gives an overview of the severe accident mitigation strategy and the related measures and systems of AREVAs current Gen 3+ reactors, with special focus on the function of the core melt stabilization system.

Evaluation of Passive Containment Cooling System design of SMART built in GBS for ocean environment under the Fukushima Accident Condition

Energy Technology Data Exchange (ETDEWEB)

Kim, Min Gil; Kim, Seong Gu; Lee, Jeong Ik; Lee, Kang Heon; Lee, Phil Seung [Korea Advanced Institue of Science and Technology, Daejeon (Korea, Republic of)

2013-10-15

The ONPP can be towed to the installation site after the SMART is constructed within the GBS in a dry dock. And, by incorporating IPSS (Integrated Passive Safety System), proposed by KAIST, in the ocean SMART the safety of the whole system will be significantly increased which can potentially eliminate any possibility of repeating Fukushima accident again. In recent years, KAIST research team is developing a very advanced concept of ocean NPPs which can avoid natural disasters while potentially increasing economy and enhancing public acceptance. Authors chose Korean small reactor, SMART as a reference system to demonstrate the feasibility of the proposed ocean NPP. Ocean SMART is mounted on GBS (Gravity Based Structure)

Effective surface passivation of InP nanowires by atomic-layer-deposited Al2O3 with POx interlayer

NARCIS (Netherlands)

Black, L.E.; Cavalli, A.; Verheijen, M.A.; Haverkort, J.E.M.; Bakkers, E.P.A.M.; Kessels, W.M.M.

2017-01-01

III/V semiconductor nanostructures have significant potential in device applications, but effective surface passivation is critical due to their large surface-to-volume ratio. For InP such passivation has proven particularly difficult, with substantial depassivation generally observed following

Université de Genève | Séminaire de physique corpusculaire | 29 May

CERN Multimedia

2013-01-01

AMS – First results, Dr Mercedes Paniccia, Université de Genève.   Wednesday 29 May, 11:15 a.m. Science III, Auditoire 1S081 30, quai Ernest-Ansermet, 1211 Genève 4 Abstract: The Alpha Magnetic Spectrometer is a state-of-the-art particle physics detector operating as an external module on the International Space Station. It uses the unique environment of space to study the universe and its origin by searching for antimatter, dark matter while performing precision measurements of cosmic rays composition and flux. Since its installation on May 19, 2011 it has collected over 30 billion cosmic rays of energies ranging from several hundred MeV up to few TeV. In this talk we will present the precision measurement of the positron fraction in cosmic rays in the energy range from 0.5 to 350 GeV based on 6.8 million positron and electron events collected in the initial 18 month period of operation in space. Organised by Prof. Teresa.Montaruli@unige.ch and Prof....

Portable Filtered Air Suction System for Released Radioactive Gases Prevention under a Severe Accident of NPPs

International Nuclear Information System (INIS)

Gu, Beom W.; Choi, Su Y.; Rim, Chun T.

2013-01-01

In this paper, the portable filtered air suction system (PoFASS) for released radioactive gases prevention under a severe accident of NPP is proposed. This technology can prevent the release of the radioactive gases to the atmosphere and it can be more economical than FVCS because PoFASS can cover many NPPs with its high mobility. The conceptual design of PoFASS, which has the highest cost effectiveness and robustness to the environment condition such as wind velocity and precipitation, is suggested and the related previous research is introduced in this paper. The portable filtered air suction system (PoFASS) for released radioactive gases prevention can play a key role to mitigate the severe accident of NPP with its high cost effectiveness and robustness to the environment conditions. As further works, the detail design of PoFASS to fabricate a prototype for a demonstration will be proceeded. When released radioactive gases from the broken containment building in the severe accident of nuclear power plants (NPPs) such as the Chernobyl and Fukushima accidents occur, there are no ways to prevent the released radioactive gases spreading in the air. In order to solve this problem, several European NPPs have adopted the filtered vented containment system (FVCS), which can avoid the containment failure through a pressure relief capability to protect the containment building against overpressure. However, the installation cost of FVCS for a NPP is more than $10 million and this system has not been widely welcomed by NPP operating companies due to its high cost

Recommendations and Requirements for GenCade Simluations

Science.gov (United States)

2014-08-01

will report whether or not GenCade is enabled. If GenCade is disabled , the user will need a new license that includes GenCade...any depth but usually are not deeper than the seaward edge of the surf - zone. In the same way that some shorelines are less desirable for use in...Conference, 1919–1937. ASCE. Wang, P., N. C. Kraus, and R. A. Davis. 1998. Total rate of longshore sediment transport in the surf zone: Field

Spent fuel management of NPPs in Argentina

International Nuclear Information System (INIS)

Alvarez, D.E.; Lee Gonzalez, H.M.

2010-01-01

There are two Nuclear Power Plants in operation in Argentina: 'Atucha I' (unique PHWR design) in operation since 1974, and 'Embalse' (typical Candu reactor) which started operation in 1984. Both NPPs are operated by 'Nucleoelectrica Argentina S.A' which is responsible for the management and interim storage of spent fuel till the end of the operative life of the plants. A third NPP, 'Atucha II' is under construction, with a similar design of Atucha I. The legislative framework establishes that after final shutdown of a NPP the spent fuel will be transferred to the 'National Atomic Energy Commission', which is also responsible for the decommissioning of the Plants. In Atucha I, the spent fuel is stored underwater, until another option is implemented meanwhile in Embalse the spent fuel is stored during six years in pools and then it is moved to a dry storage. A decision about the fuel cycle back-end strategy will be taken before year 2030. (authors)

Safety management in NPPs using evolutionary algorithm

International Nuclear Information System (INIS)

Mishra, A.; Patwardhan, A.; Chauhan, A.; Verma, A.K.

2005-01-01

Technical specification and maintenance (TS and M) activities in a plant are associated with controlling risk or with satisfying requirements, and are candidates to be evaluated for their resource effectiveness in risk-informed applications. The general goal of safety management in Nuclear Power Plants (NPPs) is to make requirements and activities more risk effective and less costly. Accordingly, the risk-based analysis of Technical Specification (RBTS) is being considered in evaluating current TS. The multi objective optimization of the TS and M requirements of a NPP based on risk and cost, gives the pareto-optimal solutions, from which the utility can pick its decision variables suiting its interest. In this paper a multi objective Evolutionary Algorithm technique has been used to make a trade-off between risk and cost both at the system level and at the plant level for Loss of coolant Accident (LOCA) and Main Steam Line Break (MSLB) as initiating events. (authors)

Fuel Behaviour Simulations in Fumex III CRP at NRI

International Nuclear Information System (INIS)

Valach, M.; Klouzal, J.; Dostal, M.; Zymak, J.

2013-01-01

NRI Rez plc took part in the previous coordinated research projects focused on fuel behaviour modelling held by the IAEA - FUMEX-I and FUMEX-II. These were very helpful for the development and validation of various codes used in the Nuclear Research Institute Rez (NRI) for the evaluation of the fuel rod thermomechanical behaviour. Based on the considerations of our needs related to the modeling for Czech NPPs we have performed basic parametric calculations of two LOCA cases (IFA-650.1 and IFA-650.2) and detailed evaluation WWER related cases Kola MIR ramp rods. The AREVA ''Idealized case'' and 16x16 LTA cases were also calculated because of the high burnup reached. Report summarises simulated cases in the frame of FUMEX III Project at the NRI Rez plc. (author)

Unleashing Gen Y: Marketing Mars to Millennials

Science.gov (United States)

Leahy, Bart D.; Hidalgo, Loretta; Kloberdanz, Cassie

2007-01-01

Space advocates need to engage Generation Y (born 1977-1999).This outreach is necessary to recruit the next generation of scientists and engineers to explore Mars. Space advocates in the non-profit, private, and government sectors need to use a combination of technical communication, marketing, and politics, to develop messages that resonate with Gen Y. Until now, space messages have been generated by and for college-educated white males; Gen Y is much more diverse, including as much as one third minorities. Young women, too, need to be reached. My research has shown that messages emphasizing technology, fun, humor, and opportunity are the best means of reaching the Gen Y audience of 60 million (US population is 300 million). The important things space advocates must avoid are talking down to this generation, making false promises, or expecting them to "wait their turn" before they can participate. This is the MTV generation! We need to find ways of engaging Gen Y now to build a future where human beings can live and work on the planet Mars. In addition to the messages themselves, advocates need to keep up with Gen Y' s social networking and use of iPods, cell phones, and the Internet. NASA and space advocacy groups can use these tools for "viral marketing," where young people share targeted space-related information via cell phones or the Internet because they like it. Overall, Gen Y is a socially dynamic and media-savvy group; advocates' space messages need to be sincere, creative, and placed in locations where Gen Y lives. Mars messages must be memorable!

Unprotected Accident Analyses of the 1200MWe GEN-IV Sodium-Cooled Fast Reactor Using the SSC-K Code

International Nuclear Information System (INIS)

Kwon, Young Min; Lee, Kwi Lim; Ha, Kwi Seok; Jeong, Hae Yong; Chang, Won Pyo; Seok, Su Dong; Lee, Yong Bum

2010-02-01

A conceptual design of an advanced breakeven sodium-cooled fast reactor (G4SFR) has recently been developed by KAERI under the national nuclear R and D plan. The G4SFR is a 1,200MWe metal-fueled pool-type sodium-cooled fast reactor adopting advanced safety design features. The G4SFR development plan focuses on particular technology development efforts to effectively meet the goals of the Generation-IV (GEN-IV) nuclear system such as efficient utilization of resources, economic competitiveness, a high standard of safety, and enhanced proliferation resistance. To enhance the safety of G4SFR, advanced design features of metal-fueled core, simple and large sodium-inventory primary heat transport system, and passive safety decay heat removal system are included in the reactor design. To evaluate potential safety characteristics of such advanced design features, the plant responses and safety margins were investigated using the system transient code SSC-K for three unprotected accidents of UTOP, ULOF, and ULOHS. It was shown that the G4SFR design has inherent and passive safety characteristics and is accommodating the selected ATWS events. The inherent safety mechanism of the reactor design makes the core shutdown with sufficient margin and passive removal of decay heat with matching the core power to heat sink by passive self-regulation. The self-regulation of power without scram is mainly due to the inherent negative reactivity feedback in conjunction with the large thermal inertia of the primary heat transport system and the passive decay heat removal. Such favorable inherent and passive safety behaviors of G4SFR are expected to virtually exclude the probability of severe accidents with potential for core damage

Reliability analysis on passive residual heat removal of AP1000 based on Grey model

Energy Technology Data Exchange (ETDEWEB)

Qi, Shi; Zhou, Tao; Shahzad, Muhammad Ali; Li, Yu [North China Electric Power Univ., Beijing (China). School of Nuclear Science and Engineering; Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, Beijing (China); Jiang, Guangming [Nuclear Power Institute of China, Chengdu (China). Science and Technology on Reactor System Design Technology Laboratory

2017-06-15

It is common to base the design of passive systems on the natural laws of physics, such as gravity, heat conduction, inertia. For AP1000, a generation-III reactor, such systems have an inherent safety associated with them due to the simplicity of their structures. However, there is a fairly large amount of uncertainty in the operating conditions of these passive safety systems. In some cases, a small deviation in the design or operating conditions can affect the function of the system. The reliability of the passive residual heat removal is analysed.

Modelo poblacional con algoritmos genéticos

OpenAIRE

Veliz Quintero, Eduardo; Rodriguez Ojeda, Luis

2009-01-01

Para el desarrollo de este trabajo, “MODELO POBLACIONAL CON ALGORITMOS GENÉTICOS”, he investigado la rama de la inteligencia artificial, como son los algoritmos genéticos. Primero presento en forma general los aspectos que envuelven los algoritmos genéticos, parto de la necesidad de optimizar, así como su historia y posibles aplicaciones y luego he cubierto detalladamente todo lo que pude investigar sobre la teoría de los algoritmos genéticos, sus fundamentos matemáticos, tipos de algoritmos ...

Factors Influencing Retention of Gen Y and Non-Gen Y Teachers Working at International Schools in Asia

Science.gov (United States)

Fong, Hoi Wah Benny

2018-01-01

Quantitative studies on international-school teacher retention are few, especially studies that differentiate between Gen Y and non-Gen Y teachers. This article reports on the findings of a study that examined the relationship of job satisfaction factors to the likelihood of contract renewal by international-school teachers. Results from the study…

Metode Transfer Asam Nukleat sebagai Dasar Terapi Gen

Directory of Open Access Journals (Sweden)

Novi Silvia Hardiany

2017-01-01

Full Text Available Kemajuan ilmu biologi molekuler memberikan manfaat dalam bidang kedokteran untuk mengembangkanterapi gen. Tujuan terapi gen adalah untuk memperbaiki kerusakan gen atau mengganti gen yang rusakdengan gen yang normal. Pemindahan gen dilakukan dengan teknik transfeksi. Transfeksi merupakanproses pemindahan asam nukleat baik menggunakan vektor virus (transduksi atau menggunakan metodenonviral yaitu zat kimia, lipid dan metode fisik. Vektor virus yang digunakan pada transduksi adalahretrovirus, adenovirus, adeno-associated virus (AAV dan herpes simplex virus (HSV. Keberhasilantransfeksi ditentukan oleh berbagai faktor yang dapat dapat dinilai dengan menggunakan reporter sepertigreen fluorescence protein (GFP. Kata Kunci: terapi gen, transfeksi non viral, transduksi, vektor virus   Methods of Nucleic Acid Transfer as Basic Gene Therapy Abstract The advancement of molecular biology provides benefit in the field of medicine to develop genetherapy. The aim of gene therapy is to repair the genetic damage or to replace damaged gene with thenormal gene. Delivery of gene is carried out by transfection technique, a technique to transfer nucleic acidinto eukaryote cells either using viral vectors (known as transduction, and also using non viral methodsuch as chemical substance, lipid and physical method. Some of the viral vectors used in the transductionare retrovirus, adenovirus, Adeno-associated virus (AAV and Herpes Simplex Virus (HSV. The success oftransfection is determined by various factors which can be assessed using several reporters such as GreenFluorescence Protein (GFP. Key words: gene therapy, non viral transfection, transduction, viral vector. Normal 0 false false false IN X-NONE X-NONE

Invariant methods for an ensemble-based sensitivity analysis of a passive containment cooling system of an AP1000 nuclear power plant

International Nuclear Information System (INIS)

Di Maio, Francesco; Nicola, Giancarlo; Borgonovo, Emanuele; Zio, Enrico

2016-01-01

Sensitivity Analysis (SA) is performed to gain fundamental insights on a system behavior that is usually reproduced by a model and to identify the most relevant input variables whose variations affect the system model functional response. For the reliability analysis of passive safety systems of Nuclear Power Plants (NPPs), models are Best Estimate (BE) Thermal Hydraulic (TH) codes, that predict the system functional response in normal and accidental conditions and, in this paper, an ensemble of three alternative invariant SA methods is innovatively set up for a SA on the TH code input variables. The ensemble aggregates the input variables raking orders provided by Pearson correlation ratio, Delta method and Beta method. The capability of the ensemble is shown on a BE–TH code of the Passive Containment Cooling System (PCCS) of an Advanced Pressurized water reactor AP1000, during a Loss Of Coolant Accident (LOCA), whose output probability density function (pdf) is approximated by a Finite Mixture Model (FMM), on the basis of a limited number of simulations. - Highlights: • We perform the reliability analysis of a passive safety system of Nuclear Power Plant (NPP). • We use a Thermal Hydraulic (TH) code for predicting the NPP response to accidents. • We propose an ensemble of Invariant Methods for the sensitivity analysis of the TH code • The ensemble aggregates the rankings of Pearson correlation, Delta and Beta methods. • The approach is tested on a Passive Containment Cooling System of an AP1000 NPP.

Long-wavelength III-V/silicon photonic integrated circuits

NARCIS (Netherlands)

Roelkens, G.C.; Kuyken, B.; Leo, F.; Hattasan, N.; Ryckeboer, E.M.P.; Muneeb, M.; Hu, C.L.; Malik, A.; Hens, Z.; Baets, R.G.F.; Shimura, Y.; Gencarelli, F.; Vincent, B.; Loo, van de R.; Verheyen, P.A.; Lepage, G.; Campenhout, van J.; Cerutti, L.; Rodriquez, J.B.; Tournie, E.; Chen, X; Nedeljkovic, G.; Mashanovich, G.; Liu, X.; Green, W.S.

2013-01-01

We review our work in the field of short-wave infrared and mid-infrared photonic integrated circuits for applications in spectroscopic sensing systems. Passive silicon waveguide circuits, GeSn photodetectors, the integration of III-V and IV-VI semiconductors on these circuits, and silicon nonlinear

A Methodology for Modeling Nuclear Power Plant Passive Component Aging in Probabilistic Risk Assessment under the Impact of Operating Conditions, Surveillance and Maintenance Activities

Science.gov (United States)

Guler Yigitoglu, Askin

In the context of long operation of nuclear power plants (NPPs) (i.e., 60-80 years, and beyond), investigation of the aging of passive systems, structures and components (SSCs) is important to assess safety margins and to decide on reactor life extension as indicated within the U.S. Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) Program. In the traditional probabilistic risk assessment (PRA) methodology, evaluating the potential significance of aging of passive SSCs on plant risk is challenging. Although passive SSC failure rates can be added as initiating event frequencies or basic event failure rates in the traditional event-tree/fault-tree methodology, these failure rates are generally based on generic plant failure data which means that the true state of a specific plant is not reflected in a realistic manner on aging effects. Dynamic PRA methodologies have gained attention recently due to their capability to account for the plant state and thus address the difficulties in the traditional PRA modeling of aging effects of passive components using physics-based models (and also in the modeling of digital instrumentation and control systems). Physics-based models can capture the impact of complex aging processes (e.g., fatigue, stress corrosion cracking, flow-accelerated corrosion, etc.) on SSCs and can be utilized to estimate passive SSC failure rates using realistic NPP data from reactor simulation, as well as considering effects of surveillance and maintenance activities. The objectives of this dissertation are twofold: The development of a methodology for the incorporation of aging modeling of passive SSC into a reactor simulation environment to provide a framework for evaluation of their risk contribution in both the dynamic and traditional PRA; and the demonstration of the methodology through its application to pressurizer surge line pipe weld and steam generator tubes in commercial nuclear power plants. In the proposed methodology, a

Thiol passivation of MWIR type II superlattice photodetectors

Science.gov (United States)

Salihoglu, O.; Muti, A.; Aydinli, A.

2013-06-01

Poor passivation on photodetectors can result in catastrophic failure of the device. Abrupt termination of mesa side walls during pixel definition generates dangling bonds that lead to inversion layers and surface traps leading to surface leakage currents that short circuit diode action. Good passivation, therefore, is critical in the fabrication of high performance devices. Silicondioxide has been the main stay of passivation for commercial photodetectors, deposited at high temperatures and high RF powers using plasma deposition techniques. In photodetectors based on III-V compounds, sulphur passivation has been shown to replace oxygen and saturate the dangling bonds. Despite its effectiveness, it degrades over time. More effort is required to create passivation layers which eliminate surface leakage current. In this work, we propose the use of sulphur based octadecanethiol (ODT), CH3(CH2)17SH, as a passivation layer for the InAs/GaSb superlattice photodetectors that acts as a self assembled monolayer (SAM). ODT SAMs consist of a chain of 18 carbon atoms with a sulphur atom at its head. ODT Thiol coating is a simple process that consist of dipping the sample into the solution for a prescribed time. Excellent electrical performance of diodes tested confirm the effectiveness of the sulphur head stabilized by the intermolecular interaction due to van der Walls forces between the long chains of ODT SAM which results in highly stable ultrathin hydrocarbon layers without long term degradation.

Análise de distância genética entre acessos do gênero Psidium via marcadores ISSR

Directory of Open Access Journals (Sweden)

Názila Nayara Silva de Oliveira

2014-12-01

Full Text Available O objetivo deste trabalho foi avaliar a distância genética entre 37 acessos da espécie cultivada Psidium guajava, L. (goiaba e de araçás do gênero Psidium do banco de germoplasma da Universidade Estadual do Norte Fluminense (UENF, via marcadores moleculares ISSR. Nos 17 marcadores selecionados, foram obtidas 216 bandas polimórficas. Pelo método de agrupamento UPGMA, houve a formação de cinco principais grupos. Os acessos de araçá da espécie P. cattleyanum Sabine , ficaram alocados nos grupos I e II. No grupo II, foi observada, dentro da espécie P cattleyanum, maior proximidade com a goiabeira. No grupo III, ficou alocado o acesso da espécie P. guineense Sw (araçá-do-campo e dentre os araçás, foi o que ficou mais próximo da goiaba. Os genótipos de goiabeira ficaram alocados do grupo IV e V, confirmando sua alta divergência. Os marcadores moleculares foram eficientes em estimar a distância genética intra e interespecífica.

First experience with the installation of passive autocatalytic recombiners

International Nuclear Information System (INIS)

Snoeck, J.; Solaro, C.; Moeyaert, P.

1997-01-01

From the principle decision of installing Passive Autocatalytic Recombiners (PARs) in all Belgian NPPs to the installation on site, several problems needed to be identified and solved; it is the goal of this paper to address these issues and to present the solutions which were adopted. The first section deals with the sizing and the distribution of the catalytic surface inside the containment to be equipped. Rather than to rely on numerous multicompartment calculations, the procedure is based on a single volume approach combined with engineering judgement. The criteria applied in the successive design steps are explained and illustrated for the Doel1 unit. The second section is devoted to additional requirements concerning the resistance to poisoning agents and the maintenance constraints, and to some recommendations for the design of the supports. Because the effectiveness of the PARs entirely relies on the catalyst material, a periodic control of the active parts is of primary importance. Therefore, the Transportable In-Service Inspection Equipment (TIIE) and the test procedures are presented in the third section. Finally, recommendations are made for further work, derived from this first experience. (author)

Equipment and building structures ageing management for WWER type NPPs

International Nuclear Information System (INIS)

Mayboroda, O.

2001-01-01

This report presents the working group 'Equipment and building structures ageing management for WWER type NPPs' activities. The analysis of experience in ageing management, recommendations for regulatory guidelines on ageing management, investigation of case studies, definition suitable communication channels among regulators for ageing related data are given. Analyses of water chemistry, inspection data (safety margins criteria), plugging criteria, volume and time of ECT implementation in all WWER countries are presented. The results of Working group activity show that it is advisable to concentrate efforts on: set up the permanent communication channel among regulators, collection of regulatory criteria for WWER type NPP key components based on understanding of ageing mechanisms and data collection

Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Nie,J.; Braverman, J.; Hofmayer, C.; Kim, M. K.; Choi, I-K.

2009-04-27

describes the research effort performed by BNL for the Year 2 scope of work. This research focused on methods that could be used to represent the long-term behavior of materials used at NPPs. To achieve this BNL reviewed time-dependent models which can approximate the degradation effects of the key materials used in the construction of structures and passive components determined to be of interest in the Year 1 effort. The intent was to review the degradation models that would cover the most common time-dependent changes in material properties for concrete and steel components.

Thinned pipe management program of Korean NPPs

International Nuclear Information System (INIS)

Lee, S.H.; Kim, T.R.; Jeon, S.C.; Hwang, K.M.

2003-01-01

Wall thinning of carbon steel pipe components due to Flow-Accelerated Corrosion (FAC) is one of the most serious threats to the integrity of steam cycle systems in Nuclear Power Plants (NPP). If the thickness of a pipe component is reduced below the critical level, it cannot sustain stress and consequently results in leakage or rupture. In order to minimize the possibility of excessive wall thinning, Thinned Pipe Management Program (TPMP) has been set up and being implemented to all Korean NPPs. Important elements of the TPMP include the prediction of the FAC rate for each component based on model analysis, prioritization of pipe components for inspection, thickness measurement, calculation of wear and wear rate for each component. Additionally, decision making associated with replacement or continuous service for thinned pipe components and establishment of long-term strategic management plan based on diagnosis of plant condition regarding overall wall thinning also are essential part of the TPMP. From pre-service inspection data, it has been found that initial thickness is varies, which influences wear and wear rate calculations. (author)

Analysis on the Current Status of Chemical Decontamination Technology of Steam Generators in the Oversea Nuclear Power Plants (NPPs)

Energy Technology Data Exchange (ETDEWEB)

Yoon, Taebin; Kim, Sukhoon; Kim, Juyoul; Kim, Juyub; Lee, Seunghee [FNC Technology Co. Ltd., Yongin (Korea, Republic of)

2015-10-15

The steam generators in Hanbit Unit 3 and 4 are scheduled to be replaced in 2018 and 2019, respectively. Nevertheless, the wastes from the dismantled steam generators are currently just on-site stored in the NPP because there are no disposal measures for the waste and lack of the decontamination techniques for large-sized metallic equipment. In contrast, in the oversea NPPs, there are many practical cases of chemical decontamination not only for oversized components in the NPPs such as reactor pressure vessel and steam generator, but also for major pipes. Chemical decontamination technique is more effective in decontaminating the components with complicated shape compared with mechanical one. Moreover, a high decontamination factor can be obtained by using strong solvent, and thereby most of radionuclides can be removed. Due to these advantages, the chemical decontamination has been used most frequently for operation of decontaminating the large-sized equipment. In this study, an analysis on the current status of chemical decontamination technique used for the steam generators of the foreign commercial NPPs was performed. In this study, the three major chemical decontamination processes were reviewed, which are applied to the decommissioning process of the steam generators in the commercial NPPs of the United States, Germany, and Belgium. The three processes have the different features in aspect of solvent, while those are based in common on the oxidation and reduction between the target metal surface and solvents. In addition, they have the same goals for improving the decontamination efficiency and decreasing the amount of the secondary waste generation. Based on the analysis results on component sub-processes and major advantages and disadvantages of each process, Table 2 shows the key fundamental technologies for decontamination of the steam generator in Korea and the major considerations in the development process of each technology. It is necessary to prepare

On the heat exchange tube failures in steam generators at NPPs with WWER reactors

International Nuclear Information System (INIS)

Titov, V.F.; Banyuk, G.F.; Brykov, S.I.

1992-01-01

Data on dynamics of failed heat exchanging tube closing in steam generators of NPPs with WWER type reactors for the whole period of their operation are presented. It is shown that the main cause of the tube failures consists in their corrosion cracking under stresses. The effect of chlorine ions on tubes is intensified by the presence of porous sediments on heat exchaning surfaces in quantities exceeding 150 g/m 2

Characterization of Romboutsia ilealis gen. nov., sp. nov., isolated from the gastro-intestinal tract of a rat, and proposal for the reclassification of five closely related members of the genus Clostridium into the genera Romboutsia gen. nov., Intestinibacter gen. nov., Terrisporobacter gen. nov. and Asaccharospora gen. nov.

Science.gov (United States)

Gerritsen, Jacoline; Fuentes, Susana; Grievink, Wieke; van Niftrik, Laura; Tindall, Brian J; Timmerman, Harro M; Rijkers, Ger T; Smidt, Hauke

2014-05-01

A Gram-positive staining, rod-shaped, non-motile, spore-forming obligately anaerobic bacterium, designated CRIBT, was isolated from the gastro-intestinal tract of a rat and characterized. The major cellular fatty acids of strain CRIBT were saturated and unsaturated straight-chain C12-C19 fatty acids, with C16:0 being the predominant fatty acid. The polar lipid profile comprised six glycolipids, four phospholipids and one lipid that did not stain with any of the specific spray reagents used. The only quinone was MK-6. The predominating cell-wall sugars were glucose and galactose. The peptidoglycan type of strain CRIBT was A1σ lanthionine-direct. The genomic DNA G+C content of strain CRIBT was 28.1 mol%. On the basis of 16S rRNA gene sequence similarity, strain CRIBT was most closely related to a number of species of the genus Clostridium, including Clostridium lituseburense (97.2%), Clostridium glycolicum (96.2%), Clostridium mayombei (96.2%), Clostridium bartlettii (96.0%) and Clostridium irregulare (95.5%). All these species show very low 16S rRNA gene sequence similarity (genus Clostridium. DNA-DNA hybridization with closely related reference strains indicated reassociation values below 32%. On the basis of phenotypic and genetic studies, a novel genus, Romboutsia gen. nov., is proposed. The novel isolate CRIBT (=DSM 25109T=NIZO 4048T) is proposed as the type strain of the type species, Romboutsia ilealis gen. nov., sp. nov., of the proposed novel genus. It is proposed that C. lituseburense is transferred to this genus as Romboutsia lituseburensis comb. nov. Furthermore, the reclassification into novel genera is proposed for C. bartlettii, as Intestinibacter bartlettii gen. nov., comb. nov. (type species of the genus), C. glycolicum, as Terrisporobacter glycolicus gen. nov., comb. nov. (type species of the genus), C. mayombei, as Terrisporobacter mayombei gen. nov., comb. nov., and C. irregulare, as Asaccharospora irregularis gen. nov., comb. nov. (type species

To selecting the characteristics of saturated steam direct cycle NPPs for operation under variable loads

International Nuclear Information System (INIS)

Khrustalev, V.A.; Demidov, O.I.

1986-01-01

Problems for operating process optimization of NPPs with RBMK type reactors under load swings in the power system is considered. Determination technique for optimal values of such parameters as initial steam pressure and fuel enrichment for NPP different load factors is developed. Optimization of these parameters gives a 150000 rouble saving of annual expenditures per each 3200 MW of reactor heat output

Project investigation and analysis of soil-structure interaction effects in seismic response of NPPs EBO, EMO, Slovakia. Final report

International Nuclear Information System (INIS)

Juhasova, E.

1999-01-01

The work described in this report was devoted to investigation of expected seismic response of the structures of WWER-440/213 type NPPs, namely Mochovce and Bohunice. Special attention was devoted to the properties of subsoil materials and the transfer of seismic waves from the bedrock to the foundation structures. Theoretical background was elaborated and discussed for wave propagation of surface waves. Alternative procedure was derived for non-linear media accounting for complex modulus theory. Material characteristics of subsoils were investigated for both NPPs. The obtained results were used as a basis for forecasting and calculation of expected seismic response when the time history records from Paks explosion were used an input. It was pointed out that the used procedure, together with previous calculation of subsoil transfer characteristics completed well the comparison with experimental results

O impacto da genética na asma infantil

OpenAIRE

Pinto,Leonardo A.; Stein,Renato T.; Kabesch,Michael

2008-01-01

OBJETIVO: Apresentar os resultados dos estudos mais importantes e recentes sobre a genética da asma. Estes dados devem auxiliar os clínicos gerais a compreender o impacto da genética sobre este distúrbio complexo e como os genes e polimorfismos influenciam a asma e a atopia. FONTES DOS DADOS: Os dados foram coletados do banco de dados MEDLINE. Os estudos de associação genética foram selecionados do Genetic Association Database, um repositório de estudos de associação genética de doenças e dis...

Université de Genève | Séminaire de physique corpusculaire | 26 February

CERN Multimedia

2014-01-01

Neutrino physics in the Planck era, Prof. Gennaro Miele, University of Naples   Wednesday 26 February 2014, 11:15 a.m. Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: I briefly summarize the status of art about the properties of relic neutrino distributions and the implications of different neutrino scenarios on cosmological observables after the first measurements by Planck. In particular, I will pay particular attention to the effects due to neutrino-antineutrino asymmetry and to the presence of sterile degrees of freedom. Organised by Prof. Teresa.Montaruli@unige.ch and Prof. Giuseppe.Iacobucci@unige.ch. More information here.

Université de Genève | Séminaire de physique corpusculaire | 6 November

CERN Multimedia

2013-01-01

Particle sensors in CMOS Technologies, Dr Ivan Peric, Heidelberg University.   Wednesday 6 November 2013, 11:15 a.m. Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: The use of pixel sensors implemented in standard CMOS technologies has gained in popularity over the last decade. The most prominent application is consumer electronics – the sensors for digital cameras. CMOS sensors are also a promising option for high energy physics. An overview of existing CMOS detector structures for particle tracking will be given, and their properties compared. Organised by Prof. Teresa.Montaruli@unige.ch and Prof. Giuseppe.Iacobucci@unige.ch. More information here.

Setting Component Priorities in Protecting NPPs against Cyber-Attacks Using Reliability Analysis Techniques

International Nuclear Information System (INIS)

Choi, Moon Kyoung; Seong, Poong Hyun; Son, Han Seong

2017-01-01

The digitalization of infrastructure makes systems vulnerable to cyber threats and hybrid attacks. According to ICS-CERT report, as time goes by, the number of vulnerabilities in ICS industries increases rapidly. Digital I and C systems have been developed and installed in nuclear power plants, and due to installation of the digital I and C systems, cyber security concerns are increasing in nuclear industry. However, there are too many critical digital assets to be inspected in digitalized NPPs. In order to reduce the inefficiency of regulation in nuclear facilities, the critical components that are directly related to an accident are elicited by using the reliability analysis techniques. Target initial events are selected, and their headings are analyzed through event tree analysis about whether the headings can be affected by cyber-attacks or not. Among the headings, the headings that can be proceeded directly to the core damage by the cyber-attack when they are fail are finally selected as the target of deriving the minimum cut-sets. We analyze the fault trees and derive the minimum set-cuts. In terms of original PSA, the value of probability for the cut-sets is important but the probability is not important in terms of cyber security of NPPs. The important factors is the number of basic events consisting of the minimal cut-sets that is proportional to vulnerability.

Discusión: Explicaciones genéticas y psicológicas de la esquizofrenia.Genética de la esperanza

Directory of Open Access Journals (Sweden)

Silvio Bolaños-Salvatierra

2003-01-01

Full Text Available En este documento se rebaten críticas hechas por Raventós y Jensen al artículo “Genética y comportamiento”. Cuatro temas fueron seleccionados: 1 se determina que los antipsicóticos aparecieron veinte años después de la concepción hereditaria de la esquizofrenia; 2 se considera que la discusión es altamente pertinente, para nada bizantina o irrelevante, debido que persisten prácticas epistémicas riesgosas en los investigadores genético-conductuales; 3 aunque ninguna conducta humana está exenta de influencia constitucional, el enfoque biologicista se ha propasado al pretender explicar genéticamente casi todo, desconfirmando solapadamente la importancia de la historia personal; y, 4 se plantea que la investigación biológica sobrevalora el peso de las anomalías genéticas frente a la historia social, por lo que solo aparenta cautela. Se propone investigar genéticamente la esperanza con el objetivo de saturar a la humanidad con ese tipo de explicaciones, para alcanzar más rápido una convivencia basada en la tolerancia y el respeto.

Some aspects of nuclear fuel utilisation at Ukrainian's NPPs during last two years

International Nuclear Information System (INIS)

Ieremenko, M.; Bilodid, Y.; Ovdiienko, Y.

2011-01-01

In the first part of the report the brief characteristic of the realized fuel cycles on Ukraine's NPPs, types of loaded fuel is described. Experience of new fuel type implementation are present (FA Second Generation for WWER-440. Westinghouse FA for WWER-1000). Next issue of report is the some of problem with fuel utilisation (leakage FA, problem with C b calculation and other). And the last issue of report is presentation of future new fuel implementation (WWER-440/1000). (authors)

System code improvements for modelling passive safety systems and their validation

Energy Technology Data Exchange (ETDEWEB)

Buchholz, Sebastian; Cron, Daniel von der; Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)

2016-11-15

GRS has been developing the system code ATHLET over many years. Because ATHLET, among other codes, is widely used in nuclear licensing and supervisory procedures, it has to represent the current state of science and technology. New reactor concepts such as Generation III+ and IV reactors and SMR are using passive safety systems intensively. The simulation of passive safety systems with the GRS system code ATHLET is still a big challenge, because of non-defined operation points and self-setting operation conditions. Additionally, the driving forces of passive safety systems are smaller and uncertainties of parameters have a larger impact than for active systems. This paper addresses the code validation and qualification work of ATHLET on the example of slightly inclined horizontal heat exchangers, which are e. g. used as emergency condensers (e. g. in the KERENA and the CAREM) or as heat exchanger in the passive auxiliary feed water systems (PAFS) of the APR+.

Technical Insight of the High Level Safety Goal for the NPPs Built in China’S Thirteenth Five-Year Period (2016-2020)

Energy Technology Data Exchange (ETDEWEB)

Shi, G.; Zhan, W.; Mei, Q.; Sun, D., E-mail: shi@snerdi.com.cn [Shanghai Nuclear Engineering Research and Design Institute, SNPTC Shanghai (China)

2014-10-15

The “Nuclear Safety Planning” has been published in Oct. 2012 in China, which stipulates the safety goals for the NPPs which will be built in the future. As for the NPPs which will be built in China's Thirteenth Five-Year (2016-2020) and later, the high level safety goal is described as “the possibility of the large radioactive release should be practically eliminated by design”. A thorough investigation has been performed at SNERDI to explore the technical insights of this high level safety goal by using MEDP hierarchical safety goal approach. The definition of large release is proposed accordingly, DID requirements and probabilistic requirements are derived from this high level safety goal. (author)

Nuclear fuel for NPPs: current status and main trends of development

International Nuclear Information System (INIS)

Molchanov, V.

2013-01-01

The customer’s main requirements to nuclear fuel at the present day are: to provide high performance of operational reliability of fuel; to uprate NPP’s capacity to the level of more than 100% from the designed one; to increase fuel cycle length; to increase the burnup of the fuel; to introduce load-follow mode at NPPs. To achieve this requirements the following TVEL activities are presented: New FA designs; Modern designing methods; New automated technologies of nuclear fuel fabrication; Driving to Zero Failure; Increase in safety and reliability of operation; Increase in economical efficiency of fuel utilization; Decrease in amount of spent fuel

Impact of Fukushima NPPs Accident on Young Generation's Understanding of Radiation

International Nuclear Information System (INIS)

Choi, Yoonseok; Kim, Wook; Joo, Yeonjung; Choi, Nowoon

2013-01-01

As this study project has been conducted continuously before and after the breaking-out of the Fukushima NPPs accident (FNPPA), accumulated data were analyzed to seek impact of the accident. Results indicated that the first-hand measurement of radiation carried out so far was turned out to be an effective means for mitigation of students' over-sensitive radiation fear even though some influence of the FNPPA was identified in analysis of questionnaire data. The FNPPA brought about radiation fear to the people all over the country. However, it is believed that radiation together with nuclear energy will favorably be understandable by the public through implementation of this first-hand experience program

The concept of the innovative power reactor

Directory of Open Access Journals (Sweden)

Sang Won Lee

2017-10-01

Full Text Available The Fukushima accident reveals the vulnerability of existing active nuclear power plant (NPP design against prolonged loss of external electricity events. The passive safety system is considered an attractive alternative to cope with this kind of disaster. Also, the passive safety system enhances both the safety and the economics of NPPs. The adoption of a passive safety system reduces the number of active components and can minimize the construction cost of NPPs. In this paper, reflecting on the experience during the development of the APR+ design in Korea, we propose the concept of an innovative Power Reactor (iPower, which is a kind of passive NPP, to enhance safety in a revolutionary manner. The ultimate goal of iPower is to confirm the feasibility of practically eliminating radioactive material release to the environment in all accident conditions. The representative safety grade passive system includes a passive emergency core cooling system, a passive containment cooling system, and a passive auxiliary feedwater system. Preliminary analysis results show that these concepts are feasible with respect to preventing and/or mitigating the consequences of design base accidents and severe accidents.

Genética e hanseníase

Directory of Open Access Journals (Sweden)

Bernardo Beiguelman

Full Text Available As diferentes linhas de pesquisa utilizadas para investigar a importância dos fatores hereditários humanos na determinação da resistência/suscetibilidade à infecção pelo Mycobacterium leprae foram discutidas no presente trabalho. Uma síntese dessas abordagens permitiu analisar os resultados das investigações sobre associação da hanseníase com polimorfismos genéticos, distribuição familial da hanseníase, prevalência da hanseníase e distância genética, concordância da hanseníase em gêmeos e estudos genéticos sobre a reação de Mitsuda.

Report of a consultants meeting on backfittings and safety enhancement measures in NPPs with WWER 440/213 reactors. Extrabudgetary programme on the safety of WWER NPPS

International Nuclear Information System (INIS)

1994-01-01

The purpose of this Consultants' Meeting held by the IAEA in Vienna from 11-15 April 1994 within the framework of the Extrabudgetary Programme on WWER Safety was to review and analyze safety issues revealed during operation and through analyses of NPPs with WWER 440/213 reactors. The initial list of safety issues based on the available reports from various studies had been prepared by the IAEA secretariat before the meeting, together with indications of safety enhancement measures proposed in various NPP units. During the meeting, the underlying safety concerns and actual technical status of the plants were discussed and the ranking of the safety issues was considered. 58 refs, 1 tab

A mountain of millipedes III

DEFF Research Database (Denmark)

Enghoff, Henrik

2016-01-01

The new genus Geotypodon gen. nov. is described. It includes two species from the Udzungwa Mountains: G. millemanus gen. et sp. nov. (type species) and G. submontanus gen. et sp. nov., one species from nearby Iringa: G. iringensis gen. et sp. nov., and 18 previously described species hitherto...

Genética de la preeclampsia: una aproximación a los estudios de ligamiento genético.

Directory of Open Access Journals (Sweden)

Nora Alejandra Zuluaga

2004-06-01

Full Text Available La preeclampsia es considerada un problema de salud pública debido a su alta prevalencia. Muchas investigaciones coinciden en que su origen se relaciona con la interacción entre factores genéticos y ambientales. Por esta razón, múltiples estudios han explorado tales factores genéticos tratando de identificar regiones cromosómicas y genes candidatos cuyas variantes se relacionen con una mayor susceptibilidad a la enfermedad. Diversos estudios de asociación han identificado algunos genes de susceptibilidad a la preeclampsia, pero los resultados no se han replicado consistentemente en todas las poblaciones, quizá por su complejidad clínica y genética. El levantamiento de mapas de genes y regiones cromosómicas basado en análisis de ligamiento ha mostrado resultados interesantes con algunos marcadores en los cromosomas 2 y 4. En este sentido, hay muchas expectativas con respecto a los genes localizados en tales regiones candidatas, debido a que la identificación de los factores de riesgo genético podría ayudar al entendimiento de esta condición y en proveer claves para su prevención y tratamiento.

Electronic Biosensors Based on III-Nitride Semiconductors.

Science.gov (United States)

Kirste, Ronny; Rohrbaugh, Nathaniel; Bryan, Isaac; Bryan, Zachary; Collazo, Ramon; Ivanisevic, Albena

2015-01-01

We review recent advances of AlGaN/GaN high-electron-mobility transistor (HEMT)-based electronic biosensors. We discuss properties and fabrication of III-nitride-based biosensors. Because of their superior biocompatibility and aqueous stability, GaN-based devices are ready to be implemented as next-generation biosensors. We review surface properties, cleaning, and passivation as well as different pathways toward functionalization, and critically analyze III-nitride-based biosensors demonstrated in the literature, including those detecting DNA, bacteria, cancer antibodies, and toxins. We also discuss the high potential of these biosensors for monitoring living cardiac, fibroblast, and nerve cells. Finally, we report on current developments of covalent chemical functionalization of III-nitride devices. Our review concludes with a short outlook on future challenges and projected implementation directions of GaN-based HEMT biosensors.

Application of ASSET methodology and operational experience feedback of NPPs in China

Energy Technology Data Exchange (ETDEWEB)

Lan, Ziyong [The National Nuclear Safety Administration, Beijing (China)

1997-10-01

The introductive presentation of ASSET methodology to China started in March 1992, 3 experts from the IAEA held the ASSET Seminar in Wuhan, China. Three years later, an IAEA seminar on ASSET Method and Operational Experience Feedback proceeded in Beijing on 20-24 March 1995. Another ASSET seminar on Self-Assessment and Operational Experience Feedback was held at Guangdong NPP site on 2-6 December 1996, The NNSA and the GNPP hosted the seminar, 2 IAEA experts, 55 participants from the NPPs, research institutes, the regulatory body (NNSA) and its regional offices attended the seminar. 3 figs, 5 tabs.

Application of ASSET methodology and operational experience feedback of NPPs in China

International Nuclear Information System (INIS)

Ziyong Lan

1997-01-01

The introductive presentation of ASSET methodology to China started in March 1992, 3 experts from the IAEA held the ASSET Seminar in Wuhan, China. Three years later, an IAEA seminar on ASSET Method and Operational Experience Feedback proceeded in Beijing on 20-24 March 1995. Another ASSET seminar on Self-Assessment and Operational Experience Feedback was held at Guangdong NPP site on 2-6 December 1996, The NNSA and the GNPP hosted the seminar, 2 IAEA experts, 55 participants from the NPPs, research institutes, the regulatory body (NNSA) and its regional offices attended the seminar. 3 figs, 5 tabs

[The mutations of the D-loop hypervariable region II and hypervariable region III of mitochondrial DNA in oral squamous cell carcinoma].

Science.gov (United States)

Wang, Yao-Zhong; Jia, Mu-Yun; Yuan, Rong-Tao; Han, Guo-Dong; Bu, Ling-Xue

2010-06-01

To investigate the frequency of mitochondrial DNA (mtDNA) D-loop hypervariable region II (HVR II) and hypervariable region III (HVR III) mutations in oral squamous cell carcinoma (OSCC) and their correlation to provide the new targets for the prevention and treatment of OSCC. The D-loop HVR II and HVR III regions of mtDNA in seven cases with OSCC tissues, matched with paracancerous tissues and normal mucosa tissues from the same case, were amplified by polymerase chain raction (PCR), then were detected by direct sequencing to find the mutantsites after the comparison of all sequencing results with the mtDNA Cambridge sequence in the GenBank database. 82 (56 species) nucleotide changes, with 51(26 species) nucleotide polymorphism, were found after the comparison of all sequencing results with the mtDNA Cambridge sequence in the GenBank database. 31(30 species) mutations, with 21 located within the HVR II and HVR III regions, were found in 3 tumor tissue samples, their paracancerous and normal mucosa tissue were found more polymorphic changes but no mutation. The mtDNA D-loop HVR II and HVR III regions mutation rate was 42.9% (3/7) in OSCC. The mtDNA D-loop HVR II and HVR III regions were highly polymorphic and mutable regions in OSCC. It suggested that the D-loop HVR II and HVR III regions of mtDNA might play a significant role in the tumorigenesis of OSCC. It may become new targets for the gene therapy of OSCC by regulating the above indexes.

Divergence and genetic variability among superior rubber tree genotypes Divergência e variabilidade genética de genótipos superiores de seringueira

Directory of Open Access Journals (Sweden)

Lígia Regina Lima Gouvêa

2010-02-01

Full Text Available The objective of this work was to estimate the genetic variability and divergence among 22 superior rubber tree (Hevea sp. genotypes of the IAC 400 series. Univariate and multivariate analyses were performed using eight quantitative traits (descriptors, including yield. In the univariate analyses, the estimated parameters were: genetic and environmental variances; genetic and environmental coefficients of variation; and the variation index. The Mahalanobis generalized distance, the Tocher agglomerative method and canonical variables were used for the multivariate analyses. In the univariate analyses, variability was verified among the genotypes for all the variables evaluated. The Tocher method grouped the genotypes into 11 clusters of dissimilarity. The first four canonical variables explained 87.93% of the cumulative variation. The highest genetic variability was found in rubber yield-related traits, which contributed the most to the genetic divergence. The most divergent pairs of genotypes are suggested for crossbreeding. The genotypes evaluated are suitable for breeding and may be used to continue the IAC rubber tree breeding program.O objetivo deste trabalho foi estimar a divergência e a variabilidade genética entre 22 genótipos superiores de seringueira (Hevea sp. da série IAC 400. Análises univariadas e multivariadas foram realizadas com oito caracteres quantitativos (descritores, incluindo produtividade. Na análise univariada, os parâmetros estimados foram: variâncias genética e ambiental, coeficientes de variação genética e ambiental, e índice de variação. A distância generalizada de Mahalanobis, o método aglomerativo de Tocher e variáveis canônicas foram utilizados nas análises multivariadas. Nas análises univariadas, verificou-se variabilidade entre os genótipos para todas as variáveis avaliadas. O método de Tocher agrupou os genótipos em 11 grupos de dissimilaridade. As quatro primeiras variáveis can

Estructura y diversidad genética en vacas Holstein de Antioquia usando un polimorfismo del gen bGH

Directory of Open Access Journals (Sweden)

Juan Rincon F.

2013-03-01

Full Text Available Objetivo. Determinar las frecuencias alélicas y genotípicas del polimorfismo del intrón 3 del gen bGH y estimar algunos parámetros de estructura poblacional en ganado Holstein. Materiales y métodos. El estudio se realizó con 1366 vacas Holstein en 120 hatos de 11 municipios del departamento de Antioquia. Se extrajo DNA por el método de Salting out y la genotipificación se realizó usando la técnica de PCR-RFLPs. La diversidad genética se determinó mediante la comparación de las heterocigosidades, El equilibrio de Hardy-Weinberg (HW y la diferenciación genética entre las poblaciones se realizó usando el software Arlequín 2.0 Las frecuencias alélicas y genotípicas se evaluaron mediante el paquete estadístico SAS®. Resultados. Las frecuencias genotípicas encontradas fueron 0.764 (+/+, 0.223 (+/- y 0.013 (-/- y las frecuencias alélicas 0.876 (+ y 0.124 (-. No se encontraron desviaciones del Equilibrio de Hardy Weinberg en ninguna de las subpoblaciones. La diversidad genética determinada mediante la comparación de las heterocigosidades fue relativamente baja entre poblaciones pero al interior de estas no. El valor de FST de toda la población fue de 0.0068 y significativo (p<0.05, algunos FST pareados también lo fueron, tomando valores desde 0.0 a 0.13. Los estadísticos FIT y FIS no fueron significativos. Conclusiones. El gen bGH es un candidato interesante para evaluar características de importancia económica ya que no parece haber sido sometido a selección directa, presenta una variabilidad media en las poblaciones, observándose diferenciación genética significativa entre distintos municipios, producto de los diferentes sistemas de producción y acceso a las biotecnologías.

Next Gen One Portal Usability Evaluation

Science.gov (United States)

Cross, E. V., III; Perera, J. S.; Hanson, A. M.; English, K.; Vu, L.; Amonette, W.

2018-01-01

Each exercise device on the International Space Station (ISS) has a unique, customized software system interface with unique layouts / hierarchy, and operational principles that require significant crew training. Furthermore, the software programs are not adaptable and provide no real-time feedback or motivation to enhance the exercise experience and/or prevent injuries. Additionally, the graphical user interfaces (GUI) of these systems present information through multiple layers resulting in difficulty navigating to the desired screens and functions. These limitations of current exercise device GUI's lead to increased crew time spent on initiating, loading, performing exercises, logging data and exiting the system. To address these limitations a Next Generation One Portal (NextGen One Portal) Crew Countermeasure System (CMS) was developed, which utilizes the latest industry guidelines in GUI designs to provide an intuitive ease of use approach (i.e., 80% of the functionality gained within 5-10 minutes of initial use without/limited formal training required). This is accomplished by providing a consistent interface using common software to reduce crew training, increase efficiency & user satisfaction while also reducing development & maintenance costs. Results from the usability evaluations showed the NextGen One Portal UI having greater efficiency, learnability, memorability, usability and overall user experience than the current Advanced Resistive Exercise Device (ARED) UI used by astronauts on ISS. Specifically, the design of the One-Portal UI as an app interface similar to those found on the Apple and Google's App Store, assisted many of the participants in grasping the concepts of the interface with minimum training. Although the NextGen One-Portal UI was shown to be an overall better interface, observations by the test facilitators noted specific exercise tasks appeared to have a significant impact on the NextGen One-Portal UI efficiency. Future updates to

The dnaN gene codes for the beta subunit of DNA polymerase III holoenzyme of escherichia coli.

Science.gov (United States)

Burgers, P M; Kornberg, A; Sakakibara, Y

1981-09-01

An Escherichia coli mutant, dnaN59, stops DNA synthesis promptly upon a shift to a high temperature; the wild-type dnaN gene carried in a transducing phage encodes a polypeptide of about 41,000 daltons [Sakakibara, Y. & Mizukami, T. (1980) Mol. Gen. Genet. 178, 541-553; Yuasa, S. & Sakakibara, Y. (1980) Mol. Gen. Genet. 180, 267-273]. We now find that the product of dnaN gene is the beta subunit of DNA polymerase III holoenzyme, the principal DNA synthetic multipolypeptide complex in E. coli. The conclusion is based on the following observations: (i) Extracts from dnaN59 cells were defective in phage phi X174 and G4 DNA synthesis after the mutant cells had been exposed to the increased temperature. (ii) The enzymatic defect was overcome by addition of purified beta subunit but not by other subunits of DNA polymerase III holoenzyme or by other replication proteins required for phi X174 DNA synthesis. (iii) Partially purified beta subunit from the dnaN mutant, unlike that from the wild type, was inactive in reconstituting the holoenzyme when mixed with the other purified subunits. (iv) Increased dosage of the dnaN gene provided by a plasmid carrying the gene raised cellular levels of the beta subunit 5- to 6-fold.

IAEA/USDOE senior management workshop on promotion of safety culture for the NPPS with RBMK reactors. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

The current workshop, co-sponsored by the IAEA and USDOE, was a continuation of the previous effort for further promotion of safety culture at RBMK NPPs. The objective of the workshop was to provide a forum for senior managers from governmental organizations and operating organizations to further exchange experience in understanding the factors influencing safety culture, in assessing safety culture at their own organizations and developing safety culture at RBMK NPPs. The workshop consisted of a broad scope of presentations to review the basic concepts and major elements of safety culture (ownership, accountability, pride, job satisfaction, trust, openness, etc.), to identify and discuss the various approaches used in different countries in attaining a strong safety culture, and to explain, through the use of practical examples, what the benefits of a strong safety culture are; how to improve the behavior of people, how to gain trust and openness, how to overcome difficulties in changing staff`s attitudes, and how to manage safety culture. 2 figs.

IAEA/USDOE senior management workshop on promotion of safety culture for the NPPS with RBMK reactors. Working material

International Nuclear Information System (INIS)

1997-01-01

The current workshop, co-sponsored by the IAEA and USDOE, was a continuation of the previous effort for further promotion of safety culture at RBMK NPPs. The objective of the workshop was to provide a forum for senior managers from governmental organizations and operating organizations to further exchange experience in understanding the factors influencing safety culture, in assessing safety culture at their own organizations and developing safety culture at RBMK NPPs. The workshop consisted of a broad scope of presentations to review the basic concepts and major elements of safety culture (ownership, accountability, pride, job satisfaction, trust, openness, etc.), to identify and discuss the various approaches used in different countries in attaining a strong safety culture, and to explain, through the use of practical examples, what the benefits of a strong safety culture are; how to improve the behavior of people, how to gain trust and openness, how to overcome difficulties in changing staff's attitudes, and how to manage safety culture. 2 figs

Salud pública, genética y ética

Directory of Open Access Journals (Sweden)

Kottow Miguel H

2002-01-01

Full Text Available La investigación genética ha tenido una enorme expansión en recientes décadas, con repercusiones terapéuticas aún inciertas. El análisis bioético tradicional de las complejas prácticas genéticas ha sido insuficiente por sostenerse en la ética de la investigación y en la bioética de corte principialista. Los problemas éticos más importantes de la genética son de orden colectivo y deben ser abordados por una reflexión ético-social cuyo enfoque es más amplio que la agenda interpersonal del principialismo. Temas como exploraciones genéticas, cuestiones patrimoniales, manipulación génica y asignación de recursos, deben todos ser sometidos a un pensamiento inspirado en los requerimientos de la ciudadanía, en el bien común y en la definición del rol del Estado en fiscalizar actividades genéticas y en proteger a la población. El objetivo del estudio es mostrar cómo el amplio campo de la ética y de la genética tiene una mayor relevancia en el campo social que en el clínico. El objetivo del trabajo es señalar que la bioética principialista ha enfatizado los problemas éticos individuales que nacen con la intervención genética, a costa de marginar sus importantes repercusiones sociales.

Salud pública, genética y ética

Directory of Open Access Journals (Sweden)

Miguel H Kottow

2002-10-01

Full Text Available La investigación genética ha tenido una enorme expansión en recientes décadas, con repercusiones terapéuticas aún inciertas. El análisis bioético tradicional de las complejas prácticas genéticas ha sido insuficiente por sostenerse en la ética de la investigación y en la bioética de corte principialista. Los problemas éticos más importantes de la genética son de orden colectivo y deben ser abordados por una reflexión ético-social cuyo enfoque es más amplio que la agenda interpersonal del principialismo. Temas como exploraciones genéticas, cuestiones patrimoniales, manipulación génica y asignación de recursos, deben todos ser sometidos a un pensamiento inspirado en los requerimientos de la ciudadanía, en el bien común y en la definición del rol del Estado en fiscalizar actividades genéticas y en proteger a la población. El objetivo del estudio es mostrar cómo el amplio campo de la ética y de la genética tiene una mayor relevancia en el campo social que en el clínico. El objetivo del trabajo es señalar que la bioética principialista ha enfatizado los problemas éticos individuales que nacen con la intervención genética, a costa de marginar sus importantes repercusiones sociales.

Implementation of safeguards in Spanish NPPs: advantages of cooperation and coordination

International Nuclear Information System (INIS)

Estrampes Blanch, J.; Recio Santamaria, M.

2007-01-01

In 2002 the Spanish Ministry of Industry, Tourism and Commerce (MITYC) informed the operators of the soon entry into force of the Additional Protocol (AP) to the Safeguards Agreement, once its ratification by the Member States of the EU were completed and the Community and national legislations were adapted to the new requirements. The Spanish association for the electrical industry (UNESA) responded to that announcement setting up the UNESA's Safeguards Working Group (USWG), made up of staff of the NPPs in charge of nuclear material accountancy. The USWG was mandated to ensure coordinated implementation of the new safeguards obligation of the Additional Protocol in close cooperation with the Ministry of Industry, Tourism and Commerce (MITYC), Spanish authority for safeguards implementation follow up. Although the group was initially meant only for NPPs, later on representatives of other main nuclear facilities (i.e. ENUSA's fuel fabrication facility, the national rad waste company ENRESA, and CIEMAT national research centre) have been also participating in the group's meeting and activities when general discussion points on the entry into force of the AP were dealt with. From 2003 on, the USWG has met periodically with the aim of exchanging experiences in the field of safeguards implementation and jointly dealing with changes to EURATOM and IAEA safeguards systems lately introduced to reinforce their effectiveness and efficiency in response to the challenges posed to the international community by the recent discovery of undeclared nuclear programmes. Along the operation of the USWG, presence of Spanish nuclear industry representatives in international for a dealing with safeguards has remarkably grown up. Moreover, representatives of the USWG have also maintained an active participation in the ESARDA working groups on integrated safeguards (ISWG) and nuclear material accountancy and audit focus group (NMAC-AF)

Simulation of a passive auxiliary feedwater system with TRACE5

Energy Technology Data Exchange (ETDEWEB)

Lorduy, María; Gallardo, Sergio; Verdú, Gumersindo, E-mail: maloral@upv.es, E-mail: sergalbe@iqn.upv.es, E-mail: gverdu@iqn.upv.es [Instituto Universitario de Seguridad Industrial, Radiofísica y Medioambiental (ISIRYM), València (Spain)

2017-07-01

The study of the nuclear power plant accidents occurred in recent decades, as well as the probabilistic risk assessment carried out for this type of facility, present human error as one of the main contingency factors. For this reason, the design and development of generation III, III+ and IV reactors, which include inherent and passive safety systems, have been promoted. In this work, a TRACE5 model of ATLAS (Advanced Thermal- Hydraulic Test Loop for Accident Simulation) is used to reproduce an accidental scenario consisting in a prolonged Station BlackOut (SBO). In particular, the A1.2 test of the OECD-ATLAS project is analyzed, whose purpose is to study the primary system cooling by means of the water supply to one of the steam generators from a Passive Auxiliary Feedwater System (PAFS). This safety feature prevents the loss of secondary system inventory by means of the steam condensation and its recirculation. Thus, the conservation of a heat sink allows the natural circulation flow rate until restoring stable conditions. For the reproduction of the test, an ATLAS model has been adapted to the experiment conditions, and a PAFS has been incorporated. >From the simulation test results, the main thermal-hydraulic variables (pressure, flow rates, collapsed water level and temperature) are analyzed in the different circuits, contrasting them with experimental data series. As a conclusion, the work shows the TRACE5 code capability to correctly simulate the behavior of a passive feedwater system. (author)

Optimal trading strategy for GenCo in LMP-based and bilateral ...

African Journals Online (AJOL)

cboonchu

GenCo) ... In Li and Shahidehpour (2005), a game-based bidding strategy for GenCos with ..... With the different demands, dispatched levels of GenCos vary as shown in Table 6. .... optimisation, AI applications to power systems, and power system ...

An expert system-based aid for analysis of Emergency Operating Procedures in NPPs

International Nuclear Information System (INIS)

Jakubowski, Z.; Beraha, D.

1996-01-01

Emergency Operating Procedures (EOPs) generally and an accident management (AM) particularly play a significant part in the safety philosophy on NPPs since many years. A better methodology for development and validation of EOPs is desired. A prototype of an Emergency Operating Procedures Analysis System (EOPAS), which has been developed at GRS, is presented in the paper. The hardware configuration and software organisation of the system is briefly reviewed. The main components of the system such as the knowledge base of an expert system and the engineering simulator are described. (author)

Minimum throttling feedwater control in VVER-1000 and PWR NPPs

International Nuclear Information System (INIS)

Symkin, B.E.; Thaulez, F.

2004-01-01

This paper presents an approach for the design and implementation of advanced digital control systems that use a minimum-throttling algorithm for the feedwater control. The minimum-throttling algorithm for the feedwater control, i.e. for the control of steam generators level and of the feedwater pumps speed, is applicable for NPPs with variable speed feedwater pumps. It operates in such a way that the feedwater control valve in the most loaded loop is wide open, steam generator level in this loop being controlled by the feedwater pumps speed, while the feedwater control valves in the other loops are slightly throttling under the action of their control system, to accommodate the slight loop imbalances. This has the advantage of minimizing the valve pressure losses hence minimizing the feedwater pumps power consumption and increasing the net MWe. The benefit has been evaluated for specific plants as being roughly 0.7 and 2.4 MW. The minimum throttling mode has the further advantages of lowering the actuator efforts with potential positive impact in actuator life and of minimizing the feedwater pipelines vibrations. The minimum throttling mode of operation has been developed by the Ukrainian company LvivORGRES. It has been applied with great deal of success on several VVER-1000 NPPs, six units of Zaporizhzha in Ukraine plus, with participation of Westinghouse, Kozloduy 5 and 6 in Bulgaria and South Ukraine 1 to 3 in Ukraine. The concept operates with both ON-OFF valves and true control valves. A study, jointly conducted by Westinghouse and LvivORGRES, is ongoing to demonstrate the applicability of the concept to PWRs having variable speed feedwater pumps and having, or installing, digital feedwater control, standalone or as part of a global digital control system. The implementation of the algorithm at VVER-1000 plants provided both safety improvement and direct commercial benefits. The minimum-throttling algorithm will similarly increase the performance of PWRs. The

Probabilistic approach to requalification of existing NPPs under aircraft crash loading

International Nuclear Information System (INIS)

Birbraer, A.N.; Roleder, A.J.; Shulman, G.S.

1993-01-01

A probabilistic approach to the analysis of NPP safety under aircraft impact is discussed. It may be used both for requalification of existing NPPs and in the process of NPP design. NPP is considered as a system of components: structures, pipes, different kinds of equipment, soil, foundation. The exceeding of the limit probability of the radioactive products release out of containment (i.e. of the NPP safety requirements non-fulfilment) is taken as a system failure criterion. An example of an event tree representing the consequence of events causing the failure is given. Described are the methods of estimate of elementary events probabilities through which a composite probability of the failure is evaluated. (author)

História da genética no Brasil: um olhar a partir do Museu da Genética da Universidade Federal do Rio Grande do Sul

Directory of Open Access Journals (Sweden)

Vanderlei Sebastiao de Souza

2013-06-01

Full Text Available Aborda o contexto de criação do Museu da Genética, em 2011 no Departamento de Genética na Universidade Federal do Rio Grande do Sul, em Porto Alegre, e apresenta sua estrutura e conteúdo. Argumenta-se que os materiais disponibilizados no Museu da Genética constituem uma rica fonte para pesquisas sobre a história da genética no Brasil (e da genética de populações humanas em particular a partir da segunda metade do século XX, tema ainda pouco investigado, apesar da proeminência dessa área do conhecimento no Brasil.

Manipulación genética de seres humanos

Directory of Open Access Journals (Sweden)

Manuel Santos Alcántara

2006-08-01

Full Text Available El gran avance que ha tenido la Genética en los últimos años y, particularmente, aquello relacionado con el desciframiento del genoma humano, ha traído a la discusión pública la posibilidad concreta de manipular genéticamente a los seres humanos. El mejoramiento o perfeccionamiento genético de los seres humanos, denominado eugenesia, actualmente se ha convertido técnicamente en una realidad, motivando una profunda reflexión de tipo ético. La pregunta básica es la siguiente: aquello que es técnicamente posible de realizar ¿es ético hacerlo? ¿Tienen derecho los padres a acceder a la tecnología genética para mejorar las características de sus hijos? En este artículo se revisan las bases científicas del mejoramiento genético de los seres humanos, y se plantean los cuestionamientos éticos más relevantes derivados de esta manipulación.

Programa nacional de prevención y consejería genética del retinoblastoma mediante detección de mutaciones en el gen RB.

Directory of Open Access Journals (Sweden)

H. Frayle

2001-07-01

una la doble mutación inactivante del gen Rb, exclusivamente somática en los esporádicos y germinal más somática en los hereditarios. Esta investigacin tuvo como objetivo caracterizar las mutaciones en el gen Rb mediante secuenciación directa y evaluar su utilidad en la consejería genética.

Pre-Operational Seismic Walk-Through of NPPs in India

International Nuclear Information System (INIS)

Soni, R.S.; Mishra, R.K.; Agrawal, M.K.; Reddy, G.R.; Kushwaha, H.S.; Venkat Raj, V.; Badrinarayan, G.; Hawaldar, R.V.; Ingole, S.M.

2002-01-01

In nuclear power plants, it is essential to design the various safety and safety related systems and components of the plant in such a manner that they maintain their structural integrity as well as serve their functional performance during a seismic event. The pre-operational seismic walk-through helps in ensuring the installation of various seismic supports as per design intent, identifying the areas where supports are inadequate, identifying the interaction concerns between the systems of various safety classes and locating the various undesired loose, untied / unanchored components, tools, etc. used during the construction activity. A detailed procedure for the pre-operational seismic walk-through of the NPPs was therefore, prepared. Since the types and locations of seismic supports for the various systems and components of the plant had been already reviewed, the major emphasis during the walk-through was laid on their proper installation. (authors)

Implications of Japan's NPPs overseas expansion policy

Energy Technology Data Exchange (ETDEWEB)

Kim, S. E.; Yun, S. W. [Nuclear Policy Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

The accident at the Fukushima Daiichi contributing to nuclear power's loss of acceptability in most developed countries however new nuclear market has been growing especially in developing countries. According to IAEA, it is estimated that the construction of 121 to 743 nuclear power plants (NPPs) by 2050. Japanese government reviewed national nuclear export strategy after Korea KEPCO consortium ordered for construction of the UAE Project in 2009 and Russia won a contract of the Vietnam 1st Nuclear Power Plant Project in 2010. Japan figured out that reasons of failed at UAE project were price competitiveness and lack of top-level's attention. Also Russia offered to Vietnam military cooperation which was diagnosed as a failure to Japan. In these circumstances Fukushima accident influenced attitudes towards and acceptance of nuclear power immediately compared to before the accident. Nevertheless, Japanese government decided to keep focusing on nuclear export.

Mechanism of the transpassive dissolution and secondary passivation of chromium in sulphuric acid solutions

International Nuclear Information System (INIS)

Bojinov, M.; Betova, I.; Raicheff, R.; Fabricius, G.; Laitinen, T.; Saario, T.

1998-01-01

The transpassive dissolution and secondary passivation of Cr in 1..10 M H 2 SO 4 solutions were studied by a combination of different electrochemical methods. The steady-state polarization curves for transpassive dissolution exhibited a Tafel behaviour with a slope being independent on the acid concentration. Lower dissolution rates were measured for higher acid concentrations. Ring-disk measurements showed a release of both soluble Cr(VI) and Cr(III) during transpassivity. Impedance spectra were qualititatively similar in all acid concentrations, comprising one capacitive and two inductive semicircles. A kinetic model comprising two parallel transpassive dissolution paths was consistent with the experimental results. Typical passivation diagrams were observed for Cr in 10 M H 2 SO 4 , and a secondary passive state was established at higher potentials. The formation of the secondary passive film was confirmed by contact electric resistance (CER) measurements. A renewed version of the surface charge approach was consistent with the experimental results in the region of the secondary passivation. (orig.)

Programa nacional de prevención y consejería genética del retinoblastoma mediante detección de mutaciones en el gen rb.

OpenAIRE

Frayle, H.; Guevara, G.

2011-01-01

El retinoblastoma es un raro tumor ocular que se diagnostica en los niños, 40% de los casos se consideran hereditarios y 60% esporádicos. El modelo genético propuesto por Knudson involucra
una la doble mutación inactivante del gen Rb, exclusivamente somática en los esporádicos y germinal más somática en los hereditarios. Esta investigacin tuvo como objetivo caracterizar las mutaciones en el gen Rb mediante secuenciación directa y evaluar su utilidad en la consejería genética....

Justicia en salud y genética

Directory of Open Access Journals (Sweden)

Maria Graciela De Ortuzar

2014-06-01

Full Text Available Las expectativas puestas en el conocimiento genético exceden el ámbito de la medicina tradiciona, debido a que la intervención directa en la lotería natural demandaría el replanteamiento de conceptos centrales de justicia en salud: necesidades médicas, enfermedad, normalidad, e igualdad de oportunidades en el acceso a la salud. El punto en debate es sí el replanteo de dichos conceptos conlleva un cambio radical en las teorías de justicia (libertariana y/o liberal, mostrando su obsolescencia, o sí simplemente se requiere ampliar dichos conceptos claves por fallas estructurales en las mismas teorías. Como hipótesis general considero que los supuestos cuestionamientos, lejos de socavar las bases de las teorías de justicia, sólo ponen en evidencia sus viejos problemas estructurales. Por razones expositivas, dividiré la presentación tres partes. En la Primera parte, analizo la teoría libertariana, estudiando las contradicciones del modelo a través del impacto de la información genética en el seguro privado de salud. En la Segunda Parte, desarrollo la propuesta alternativa liberal rawlsianadanielsiana del modelo de seguro público, evaluando las implicaciones de la genética a partir de la crítica de su concepto biológico de enfermedad y su restricción al acceso a la salud por necesidades naturales. En la Tercera parte presento un modelo integral de necesidades y capacidades básicas, comprendiendo la prevención, el tratamiento y el mejoramiento moralmente permisible (genético y no genético.Mi aporte principal consiste en la elaboración de este modelo normativo integral de necesidades y capacidades para la regulación conjunta de la información y terapia genética con los restantes problemas de salud.

Of creation of up-to-date system for liquid radwaste management at Ukraine's NPPs. Problem statement

International Nuclear Information System (INIS)

Andronov, O.B.

2015-01-01

The main aspects are addressed of problems in the field of liquid radwaste (LRW) management for Ukrainian NPPs; approaches for its decision, and offers of NNEGC Energoatom SE STC specialists concerning the above issue. Conceptual principle of creation of up-to-date hi-tech complex for LRW management is considered

GenBank.

OpenAIRE

Benson, D; Lipman, D J; Ostell, J

1993-01-01

The GenBank sequence database has undergone an expansion in data coverage, annotation content and the development of new services for the scientific community. In addition to nucleotide sequences, data from the major protein sequence and structural databases, and from U.S. and European patents is now included in an integrated system. MEDLINE abstracts from published articles describing the sequences provide an important new source of biological annotation for sequence entries. In addition to ...

Passivation of laser-treated nickel aluminum bronze as measured by electrochemical impedance spectroscopy

International Nuclear Information System (INIS)

Klassen, R.D.; Hyatt, C.V.; Roberge, P.R.

2000-01-01

Electrochemical impedance spectroscopy was used to assess the corrosion behavior of the weld zones and surface conditions of a laser-clad nickel aluminum bronze immersed in a 3.5% neutral saline solution. The zones and conditions examined included: (i) as-cast base material; (ii) laser-clad material with the high temperature oxide from welding intact; (iii) polished laser-clad material and (iv) specimens representative of just the as-deposited and reheated zones of the laser-clad surface. A pseudo steady-state level of passivation was reached in all the samples within 40 hours. The reheated zone passivated more slowly than the as-deposited region and both weld zones passivated more quickly than the base material. Electrochemical impedance data illustrated a transition during the passivation process of the polished specimens that is consistent with the development of a film layer that restricted mass transfer. The welding oxide from the laser treatment immediately behaved as a passivation film that was indistinguishable from that which eventually develops on polished specimens. (author)

Gen IV Materials Handbook Implementation Plan

International Nuclear Information System (INIS)

Rittenhouse, P.; Ren, W.

2005-01-01

A Gen IV Materials Handbook is being developed to provide an authoritative single source of highly qualified structural materials information and materials properties data for use in design and analyses of all Generation IV Reactor Systems. The Handbook will be responsive to the needs expressed by all of the principal government, national laboratory, and private company stakeholders of Gen IV Reactor Systems. The Gen IV Materials Handbook Implementation Plan provided here addresses the purpose, rationale, attributes, and benefits of the Handbook and will detail its content, format, quality assurance, applicability, and access. Structural materials, both metallic and ceramic, for all Gen IV reactor types currently supported by the Department of Energy (DOE) will be included in the Gen IV Materials Handbook. However, initial emphasis will be on materials for the Very High Temperature Reactor (VHTR). Descriptive information (e.g., chemical composition and applicable technical specifications and codes) will be provided for each material along with an extensive presentation of mechanical and physical property data including consideration of temperature, irradiation, environment, etc. effects on properties. Access to the Gen IV Materials Handbook will be internet-based with appropriate levels of control. Information and data in the Handbook will be configured to allow search by material classes, specific materials, specific information or property class, specific property, data parameters, and individual data points identified with materials parameters, test conditions, and data source. Details on all of these as well as proposed applicability and consideration of data quality classes are provided in the Implementation Plan. Website development for the Handbook is divided into six phases including (1) detailed product analysis and specification, (2) simulation and design, (3) implementation and testing, (4) product release, (5) project/product evaluation, and (6) product

Algoritmos para genómica comparativa

OpenAIRE

Figueiras, Vasco da Rocha

2010-01-01

Com o surgimento da Genómica e da Proteómica, a Bioinformática conduziu a alguns dos avanços científicos mais relevantes do século XX. A Unidade de Investigação e Desenvolvimento do Biocant, parque biotecnológico de Cantanhede, assume actualmente o papel de motor no desenvolvimento da Genómica. O Biocant possui um importante sequenciador de larga escala que permite armazenar um elevado número de genomas, nomeadamente, genomas de bactérias. O estudo proposto reflecte a necessidade do Bio...

Medicamentos genéricos y de marca-Calidad e intercambiabilidad

Directory of Open Access Journals (Sweden)

Rua F.

2012-03-01

Full Text Available El interés por los medicamentos genéricos procede de la necesidad de los sistemas sanitarios de reducir la factura sanitaria sin merma de los objetivos de salud. Su expansión y uso requieren la aceptación de la población y de los profesionales. También requieren que se despejen algunas dudas sobre su verdadera equivalencia respecto a los medicamentos originales. Desde su introducción en el mercado farmacéutico existe el debate de si son correctamente investigados y de alta calidad. No son infrecuentes los conceptos equivocados entre los profesionales sobre los genéricos, en especial, el supuesto hecho de que pueden llegar a contener hasta un 20% menos de concentración en principio activo. Estas creencias erróneas sugieren una situación de desventaja en la eficacia y la tolerabilidad de los medicamentos genéricos comparados con sus equivalentes de marca, disminuyendo la credibilidad de los mismos. Así, en una encuesta realizada en 2008 los farmacéuticos opinaron que los genéricos y las marcas son diferentes en eficacia (26%, equivalencia (28% y, sobre todo, en la calidad del excipiente (46%, aumentando la percepción de que los genéricos son diferentes en función del laboratorio que los fabrica (52,8%. En este artículo, con el fin de ampliar los conocimientos sobre medicamentos genéricos, solucionar dudas y proporcionar información, objetiva, clara y rigurosa, se revisan los posibles prejuicios sobre genéricos y se exponen las evidencias que existen en torno a los mismos, como los requisitos de bioequivalencia de los productos genéricos, analizando si ésta corrobora adecuadamente la equivalencia terapéutica y de intercambio.

Sobre el significado del descubrimiento del gen FOXP2

OpenAIRE

Longa Martínez, Víctor Manuel

2006-01-01

El reciente descubrimiento del gen FOXP2 ha ofrecido la primera evidencia clara de la base genética del lenguaje, mostrando una correlación inequívoca desde la perspectiva genética entre una versión mutada de F0XP2 y los trastornos lingüísticos de diferente tipo sufridos por una familia inglesa, conocida como KE. El objetivo central del presente trabajo es discutir diferentes aspectos relacionados con tal descubrimiento; especialmente, la discusión del significado de FOXP2 con ...

Safety management in NPPs using an evolutionary algorithm technique

International Nuclear Information System (INIS)

Mishra, Alok; Patwardhan, Anand; Verma, A.K.

2007-01-01

The general goal of safety management in Nuclear Power Plants (NPPs) is to make requirements and activities more risk effective and less costly. The technical specification and maintenance (TS and M) activities in a plant are associated with controlling risk or with satisfying requirements, and are candidates to be evaluated for their resource effectiveness in risk-informed applications. Accordingly, the risk-based analysis of technical specification (RBTS) is being considered in evaluating current TS. The multi-objective optimization of the TS and M requirements of a NPP based on risk and cost, gives the pareto-optimal solutions, from which the utility can pick its decision variables suiting its interest. In this paper, a multi-objective evolutionary algorithm technique has been used to make a trade-off between risk and cost both at the system level and at the plant level for loss of coolant accident (LOCA) and main steam line break (MSLB) as initiating events

Distributed Generation Market Demand Model (dGen): Documentation

Energy Technology Data Exchange (ETDEWEB)

Sigrin, Benjamin [National Renewable Energy Lab. (NREL), Golden, CO (United States); Gleason, Michael [National Renewable Energy Lab. (NREL), Golden, CO (United States); Preus, Robert [National Renewable Energy Lab. (NREL), Golden, CO (United States); Baring-Gould, Ian [National Renewable Energy Lab. (NREL), Golden, CO (United States); Margolis, Robert [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2016-02-01

The Distributed Generation Market Demand model (dGen) is a geospatially rich, bottom-up, market-penetration model that simulates the potential adoption of distributed energy resources (DERs) for residential, commercial, and industrial entities in the continental United States through 2050. The National Renewable Energy Laboratory (NREL) developed dGen to analyze the key factors that will affect future market demand for distributed solar, wind, storage, and other DER technologies in the United States. The new model builds off, extends, and replaces NREL's SolarDS model (Denholm et al. 2009a), which simulates the market penetration of distributed PV only. Unlike the SolarDS model, dGen can model various DER technologies under one platform--it currently can simulate the adoption of distributed solar (the dSolar module) and distributed wind (the dWind module) and link with the ReEDS capacity expansion model (Appendix C). The underlying algorithms and datasets in dGen, which improve the representation of customer decision making as well as the spatial resolution of analyses (Figure ES-1), also are improvements over SolarDS.

Revision of Corallinaceae (Corallinales, Rhodophyta): recognizing Dawsoniolithon gen. nov., Parvicellularium gen. nov. and Chamberlainoideae subfam. nov. containing Chamberlainium gen. nov. and Pneophyllum.

Science.gov (United States)

Caragnano, Annalisa; Foetisch, Alexandra; Maneveldt, Gavin W; Millet, Laurent; Liu, Li-Chia; Lin, Showe-Mei; Rodondi, Graziella; Payri, Claude E

2018-03-25

A multi-gene (SSU, LSU, psbA and COI) molecular phylogeny of the family Corallinaceae (excluding the subfamilies Lithophylloideae and Corallinoideae) showed a paraphyletic grouping of six monophyletic clades. Pneophyllum and Spongites were reassessed and recircumscribed using DNA sequence data integrated with morpho-anatomical comparisons of type material and recently collected specimens. We propose Chamberlainoideae subfam. nov., including the type genus Chamberlainium gen. nov., with C. tumidum comb. nov. as the generitype, and Pneophyllum. Chamberlainium is established to include several taxa previously ascribed to Spongites, the generitype of which currently resides in Neogoniolithoideae. Additionally we propose two new genera, Dawsoniolithon gen. nov. (Metagoniolithoideae), with D. conicum comb. nov. as the generitype and Parvicellularium gen. nov. (subfamily incertae sedis), with P. leonardi sp. nov. as the generitype. Chamberlainoideae has no diagnostic morpho-anatomical features that enable one to assign specimens to it without DNA sequence data, and it is the first subfamily to possess both Type 1 (Chamberlainium) and Type 2 (Pneophyllum) tetra/bisporangial conceptacle roof development. Two characters distinguish Chamberlainium from Spongites: tetra/biasporangial conceptacle chamber diameter (300 μm in Spongites) and tetra/bisporangial conceptacle roof thickness (8 cells in Spongites). Two characters also distinguish Pneophyllum from Dawsoniolithon: tetra/bisporangial conceptacle roof thickness (8 cells in Dawsoniolithon) and thallus construction (dimerous in Pneophyllum vs. monomerous in Dawsoniolithon). This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

Experimental results of passive vibro-acoustic leak detection in SFR steam generator mock-up

International Nuclear Information System (INIS)

Moriot, J.; Gastaldi, O.; Maxit, L.; Guyader, J-L.; Perisse, J.; Migot, B.

2013-06-01

Regarding to GEN 4 context, it is necessary to fulfil the high safety standards for sodium fast reactors (SFR), particularly against water-sodium reaction which may occur in the steam generator units (SGU) in case of leak. This reaction can cause severe damages in the component in a short time. Detecting such a leak by visual in-sodium inspection is impossible because of sodium opacity. Hydrogen detection is then used but the time response of this method can be high in certain operating conditions. Active and passive acoustic leak detection methods were studied before SUPERPHENIX plant shutdown in 1997 to detect a water-into-sodium leak with a short time response. In the context of the new R and D studies for SFR, an innovative passive vibro-acoustic method is developed in the framework of a Ph.D. thesis to match with GEN 4 safety requirements. The method consists in assuming that a small leak emits spherical acoustic waves in a broadband frequency domain, which propagate in the liquid sodium and excite the SGU cylindrical shell. These spatially coherent waves are supposed to be buried by a spatially incoherent background noise. The radial velocities of the shell is measured by an array of accelerometers positioned on the external envelop of the SGU and a beam forming treatment is applied to increase the signal-to-noise ratio (SNR) and to detect and localize the acoustic source. Previous numerical experiments were achieved and promising results were obtained. In this paper, experimental results of the proposed passive vibro-acoustic leak detection are presented. The experiment consists in a cylindrical water-filled steel pipe representing a model of SGU shell without tube bundle. A hydro-phone emitting an acoustic signal is used to simulate an acoustic monopole. Spatially uncorrelated noise or water-flow induced shell vibrations are considered as the background noise. The beam-forming method is applied to vibration signals measured by a linear array of

Biometria e armazenamento de sementes de genótipos de cacaueiro

Directory of Open Access Journals (Sweden)

Lucimara Ribeiro Venial

2017-03-01

Full Text Available Genótipos de Theobroma cacao L. devem ser melhor estudados, para se identificar aqueles que produzem sementes mais desenvolvidas e viáveis após o armazenamento. Objetivou-se com este trabalho estudar a biometria e dois tempos de armazenamento de sementes de genótipos de cacaueiro. A biometria foi avaliada em oito genótipos de cacaueiro (tratamentos. Foram instalados testes de germinação em delineamento inteiramente ao acaso, no esquema fatorial 8 x 2 (genótipos: CCN51, PH16, CEPEC2002, Ipiranga, SJ02, PS1319, TSH1188 e Comum x dois períodos de armazenamento: 0 e dois dias. O genótipo TSH1188 apresentou maior comprimento, relação comprimento/largura, espessura e massa de 100 sementes. A absorção de água das sementes recém-colhidas dos genótipos é lenta, justificada pelos altos teores de água, o que não caracteriza padrão-trifásico. Os teores de água reduziram em média 2,3 vezes nas sementes armazenadas em relação às recém-colhidas. A germinação das sementes recém-colhidas dos genótipos foi de 100%. Após o armazenamento, as sementes do PS1319 apresentaram a menor redução da germinação (39%, enquanto as dos PH16, CEPEC2002 e SJ02 reduziram 96%. A velocidade de germinação foi maior e o tempo médio menor que dois dias nas sementes recém-colhidas do PS1319, indicando serem mais tolerante à dessecação. Sugere-se o uso dos genótipos TSH1188 e PS1319 em programas de melhoramento genético.

Computational Analysis of the G-III Laminar Flow Glove

Science.gov (United States)

Malik, Mujeeb R.; Liao, Wei; Lee-Rausch, Elizabeth M.; Li, Fei; Choudhari, Meelan M.; Chang, Chau-Lyan

2011-01-01

Under NASA's Environmentally Responsible Aviation Project, flight experiments are planned with the primary objective of demonstrating the Discrete Roughness Elements (DRE) technology for passive laminar flow control at chord Reynolds numbers relevant to transport aircraft. In this paper, we present a preliminary computational assessment of the Gulfstream-III (G-III) aircraft wing-glove designed to attain natural laminar flow for the leading-edge sweep angle of 34.6deg. Analysis for a flight Mach number of 0.75 shows that it should be possible to achieve natural laminar flow for twice the transition Reynolds number ever achieved at this sweep angle. However, the wing-glove needs to be redesigned to effectively demonstrate passive laminar flow control using DREs. As a by-product of the computational assessment, effect of surface curvature on stationary crossflow disturbances is found to be strongly stabilizing for the current design, and it is suggested that convex surface curvature could be used as a control parameter for natural laminar flow design, provided transition occurs via stationary crossflow disturbances.

Enfermedades genéticas más frecuentes en pacientes atendidos en consulta de genética clínica

Directory of Open Access Journals (Sweden)

Elibett Carcasés Carcasés

2015-02-01

Full Text Available La estimación de la prevalencia de las enfermedades genéticas se dificulta, entre otras causas, por su rareza. Se realizó un estudio descriptivo retrospectivo, para identificar las enfermedades genéticas de mayor prevalencia en pacientes atendidos por este programa en el Centro Provincial de Genética Médica de Las Tunas, Cuba; desde el año 1989 hasta julio de 2014. Se revisaron todas las historias clínicas. Predominó el origen monogénico (69 %, siendo los síndromes dismórficos los más numerosos y diversos, entre ellos los neurocutáneos, que representaron el 35 %. La enfermedad genética monogénica con mayor número de casos fue la Neurofibromatosis I con el 14,4 % y el 22,2 % de las enfermedades eran de origen monogénico y dismórfico. La Trisomía 21 representó el 77 % de la causa cromosómica. En el origen multifactorial prevalecieron los defectos congénitos mayores, entre ellos los defectos reductivos de miembros (27 %

Hydrogen passivation of polycrystalline Si thin film solar cells

International Nuclear Information System (INIS)

Gorka, Benjamin

2010-01-01

Hydrogen passivation is a key process step in the fabrication of polycrystalline Si (poly-Si) thin film solar cells. In this work a parallel plate rf plasma setup was used for the hydrogen passivation treatment. The main topics that have been investigated are (i) the role of plasma parameters (like hydrogen pressure, electrode gap and plasma power), (ii) the dynamics of the hydrogen treatment and (iii) passivation of poly-Si with different material properties. Passivation was characterized by measuring the open-circuit voltage V OC of poly-Si reference samples. Optimum passivation conditions were found by measurements of the breakdown voltage V brk of the plasma for different pressures p and electrode gaps d. For each pressure, the best passivation was achieved at a gap d that corresponded to the minimum in V brk . Plasma simulations were carried out, which indicate that best V OC corresponds to a minimum in ion energy. V OC was not improved by a larger H flux. Investigations of the passivation dynamic showed that a plasma treatment in the lower temperature range (≤400 C) is slow and takes several hours for the V OC to saturate. Fast passivation can be successfully achieved at elevated temperatures around 500 C to 600 C with a plateau time of 10 min. It was found that prolonged hydrogenation leads to a loss in V OC , which is less pronounced within the observed optimum temperature range (500 C-600 C). Electron beam evaporation has been investigated as an alternative method to fabricate poly-Si absorbers. The material properties have been tuned by alteration of substrate temperature T dep =200-700 C and were characterized by Raman, ESR and V OC measurements. Largest grains were obtained after solid phase crystallization (SPC) of a-Si, deposited in the temperature range of 300 C. The defect concentration of Si dangling bonds was lowered by passivation by about one order of magnitude. The lowest dangling bond concentration of 2.5.10 16 cm -3 after passivation was

An Axiomatic Design Approach of Nanofluid-Engineered Nuclear Safety Features for Generation III+ React

International Nuclear Information System (INIS)

Bang, In Cheol; Heo, Gyun Young; Jeong, Yong Hoon; Heo, Sun

2009-01-01

A variety of Generation III/III+ reactor designs featuring enhanced safety and improved economics are being proposed by nuclear power industries around the world to solve the future energy supply shortfall. Nanofluid coolants showing an improved thermal performance are being considered as a new key technology to secure nuclear safety and economics. However, it should be noted that there is a lack of comprehensible design works to apply nanofluids to Generation III+ reactor designs. In this work, the review of accident scenarios that consider expected nanofluid mechanisms is carried out to seek detailed application spots. The Axiomatic Design (AD) theory is then applied to systemize the design of nanofluid-engineered nuclear safety systems such as Emergency Core Cooling System (ECCS) and External Reactor Vessel Cooling System (ERVCS). The various couplings between Gen-III/III+ nuclear safety features and nanofluids are investigated and they try to be reduced from the perspective of the AD in terms of prevention/mitigation of severe accidents. This study contributes to the establishment of a standard communication protocol in the design of nanofluid-engineered nuclear safety systems

Fundamental studies of passivity and passivity breakdown

International Nuclear Information System (INIS)

Macdonald, D.D.; Urquidi-Macdonald, M.; Song, H.; Biaggio-Rocha, S.; Searson, P.

1991-11-01

This report summarizes the findings of our fundamental research program on passivity and passivity breakdown. During the past three and one half years in this program (including the three year incrementally-funded grant prior to the present grant), we developed and experimentally tested various physical models for the growth and breakdown of passive films on metal surfaces. These models belong to a general class termed ''point defects models'' (PDMs), in which the growth and breakdown of passive films are described in terms of the movement of anion and cation vacancies

Nuclear safeguard assessment in nuclear power plants (NPPs) using loss function with modified random numbers

International Nuclear Information System (INIS)

Woo, Tae Ho

2012-01-01

Highlights: ► The safeguard is analyzed by quantification. ► Newly introduced SF is analyzed by the electrical power output. ► The relative value of SF is shown in the month level. ► The better operation could be indicated numerical values. ► There are several secure operation factors to be suggested. - Abstract: The energy production in nuclear power plants (NPPs) is investigated for the safeguard risk management using economic factors. The economic loss function is used for the life quality in the social and natural objects. For the basic event elements, the game theory is applied for the basic elements of the incidents in non-secure situations. The Safeguard Factor (SF) is introduced for the quantifications of simulation. The results are shown by the standard productivity comparisons with the designed power operations, which is obtained as the range of secure life extension in 2000 MW e is between 0.0000 and 9.1985 and the range in 600 MW e is between 0.0000 and 2.7600. So, the highest value in the range of secure power operation increases about 3.33 times higher than that of the interested power operation in this study, which means the safeguard assessment is quantified by the power rate in the life extension of the NPPs. The Nuclear Safeguard Protocol (NSP) is constructed for the safe operation successfully.

A Case Study on Cyber-security Program for the Programmable Logic Controller of Modern NPPs

International Nuclear Information System (INIS)

Song, S. H.; Lee, M. S.; Kim, T. H.; Park, C. H.; Park, S. P.; Kim, H. S.

2014-01-01

As instrumentation and control (I and C) systems for modern Nuclear Power Plants (NPPs) have been digitalized to cope with their growing complexity, the cyber-security has become an important issue. To protect the I and C systems adequately from cyber threats, such as Stuxnet that attacked Iran's nuclear facilities, regulations of many countries require a cyber-security program covering all the life cycle phases of the system development, from the concept to the retirement. This paper presents a case study of cyber-security program that has been performed during the development of the programmable logic controller (PLC) for modern NPPs of Korea. In the case study, a cyber-security plan, including technical, management, and operational controls, was established through a security risk assessment. Cyber-security activities, such as development of security functions and periodic inspections, were conducted according to the plan: the security functions were applied to the PLC as the technical controls, and periodic inspections and audits were held to check the security of the development environment, as the management and operational controls. A final penetration test was conducted to inspect all the security problems that had been issued during the development. The case study has shown that the systematic cyber-security program detected and removed the vulnerabilities of the target system, which could not be found otherwise, enhancing the cyber-security of the system

A Case Study on Cyber-security Program for the Programmable Logic Controller of Modern NPPs

Energy Technology Data Exchange (ETDEWEB)

Song, S. H. [Korea University, Seoul (Korea, Republic of); Lee, M. S.; Kim, T. H. [Formal Work Inc., Seoul (Korea, Republic of); Park, C. H. [LINE Corp., Tokyo (Japan); Park, S. P. [Ahnlab Inc., Seoul (Korea, Republic of); Kim, H. S. [Sejong University, Seoul (Korea, Republic of)

2014-08-15

As instrumentation and control (I and C) systems for modern Nuclear Power Plants (NPPs) have been digitalized to cope with their growing complexity, the cyber-security has become an important issue. To protect the I and C systems adequately from cyber threats, such as Stuxnet that attacked Iran's nuclear facilities, regulations of many countries require a cyber-security program covering all the life cycle phases of the system development, from the concept to the retirement. This paper presents a case study of cyber-security program that has been performed during the development of the programmable logic controller (PLC) for modern NPPs of Korea. In the case study, a cyber-security plan, including technical, management, and operational controls, was established through a security risk assessment. Cyber-security activities, such as development of security functions and periodic inspections, were conducted according to the plan: the security functions were applied to the PLC as the technical controls, and periodic inspections and audits were held to check the security of the development environment, as the management and operational controls. A final penetration test was conducted to inspect all the security problems that had been issued during the development. The case study has shown that the systematic cyber-security program detected and removed the vulnerabilities of the target system, which could not be found otherwise, enhancing the cyber-security of the system.

Introducing AstroGen: The Astronomy Genealogy Project

OpenAIRE

Tenn, Joseph S.

2016-01-01

The Astronomy Genealogy Project ("AstroGen"), a project of the Historical Astronomy Division of the American Astronomical Society (AAS), will soon appear on the AAS website. Ultimately, it will list the world's astronomers with their highest degrees, theses for those who wrote them, academic advisors (supervisors), universities, and links to the astronomers or their obituaries, their theses when on-line, and more. At present the AstroGen team is working on those who earned doctorates with ast...

Genética humana e sociedade

OpenAIRE

Rosa, Vivian Leyser da

2000-01-01

Tese (doutorado) - Universidade Federal de Santa Catarina, Centro de Ciências da Educação. Análise do campo de estudos sobre o entendimento público da ciência, distinguindo os modelos de deficit cognitivo e interativo, bem como suas implicações na esfera educacional. Estudo do panorama dos avanços atuais da genética humana, do ponto de vista científico, ético e social. Análise de aspectos relativos ao ensino de genética humana nos cursos de graduação da área da saúde, em nove Universidades...

Manipulación genética de seres humanos

OpenAIRE

Manuel Santos Alcántara

2006-01-01

El gran avance que ha tenido la Genética en los últimos años y, particularmente, aquello relacionado con el desciframiento del genoma humano, ha traído a la discusión pública la posibilidad concreta de manipular genéticamente a los seres humanos. El mejoramiento o perfeccionamiento genético de los seres humanos, denominado eugenesia, actualmente se ha convertido técnicamente en una realidad, motivando una profunda reflexión de tipo ético. La pregunta básica es la siguiente: aquello que es téc...

Integral effect test and code analysis on the cooling performance of the PAFS (passive auxiliary feedwater system) during an FLB (feedwater line break) accident

International Nuclear Information System (INIS)

Bae, Byoung-Uhn; Kim, Seok; Park, Yu-Sun; Kang, Kyoung-Ho

2014-01-01

Highlights: • This study focuses on the experimental validation of the operational performance of the PAFS (passive auxiliary feedwater system). • A transient simulation of the FLB (feedwater line break) in the integral effect test facility, ATLAS-PAFS, was performed to investigate thermal hydraulic behavior during the PAFS actuation. • The test result confirmed that the APR+ has the capability of coping with the FLB scenario by adopting the PAFS and proper set-points for its operation. • The experimental result was utilized to evaluate the prediction capability of a thermal hydraulic system analysis code, MARS-KS. - Abstract: APR+ (Advanced Power Reactor Plus), which is a GEN-III+ nuclear power plant developed in Korea, adopts PAFS (passive auxiliary feedwater system) as an advanced safety feature. The PAFS can completely replace an active auxiliary feedwater system by cooling down the secondary side of steam generators with a natural convection mechanism. This study focuses on experimental and analytical investigation for cooling and operational performance of the PAFS during an FLB (feedwater line break) transient with an integral effect test facility, ATLAS-PAFS. To realistically simulate the FLB accident of the APR+, the three-level scaling methodology was taken into account to design the test facility and determine the test condition. From the test result, the PAFS was actuated to successfully cool down the decay heat of the reactor core by the condensation heat transfer at the PCHX (passive condensation heat exchanger), and thus it could be confirmed that the APR+ has the capability of coping with a FLB scenario by adopting the PAFS and proper set-points for its operation. This integral effect test data were used to evaluate the prediction capability of a thermal hydraulic system analysis code, MARS-KS. The code analysis result proved that it could reasonably predict the FLB transient including the actuation of the PAFS and the natural convection

Estudio molecular del gen MLL en 30 pacientes con leucemias agudas Molecular study of MLL gen in 30 patients with acute leukemias

Directory of Open Access Journals (Sweden)

Raquel Levón Herrera

2000-04-01

Full Text Available Los reordenamientos del gen MLL en la banda cromosómica 11q23 son frecuentes en leucemias agudas (LA en niños y en las LA secundarias desarrolladas después de la terapia con inhibidores de la enzima topoisomerasa II. En menor medida también se aprecia en adultos con LA. La presencia de estos reordenamientos se considera un indicador de mal pronóstico asociado con resultados clínicos desfavorables, por ello es muy importante realizar su determinación en las LA. En este trabajo mostramos los resultados preliminares de la introducción del estudio del gen MLL en nuestro país mediante la técnica de Southern. Analizamos ADN de 30 pacientes con LA, incluidos niños y adultos, que en el momento del estudio se encontraban al debut o en recaída. El estudio molecular se realizó con la sonda FA4, que es un inserto genómico del gen MLL. Sólo uno de los 30 pacientes mostró bandas de reordenamiento con 2 enzimas de restricción diferentes, el resto mostró el gen MLL en configuración germinal. Es interesante destacar que el paciente con el reordenamiento era un niño con leucemia mieloblástica aguda subtipo M5b, lo cual concuerda con la literatura, donde se describe que estos reordenamientos están estrechamente correlacionados con los subtipos mielomonocítico (M4 y monocítico (M5 de leucemia mieloide aguda (LMARearrangements of MLL gen in llq23 chromosomal band are frequents in childhood type of acute leukemia (AL and in secondary AL, developed after therapy with II topoisomerase enzyme. To a lesser extent also is seen in adults with AL. Presence of theses rearrangements is considered to be a worse prognosis indicator, associated with unfavourable clinical results, that is why it is very important to carry our its assessment in AL. In this paper authors present preliminary results from introduction of study on MLL gen in our country through Southern technique. DNA from 30 patients was analized, including children and adults, that at the

Passive BWR integral LOCA testing at the Karlstein test facility INKA

Energy Technology Data Exchange (ETDEWEB)

Drescher, Robert [AREVA GmbH, Erlangen (Germany); Wagner, Thomas [AREVA GmbH, Karlstein am Main (Germany); Leyer, Stephan [TH University of Applied Sciences, Deggendorf (Germany)

2014-05-15

KERENA is an innovative AREVA GmbH boiling water reactor (BWR) with passive safety systems (Generation III+). In order to verify the functionality of the reactor design an experimental validation program was executed. Therefore the INKA (Integral Teststand Karlstein) test facility was designed and erected. It is a mockup of the BWR containment, with integrated pressure suppression system. While the scaling of the passive components and the levels match the original values, the volume scaling of the containment compartments is approximately 1:24. The storage capacity of the test facility pressure vessel corresponds to approximately 1/6 of the KERENA RPV and is supplied by a benson boiler with a thermal power of 22 MW. In March 2013 the first integral test - Main Steam Line Break (MSLB) - was executed. The test measured the combined response of the passive safety systems to the postulated initiating event. The main goal was to demonstrate the ability of the passive systems to ensure core coverage, decay heat removal and to maintain the containment within defined limits. The results of the test showed that the passive safety systems are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them. The test proved that INKA is an unique test facility, capable to perform integral tests of passive safety concepts under plant-like conditions. (orig.)

The Conceptual Design of Innovative Safe PWR

Energy Technology Data Exchange (ETDEWEB)

Kim, Han-Gon [Centural Research Institute, Daejeon (Korea, Republic of); Heo, Sun [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2016-10-15

Most of countries operating NPPs have been performed post-Fukushima improvements as short-term countermeasure to enhance the safety of operating NPPs. Separately, vendors have made efforts on developing passive safety systems as long-term and ultimate countermeasures. AP1000 designed by Westinghouse Electric Company has passive safety systems including the passive emergency core cooling system (PECCS), the passive residual heat removal system (PRHRS), and the passive containment cooling system (PCCS). ESBWR designed by GE-Hitachi also has passive safety systems consisting of the isolation condenser system, the gravity driven cooling system and the PCCS. Other countries including China and Russia have made efforts on developing passive safety systems for enhancing the safety of their plants. In this paper, we summarize the design goals and main design feature of innovative safe PWR, iPOWER which is standing for Innovative Passive Optimized World-wide Economical Reactor, and show the developing status and results of research projects. To mitigate an accident without electric power and enhance the safety level of PWR, the conceptual designs of passive safety system and innovative safe PWR have been performed. It includes the PECCS for core cooling and the PCCS for containment cooling. Now we are performing the small scale and separate effect tests for the PECCS and the PCCS and preparing the integral effect test for the PECCS and real scale test for the PCCS.

Inclusion of Premeditated Threats in the Safety Methodology for NPPs

International Nuclear Information System (INIS)

Levanon, I.

2014-01-01

During the last decade the global effort to prevent terrorism or to mitigate its harm, if prevention fails, has increased. The nuclear power community was involved in this effort trying to prevent terrorist attacks on NPPs (Nuclear Power Plants). A natural extension of terror restraining is the prevention of any premeditated damage to the plant, including acts of state. The pre-feasibility study of an Israeli NPP, conducted by the Ministry of National Infrastructures, has identified the risk of hostile damage to the NPP as a major obstacle to the establishment of nuclear power in Israel, second only to the refusal of nuclear exporting nations to sell an NPP to Israelv. The General Director of the Ministry and the Head of the IAEC (Israeli Atomic Energy Commission) have approved continuation of the pre-feasibility study. This synopsis presents a study, regarding premeditated threats to NPPs, commissioned by the Ministry of National Infrastructures as part of the continuation. It focuses on the safety aspect of premeditated threats originating outside the plant, although a significant part of the analysis can be extended to other subjects such as theft or diversion of strategic materials. The study deals only with methodology and does not encompass specific threats or protection measures. Conclusions and recommendations and marked by bold italics Arial font. The theory of nuclear safety regarding non-premeditated safety events (equipment failures, human errors, natural events, etc.) is well developed. The study refers to these events and the theory attached to them as c lassical , distinguishing them from premeditated events. The study defines two postulates, related to premeditated threats: Correspondence – We should adopt the classical methodology whenever possible. Regulation – The safety of an NPP from premeditated threats requires examination, approval and inspection by a regulator. Key issues of the methodology with substantial differences from the

Genética em transtornos alimentares: ampliando os horizontes de pesquisa

Directory of Open Access Journals (Sweden)

Pinheiro Andréa Poyastro

2006-01-01

Full Text Available OBJETIVO: Revisar a literatura atual concernente à pesquisa genética em transtornos do comportamento alimentar e discutir questões relevantes ao desenvolvimento de um projeto de pesquisa genética nessa área no Brasil. MÉTODO: A revisão realizada utilizou a base de dados Medline, no período de 1984 a maio de 2005, com os seguintes termos de busca: "anorexia nervosa", "bulimia nervosa", "eating disorders", "binge eating disorder", "family studies", "twin studies", "molecular genetics studies". RESULTADOS: Os dados atuais apontam para uma contribuição relevante dos fatores genéticos na suscetibilidade à anorexia e à bulimia nervosa. A pesquisa genética com populações miscigenadas deve levar em consideração o tamanho da amostra, a densidade de genotipagem e a estratificação populacional. Através de "admixture mapping" é possível estimar a estrutura genética destas populações e localizar genes relacionados à variação étnica de doenças ou traços de interesse. CONCLUSÕES: O desenvolvimento de uma grande iniciativa de colaboração em genética de transtornos alimentares no Brasil e na América Latina viabilizará estudar os fatores genéticos em transtornos do comportamento alimentar no contexto de grupos inter-étnicos, e integrar uma nova perspectiva biológica à etiologia destes distúrbios.

Resistência genética em genótipos de feijoeiro a Curtobacterium flaccumfaciens pv. flaccumfaciens Genetic resistance to Curtobacterium flaccumfaciens pv. flaccumfaciens in bean genotypes

Directory of Open Access Journals (Sweden)

Valmir Luiz de Souza

2006-09-01

Full Text Available Curtobacterium flaccumfaciens pv. flaccumfaciens (Cff agente causal da murcha-de-curtobacterium em feijoeiro (Phaseolus vulgaris, é um patógeno vascular de difícil controle. A doença foi detectada pela primeira vez no Brasil na safra das águas de 1995, no Estado de São Paulo. Por se tratar de uma doença de difícil controle, a resistência genética tem sido a melhor opção. O objetivo deste trabalho foi avaliar a reação de genótipos de feijoeiro à murcha-de-curtobacterium, frente a 333 acessos pertencentes ao banco de germoplasma de feijoeiro do Instituto Agronômico de Campinas (IAC. Oportunamente, foram selecionados genótipos de feijoeiro altamente resistentes e suscetíveis, com a finalidade de comparar a colonização de Cff no vaso do xilema a partir da visualização sob microscopia eletrônica de varredura. Os resultados da triagem da resistência genética em genótipos de feijoeiro indicaram a existência de variabilidade genética nas amostras dos 333 genótipos avaliados, ao isolado de Cff Feij 2634. Os materiais foram classificados em 4 grupos de resistência: 29 genótipos (8,7% comportaram-se como altamente resistentes, 13 genótipos (3,9% como resistentes, 18 genótipos (5% como moderadamente resistentes e 273 genótipos (81% suscetíveis. A partir dos resultados obtidos, cerca de 18% dos genótipos de feijoeiros, desde altamente resistentes à moderadamente resistentes, poderão ser úteis para o programa de melhoramento genético como fonte de genes para resistência a Cff. Através da microscopia eletrônica de varredura, foram observadas em genótipos altamente resistentes, várias aglutinações da bactéria envolvidas por filamentos e estruturas rendilhadas sob pontuações da parede do vaso do xilema, não verificados em genótipos suscetíveis, o que sugere a ativação de mecanismos de defesa estruturais e bioquímicos nas plantas resistentes.Curtobacterium flaccumfaciens pv. flaccumfaciens (Cff, the causal

Realization of sanitary requirements concerning standardization of rare radioactive gas effluents at NPPs

International Nuclear Information System (INIS)

Doroshenko, G.G.; Panchenko, S.V.; Chudajkin, O.G.

1987-01-01

The paper is aimed at determination of ways for practical realization of main sanitary requirements concerning environment and population protection under NPP operation. The idea of the requirements is reduced to not increasing permissible limits for radiation doses, minimum irradiation of population and decrease of unjustified irradiation of personnel. The given problem may be fully solved only in case of studying real chacteristics of operating reactors, taking into account statistic nature of effluents of inert radioactive gases (IRG). Methods of developing a system of working and reference standards of IRG effluents at NPPs are suggested. The considered approach may be realized in practice as the All-Union state on branch standards

Passive solar technology

Energy Technology Data Exchange (ETDEWEB)

Watson, D

1981-04-01

The present status of passive solar technology is summarized, including passive solar heating, cooling and daylighting. The key roles of the passive solar system designer and of innovation in the building industry are described. After definitions of passive design and a summary of passive design principles are given, performance and costs of passive solar technology are discussed. Passive energy design concepts or methods are then considered in the context of the overall process by which building decisions are made to achieve the integration of new techniques into conventional design. (LEW).

Université de Genève | Particle Physics Colloquium | 30 April

CERN Multimedia

2014-01-01

Astronomical imaging a thousand times sharper than Hubble: optical interferometry with the Cherenkov Telescope Array, Prof. Dainis Dravins, Lund Observatory.   Wednesday 30 April 2014, 11:15 a.m. Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: Much of the progress in astronomy is led by improved imaging. In the optical, one tantalizing threshold will be two-dimensional imaging of stellar surfaces. With typical sizes of a few milliarcseconds, bright stars require interferometry over kilometer-long baselines. Although several concepts for such interferometer complexes on the ground and in space have been proposed, their realization is not imminent. However, the availability of large optical flux collectors (air Cherenkov telescopes, in particular CTA – the Cherenkov Telescope Array – primarily erected for gamma-ray studies) enable a revival of the quantum-optical method of intensity interferometry, once developed for astronomy but re...

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Directory of Open Access Journals (Sweden)

Jaewoon Yoo

2016-10-01

Full Text Available The Prototype Gen IV sodium cooled fast reactor (PGSFR has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper.

Overall system description and safety characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

International Nuclear Information System (INIS)

Yoo, Jae Woon; Chang, Jin Wook; Lim, Jae Yong; Cheon, Jin Sik; Lee, Tae Ho; Kim, Sung Kyun; Lee, Kwi Lim; Joo, Hyung Kook

2016-01-01

The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper

Decommissioning of NPPs with spent nuclear fuel present - efforts to amend the German regulatory framework to cope with this situation

International Nuclear Information System (INIS)

Brendebach, Boris; Rehs, Bernd

2016-01-01

The authorization to operate an installation for the fission of nuclear fuel for the commercial production of electricity was withdrawn for the seven oldest NPPs and NPP Kruemmel in Germany on August 6, 2011 after the events at Japanese Nuclear Power Plant (NPP) Fukushima Daiichi in March 2011. In the meantime, all these NPPs applied for decommissioning. One aspect reflected in the applications for these NPPs is the possibility that spent nuclear fuel elements or fuel rods will still be present in the cooling ponds at least during the first stage of decommissioning, i.a. due to limited availability of spent fuel casks. Although considerable decommissioning experiences are available in Germany, the approach 'decommissioning with fuel elements present' has been the exceptional case so far. The paper highlights the efforts undertaken to strengthen the regulatory framework with respect to decommissioning in Germany taking into account this changed approach. The paper presents a short introduction to the legal and regulatory requirements for decommissioning in Germany. Afterwards, the updates to the Decommissioning Guide, which includes proposals for an appropriate procedure for the decommissioning, safe enclosure and dismantling of facilities or parts thereof as defined in item 7 of the German Atomic Energy Act in respect of the application of the technical rules for planning and preparation of decommissioning measures as well as for licensing and supervision, are highlighted. In addition, the amendments to the Guidelines for the Decommissioning of Nuclear Facilities of the Nuclear Waste Management Commission (ESK), which is complementary to the Decommissioning Guide in a technical sense, are reported as well. (authors)

Hydrogen passivation of polycrystalline Si thin film solar cells

Energy Technology Data Exchange (ETDEWEB)

Gorka, Benjamin

2010-12-15

Hydrogen passivation is a key process step in the fabrication of polycrystalline Si (poly-Si) thin film solar cells. In this work a parallel plate rf plasma setup was used for the hydrogen passivation treatment. The main topics that have been investigated are (i) the role of plasma parameters (like hydrogen pressure, electrode gap and plasma power), (ii) the dynamics of the hydrogen treatment and (iii) passivation of poly-Si with different material properties. Passivation was characterized by measuring the open-circuit voltage V{sub OC} of poly-Si reference samples. Optimum passivation conditions were found by measurements of the breakdown voltage V{sub brk} of the plasma for different pressures p and electrode gaps d. For each pressure, the best passivation was achieved at a gap d that corresponded to the minimum in V{sub brk}. Plasma simulations were carried out, which indicate that best V{sub OC} corresponds to a minimum in ion energy. V{sub OC} was not improved by a larger H flux. Investigations of the passivation dynamic showed that a plasma treatment in the lower temperature range ({<=}400 C) is slow and takes several hours for the V{sub OC} to saturate. Fast passivation can be successfully achieved at elevated temperatures around 500 C to 600 C with a plateau time of 10 min. It was found that prolonged hydrogenation leads to a loss in V{sub OC}, which is less pronounced within the observed optimum temperature range (500 C-600 C). Electron beam evaporation has been investigated as an alternative method to fabricate poly-Si absorbers. The material properties have been tuned by alteration of substrate temperature T{sub dep}=200-700 C and were characterized by Raman, ESR and V{sub OC} measurements. Largest grains were obtained after solid phase crystallization (SPC) of a-Si, deposited in the temperature range of 300 C. The defect concentration of Si dangling bonds was lowered by passivation by about one order of magnitude. The lowest dangling bond concentration

Aspects of a Co-free hardfacing Materials Development to Reduce the Radioactivity in NPPs

Energy Technology Data Exchange (ETDEWEB)

Kim, Joung Soo; Kim, Hong Pyo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Suh, Jeong Hun [Inss Tek Co., Daejeon (Korea, Republic of)

2007-07-01

For the last one or two decades, active researches to develop Co-free hardfacing materials in order to replace Co-base stellite alloys have been done to reduce the radioactivity in the primary systems in nuclear power plants(NPPs). However, Co-free materials having superior mechanical properties to stellite alloys have not been developed up to now. There are two ways to increase the performance characteristics of the key parts needed to be coated with hardfacing materials, thus resulting in replacing the Co-base stellite alloys with superior mechanical properties; one of them is to develop new Co-free materials with a better quality in performance than that of satellite alloys. The other is to use new coating techniques developed to increase the coated surface properties of already developed Co-free materials. In this study, the aspect of newly developed Co-free materials is reviewed and the necessity of the development of new Co-free materials is emphasized for the replacement of Co-base satellite alloys. In addition, a new coating technique, which is called a laser hardfacing(cladding) technique(LHT), is introduced and its advantage and applicability to the key parts in NPPs are discussed using our experimental results to improve the properties of a surface coated with existing Co-free hardfacing materials. The coating technique using a laser beam having a high energy density has unique advantages to obtain various microstructures such as crystalline, amorphous, porous, and nano structures and also to get coating layers having high a hardness to result in an excellent resistance to erosion corrosion and wear.

Consideraciones genéticas sobre las dislipidemias y la aterosclerosis

OpenAIRE

Julio César Fernández Travieso

2008-01-01

La interacción entre factores genéticos y ambientales explican muchos aspectos de la aterosclerosis y las variaciones genéticas constituyen marcadores de riesgo de la enfermedad coronaria (EC), la cual ocupa el primer lugar entre las causas de morbilidad y mortalidad a nivel mundial. La predisposición familiar a padecer EC, junto al avance vertiginoso en técnicas de análisis de ADN y la disponibilidad de secuencias del genoma humano, han orientado la investigación de alteraciones genéticas re...

Université de Genève | Séminaire de physique corpusculaire | 24 April

CERN Multimedia

2013-01-01

Ultra low-noise amplifiers for silicon and diamond detectors, by Dr Roberto Cardarelli, University Tor Vergata. Wednesday 24 April 2013 at 11:15 a.m. Science III, Auditoire 1S081 30, quai Ernest-Ansermet, 1211 Genève 4 Abstract: Thanks to the SiGe heterojunction, in the last years the BJT transistor technology has been experiencing a great development for high frequency and low-noise operation. The performance of an ultra-low-noise preamplifier (500 e- RMS) with low frequency (100 MHz BW) will be shown. This amplifier, given the low dependence of the noise from the source capacitance (up to 1 nF), the very fast rise time (up to 100 ps) and the 50 Ohm input impedance, is particularly promising for silicon, diamond and high rate gas detectors. More information here.

The experience from operation of electronic personal dosimetry system at Dukovany, Temelin and Mochovce NPPs after repair of Siemens dosemeters eliminating false doses

International Nuclear Information System (INIS)

Malysak, J.; Kocvara, S.; Jurochova, B.; Zelenka, Z.; Schacherl, M.; Zrubec, M.; Kaiser, H.

2003-01-01

This presentation summarizes the operational experience of the Electronic Personal Dosimetry Systems installed at Dukovany, Temelin and Mochovce NPPs. The system consists of three basic parts: Electronic personal dosemeters (EPD); Physical layer (HW); Logical layer (SW). Number of false doses before and after correction is presented. This presentation has demonstrated the possibilities of SEOD system and the possibility of easy dose comparison between the individual NPPs after introducing this electronic dosimetry system. Basically, the results of film and electronic dosimetry systems are according to our findings nearly identical. Electronic dosemeter sensitivity to interfering electromagnetic fields is a problem which is easily re-movable. In addition, if we know this problem, these false doses in the SEOD system can be easily revealed (e.g. by investigation of histograms) and repaired

Divergencia genética en poblaciones peruanas detectada a partir de las frecuencias haplotípicas del mtDNA y del gen nuclear MBL

Directory of Open Access Journals (Sweden)

Jesús H. Córdova

2011-01-01

Full Text Available Objetivos: Avanzar en el conocimiento del origen de las poblaciones peruanas estudiadas en un contexto filogeográfico. Diseño: Estudio genético poblacional. Instituciones: Laboratorio de Genética Humana, Facultad de Ciencias Biológicas, Universidad Nacional Mayor de San Marcos, e Instituto de Genética y Biología Molecular, Facultad de Medicina, Universidad San Martín de Porras, Lima, Perú. Participantes: Siete poblaciones peruanas. Metodología: Análisis comparativo de los resultados a partir del estudio del mtDNA y el gen nuclear MBL de siete poblaciones peruanas, procesados de manera separada y luego combinados, utilizando el programa PHYLYP 3.65, para obtener valores FST de diferenciación genética y la construcción de árboles de distancias por aplicación del algorritmo UPGMA y el análisis subsecuente de los agrupamientos (clusters generados. Principales medidas de resultados: Árboles genéticos generados. Resultados: De manera separada, los árboles generados para cada marcador genético tuvieron topologías propias y diferentes entre sí. Procesados de manera combinada, el árbol resultante demostró que los mayores valores de diferenciación genética se hallaron en las Islas del Lago Titicaca (Puno, Perú conocidas -Taquile, Amantani y Anapia-, que fue calificada como muy alta, porque mostró valores de FST de 0.3113, 0.2949 y 0.3348 respecto de las poblaciones estudiadas, tanto fuera del Departamento de Puno -como Chachapoyas, Pucallpa y Chiclayo, respectivamente-, así como a la de los Uro del mismo Puno y del mismo Lago Titicaca (0.2837. Fuera de Puno, el par de poblaciones Chachapoyas-Pucallpa fue el menos divergente, al alcanzar entre ellas un valor de FST de 0.0108, calificándosele de pequeña. Conclusiones: El árbol obtenido del procesamiento de los marcadores vía una matriz combinada demostró que las poblaciones que habitan las islas de Taquile, Amantani y Anapia, divergen notablemente de las restantes cuatro

Towards an International Culture: Gen Y Students and SNS?

Science.gov (United States)

Lichy, Jessica

2012-01-01

This article reports the findings of a small-scale investigation into the Internet user behaviour of generation Y (Gen Y) students, with particular reference to social networking sites. The study adds to the literature on cross-cultural Internet user behaviour with specific reference to Gen Y and social networking. It compares how a cohort of…

Uros, genética, indígenas y colonos. A propósito de la Neolitización de Europa

OpenAIRE

Alday, Alfonso .; Carretero, José Miguel; Anderung, Cecilia .; Götherström, Anders .

2012-01-01

Las analíticas genéticas realizadas sobre los uros (Bos primigenius) del yacimiento de Mendandia (Treviño), han ofrecido un resultado sorprendente: uno de los individuos pertenece al haplotypo T3, generalmente asociado a animales domésticos (Bos taurus). La datación de la muestra (7265 ± 70 BP; Ua 34366) es acorde con las otras conocidas de su nivel, el III-superior, incidiendo en la antigüedad de su Neolítico. El dato es la excusa para reflexionar sobre el proceso neolitizador y adentrarnos ...

Introducing AstroGen: the Astronomy Genealogy Project

Science.gov (United States)

Tenn, Joseph S.

2016-12-01

The Astronomy Genealogy Project (AstroGen), a project of the Historical Astronomy Division of the American Astronomical Society (AAS), will soon appear on the AAS website. Ultimately, it will list the world's astronomers with their highest degrees, theses for those who wrote them, academic advisors (supervisors), universities, and links to the astronomers or their obituaries, their theses when online, and more. At present the AstroGen team is working on those who earned doctorates with astronomy-related theses. We show what can be learned already, with just ten countries essentially completed.

An electronic flight bag for NextGen avionics

Science.gov (United States)

Zelazo, D. Eyton

2012-06-01

The introduction of the Next Generation Air Transportation System (NextGen) initiative by the Federal Aviation Administration (FAA) will impose new requirements for cockpit avionics. A similar program is also taking place in Europe by the European Organisation for the Safety of Air Navigation (Eurocontrol) called the Single European Sky Air Traffic Management Research (SESAR) initiative. NextGen will require aircraft to utilize Automatic Dependent Surveillance-Broadcast (ADS-B) in/out technology, requiring substantial changes to existing cockpit display systems. There are two ways that aircraft operators can upgrade their aircraft in order to utilize ADS-B technology. The first is to replace existing primary flight displays with new displays that are ADS-B compatible. The second, less costly approach is to install an advanced Class 3 Electronic Flight Bag (EFB) system. The installation of Class 3 EFBs in the cockpit will allow aircraft operators to utilize ADS-B technology in a lesser amount of time with a decreased cost of implementation and will provide additional benefits to the operator. This paper describes a Class 3 EFB, the NexisTM Flight-Intelligence System, which has been designed to allow users a direct interface with NextGen avionics sensors while additionally providing the pilot with all the necessary information to meet NextGen requirements.

The concept of information support system for operational personnel of operating NPPs

International Nuclear Information System (INIS)

Dunaev, V.G.; Golovanov, V.V.

1993-01-01

The paper has been prepared on the materials of the concept developed by the order of ''Rosenergoatom'' concern. In the present paper the main definitions, the principal objectives and functions of the operator support system (OSS) are stated, a brief analysis of operation features of some existing operator information systems is presented, the main trends of development of operator information support system are given, the way and the sequence for implementation of the systems for operating NPPs are reviewed. In this proposed concept in the first place are considered the information support systems for the operators of the power unit main control rooms, however, the presented principles may be applied while designing information support systems for operators of other control rooms of NPP. 4 refs

Activities in Argentina related to the use of slightly enriched uranium in heavy water reactor NPPs

International Nuclear Information System (INIS)

Corcuera, R.

1999-01-01

An overview of activities related to the use of Slightly Enriched Uranium (SEU) fuel in HWR type NPPs, currently under execution in Argentina, is presented. The activities here described cover certain R and D lines as well as the main aspects of the Project 'Transition from full Natural-U to full SEU core in Atucha-I NPP'. Concerning the R and D lines, a summary is given on investigations related to reduction of void-coefficient using SEU fuel assemblies, annular pellet SEU fuel for bundle power flattening, etc. The main aspects of the above mentioned Project are outlined. At present, Atucha-I core is approaching a 40% of core load with SEU fuel, while the target of full SEU fuel core should be reached in 2-3 years. The expected exit burnup for such a core, namely 11000 MWD/tnU, is already currently obtained for SEU fuel in the present mixed core, while an increase in exit burnup of Natural-U fuel has also been obtained in very good agreement with reactor physics calculations. The comprehensive safety analysis carried out for each phase of the Project showed very moderated changes in plant behaviour under the set of postulated accidents and abnormal transients. A recent development, namely the CARA Project, aimed at unifying manufacturing of fuel assemblies for both operating NPPs in Argentina is presented in an accompanying paper. (author)

Arsenic removal with iron(II) and iron(III) in waters with high silicate and phosphate concentrations.

Science.gov (United States)

Roberts, Linda C; Hug, Stephan J; Ruettimann, Thomas; Billah, Morsaline; Khan, Abdul Wahab; Rahman, Mohammad Tariqur

2004-01-01

Arsenic removal by passive treatment, in which naturally present Fe(II) is oxidized by aeration and the forming iron(III) (hydr)oxides precipitate with adsorbed arsenic, is the simplest conceivable water treatment option. However, competing anions and low iron concentrations often require additional iron. Application of Fe(II) instead of the usually applied Fe(III) is shown to be advantageous, as oxidation of Fe(II) by dissolved oxygen causes partial oxidation of As(III) and iron(III) (hydr)oxides formed from Fe(II) have higher sorption capacities. In simulated groundwater (8.2 mM HCO3(-), 2.5 mM Ca2+, 1.6 mM Mg2+, 30 mg/L Si, 3 mg/L P, 500 ppb As(III), or As(V), pH 7.0 +/- 0.1), addition of Fe(II) clearly leads to better As removal than Fe(III). Multiple additions of Fe(II) further improved the removal of As(II). A competitive coprecipitation model that considers As(III) oxidation explains the observed results and allows the estimation of arsenic removal under different conditions. Lowering 500 microg/L As(III) to below 50 microg/L As(tot) in filtered water required > 80 mg/L Fe(III), 50-55 mg/L Fe(II) in one single addition, and 20-25 mg/L in multiple additions. With As(V), 10-12 mg/L Fe(II) and 15-18 mg/L Fe(III) was required. In the absence of Si and P, removal efficiencies for Fe(II) and Fe(III) were similar: 30-40 mg/L was required for As(II), and 2.0-2.5 mg/L was required for As(V). In a field study with 22 tubewells in Bangladesh, passive treatment efficiently removed phosphate, but iron contents were generally too low for efficient arsenic removal.

A Strategy for Accomplishing Human-Performance Monitoring of Constructing NPPs

Energy Technology Data Exchange (ETDEWEB)

Sung, Chanho; Jung, Yeonsub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The main purpose of HPM(Human performance monitoring) is that no significant safety degradation occurs due to changes in design, procedures, training, or staffing during the plant operation. Accordingly, the strategy for accomplishing HPM should be to maintain the acceptable level of human performance for safety operation. This paper presents a strategy to fulfill HPM effectively for constructing NPPs in Korea. Activities for HPM in constructing plants need to be divided into two large parts on the basis of the fuel loading, which could be a good strategy to accomplish HPM effectively. That is, the activities such as making HPM plan and developing its indexes are performed before the fuel loading, while the activities of maintaining acceptable HP levels are conducted after the fuel loading. This HPM strategy includes not only maintaining the criteria of human performance established during ISV, but also improving human performance through existing activities during the plant operation. Constructing plants will also make actively use of the existing programs for enhancing human performance.

Conceptos básicos de programación genética

Directory of Open Access Journals (Sweden)

José Jesús Martínez Páez

2001-04-01

Full Text Available La Programación Genética, PG, es un retoño de los Algoritmos Genéticos, en la cual los cromosomas que sufren la adaptación son en sí mismos programas de computador. Se usan operadores genéticos  especializados que generalizan la recombinación sexual y la mutación, para los programas de computador estructurados en árbol que están bajo adaptación.

Treatment of As(V) and As(III) by electrocoagulation using Al and Fe electrode.

Science.gov (United States)

Kuan, W H; Hu, C Y; Chiang, M C

2009-01-01

A batch electrocoagulation (EC) process with bipolar electrode and potentiodynamic polarization tests with monopolar systems were investigated as methods to explore the effects of electrode materials and initial solution pH on the As(V) and As(III) removal. The results displayed that the system with Al electrode has higher reaction rate during the initial period from 0 to 25 minutes than that of Fe electrode for alkaline condition. The pH increased with the EC time because the As(V) and As(III) removal by either co-precipitation or adsorption resulted in that the OH positions in Al-hydroxide or Fe-hydroxide were substituted by As(V) and As(III). The pH in Fe electrode system elevate higher than that in Al electrode because the As(V) removal substitutes more OH position in Fe-hydroxide than that in Al-hydroxide. EC system with Fe electrode can successfully remove the As(III) but system with Al electrode cannot because As(III) can strongly bind to the surface of Fe-hydroxide with forming inner-sphere species but weakly adsorb to the Al-hydroxide surface with forming outer-sphere species. The acidic solution can destroy the deposited hydroxide passive film then allow the metallic ions liberate into the solution, therefore, the acidic initial solution can enhance the As(V) and As(III) removal. The over potential calculation and potentiodynamic polarization tests reveal that the Fe electrode systems possess higher over potential and pitting potential than that of Al electrode system due to the fast hydrolysis of and the occurrence of Fe-hydroxide passive film.

A study on fatigue measurement of operators for human error prevention in NPPs

Energy Technology Data Exchange (ETDEWEB)

Ju, Oh Yeon; Il, Jang Tong; Meiling, Luo; Hee, Lee Young [KAERI, Daejeon (Korea, Republic of)

2012-10-15

The identification and the analysis of individual factor of operators, which is one of the various causes of adverse effects in human performance, is not easy in NPPs. There are work types (including shift), environment, personality, qualification, training, education, cognition, fatigue, job stress, workload, etc in individual factors for the operators. Research at the Finnish Institute of Occupational Health (FIOH) reported that a 'burn out (extreme fatigue)' is related to alcohol dependent habits and must be dealt with using a stress management program. USNRC (U.S. Nuclear Regulatory Commission) developed FFD (Fitness for Duty) for improving the task efficiency and preventing human errors. 'Managing Fatigue' of 10CFR26 presented as requirements to control operator fatigue in NPPs. The committee explained that excessive fatigue is due to stressful work environments, working hours, shifts, sleep disorders, and unstable circadian rhythms. In addition, an International Labor Organization (ILO) developed and suggested a checklist to manage fatigue and job stress. In domestic, a systematic evaluation way is presented by the Final Safety Analysis Report (FSAR) chapter 18, Human Factors, in the licensing process. However, it almost focused on the interface design such as HMI (Human Machine Interface), not individual factors. In particular, because our country is in a process of the exporting the NPP to UAE, the development and setting of fatigue management technique is important and urgent to present the technical standard and FFD criteria to UAE. And also, it is anticipated that the domestic regulatory body applies the FFD program as the regulation requirement so that a preparation for that situation is required. In this paper, advanced researches are investigated to find the fatigue measurement and evaluation methods of operators in a high reliability industry. Also, this study tries to review the NRC report and discuss the causal factors and

A study on fatigue measurement of operators for human error prevention in NPPs

International Nuclear Information System (INIS)

Ju, Oh Yeon; Il, Jang Tong; Meiling, Luo; Hee, Lee Young

2012-01-01

The identification and the analysis of individual factor of operators, which is one of the various causes of adverse effects in human performance, is not easy in NPPs. There are work types (including shift), environment, personality, qualification, training, education, cognition, fatigue, job stress, workload, etc in individual factors for the operators. Research at the Finnish Institute of Occupational Health (FIOH) reported that a 'burn out (extreme fatigue)' is related to alcohol dependent habits and must be dealt with using a stress management program. USNRC (U.S. Nuclear Regulatory Commission) developed FFD (Fitness for Duty) for improving the task efficiency and preventing human errors. 'Managing Fatigue' of 10CFR26 presented as requirements to control operator fatigue in NPPs. The committee explained that excessive fatigue is due to stressful work environments, working hours, shifts, sleep disorders, and unstable circadian rhythms. In addition, an International Labor Organization (ILO) developed and suggested a checklist to manage fatigue and job stress. In domestic, a systematic evaluation way is presented by the Final Safety Analysis Report (FSAR) chapter 18, Human Factors, in the licensing process. However, it almost focused on the interface design such as HMI (Human Machine Interface), not individual factors. In particular, because our country is in a process of the exporting the NPP to UAE, the development and setting of fatigue management technique is important and urgent to present the technical standard and FFD criteria to UAE. And also, it is anticipated that the domestic regulatory body applies the FFD program as the regulation requirement so that a preparation for that situation is required. In this paper, advanced researches are investigated to find the fatigue measurement and evaluation methods of operators in a high reliability industry. Also, this study tries to review the NRC report and discuss the causal factors and management

CLONACIÓN Y FILOGENIA MOLECULAR DE UN SEGMENTO DEL GEN CODANTE DE LA ACTINA DE MYRCIARIA DUBIA “CAMU-CAMU”: UN CANDIDATO PARA GEN DE REFERENCIA

Directory of Open Access Journals (Sweden)

Juan Carlos Castro Gómez

2012-12-01

Full Text Available Myrciaria dubia “camu-camu” es un frutal amazónico caracterizado por su amplia variación de vitamina C. Pero los estudios genético moleculares que puedan explicar esta variación son limitados. Por ello nuestro objetivo fue realizar la clonación y filogenia molecular de un segmento del gen codante de la actina de M. dubia. Las muestras fueron obtenidas de la colección de germoplasma del INIA. Luego, el ARN fue purificado y mediante RT-PCR con cebadores degenerados se amplificó un segmento del gen. En base a la secuencia obtenida se diseñaron cebadores específicos para PCR en tiempo real. Los resultados muestran que se ha aislado, clonado y secuenciado un segmento del gen codante de actina de M. dubia y detectado su expresión en hojas, pulpa y cáscara de M. dubia. Así, con el soporte de herramientas bioinformáticas y uso de técnicas de biología molecular hemos aislado, clonado y secuenciado un segmento del gen codante de la actina de M. dubia. Asimismo, los análisis realizados muestran que el gen se expresa y presenta niveles similares de expresión en hojas, pulpa y cáscara de M. dubia. Sin embargo, es necesario realizar más experimentos a fin de verificar su estabilidad de expresión.

Impact of Fukushima NPPs Accident on Young Generation's Understanding of Radiation

Energy Technology Data Exchange (ETDEWEB)

Choi, Yoonseok; Kim, Wook; Joo, Yeonjung; Choi, Nowoon [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

2013-05-15

As this study project has been conducted continuously before and after the breaking-out of the Fukushima NPPs accident (FNPPA), accumulated data were analyzed to seek impact of the accident. Results indicated that the first-hand measurement of radiation carried out so far was turned out to be an effective means for mitigation of students' over-sensitive radiation fear even though some influence of the FNPPA was identified in analysis of questionnaire data. The FNPPA brought about radiation fear to the people all over the country. However, it is believed that radiation together with nuclear energy will favorably be understandable by the public through implementation of this first-hand experience program.

Importance of the Design Basis Knowledge Management for New Builds and Existing NPPs

International Nuclear Information System (INIS)

Bychkov, Alexander

2013-01-01

The Fukushima Daiichi NPP accident in Japan reminds us that sustaining a high level of nuclear safety over the life of a plant is of paramount importance to us all. This and previous major accidents have shaken the confidence of the public and even some governments in the safety of nuclear energy. However, a key message from the St. Petersburg Ministerial Conference this past June was that nuclear power will continue to play an important role in energy security and sustainable development. The IAEA will obviously need to continue to assist Member States in strengthening the safety of NPPs. We will also continue to give technical support to both newcomer countries and to countries with established nuclear energy programmes

Safety Design Criteria (SDC) for Gen-IV Sodium-cooled Fast Reactor

International Nuclear Information System (INIS)

Nakai, Ryodai

2013-01-01

SDC Development Background & Objectives: • Safety Design Criteria (SDC) Development for Gen-IV SFR: – Proposed at the GIF Policy Group (PG) meeting in October 2010 –SDC “harmonization” is increasingly important for: • Realization of enhanced safety designs meeting to Gen-IV safety goals and safety approach common to SFR systems; • Preparation for the forthcoming licensing in the near future; • Because Gen-IV SFR are progressing into conceptual design stage. • The SDC is the Reference criteria: – Of the designs of safety-related Structures, Systems & Components that are specific to the SFR system; – For clarifying the requisites systematically & comprehensively; – When the technology developers apply the basic safety approach and use the codes & standards for conceptual design of the Gen-IV SFR system

Aproximación genómica al diagnóstico genético de las distrofias hereditarias de retina y búsqueda de nuevos genes relacionados

OpenAIRE

González del Pozo, María

2014-01-01

Diagnosticar genéticamente a las familias afectas de alguna de las distrofias hereditarias de retina (DHR) es, desde el punto de vista del genetista, una tarea ardua y complicada, si atendemos a la gran cantidad de genes y mutaciones reportados hasta la fecha. La gran heterogeneidad clínica y genética que caracteriza a este conjunto de enfermedades, es sin duda el mayor impedimento para su resolución genética. En este escenario, el empleo de herramientas cada vez más poderosas es indispensabl...

Genética e hanseníase

OpenAIRE

Beiguelman Bernardo

2002-01-01

As diferentes linhas de pesquisa utilizadas para investigar a importância dos fatores hereditários humanos na determinação da resistência/suscetibilidade à infecção pelo Mycobacterium leprae foram discutidas no presente trabalho. Uma síntese dessas abordagens permitiu analisar os resultados das investigações sobre associação da hanseníase com polimorfismos genéticos, distribuição familial da hanseníase, prevalência da hanseníase e distância genética, concordância da hanseníase em gêmeos e est...

Analisis Mutasi Gen Protein X Virus Hbv Pada Penderita Hepatitis B Akut Di Manado

OpenAIRE

Fatimawali; Kepel, Billy

2014-01-01

Faktor-faktor yang mempengaruhi perkembangan hepatitis B kronis menjadi kanker hati antara lain mutasi pada gen x. Penelitian ini bertujuan untuk mengidentifikasi gen protein x virus HBV dan menganalisis apakah terjadi mutasi gen yang terkait dengan munculnya tumor ganas sirosis hati (HCC). Penelitian ini menggunakan primer untuk proses nested PCR yang telah dirancang sebelumnya. Proses nested PCR terhadap 10 sampel DNA HBV pasien dilakukan untuk mengamplifikasi fragmen DNA gen x dilanjutkan ...

Caracterización, diseño y producción recombinante de bacteriocinas y otros péptidos antimicrobianos, secuenciación genómica y efecto en la microbiota de péptidos bioactivos producidos por enterococos

OpenAIRE

Arbulu Ruiz, Sara

2016-01-01

El trabajo desarrollado en esta tesis doctoral ha empleado técnicas de microbiología y bioquímica clásicas, así como técnicas recientes de ingeniería genética, genómica y proteómica y describe en capítulos diferenciados, los siguientes objetivos: En el capítulo III, se describe la identificación y caracterización de bacterias lácticas (BAL) aísladas de heces de buitres leonados (Gyps fulvus subesp. fulvus) por su actividad antimicrobiana, genes que codifican bacteriocinas, factores potenciale...

Université de Genève | Particle Physics Colloquium | 9 April

CERN Multimedia

2014-01-01

A window to the future : the Hyper-Kamiokande project, by Prof. Francesca Di Lodovico, London University.   Wednesday 9 April 2014, 11:15 a.m. Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: In this talk we present the latest status of the Hyper-Kamiokande project. The experiment, based in Japan, has an extremely rich physics portfolio that spans from the study of the CP violation in the leptonic sector and neutrino mixing parameters to proton decay, atmospheric neutrinos and neutrinos of an astronomical origin. In particular, thanks to an upgraded beam power, we will focus on the extremely high sensitivity to CP violation. The project was recently selected as one of the top 27 projects by the Japanese Science Council in the "Japanese Master Plan of Large Research Projects" and is supported worldwide by the international community. It is currently in the design and R&D phase. In this talk we will review both the physics potenti...

Development of a Quantitative Method for Evaluating the Efficacy of Cyber Security Controls in NPPs based on Intrusion Tolerant Concept

International Nuclear Information System (INIS)

Lee, Chanyoung; Seong, Poong Hyun

2017-01-01

Digital I and C systems have been developed and installed in nuclear power plants (NPPs). However, due to installation of digital I and C systems, cyber security concerns are increasing in the nuclear industry. In order to provide useful information about cyber security issues, many regulatory documents, guides and standards were already published in the nuclear industry. The documents include cyber security plans, methods for cyber security assessments and comprehensive set of security controls. In order for useful information about cyber security issues, many regulatory documents, guides and standards have been already published in the nuclear industry. However, there are still difficulties when it comes to deciding which security controls are needed and to defining appropriate security control requirements. It is because practical examples for the application of security controls have not been available to system designers and there is a lack of means for estimating the effectiveness of security controls. In this regard, this paper suggested a framework to quantitatively evaluate how much cyber security is improved when specific cyber security controls are applied in NPPs.

Third-Party Evaluation of Petro Tex Hydrocarbons, LLC, ReGen Lubricating Oil Re-refining Process

Energy Technology Data Exchange (ETDEWEB)

Compere, A L [ORNL; Griffith, William {Bill} L [ORNL

2009-04-01

This report presents an assessment of market, energy impact, and utility of the PetroTex Hydrocarbons, LLC., ReGen process for re-refining used lubricating oil to produce Group I, II, and III base oils, diesel fuel, and asphalt. PetroTex Hydrocarbons, LLC., has performed extensive pilot scale evaluations, computer simulations, and market studies of this process and is presently evaluating construction of a 23 million gallon per year industrial-scale plant. PetroTex has obtained a 30 acre site in the Texas Industries RailPark in Midlothian Texas. The environmental and civil engineering assessments of the site are completed, and the company has been granted a special use permit from the City of Midlothian and air emissions permits for the Texas Commission on Environmental Quality.

Craniostenose em gêmeos: estudo genético

Directory of Open Access Journals (Sweden)

Walter Carlos Pereira

1968-09-01

Full Text Available É relatada a ocorrência de formas clínicas diversas de craniostenose em gêmeos de sexo diferente. A menina apresentava obliteração completa da sutura coronaria e dos dois terços anteriores da sutura sagital; no menino a sutura sagital era a única afetada. O estudo genético mostrou que a craniostenose independe de aberrações cromossômicas, indicando ser transmitida por gens recessivos raros de natureza autossômica.

Transformação genética em espécies florestais.

OpenAIRE

Claudia Studart-Guimarães; Cristiano Lacorte; Ana Cristina Miranda Brasileiro

2010-01-01

A transformação genética, que compreende a introdução de genes exógenos de forma controlada no genoma de uma célula vegetal e posterior regeneração da planta transgênica, tem contribuído com os programas de melhoramento genético de plantas pela obtenção de genótipos com novas características de interesse. O melhoramento de espécies florestais é limitado por características intrínsecas a tais espécies, como a altura dos indivíduos e o ciclo longo de vida. A transformação genética constitui, po...

Emprego de modelos gráficos na seleção de genitores de milho para hibridização e mapeamento genético

Directory of Open Access Journals (Sweden)

Vieira Eduardo Alano

2005-01-01

Full Text Available A dissimilaridade genética estimada por meio de marcadores moleculares, quando acompanhada de informações fenotípicas, é importante para a seleção de genótipos para o melhoramento e o mapeamento genético. Desta forma, os objetivos deste estudo foram: i estimar a dissimilaridade genética entre 30 linhagens de milho contrastantes para a tolerância ao encharcamento; ii selecionar genitores para mapeamento e melhoramento genético; iii comparar diferentes métodos de visualização gráfica das distâncias. Foram utilizados 21 iniciadores de RAPD. A dissimilaridade genética foi estimada por meio do complemento do coeficiente de similaridade de Dice, posteriormente foi construído um dendrograma pelo método de agrupamento da distância média e calculado o coeficiente de correlação cofenética entre a matriz de dissimilaridade e o dendrograma gerado. O complemento da matriz de similaridade foi submetido também à análise de componentes principais e de escala multidimensional. Para ambas as análises, foi testada a eficiência das projeções, por meio da correlação entre as distâncias originais e as representadas nos gráficos. As técnicas de agrupamento não revelaram um bom ajuste entre as distâncias apresentadas graficamente e a matriz original de distâncias, com correlações de 0,70, 0,53 e 0,75 para o dendrograma, componentes principais e análise de escala multidimensional, respectivamente. Dentre as técnicas de agrupamento empregadas, a que atendeu de forma mais precisa aos objetivos do trabalho foi a análise multidimensional, uma vez que esta, além de apresentar a maior correlação com a matriz original de distâncias, preservou as distâncias entre todos os pares de genótipos. Além disso, esta técnica é a mais indicada quando o objetivo do trabalho é a definição de cruzamentos, pois ela permite uma observação mais fácil das distâncias entre todos os pares de genótipos.

Preserving Accuracy in GenBank

DEFF Research Database (Denmark)

Bidartondo, M.I.; Bruns, T. D.; Blackwell, M.

2008-01-01

GenBank, the public repository for nucleotide and protein sequences, is a critical resource for molecular biology, evolutionary biology, and ecology. While some attention has been drawn to sequence errors (1), common annotation errors also reduce the value of this database. In fact, for organisms...

GenMAPP 2: new features and resources for pathway analysis

Directory of Open Access Journals (Sweden)

Dahlquist Kam D

2007-06-01

Full Text Available Abstract Background Microarray technologies have evolved rapidly, enabling biologists to quantify genome-wide levels of gene expression, alternative splicing, and sequence variations for a variety of species. Analyzing and displaying these data present a significant challenge. Pathway-based approaches for analyzing microarray data have proven useful for presenting data and for generating testable hypotheses. Results To address the growing needs of the microarray community we have released version 2 of Gene Map Annotator and Pathway Profiler (GenMAPP, a new GenMAPP database schema, and integrated resources for pathway analysis. We have redesigned the GenMAPP database to support multiple gene annotations and species as well as custom species database creation for a potentially unlimited number of species. We have expanded our pathway resources by utilizing homology information to translate pathway content between species and extending existing pathways with data derived from conserved protein interactions and coexpression. We have implemented a new mode of data visualization to support analysis of complex data, including time-course, single nucleotide polymorphism (SNP, and splicing. GenMAPP version 2 also offers innovative ways to display and share data by incorporating HTML export of analyses for entire sets of pathways as organized web pages. Conclusion GenMAPP version 2 provides a means to rapidly interrogate complex experimental data for pathway-level changes in a diverse range of organisms.

The installation and operation of the seismic instrumentation in Korean NPPs

International Nuclear Information System (INIS)

Lee, Kye Hyun; Baek, Yong Lak; Chung, Yun Suk

1994-01-01

Including the 7 October, 1978, Hongsung earthquake, many earthquakes have occurred in our country. The Korean peninsular is no longer a safety zone against earthquakes, and there are possibilities of the damage they cause. So therefore, it is essential to verify the safety of the safety-related facilities in the event of an earthquake. If an earthquake occurs, seismic instrumentation provides information on the vibratory ground motion and resultant vibratory responses of representative safety-related structures and equipment so that an evaluation can be made immediately as to whether or not the design response spectra have been exceeded. In this paper, general descriptions of the seismic instrumentation installed in domestic NPPs will be discussed; this includes instrument type and location, the Operating Basis Earthquake (OBE) exceedance criteria, and processing and evaluation of earthquake response data, and items to be studied for further enhancement of post-earthquake evaluation techniques are presented

Principal components based support vector regression model for on-line instrument calibration monitoring in NPPs

International Nuclear Information System (INIS)

Seo, In Yong; Ha, Bok Nam; Lee, Sung Woo; Shin, Chang Hoon; Kim, Seong Jun

2010-01-01

In nuclear power plants (NPPs), periodic sensor calibrations are required to assure that sensors are operating correctly. By checking the sensor's operating status at every fuel outage, faulty sensors may remain undetected for periods of up to 24 months. Moreover, typically, only a few faulty sensors are found to be calibrated. For the safe operation of NPP and the reduction of unnecessary calibration, on-line instrument calibration monitoring is needed. In this study, principal component based auto-associative support vector regression (PCSVR) using response surface methodology (RSM) is proposed for the sensor signal validation of NPPs. This paper describes the design of a PCSVR-based sensor validation system for a power generation system. RSM is employed to determine the optimal values of SVR hyperparameters and is compared to the genetic algorithm (GA). The proposed PCSVR model is confirmed with the actual plant data of Kori Nuclear Power Plant Unit 3 and is compared with the Auto-Associative support vector regression (AASVR) and the auto-associative neural network (AANN) model. The auto-sensitivity of AASVR is improved by around six times by using a PCA, resulting in good detection of sensor drift. Compared to AANN, accuracy and cross-sensitivity are better while the auto-sensitivity is almost the same. Meanwhile, the proposed RSM for the optimization of the PCSVR algorithm performs even better in terms of accuracy, auto-sensitivity, and averaged maximum error, except in averaged RMS error, and this method is much more time efficient compared to the conventional GA method

Update History of This Database - GenLibi | LSDB Archive [Life Science Database Archive metadata

Lifescience Database Archive (English)

Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...List Contact us GenLibi Update History of This Database Date Update contents 2014/03/25 GenLibi English archi...base Description Download License Update History of This Database Site Policy | Contact Us Update History of This Database - GenLibi | LSDB Archive ... ...ve site is opened. 2007/03/01 GenLibi ( http://gene.biosciencedbc.jp/ ) is opened. About This Database Data

Comprehensive safety analysis code system for nuclear fusion reactors III: Ex-vessel LOCA analyses considering passive safety

International Nuclear Information System (INIS)

Honda, T.; Okazaki, T.; Maki, K.; Uda, T.; Seki, Y.; Aoki, I.; Kunugi, T.

1996-01-01

Ex-vessel loss-of-coolant accidents (LOCAs) in a fusion reactor have been analyzed to investigate the possibility of passive plasma shutdown. For this purpose, a hybrid code of the plasma dynamics and thermal characteristics of the reactor structures, which has been modified to include the impurity emission from plasma-facing components (PFCs), has been developed. Ex-vessel LOCAs of the cooling system during the ignition operation in the International Thermonuclear Experimental Reactor (ITER), in which graphite PFCs were employed in conceptual design activity, were assumed. When double-ended break occurs at the cold leg of the divertor cooling system, the copper cooling tube begins to melt within 3 s after the LOCA, even though the plasma is passively shut down at nearly 4 s. An active plasma shutdown system will be needed for such rapid transient accidents. On the other hand, when a small (1%) break LOCA occurs there, the plasma is passively shut down at nearly 36 s, which happens before the copper cooling tube begins to melt. When the double-ended break LOCA occurs at the cold leg of the first-wall cooling system, there is enough time (nearly 100 s) to shut down the plasma with a controllable method before the reactor structures are damaged. 21 refs., 8 figs

Advances in passive neutron instruments for safeguards use

International Nuclear Information System (INIS)

Menlove, H.O.; Krick, M.S.; Langner, D.G.; Miller, M.C.; Stewart, J.E.

1994-01-01

Passive neutron and other nondestructive assay techniques have been used extensively by the International Atomic Energy Agency to verify plutonium metal, powder, mixed oxide, pellets, rods, assemblies, scrap, and liquids. Normally, the coincidence counting rate is used to measure the 240 Pu-effective mass and gamma-ray spectrometry or mass spectrometry is used to verify the plutonium isotopic ratios. During the past few years, the passive neutron detectors have been installed in plants and operated in the unattended/continuous mode. These radiation data with time continuity have made it possible to use the totals counting rate to monitor the movement of nuclear material. Monte Carlo computer codes have been used to optimize the detector designs for specific applications. The inventory sample counter (INVS-III) has been designed to have a higher efficiency (43%) and a larger uniform counting volume than the original INVS. Data analyses techniques have been developed, including the ''known alpha'' and ''known multiplication'' methods that depend on the sample. For scrap and other impure or poorly characterized samples, we have developed multiplicity counting, initially implemented in the plutonium scrap multiplicity counter. For large waste containers such as 200-L drums, we have developed the add-a-source technique to give accurate corrections for the waste-matrix materials. This paper summarizes recent developments in the design and application of passive neutron assay systems

Historia del nombre genérico Escallonia mutis ex L. Fil. Historia del nombre genérico Escallonia mutis ex L. Fil.

Directory of Open Access Journals (Sweden)

Fernández Alonso J. L.

1991-06-01

Full Text Available According with the historical context of the Real Expedición Botánica del Nuevo Reino de Granada (1783-1816, the nomenclatural history of the generic name Escallonia Mutis ex L. fiI. (Grossulariaceae is discussed. The extant misinterpretation concerning the name in the manuscript documentation of the Expedition, is brigthened; four species of diferent  families appear associated to this name in the manuscripts. Type specimens of two species, Escallonia myrtilloides L. fiI. and Dichondra evolvulacea (L. fiI. Britton are located or selected. Dentro del contexto histórico de la Real Expedición Botánica del Nuevo Reino de Granada (1783-1816, se realiza el seguimiento del nombre genérico Escallonia Mutis ex L. fiI. (Grossulariaceae. Se aclara la confusión existente acerca de este nombre en la documentación manuscrita de la Expedición (Archivos de Mutis y Linneo, donde se encuentra asociado a descripciones originales de cuatro especies de diferentes familias. Se localiza y selecciona material tipo de dos de ellas: Escallonia myrtilloides L. fil. Y Dichondra evolvulacea (L. IiI. Britton.

Sistema inmune y genética: un abordaje diferente a la diversidad de anticuerpos.

OpenAIRE

Matta Camacho, Nubia Estela

2011-01-01

RESUMEN Es común encontrar en los libros de inmunología o de genética un capítulo con el título de “sistema inmune y genética”, sin embargo su asociación se centra en cómo la generación de anticuerpos rompió el paradigma “un gen, una proteína”, pues en el caso de la producción de anticuerpos, un gen produce millones de proteínas. El sistema inmune tiene muchos vínculos con la genética y la herencia; esta asociación se da porque cualquier sustancia o compuesto que produzca un organi...

Passive Stretch Versus Active Stretch on Intervertebral Movement in Non - Specific Neck Pain

International Nuclear Information System (INIS)

Abd El - Aziz, A.H.; Amin, D.I.; Moustafa, I.

2016-01-01

Neck pain is one of the most common and painful musculoskeletal conditions. Point prevalence ranges from 6% to 22% and up to 38% of the elderly population, while lifetime prevalence ranges from 14,2% to 71%. Up till now no randomized study showed the effect between controversy of active and passive stretch on intervertebral movement. The purpose: the current study was to investigate the effect of the passive and active stretch on intervertebral movement in non - specific neck pain. Material and methods: Forty five subjects from both sexes with age range between 18 and 30 years and assigned in three groups, group I (15) received active stretch, ultrasound and TENS. Group II (15) received passive stretch, ultrasound and TENS. Group III (15) received ultrasound and TENS. The radiological assessment was used to measure rotational and translational movement of intervertebral movement before and after treatment. Results: MANOVA test was used for radiological assessment before and after treatment there was significant increase in intervertebral movement in group I as p value =0.0001. Conclusion: active stretch had a effect in increasing the intervertebral movement compared to the passive stretch

Positive experience in introduction of functional group control at NPPs. What are the future prospects

International Nuclear Information System (INIS)

Fedorov, O.M.; Antonyuk, A.S.

1989-01-01

Experience in introduction of functional group control (FGC) on the basis of the ULU2-computer at the Rovno-3 NPP unit is generalized. A list of additional improvements realized during subsystems RY (steam generator blowing through) and TZ (special waste water system) introduction in the NPP reactor compartment is given. Reguirements to equipment, FGC actuating mechanisms, technological part of the design, necessary for FGC realization, are formulated. FGC relieves NPP operator of routine operations, reduces his fatigue and increases sharply the technological discipline. Rigorous standardization of designs and equipment and centralized management are reguired for FGC introduction at the operating NPPs

Compositional properties of passivity

NARCIS (Netherlands)

Kerber, Florian; van der Schaft, Arjan

2011-01-01

The classical passivity theorem states that the negative feedback interconnection of passive systems is again passive. The converse statement, - passivity of the interconnected system implies passivity of the subsystems -, turns out to be equally valid. This result implies that among all feasible

Perda auditiva genética Genetic hearing loss

Directory of Open Access Journals (Sweden)

Ricardo Godinho

2003-01-01

Full Text Available O progresso das pesquisas relacionadas à perda auditiva genética tem provocado um importante avanço do entendimento dos mecanismos moleculares que governam o desenvolvimento, a função, a resposta ao trauma e o envelhecimento do ouvido interno. Em países desenvolvidos, mais de 50% dos casos de surdez na infância é causada por alterações genéticas e as perdas auditivas relacionadas à idade têm sido associadas com mecanismos genéticos. OBJETIVO: O objetivo desta revisão é relatar as informações mais recentes relacionadas às perdas audtivas de origem genética. FORAMA DE ESTUDO: Revisão sistemática. MATERIAL E MÉTODO: A revisão da literatura inclui artigos indexados à MEDLINE (Biblioteca Nacional de Saúde, NIH-USA e publicados nos últimos 3 anos, além das informações disponíveis na Hereditary Hearing Loss Home Page. CONCLUSÃO: Os recentes avanços no entendimento das perdas auditivas de origem genética têm favorecido a nossa compreensão da função auditiva e tornado o diagnóstico mais apurado. Possivelmente, no futuro, este conhecimento também proporcionará o desenvolvimento de novas terapias para o tratamento das causas genéticas das perdas auditivas.The progress in the research of genetic hearing loss has advanced our understanding of the molecular mechanisms that govern inner ear development, function and response to injury and aging. In the developed world, over 50% of childhood deafness is attributable to genetic causes and even age-related hearing loss has been associated with genetic mechanisms. AIM: The objective of this review is to summarize recent knowledge in genetic hearing loss. STUDY DESIGN: Sistematic review. MATERIAL AND METHODS: The literature review included articles indexed at MEDLINE (The National Library of Medicine, The National Institute of Health - USA focusing on publications from the past 3 years plus the information available at the Hereditary Hearing Loss Home Page. CONCLUSION

KARAKTERISTIK SEKUEN cDNA PENGKODE GEN ANTI VIRUS DARI UDANG WINDU, Penaeus monodon

Directory of Open Access Journals (Sweden)

Andi Parenrengi

2016-11-01

Full Text Available Transgenesis pada ikan merupakan sebuah teknik modern yang berpotensi besar dalam menghasilkan organisme yang memiliki karakter lebih baik melalui rekombinan DNA gen target termasuk gen anti virus dalam peningkatan resistensi pada udang. Gen anti virus PmAV (Penaeus monodon Anti Viral gene merupakan salah satu gen pengkode anti virus yang berasal dari spesies krustase. Penelitian ini dilakukan untuk mengetahui karakteristik gen anti virus yang diisolasi dari udang windu, Penaeus monodon. Isolasi gen anti virus menggunakan metode Polymerase Chain Reaction (PCR dan selanjutnya dipurifikasi untuk sekuensing. Data yang dihasilkan dianalisis dengan program Genetyx Versi 7 dan basic local alignment search tool (BLAST. Hasil penelitian menunjukkan bahwa gen anti virus PmAV yang berhasil diisolasi dari cDNA udang windu dengan panjang sekuen 520 bp yang mengkodekan 170 asam amino. BLAST-N menunjukkan tingkat similaritas yang sangat tinggi (100% dengan gen anti virus yang ada di GeneBank. Komposisi asam amino penyusun gen anti virus yang paling besar adalah serin (10,00%, sedangkan yang terkecil adalah asam amino prolin dan lisin masing-masing 1,76%. Analisis sekuen gen dan deduksi asam amino (BLAST-P memperlihatkan adanya C-type lectin-like domain (CTLD yang memiliki kemiripan dengan gen C-type lectin yang diisolasi dari beberapa spesies krustase. Transgenic fish technology is a potential modern technique in producing better character organism through DNA recombinant of target genes including anti viral gene for improvement of shrimp immunity. PmAV (Penaeus monodon Anti Viral gene is one of anti viral genes isolated from crustacean species. The research was conducted to analyze the characteristics anti viral gene isolated from tiger prawn, Penaeus monodon. Anti viral gene was isolated using Polymerase Chain Reaction (PCR technique and then purified for sequencing. Data obtained were analyzed using Genetyx Version 7 software and basic local alignment

Algoritmos genéticos

Directory of Open Access Journals (Sweden)

José Jesús Martínez Páez

1998-10-01

Full Text Available Esta técnica se basa en el concepto de evolución a través de selección de los mejores individuos, y de los operadores genéticos de selección, reproducción y mutación. Se trata entonces, de definir un espacio de soluciones para el problema que se quiere solucionar, en una cadena de bits. A esto se le conoce como la codificación del cromosoma, donde cada bit, denominado gen  tiene cierto significado especial. Inicialmente el algoritmo genera al azar muchas de estas cadenas o seres, es decir, una población, que luego confronta can un ambiente, que es el problema solucionar o función que se quiere optimizar. De esta confrontación  o evaluación a que se somete cada ser. Se obtiene información sobre cómo se comporto cada uno. A través de métodos aleatorios, pero con probabilidad de selección proporcional a su comportamiento, es decir, a mejor comportamiento mayor probabilidad, se selecciona una nueva población de seres supuestamente mejores que la generación anterior.

Ekspresi Gen CYP19 Aromatase, Estrogen, Androgen pada penderita Periodontitis Agresif

Directory of Open Access Journals (Sweden)

Dahlia Herawati

2016-11-01

Full Text Available Kepadatan tulang tubuh ditentukan oleh gen CYP19 aromatase, hormon estrogen dan androgen. Pada periodontitis agresif terjadi perkembangan cepat kerusakan tulang alveolar, dan kerusakan tulang alveoler tersebut tidak diimbangioleh regenerasi tulang. Tujuan penelitian ini adalah menunjukkan ekspresi gen CYP19 aromatase, estrogen, androgen pada penderita periodontitis agresif agar dapat untuk menjadi pertimbangan pada saat melakukan perawatan periodontal. Metode penelitian, pemeriksaan ekspresi gen aromatse CYP19 berasal dari spesimen tulang alveolar menggunakan imunohistokimia, pengukuran hormon estrogen dan androgen dari serum menggunakan Vidas: Elfa. Hasil penelitian ekspresi gene CYP19 aromatase pada periodontitis agresif menunjukkan gambaran lebih rendah densitasnya dibandingkan pada nonperiodontitis. Estrogen dan androgen pad aperiodontitis agresif ada kecenderungan lebih rendah dibandingkan pada nonperiodontitis. Kesimpulan regenerasi tulang alveoler pad a periodontitis agresif terhambat karena sedikitnya gen CYP19 aromatase dan hormon estrogen dan androgen yang berperan pada pembentukan tulang alveoler kurang memadai.

Knowledge management in Nordic NPPs. Summary report of the findings from the workshop

Energy Technology Data Exchange (ETDEWEB)

Nilsen, S. [Inst. for Energy Technology, Halden (Norway)

2005-04-01

The title of the reported project is 'Nordic Nuclear Safety Research (NKS) Workshop on Knowledge Management in Nordic NPPs'. One important objective of this workshop was to explore if and how knowledge retention activities could be coordinated between the various Nordic utilities. The main conclusions of the workshop can be summed up as follows: Establishing good knowledge management routines is recognized by many utilities today. However, there seem to be no real consensus on what should be focused on in the present situation. Maybe the most pressing problem is to avoid undesirable consequences of the massive retirement soon to follow. Still, there is no consensus on what those consequences might be, and what should be done to avoid them. (au)

Knowledge management in Nordic NPPs. Summary report of the findings from the workshop

International Nuclear Information System (INIS)

Nilsen, S.

2005-04-01

The title of the reported project is 'Nordic Nuclear Safety Research (NKS) Workshop on Knowledge Management in Nordic NPPs'. One important objective of this workshop was to explore if and how knowledge retention activities could be coordinated between the various Nordic utilities. The main conclusions of the workshop can be summed up as follows: Establishing good knowledge management routines is recognized by many utilities today. However, there seem to be no real consensus on what should be focused on in the present situation. Maybe the most pressing problem is to avoid undesirable consequences of the massive retirement soon to follow. Still, there is no consensus on what those consequences might be, and what should be done to avoid them. (au)

Increasing of leak-tightness of hermetic zone and other important components in NPPs

International Nuclear Information System (INIS)

Murani, J.

2001-01-01

The performed by VUEZ resealing works in the hermetic compartments/containment of WWER 440 and WWER 1000 NPPs in Slovakia (Jaslovske Bohunice V-1 NPP, Jaslovske Bohunice V-2 NPP, Mochovce NPP), the Czech Republic (Dukovany NPP, Temelin NPP) and Hungary (Pask NPP) are presented. The leakage rate from hermetic compartments at individual NPP reactor units are shown.The VUEZ activities in field of resealing of weld joints in pools and tanks in the Jaslovske Bohunice V-1 NPP and innovation of the seal of reactor pit protective hood (kolpak) are described. The principle of operation and practical experience of the SMU-V system implemented in the Jaslovske Bohunice V-1 NPP (WWER 440 - V 230) for NPP primary circuit leakage monitoring are also given

Brief review of 1995 events at Ukraine's NPPs. Report on the ChNPP unit 1 of November 27.1995 ''strict regime area premises contamination after reactor refuelling''

International Nuclear Information System (INIS)

Lomakin, V.

1996-01-01

In 1995 number of events at NPP had considerably decreased as compared with that for previous 1992-94, amounted in 87. In particular, as compared with 1994, events number had decreased by 36%. It characterizes a total improvement of current NPPs safety level during 1995. The most events number as recalculated per single unit was at the South Ukraine NPP - 8. The least - at the ChNPP - 4 in total, and 1,3 per unit. Decreasing of a total events number for 1995 did also accordingly reduce other quantitative system indices which reflect state of NPPs safety level. Among event root causes, as it was before, ''administrative management deficiencies'' and ''staff training deficiencies'' are still dominanting. ''Human factor'' issues are still pending for NPPs safety, despite of considerable efforts applied to improved efficiency of correcting measures aimed at their solution. Of sufficient importance for events system development in 1995 was the work implemented at the SSTC NRS/NRA as regards preparation of modern edition of the ''Regulation on order of NPP events investigation and account''. The IAEA/Nuclear Safety Division rendered a sufficient assistance for this work to be done through arrangement of advisory help to Ukrainian specialists from international experts. 2 figs, 8 diagrams

La genética de las poblaciones centroamericanas

OpenAIRE

Barrantes, Ramiro

2005-01-01

Las poblaciones centroamericanas no han sido objeto de muchos estudios genéticos con la excepción de análisis esporádicos de la variación entre y dentro de los grupos amerindios y de origen africano ubicados en el área. No obstante, en los últimos 15 años se efectuaron investigaciones sistemáticas en este sentido incluyendo poblaciones mestizas, particularmente las de Costa Rica y Panamá. En los amerindios se efectuaron estudios detallados de su estructura genética y las relaciones filogenéti...

Gas Identification Using Passive UHF RFID Sensor Platform

Directory of Open Access Journals (Sweden)

Muhammad Ali AKBAR

2015-11-01

Full Text Available The concept of passive Radio Frequency Identification (RFID sensor tag is introduced to remove the dependency of current RFID platforms on battery life. In this paper, a gas identification system is presented using passive RFID sensor tag along with the processing unit. The RFID system is compliant to Electronics Product Code Generation 2 (EPC-Gen2 protocol in 902-928 MHz ISM band. Whereas the processing unit is implemented and analyzed in software and hardware platforms. The software platform uses MATLAB, whereas a High Level Synthesis (HLS tool is used to implement the processing unit on a Zynq platform. Moreover, two sets of different gases are used along with Principal Component Analysis (PCA and Linear Discriminant Analysis (LDA based feature reduction approaches to analyze in detail the best feature reduction approach for efficient classification of gas data. It is found that for the first set of gases, 90 % gases are identified using first three principal components, which is 7 % more efficient than LDA. However in terms of hardware overhead, LDA requires 50 % less hardware resources than PCA. The classification results for the second set of gases reveal that 91 % of gas classification is obtained using LDA and first four PCA, while LDA requires 52 % less hardware resources than PCA. The RFID tag used for transmission is implemented in 0.13 µm CMOS process, with simulated average power consumption of 2.6 µW from 1.2 V supply. ThingMagic M6e embedded reader is used for RFID platform implementation. It shows an output power of 31.5 dBm which allows a read range up to 9 meters.

Safety aspects in life extension of NPPs. Working material

International Nuclear Information System (INIS)

2002-01-01

Due to current social and economical framework, in last years many Member States (MS) started a process of Plant Life Extension (PLEX) for their older nuclear facilities. The process followed many different approaches, being intrinsically dependent on the national regulatory framework and technical tradition. This process has many nuclear safety implications, other than strategic and political ones, and therefore a need for tailoring the available safety assessment tools to such applications has become urgent in recent years. Typical safety assessment processes such as the Periodic Safety Review has been used already and can be used in the future as a framework for a PLEX. Also the review of regular maintenance and ageing management programs and the continuous upgrading of the Safety Analysis Report are tools widely used in a life extension context in many MS. However, recently some MS highlighted the need to identify in a clear way the technical aspects more directly affecting the decision for a long-term operation of a nuclear facility. Many Technical Cooperation projects have been requested for the year 2003-2004 on this subject and a generic task in Nuclear Safety proved necessary as a background activity. Therefore, on May 6-10, 2002, a Consultant Meeting dealing with Safety Aspects of life extension for NPPs was convened at the Nuclear Safety Dept. of the IAEA. It was attended by representatives of Regulatory Bodies and Utilities, both from countries with experience of life extension of NPPs and countries where the process is at the beginning. The main application problems were identified and discussed and a first attempt was carried out to define the key elements of the life extension process, isolating peculiar technical items, LTO related, from generic safety related tasks. The result was a preliminary technical document with a collection of basic experience and information for the implementation of a PLEX program. Therefore the draft document was thought

Management of safety and safety culture at the NPPs of Ukraine

International Nuclear Information System (INIS)

Koltakov, Vladimir

2002-01-01

The report contains general aspects of safety and safety culture. The brief description of operational characteristics and basic indexes of atomic power plants at the Ukraine are represented. The information referring to structure of NPPs of Operation organization license-holder, safety responsibility of both Regulatory and Utility Bodies also is given. The main part of the report include seven sections: 1. Practical application of safety management models; 2. erspective on the relationship between safety management and safety culture; 3. The role of leadership in achieving high standards of safety; 4. Current and future challengers that impact on safety culture and safety management (e.g. the impact of competition, changing, economic and political circumstances, workforce demographics, etc.); 5. Key lessons learned from major events; 6. Practical applications of safety culture concepts (e.g. learning organizations, training staff communications, etc.); 7. dvance in human performance. Some of the main pending safety and safety culture problems that are necessary to achieve in the near future are mentioned

Chemical and physical passivation of type II strained-layer superlattice devices by means of thiolated self-assembled monolayers and polymer encapsulates

Science.gov (United States)

Henry, Nathan C.; Knorr, Daniel B.; Williams, Kristen S.; Baril, Neil; Nallon, Eric; Lenhart, Joseph L.; Andzelm, Jan W.; Pellegrino, Joseph; Tidrow, Meimei; Cleveland, Erin; Bandara, Sumith

2015-05-01

The efficacy of solution deposition of thiolated self-assembled monolayers (SAMs) has been explored for the purpose of passivating III-V type II superlattice (T2SL) photodetectors, more specifically a p-type heterojunction device. Sulfur passivation has previously been achieved on T2SL devices. However, degradation over time, temperature sensitivity and inconsistent reproducibility necessitate a physical encapsulate that can chemically bond to the chemical passivant. Thus, this research investigates two passivation methods, surface passivation with a thiol monolayer and passivation with a polymer encapsulant with a view toward future combination of these techniques. Analysis of the physical and chemical condition of the surface prior to deposition assisted in the development of ideal processes for optimized film quality. Successful deposition was facilitated by in situ oxide removal. Various commercially available functional (cysteamine) and non-functional (alkane) thiolated monolayers were investigated. Dark current was reduced by 3 orders of magnitude and achieved negligible surface leakage at low bias levels. The lowest dark current result, 7.69 × 10-6 A/cm2 at 50 mV, was achieved through passivation with cysteamine.

Traffic Generator (TrafficGen) Version 1.4.2: Users Guide

Science.gov (United States)

2016-06-01

the network with Transmission Control Protocol and User Datagram Protocol Internet Protocol traffic. Each node generating network traffic in an...TrafficGen Graphical User Interface (GUI) 3 3.1 Anatomy of the User Interface 3 3.2 Scenario Configuration and MGEN Files 4 4. Working with...for public release; distribution is unlimited. vi List of Figures Fig. 1 TrafficGen user interface

Human error and the associated recovery probabilities for soft control being used in the advanced MCRs of NPPs

International Nuclear Information System (INIS)

Jang, Inseok; Jung, Wondea; Seong, Poong Hyun

2016-01-01

Highlights: • The operation environment of MCRs in NPPs has changed by adopting digital HSIs. • Most current HRA databases are not explicitly designed to deal with digital HSI. • Empirical analysis for new HRA DB under an advanced MCR mockup are carried. • It is expected that the results can be used for advanced MCR HRA. - Abstract: Since the Three Mile Island (TMI)-2 accident, human error has been recognized as one of the main causes of Nuclear Power Plant (NPP) accidents, and numerous studies related to Human Reliability Analysis (HRA) have been carried out. Most of these studies were focused on considering the conventional Main Control Room (MCR) environment. However, the operating environment of MCRs in NPPs has changed with the adoption of new human-system interfaces (HSI) largely based on up-to-date digital technologies. The MCRs that include these digital and computer technologies, such as large display panels, computerized procedures, and soft controls, are called advanced MCRs. Among the many features of advanced MCRs, soft controls are a particularly important because operating actions in advanced MCRs are performed by soft control. Due to the difference in interfaces between soft control and hardwired conventional controls, different HEP should be used in the HRA for advanced MCRs. Unfortunately, most current HRA databases deal with operations in conventional MCRs and are not explicitly designed to deal with digital Human System Interface (HSI). For this reason, empirical human error and the associated error recovery probabilities were collected from the mockup of an advanced MCR equipped with soft controls. To this end, small-scaled experiments are conducted with 48 graduated students in the department of nuclear engineering in Korea Advanced Institute of Science and Technology (KAIST) are participated, and accident scenarios are designed with respect to the typical Design Basis Accidents (DBAs) in NPPs, such as Steam Generator Tube Rupture

Former Soviet Regulations for seismic design of NPPs and comparison with current international practice

International Nuclear Information System (INIS)

Kostarev, V.; Schukin, A.; Berkovski, A.

1997-01-01

This paper presents a summary of current earthquake design criteria used in former Soviet Regulations for equipment and piping systems of nuclear power plants in light of those used in United States and Japan. The detailed comparative seismic analysis of PWR (WWER) Primary Coolant Loop System (PCLS) according to Former Soviet (Russian) PNAE Code and ASME BPV Code with some comments regarding to Japan Code JEAG - 4601 was undertaken for better understanding of the differences and coincidences of seismic design criteria and requirements. The selection of these three guides for the study has very simple explanation: according to ASME BVPC, JEAG and PNAE the huge majority of existing NPPs has been designed. (J.P.N.)

Former Soviet Regulations for seismic design of NPPs and comparison with current international practice

Energy Technology Data Exchange (ETDEWEB)

Kostarev, V; Schukin, A; Berkovski, A [CKTI-Vibroseism Co. Ltd. (Cape Verde)

1997-03-01

This paper presents a summary of current earthquake design criteria used in former Soviet Regulations for equipment and piping systems of nuclear power plants in light of those used in United States and Japan. The detailed comparative seismic analysis of PWR (WWER) Primary Coolant Loop System (PCLS) according to Former Soviet (Russian) PNAE Code and ASME BPV Code with some comments regarding to Japan Code JEAG - 4601 was undertaken for better understanding of the differences and coincidences of seismic design criteria and requirements. The selection of these three guides for the study has very simple explanation: according to ASME BVPC, JEAG and PNAE the huge majority of existing NPPs has been designed. (J.P.N.)

Seismic margin assessment and earthquake experience based methods for WWER-440/213 type NPPs

International Nuclear Information System (INIS)

Masopust, R.

1996-01-01

This report covers the review of the already completed studies, namely, safe shutdown system identification and classification for Bohunice NPP and the comparative study of standards and criteria. It contains a report on currently ongoing studies concerning seismic margin assessment and earthquake experience based methods in application for seismic evaluation and verification of structures and equipment components of the operating WWER-440/213 type NPPs. This is based on experiences obtained from Paks NPP. The work plan for the remaining period of Benchmark CRP and the new proposals are included. These are concerned with seismic evaluation of selected safety related mechanical equipment and pipes of Paks NPP, and the actual seismic issues of the Temelin WWER-1000 type NPP

Université de Genève | Séminaire de physique corpusculaire | 16 octobre

CERN Multimedia

2013-01-01

Particle accelerators in tumour therapy, Dr Ugo Amaldi, Technische Universität München and TERA Foundation.   Mercredi 16 octobre 2013, 11h15 Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: "Hadrontherapy", or "particle therapy", is a collective word which covers all cancer therapy modalities which irradiate patients with beams of hadrons. The most used hadrons are protons and carbon ions. Protontherapy is developing very rapidly: more than 100,000 patients have been treated and eight companies offer turn-key centres. Carbon ions, used for about 8,000 patients, have a larger radiobiological effectiveness and, being a qualitatively different radiation, require still radiobiological and, in particular, clinical studies to define the best tumour targets. After a review of the rationale for hadrontherapy and of the accelerators used in protontherapy, the European centres for carbon ion therapy will be discussed. Fin...

Université de Genève | Séminaire de physique corpusculaire | 15 May

CERN Multimedia

2013-01-01

Thorium or Uranium fuel cycle for advanced nuclear reactors ? Fuel recycling, multi-recycling, breeding and burning, Dr Jiri Krepel, Paul Scherrer Institut (PSI).   Wednesday 15 May, 11:15 a.m. Science III, Auditoire 1S081 30, quai Ernest-Ansermet, 1211 Genève 4 Abstract: The Thorium fuel cycle provides several advantages, which make it very attractive; e.g. lower waste production and possibly improved reactor safety. However, there are also some drawbacks if compared with the Uranium cycle. The seminar will provide an overview of the basic physical features of both the Thorium and the Uranium fuel cycles and comparison of their performance (criticality, breeding gain) and safety-related parameters (Doppler effect, coolant density effect), with respect to fuel recycling, multi-recycling, breeding and burning. Organised by Prof. Teresa.Montaruli@unige.ch and Prof. Giuseppe.Iacobucci@unige.ch. More information here.

Experience in scientific guidance during start-up and normal operation of NPPs with WWER reactors; Opyt nauchnogo rukovodstva puskom i soprovozhdeniya pri ehkspluatatsii ehnergoblokov AEhS s WWER

Energy Technology Data Exchange (ETDEWEB)

Abagyan, A; Kazakov, V; Kryakvin, L [All-Russian Inst. for NPP Operation, Moscow (Russian Federation)

1996-12-31

The experience gained in the All-Russian Research Institute of NPP Operation (RU) in improvement of reactor start-up and normal operation of NPPs has been reported. The work was carried out on NPPs in Russia, Ukraine, Bulgaria, Hungary and Czechoslovakia. All scientific programmes applied use the system approach, modern methods of safety assessment and the principle of loss effect optimization. For the Kozloduy NPP the following projects have been implemented: design of accelerated unloading system for WWER-1000; refinement of water feeding unit for the WWER-1000 steam generator; response analysis of the safety anti-breakdown system of the second loop. The importance of technical substantiation in the process of decision making is stressed. 6 refs.

Concept of passive safe small reactor for distributed energy supply system

International Nuclear Information System (INIS)

Ishida, Toshihisa; Nakajima, Nobuya; Sawada, Ken-ichi; Yoritsune, Tsutomu; Shimada, Shoichiro; Nakano, Yoshihiro; Yonomoto, Taisuke; Takahashi, Hiroki

2003-01-01

This paper presents a concept of a Passive Safe Small Reactor for Distributed energy supply system (PSRD). The PSRD is an integrated-type PWR with reactor thermal power of 100 to 300 MW aimed at supplying electricity, district heating, etc. In design of the PSRD, high priority is laid on enhancement of safety as well as improvement of economy. Safety is enhanced by the following means: i) Extreme reduction of pipes penetrating the reactor vessel, by limiting to only those of the steam, the feed water and the safety valves, ii) Adoption of the water filled containment and the passive safety systems with fluid driven by natural circulation force, and iii) Adoption of the in-vessel type control rod drive mechanism, accompanying a passive reactor shut-down. To comply with a severe operation condition of PSRD, material of the ball bearing with graphite retainer has been selected by test. For improvement of economy, simplification of the reactor system and long operation of the core are achieved. Optimization of core design concerning the burnable poison ensures the burn-up of 28 GWd/t for low enriched UO 2 fuel rods. (author)

TRANSFER GEN ANTIVIRUS PADA EMBRIO UDANG WINDU, Penaeus monodon DALAM BERBAGAI KONSENTRASI DEOXYRIBO NUCLEIC ACID

Directory of Open Access Journals (Sweden)

Andi Parenrengi

2011-12-01

Full Text Available Teknologi transgenesis khususnya rekayasa genetik untuk menghasilkan udang windu resisten penyakit merupakan salah satu strategi yang dapat dilakukan dalam upaya pemecahan masalah penyakit yang menimpa budidaya udang windu. Teknologi transgenesis khususnya transfer gen antivirus pada udang windu telah berhasil dilakukan melalui teknik transfeksi. Meskipun demikian optimalisasi komponen teknologi tersebut masih perlu dilakukan. Konsentrasi DNA gen merupakan salah satu komponen teknologi transgenesis yang harus dioptimalkan untuk mendapatkan efisiensi dalam transfer gen. Penelitian bertujuan untuk mengetahui konsentrasi DNA gen antivirus yang optimal sebagai bahan transfer gen ke embrio menggunakan metode transfeksi. Embrio udang windu yang diperoleh dari hasil pemijahan induk asal Aceh, dikoleksi 5-10 menit setelah memijah dengan kepadatan 625 telur/2 mL. Transfeksi dilakukan dengan menggunakan media larutan transfeksi jetPEI dengan konsentrasi DNA gen antivirus sebagai perlakuan, yakni: 5, 10, dan 15 µg serta kontrol positif (tanpa plasmid DNA dan negatif (tanpa plasmid DNA dan larutan transfeksi, masing-masing 3 ulangan. Embrio hasil transfeksi ditetaskan pada stoples berisi air laut sebanyak 2 L yang diletakkan pada waterbath. Hasil penelitian menunjukkan bahwa gen antivirus telah berhasil diintroduksi ke embrio udang windu. Hasil analisis ragam menunjukkan bahwa perbedaan konsentrasi DNA (5-15 µg tidak berpengaruh nyata (P>0,05 terhadap daya tetas embrio udang windu. Analisis ekspresi gen pada larva udang windu juga menunjukkan adanya aktivitas ekspresi gen antivirus pada semua perlakuan konsentrasi DNA, di mana ekspresi gen antivirus pada larva transgenik lebih tinggi dibandingkan dengan kontrol (tanpa transfeksi. Sintasan pasca-larva PL-1 yang didapatkan pada penelitian ini adalah 12,0%; 10,0%; 10,6%; 12,3%; dan 14,2% masing-masing untuk perlakuan konsentrasi plasmid DNA 5 µg, 10 µg, 15 µg, kontrol positif dan negatif, di mana

Monte-Carlo simulation of crystallographical pore growth in III-V-semiconductors

International Nuclear Information System (INIS)

Leisner, Malte; Carstensen, Juergen; Foell, Helmut

2011-01-01

The growth of crystallographical pores in III-V-semiconductors can be understood in the framework of a simple model, which is based on the assumption that the branching of pores is proportional to the current density at the pore tips. The stochastic nature of this model allows its implementation into a three-dimensional Monte-Carlo-simulation of pore growth. The simulation is able to reproduce the experimentally observed crysto pore structures in III-V-semiconductors in full quantitative detail. The different branching probabilities for different semiconductors, as well as doping levels, can be deduced from the specific passivation behavior of the semiconductor-electrolyte-interface at the pore tips.

Mejoramiento genético acelerado de angiospermas perennes vía inducción floral por sobre-expresión del gen FT

Directory of Open Access Journals (Sweden)

Rafael Urrea López

2018-05-01

Full Text Available Los bosques y selvas enfrentan el reto de satisfacer la demanda por recursos de una población en crecimiento, así como la amenaza del rápido cambio climático que exacerba la magnitud y frecuencia de estreses bióticos y abióticos. Para ello, es urgente acelerar el mejoramiento genético de especies forestales. Sin embargo, sus largas etapas juveniles y asincronía floral retrasan peligrosamente este proceso. El presente ensayo explora los adelantos biotecnológicos en inducción floral y su potencial aplicación en especies forestales. Entre los genes identificados y caracterizados que participan en la ruta de señalización de la floración, especial atención se destina al gen FLOWERING LOCUS T, considerado un integrador de rutas de señalización altamente conservado entre las angiospermas, que, al sobre-expresarse por ingeniería genética, es capaz de inducir la floración de forma eficiente. Esta novedosa estrategia biotecnológica se ha utilizado, recientemente, para segregar genes de resistencia a enfermedades, en un menor tiempo, en germoplasma comercial de manzana y ciruela. Permite soslayar barreras naturales que por mucho tiempo han restringido a las especies forestales al mejoramiento por selección, principalmente. Entre sus ventajas está la de poder restringirla al proceso y no al producto, para acelerar las cruzas sexuales sin modificar genéticamente la progenie; se aleja así de la controversia alrededor de la liberación y consumo de organismos genéticamente modificados, y de los costos y trámites obligatorios para los OGM para monitoreo de posibles riesgos. Se proyecta como una tecnología que puede acelerar, significativamente, el mejoramiento de especies forestales.

Structural mechanics research and development for main components of chinese 300 MWe PWR NPPs: from design to life management

International Nuclear Information System (INIS)

Yao Weida; Dou Yikang; Xie Yongcheng; He Yinbiao; Zhang Ming; Liang Xingyun

2005-01-01

Qinshan Nuclear Power Plant (Unit I), is a 300 MWe prototype PWR independently developed by Chinese own efforts, from design, manufacture, construction, installation, commissioning, to operation, inspection, maintenance, ageing management and lifetime assessment. Shanghai Nuclear Engineering Research and Design Institute (SNERDI) has taken up with and involved in deeply the R and D to tackle problems of this type of reactor since very beginning in early 1970s. Structural mechanics is one of the important aspects to ensure the safety and reliability for NPP components. This paper makes a summary on role of structural mechanics for component safety and reliability assessment in different stages of design, commissioning, operation, as well as lifetime assessment on this type PWR NPPs, including Qinshan-I and Chashma-I, a sister plant in Pakistan designed by SNERDI. The main contents of the paper cover design by analysis for key components of NSSS; mechanical problems relating to safety analysis; special problems relating to pressure retaining components, such as fracture mechanics, sealing analysis and its test verifications, etc.; experimental research on flow-induced vibration; seismic qualification for components; component failure diagnosis and root cause analysis; vibration qualification and diagnosis technique; component online monitoring technique; development of defect assessment; methodology of aging management and lifetime assessment for key components of NPPs, etc. (authors)

Aconselhamento genético Genetic counseling

Directory of Open Access Journals (Sweden)

João Monteiro de Pina-Neto

2008-08-01

Full Text Available OBJETIVO: Esta revisão sobre aconselhamento genético (AG teve o objetivo de mostrar os conceitos atuais e os princípios filosóficos e éticos aceitos na grande maioria dos países e recomendados pela Organização Mundial da Saúde, as fases do processo, seus resultados e o impacto psicológico de uma doença genética em uma família. FONTES DOS DADOS: Os conceitos apresentados são baseados em uma síntese histórica da literatura sobre AG desde a década de 1930 até o momento atual, sendo que os artigos citados representam os principais trabalhos publicados e que hoje fundamentam a teoria e a prática do AG. SÍNTESE DOS DADOS: O AG modernamente é definido como um processo de comunicação que trata dos problemas humanos relacionados à ocorrência de uma doença genética em uma família. É fundamental que os profissionais da saúde conheçam os aspectos psicológicos desencadeados pela doença genética e como estes aspectos podem ser manejados. Vivemos ainda na genética humana e médica uma fase de predomínio dos aspectos técnicos e científicos e de pouca ênfase no estudo das reações emocionais e dos processos de adaptação das pessoas a estas doenças, o que leva ao baixo entendimento dos clientes sobre os fatos ocorridos, com conseqüências negativas sobre a vida familiar e para a sociedade. CONCLUSÕES: Conclui-se pela necessidade de que as famílias com doenças genéticas sejam encaminhadas para AG e que os profissionais desta área invistam mais na humanização do atendimento, desenvolvendo mais as técnicas do AG psicológico não-diretivo.OBJECTIVE: The objective of this review of genetic counseling (GC is to describe the current concepts and philosophical and ethical principles accepted by the great majority of countries and recommended by the World Health Organization, the stages of the process, its results and the psychological impact that a genetic disease has on a family. SOURCES: The concepts presented are

Main trends in modernization of I and C systems at NPPs in the Russian Federation

International Nuclear Information System (INIS)

Pobedonostsev, A.B.; Chudin, A.G.

1998-01-01

There are more than 20 nuclear power reactors in operation in Russia, which have been operated over 10 years. Operational time of I and C systems of those NPPs is about 30 years, though the lifetime of individual parts of I and C systems is limited by 10-15 years. I and C systems were designed in 60-70-th in accordance with the existing regulations and available technical solutions. Obsolescence of those I and C systems require the reconstruction of existing systems. There are considerations that don't allow to perform equipment replacement one-to-one but require to modernize I and C systems at NPP. (author)

Estudio de la variabilidad genética en camélidos bolivianos

OpenAIRE

Barreta Pinto, Julia

2013-01-01

El estudio de los camélidos sudamericanos es de gran interés en los países andinoscomo Perú, Bolivia, Chile, Argentina, debido a su importante valor económico y suimportancia en el mantenimiento y desarrollo de las poblaciones rurales en dichos países. Dada la falta de estudios genéticos centrados en las poblaciones de camélidos quehabitan en Bolivia, y la necesidad de realizar una valoración de la diversidad genética deestas poblaciones, la presente Tesis doctoral ha abordado el estudio gené...

ASN’s actions in GEN IV reactors and Sodium Fast Reactors (SFR)

International Nuclear Information System (INIS)

Belot, Clotilde

2013-01-01

The ASN is involved in 3 actions concerning GEN IV: • Overview of nuclear reactor GEN IV systems; • Specific analysis about transmutation; • Prototype reactor ASTRID (SFR). Furthermore theses actions are in the beginning (no conclusions or results available)

75 FR 52790 - Small Business Size Standards: Waiver of the Nonmanufacturer Rule

Science.gov (United States)

2010-08-27

... for GEN II and GEN III Image Intensifier Tubes. SUMMARY: The U.S. Small Business Administration (SBA) is considering granting a class waiver of the Nonmanufacturer Rule for Optical Instrument and Lens Manufacturing. On August 13, 2010, SBA received a request that a class waiver be granted for GEN II and GEN III...

Novel Metal-Sulfur-Based Air-Stable Passivation of GaAs with Very Low Surface State Densities

Energy Technology Data Exchange (ETDEWEB)

Ashby, Carol I.H.; Baca, Albert G.; Chang, P.-C; Hafich, M.J.; Hammons, B.E.; Zavadil, Kevin R.

1999-08-09

A new air-stable electronic surface passivation for GaAs and other III-V compound semiconductors that employs sulfur and a suitable metal ion, e.g., Zn, and that is robust towards plasma dielectric deposition has been developed. Initial improvements in photoluminescence are twice that of S-only treatments and have been preserved for >11 months with SiO{sub x}N{sub y} dielectric encapsulation. Photoluminescence and X-ray photoelectron spectroscopies indicate that the passivation consists of two major components with one being stable for >2 years in air. This process improves heterojunction bipolar transistor current gain for both large and small area devices.

SIPSMetGen: It's Not Just For Aircraft Data and ECS Anymore.

Science.gov (United States)

Schwab, M.

2015-12-01

The SIPSMetGen utility, developed for the NASA EOSDIS project, under the EED contract, simplified the creation of file level metadata for the ECS System. The utility has been enhanced for ease of use, efficiency, speed and increased flexibility. The SIPSMetGen utility was originally created as a means of generating file level spatial metadata for Operation IceBridge. The first version created only ODL metadata, specific for ingest into ECS. The core strength of the utility was, and continues to be, its ability to take complex shapes and patterns of data collection point clouds from aircraft flights and simplify them to a relatively simple concave hull geo-polygon. It has been found to be a useful and easy to use tool for creating file level metadata for many other missions, both aircraft and satellite. While the original version was useful it had its limitations. In 2014 Raytheon was tasked to make enhancements to SIPSMetGen, this resulted a new version of SIPSMetGen which can create ISO Compliant XML metadata; provides optimization and streamlining of the algorithm for creating the spatial metadata; a quicker runtime with more consistent results; a utility that can be configured to run multi-threaded on systems with multiple processors. The utility comes with a java based graphical user interface to aid in configuration and running of the utility. The enhanced SIPSMetGen allows more diverse data sets to be archived with file level metadata. The advantage of archiving data with file level metadata is that it makes it easier for data users, and scientists to find relevant data. File level metadata unlocks the power of existing archives and metadata repositories such as ECS and CMR and search and discovery utilities like Reverb and Earth Data Search. Current missions now using SIPSMetGen include: Aquarius, Measures, ARISE, and Nimbus.

Experience in integration of on-line control systems for turbine plants at the Ignalina and Zaporozhe NPPs

International Nuclear Information System (INIS)

Gapunin, A.Ya.; Guchshin, V.I.; Kozlov, N.Yu.; Kravtsov, V.F.; Rasskazov, I.Eh.; Fridman, P.Yu.

1989-01-01

The main stages of designing and improvement of turbine on-line control systems (TOCS) are considered. TOCS is mainly designed for the optimization of NPP equipment operation modes taking into account power system requirements, as well as reactor and steam generator capabilities. TOCS of the Ignalina (K750-65/1300 turbine) and Zaporozhe (K1000-60/1500-2) NPPs are the systems of the third generation and are produced in the form of decentralized complex of software and hardware on the basis of the Ehlektronika S5-2200 computer. 3 refs.; 2 figs

O futuro da epidemiologia genética de características complexas

Directory of Open Access Journals (Sweden)

Feitosa Mary F.

2002-01-01

Full Text Available A epidemiologia genética evoluiu de um enfoque em estudos sobre doenças mendelianas raras para a análise genética de características complexas. Com o advento de informações sobre a completa seqüência de genes ao longo do genoma humano e de outros organismos, o interesse da epidemiologia genética em desvendar a natureza dos fatores que influenciam essas características se tornou primordial. São apresentados os principais métodos empregados no estudo de doenças complexas bem como suas principais vantagens e desvantagens. Discute-se a importância na determinação da amostra e o uso de fenótipos e marcadores genéticos apropriados. Como exemplo das estratégias citadas tomamos o estudo de índice de massa corporal (BMI para ilustrar um fator genético principal localizado no cromossomo 7. Em uma discussão sobre tendências no estudo de ligação, embora reconhecendo que famílias e genealogias continuarão sendo o foco principal das amostras, discute-se alguns novos e eficientes tipos de amostragem (como por exemplo, controles não-relacionados em que amostras de conjunto de DNA serão universalmente empregadas. O reconhecimento da heterogeneidade genética entre estudos e sua interpretação será uma das mais importantes características no futuro das análises de características complexas.

Doping Genético e Eugenia: Diálogos além do esporte

Directory of Open Access Journals (Sweden)

Tiago Vieira Bomtempo

2016-01-01

Full Text Available La ingeniería genética trajo posibilidades antes inimaginables, en la que no hace mucho tiempo era visto sólo en las películas. De la terapia génica, dirigida hacia una corrección o cura de una enfermedad, pasa a la posibilidad del mejoramiento genético, actualmente vislumbrado en el mundo del deporte con el doping genético. ¿Pero, el doping genético no estaría violando el derecho al patrimonio genético no modificado? Aunque la intervención genética no se transmita a los descendentes, habría un mejoramiento genético, que afectaría el genoma del atleta y lo diferenciaría de los demás atletas y otros individuos, hiriendo el principio de igualdad en detrimento de la autonomía privada, pudiéndose estar hablando inicialmente de una relación de dominación, aunque sea en razón al rendimiento físico en el deporte. En este sentido, estas innovaciones que atraviesan el campo de la ingeniería genética, infunden una preocupación acerca de la manipulación genética en las generaciones futuras, punto de discusión no sólo biomédica, sino también bioético y biojurídico. Así, surge una preocupación si estos nuevos avances pueden afectar a la dignidad humana delante de una posible eugenesia, debido a la proyección de personas y la consecuente discriminación por determinada identidad genética. Junto a esto, el objetivo de este artículo es investigar si el dopaje genético ofendería el derecho al patrimonio genético no modificado y los derechos de las generaciones futuras, dando lugar a una nueva forma de eugenesia, al no permitir el ejercicio igualitario de las libertades fundamentales. Por lo tanto, se hace necesaria una investigación basada en los autores de la bioética y el bioderecho, así como también los textos legales nacionales e internacionales que involucran el tema. Es indispensable la discusión de estas cuestiones, sobre todo con la proximidad de los Juegos Olímpicos de Verano en Brasil en este año 2016

Development of stair-climbing mechanism with passive crawlers. Analysis of limitation for crawler rotation angle and test vehicle performance

International Nuclear Information System (INIS)

Hirasawa, Junji; Kimura, Tetsuya

2016-01-01

This paper describes a novel mechanism with passive crawlers that will realize a stair-climbing rescue robot with simple system. The proposed mechanism is called 'SMART-III', it is named after 'Simple Mechanism Adaptive for Rough Terrain'. Some quasi-static dynamic analysis were implemented and effectiveness of limitation for crawler rotation angle were verified. A prototype robot with the SMART-III mechanism had been improved. Experimental results show the effectiveness and performance of the proposed mechanism against a step and continuous stairs. (author)

Microsatélites, distancias genéticas y estructura de poblaciones nativas sudamericanas

Directory of Open Access Journals (Sweden)

Demarchi, Darío Alfredo

2009-01-01

Full Text Available En este trabajo se investigaron las relaciones genéticas entre 17 poblaciones nativas sudamericanas en relación a 15 microsatélites (STRs autosómicos, utilizando 3 distancias genéticas- DST, DAy (δu2-que se ajustan a diferentes postulados teóricos. A través de diferentes técnicas de análisis (escalamiento multidimensional, correlación y correlación parcial de matrices se puso a prueba si las distancias genéticas reflejaban las relaciones interpoblacionales esperadas a partir de la distribución geográfica o de relaciones lingüísticas entre las poblaciones. Además, se estimó en que grado las distintas medidas de distancias genéticas eran influenciadas por la diversidad (He de cada población. Los mapas genéticos muestran, principalmente para DST y DA, que las poblaciones aisladas y con bajo tamaño efectivo (Ne aparecen como outliers, mientras que las poblaciones con alto Ne y mayor flujo génico ocupan una posición central a bajos valores de distancia unas de otras y sin un patrón definido de agrupamiento. La falta de asociación entre distancias genéticas y lingüísticas o geográficas y por otra parte, la alta correlación negativa entre He y distancias génicas promedio por población confiman ese patrón, demostrando que la mayor parte de la variación interpoblacional puede ser explicada en función del grado de diversidad intrapoblacional. Es decir, las distancias genéticas no reflejan relaciones filogenéticas, lingüísticas o geográficas, sino más bien eventos demográficos recientes tales como cuellos de botella genético, efecto fundador o migración externa masiva. Este hecho puede ser comprobado por medio de otra metodología analítica, el modelo de Harpending y Ward.

Safer Systems: A NextGen Aviation Safety Strategic Goal

Science.gov (United States)

Darr, Stephen T.; Ricks, Wendell R.; Lemos, Katherine A.

2008-01-01

The Joint Planning and Development Office (JPDO), is charged by Congress with developing the concepts and plans for the Next Generation Air Transportation System (NextGen). The National Aviation Safety Strategic Plan (NASSP), developed by the Safety Working Group of the JPDO, focuses on establishing the goals, objectives, and strategies needed to realize the safety objectives of the NextGen Integrated Plan. The three goal areas of the NASSP are Safer Practices, Safer Systems, and Safer Worldwide. Safer Practices emphasizes an integrated, systematic approach to safety risk management through implementation of formalized Safety Management Systems (SMS) that incorporate safety data analysis processes, and the enhancement of methods for ensuring safety is an inherent characteristic of NextGen. Safer Systems emphasizes implementation of safety-enhancing technologies, which will improve safety for human-centered interfaces and enhance the safety of airborne and ground-based systems. Safer Worldwide encourages coordinating the adoption of the safer practices and safer systems technologies, policies and procedures worldwide, such that the maximum level of safety is achieved across air transportation system boundaries. This paper introduces the NASSP and its development, and focuses on the Safer Systems elements of the NASSP, which incorporates three objectives for NextGen systems: 1) provide risk reducing system interfaces, 2) provide safety enhancements for airborne systems, and 3) provide safety enhancements for ground-based systems. The goal of this paper is to expose avionics and air traffic management system developers to NASSP objectives and Safer Systems strategies.

Genetic similarity between coriander genotypes using ISSR markers Similaridade genética entre genótipos de coentro por marcadores ISSR

Directory of Open Access Journals (Sweden)

Roberto de A Melo

2011-12-01

Full Text Available With the development of new cultivars, a precise genetic characterization is essential for improvement programs or for cultivar registration and protection. Molecular markers have been complementing the traditional morphological and agronomic characterization techniques because they are virtually unlimited, cover the whole genome and are not environmentally influenced. Genetic characterization constitutes the basis for studies involving estimates of genetic similarity. Therefore, the objective of the present study was to evaluate the genetic similarity between ten coriander genotypes (nine cultivars and one line using ISSR markers. The cultivars used were: Americano, Asteca, Palmeira, Português, Santo, Supéria, Tabocas, Tapacurá, Verdão and the experimental line HTV-9299. The genetic similarity between the cultivars was estimated using 227 banded regions of ISSR molecular markers. The UBC 897 oligonucleotide generated the highest number of fragments (16, resulting in a higher polymorphism. The results indicate that the twenty-nine oligonucleotides chosen were satisfactory for detecting polymorphism. Based on the grouping analysis determined from the similarity data, there were two groups and two sub-groups. The calculated similarity for the genotypes varied from 52 to 75%. The lowest similarity was observed between Português and Verdão, at 52%. The highest similarity was found between Português and Palmeira, at 75%. The ISSR is efficient for identifying DNA polymorphism in coriander.Com o surgimento de novas cultivares, uma caracterização genética precisa é essencial, visando à utilização em programas de melhoramento ou para fins de registros e ou proteção de cultivares. Marcadores moleculares vêm complementando a caracterização morfológica e agronômica tradicional, uma vez que são virtualmente ilimitados, cobrem todo o genoma e não são influenciados pelo ambiente. A caracterização genética constitui a base para

Passive film growth on carbon steel and its nanoscale features at various passivating potentials

International Nuclear Information System (INIS)

Li, Yuan; Cheng, Y. Frank

2017-01-01

Highlights: • Imaged the topography of passivated steel at various film-forming potentials. • Characterized the nanoscale features of passive films. • Determined the composition of passive films formed at various potentials. - Abstract: In this work, the passivation and topographic sub-structure of passive films on a carbon steel in a carbonate/bicarbonate solution was characterized by electrochemical measurements, atomic force microscopy and X-ray photoelectron spectroscopy. When passivating at a potential near the active-passive transition, the film contains the mixture of Fe_3O_4, Fe_2O_3 and FeOOH, with numerous nanoscale features. As the film-forming potential shifts positively, the passive film becomes more compact and the nanoscale features disappear. When the film is formed at a passive potential where the oxygen evolution is enabled, the content of FeOOH in the film increases, resulting in an amorphous topography and reduced corrosion resistance.

Round table on the Supply Chain for NPPs construction: Localization - Daya Bay Experience; REEL Handling and Lifting Systems, More than 60 years expertise in lifting and handling equipment in production process

International Nuclear Information System (INIS)

Frantz, Philippe; Lachaise, Marc; Lau, Steven

2014-01-01

The second day afternoon began with the round table on the Supply Chain for NPPs construction with Philippe Frantz, President of REEL, Marc Lachaise, Head of procurement of NNB at EDF Energy, and Steven Lau, First Deputy General Manager of DNMC. Philippe Frantz started to present the activities and the contribution of REEL in the construction of NPPs as a main supplier of handling system. Then, Marc Lachaise took the lead to present Hinkley Point C Project, the Values of NNB and the key role of the supply chain in this Project. Steven Lau went on to describe the link of the supply chain with the operating of NPPs and explained the cooperation between EDF and CGNPC in order to secure the supply of equipment. Following their presentation, they started the open discussion with the audience by explaining their strategy to make or to buy and the link of this strategy to their core business. They also highlighted the new relations and the new partnership between supplier and customer. They insisted on the necessity to invest on supply chain and to have a strong Nuclear Safety Culture in the supply chain

Crystal Structure of a Eukaryotic GEN1 Resolving Enzyme Bound to DNA

Directory of Open Access Journals (Sweden)

Yijin Liu

2015-12-01

Full Text Available We present the crystal structure of the junction-resolving enzyme GEN1 bound to DNA at 2.5 Å resolution. The structure of the GEN1 protein reveals it to have an elaborated FEN-XPG family fold that is modified for its role in four-way junction resolution. The functional unit in the crystal is a monomer of active GEN1 bound to the product of resolution cleavage, with an extensive DNA binding interface for both helical arms. Within the crystal lattice, a GEN1 dimer interface juxtaposes two products, whereby they can be reconnected into a four-way junction, the structure of which agrees with that determined in solution. The reconnection requires some opening of the DNA structure at the center, in agreement with permanganate probing and 2-aminopurine fluorescence. The structure shows that a relaxation of the DNA structure accompanies cleavage, suggesting how second-strand cleavage is accelerated to ensure productive resolution of the junction.

Université de Genève | Séminaire de physique corpusculaire | 30 octobre

CERN Multimedia

2013-01-01

Heavy Ions in Therapy and Space, Dr Marco Durante, Universität Darmstadt.   Mercredi 30 octobre 2013, 11h15 Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: Research in the field of biological effects of energetic charged particles is rapidly increasing. It is needed for both radiotherapy and protection from the exposure to galactic cosmic radiation in long-term manned space missions. Although the exposure conditions are different in therapy and space (e.g. low- vs. high-dose rate; total- vs. partial-body exposure), a substantial overlap exists in several research topics, such as: individual radiosensitivity, mixed radiation fields, normal tissue degenerative effects, biomarkers of risk, radioprotectors, non-targeted effects. Late effects of heavy ions are arguably the main health risk for human space exploration, and with the increasing number of cancer patients (including young adults and children) treated by protons and carbon ions, this iss...

Université de Genève | Séminaire de physique corpusculaire | 20 November

CERN Multimedia

2013-01-01

Standard Model measurements at the LHC: importance and prospects, Dr Michelangelo Mangano, CERN.   Wednesday 20 November 2013, 11:15 a.m. Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: The key missions of the LHC include the study of the Higgs boson and of electroweak symmetry, and the search for new physics phenomena. These goals, nevertheless, rely on the precise measurements of Standard Model (SM) particles, which are the ultimate measurable decay products of any phenomenon emerging from the LHC. The detailed and accurate study of the dynamics of SM interactions, therefore, becomes a crucial step in fulfilling the LHC's key missions. The dynamical regime exposed by the LHC, with the highest energies ever produced in the laboratory, and the precision required by the experimental measurements, challenge our ability to deliver accurate enough theoretical predictions, and limit the fullest exploitation of the LHC results. A global and coordinat...

Université de Genève | Séminaire de physique corpusculaire | 19 March

CERN Multimedia

2014-01-01

Hunting for sterile neutrinos: short baseline neutrinos at FERMILAB, by Prof. Antonio Ereditato, Bern University.   Wednesday 19 March 2014, 11:15 a.m. Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: The "anomaly" constituted by the LSND/MiniBooNE neutrino signal is still there after many years. This points to the possible existence of sterile neutrinos. An extensive short-mid term program aimed at solving the "puzzle" is being conducted at Fermilab in the Booster neutrino beam, centered on the use of new detectors based on the liquid Argon TPC technology. A multi-step strategy envisions at first the use of the MicroBooNE apparatus, being commissioned in the next months. In a second phase, MicroBooNE will be possibly complemented by the LAr1-ND near detector, being proposed to the Fermilab scientific committee. This program and its prospects will be presented, as well as the parallel work being conducted on LAr TPC...

Université de Genève | Séminaire de physique corpusculaire | 8 May

CERN Multimedia

2013-01-01

The PAMELA mission: more than six years of Cosmic Rays investigation, Dr Francesco Cafagna, Bari University and INFN.   Wednesday 8 May, 11:15 am Science III, Auditoire 1S081 30, quai Ernest-Ansermet, 1211 Genève 4 Abstract: The PAMELA mission major scientific objective is the measurements of Cosmic Rays energy spectra, with special focus on the antiparticles, i.e. antiprotons and positrons, ones. The PAMELA apparatus is a satellite borne magnetic spectrometer and comprises a time-of-flight system, a silicon-microstrip magnetic spectrometer, a silicon-tungsten electromagnetic calorimeter, an anticoincidence system, and shower tail catcher scintillator. It has been more than six years that the PAMELA mission is taking data in space, on board of the russian satellite Resurs-DK. Important results have been obtained on the positron and antiproton abundance and spectra. Moreover new results have been obtained on the composition of the charged cosmic radiation that challenge our current und...

Passive film growth on carbon steel and its nanoscale features at various passivating potentials

Energy Technology Data Exchange (ETDEWEB)

Li, Yuan; Cheng, Y. Frank, E-mail: fcheng@ucalgary.ca

2017-02-28

Highlights: • Imaged the topography of passivated steel at various film-forming potentials. • Characterized the nanoscale features of passive films. • Determined the composition of passive films formed at various potentials. - Abstract: In this work, the passivation and topographic sub-structure of passive films on a carbon steel in a carbonate/bicarbonate solution was characterized by electrochemical measurements, atomic force microscopy and X-ray photoelectron spectroscopy. When passivating at a potential near the active-passive transition, the film contains the mixture of Fe{sub 3}O{sub 4}, Fe{sub 2}O{sub 3} and FeOOH, with numerous nanoscale features. As the film-forming potential shifts positively, the passive film becomes more compact and the nanoscale features disappear. When the film is formed at a passive potential where the oxygen evolution is enabled, the content of FeOOH in the film increases, resulting in an amorphous topography and reduced corrosion resistance.

Gold Nanoparticles Obtained by Bio-precipitation from Gold(III) Solutions

International Nuclear Information System (INIS)

Gardea-Torresdey, J.L.; Tiemann, K.J.; Gamez, G.; Dokken, K.; Tehuacanero, S.; Jose-Yacaman, M.

1999-01-01

The use of metal nanoparticles has shown to be very important in recent industrial applications. Currently gold nanoparticles are being produced by physical methods such as evaporation. Biological processes may be an alternative to physical methods for the production of gold nanoparticles. Alfalfa biomass has shown to be effective at passively binding and reducing gold from solutions containing gold(III) ions and resulting in the formation of gold(0) nanoparticles. High resolution microscopy has shown that five different types of gold particles are present after reaction with gold(III) ions with alfalfa biomass. These particles include: fcc tetrahedral, hexagonal platelet, icosahedral multiple twinned, decahedral multiple twinned, and irregular shaped particles. Further analysis on the frequency of distribution has shown that icosahedral and irregular particles are more frequently formed. In addition, the larger particles observed may be formed through the coalescence of smaller particles. Through modification of the chemical parameters, more uniform particle size distribution may be obtained by the alfalfa bio-reduction of gold(III) from solution

III-V quantum light source and cavity-QED on silicon.

Science.gov (United States)

Luxmoore, I J; Toro, R; Del Pozo-Zamudio, O; Wasley, N A; Chekhovich, E A; Sanchez, A M; Beanland, R; Fox, A M; Skolnick, M S; Liu, H Y; Tartakovskii, A I

2013-01-01

Non-classical light sources offer a myriad of possibilities in both fundamental science and commercial applications. Single photons are the most robust carriers of quantum information and can be exploited for linear optics quantum information processing. Scale-up requires miniaturisation of the waveguide circuit and multiple single photon sources. Silicon photonics, driven by the incentive of optical interconnects is a highly promising platform for the passive optical components, but integrated light sources are limited by silicon's indirect band-gap. III-V semiconductor quantum-dots, on the other hand, are proven quantum emitters. Here we demonstrate single-photon emission from quantum-dots coupled to photonic crystal nanocavities fabricated from III-V material grown directly on silicon substrates. The high quality of the III-V material and photonic structures is emphasized by observation of the strong-coupling regime. This work opens-up the advantages of silicon photonics to the integration and scale-up of solid-state quantum optical systems.

Passivity-based design of robust passive damping for LCL-filtered voltage source converters

DEFF Research Database (Denmark)

Wang, Xiongfei; Blaabjerg, Frede; Loh, Poh Chiang

2015-01-01

Passive damping is proven as a robust stabilizing technique for LCL-filtered voltage source converters. However, conventional design methods of passive dampers are based on the passive components only, while the inherent damping effect of time delay in the digital control system is overlooked....... In this paper, a frequency-domain passivity-based design approach is proposed, where the passive dampers are designed to eliminate the negative real part of the converter output admittance with closed-loop current control, rather than shaping the LCL-filter itself. Thus, the influence of time delay...... in the current control is included, which allows a relaxed design of the passive damper with the reduced power loss and improved stability robustness against grid parameters variations. Design procedures of two commonly used passive dampers with LCL-filtered VSCs are illustrated. Experimental results validate...

Safety regulations regarding to accident monitoring and accident sampling at Russian NPPs with VVER type reactors

International Nuclear Information System (INIS)

Sharafutdinov, Rachet; Lankin, Michail; Kharitonova, Nataliya

2014-01-01

The paper describes a tendency by development of regulatory document requirements related to accident monitoring and accident sampling at Russia's NPPs. Lessons learned from the Fukushima Daiichi accident pointed at the importance and necessary to carry out an additional safety check at Russia's nuclear power plants in the preparedness for management of severe accidents at NPPs. Planned measures for improvement of severe accidents management include development and implementation of the accident instrumentation systems, providing, monitoring, management and storage of information in a severe accident conditions. The draft of Safety Guidelines <

GenMapDB: a database of mapped human BAC clones

OpenAIRE

Morley, Michael; Arcaro, Melissa; Burdick, Joshua; Yonescu, Raluca; Reid, Thomas; Kirsch, Ilan R.; Cheung, Vivian G.

2001-01-01

GenMapDB (http://genomics.med.upenn.edu/genmapdb) is a repository of human bacterial artificial chromosome (BAC) clones mapped by our laboratory to sequence-tagged site markers. Currently, GenMapDB contains over 3000 mapped clones that span 19 chromosomes, chromosomes 2, 4, 5, 9–22, X and Y. This database provides positional information about human BAC clones from the RPCI-11 human male BAC library. It also contains restriction fragment analysis data and end sequen...

Development of a site specific environmental radiation assessment model for Youngkwang NPPs

Energy Technology Data Exchange (ETDEWEB)

Chung, Yang Geun; Song, Myung Jae; Shon, Soon Hwan; Shin, Sang Woon; Lee, Gap Bock; Yang, Kyung Hwa [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Seong Pyung; Kim, Jeong Kyu; Shin, Dae Yoon; Kim, Hyun Ku; Lee, Kyung Jin [Chosun University, Kwangju (Korea, Republic of)

1996-12-31

During the normal operation of nuclear power plants, a very small amount of radionuclide materials is released to the environment. The radionuclide releases to the environment may give rise to some additional radiation dose through a number of pathways. With a few exception, radionuclide transports are highly dependent on the environmental conditions such as topological features, atmospheric and oceanic conditions and socio-environmental characteristics, etc. The dose calculation in Korea are presently being performed using the models in US NRC Reg. Guide. However, these models which were originally released by the US NRC in 1977 are inadequate to deal with environmental movement of radionuclides in consideration of complex terrain, tidal condition of the Yellow Sea, and Youngkwang site specific conditions. KEPRI has developed the models to consider the site specific characteristics around Youngkwang NPPs, to give the realistic dose assessment, and to improve assurance and reliability in public dose calculation. (author). 41 figs., 70 refs.

Passivity and Evolutionary Game Dynamics

KAUST Repository

Park, Shinkyu; Shamma, Jeff S.; Martins, Nuno C.

2018-01-01

This paper investigates an energy conservation and dissipation -- passivity -- aspect of dynamic models in evolutionary game theory. We define a notion of passivity using the state-space representation of the models, and we devise systematic methods to examine passivity and to identify properties of passive dynamic models. Based on the methods, we describe how passivity is connected to stability in population games and illustrate stability of passive dynamic models using numerical simulations.

Passivity and Evolutionary Game Dynamics

KAUST Repository

Park, Shinkyu

2018-03-21

This paper investigates an energy conservation and dissipation -- passivity -- aspect of dynamic models in evolutionary game theory. We define a notion of passivity using the state-space representation of the models, and we devise systematic methods to examine passivity and to identify properties of passive dynamic models. Based on the methods, we describe how passivity is connected to stability in population games and illustrate stability of passive dynamic models using numerical simulations.

A Novel Role of Human Holliday Junction Resolvase GEN1 in the Maintenance of Centrosome Integrity

DEFF Research Database (Denmark)

Gao, M.; Danielsen, Jannie Michaela Rendtlew; Wei, L.-Z.

2012-01-01

but not catalytic activity of GEN1 is required for preventing centrosome hyper-amplification, formation of multiple mitotic spindles, and multi-nucleation. Our findings provide novel insight into the biological functions of GEN1 by uncovering an important role of GEN1 in the regulation of centrosome integrity....

PARTOS - Passive and Active Ray TOmography Software: description and preliminary analysis using TOMO-ETNA experiment’s dataset

Directory of Open Access Journals (Sweden)

Alejandro Díaz-Moreno

2016-09-01

Full Text Available In this manuscript we present the new friendly seismic tomography software based on joint inversion of active and passive seismic sources called PARTOS (Passive Active Ray TOmography Software. This code has been developed on the base of two well-known widely used tomographic algorithms (LOTOS and ATOM-3D, providing a robust set of algorithms. The dataset used to set and test the program has been provided by TOMO-ETNA experiment. TOMO-ETNA database is a large, high-quality dataset that includes active and passive seismic sources recorded during a period of 4 months in 2014. We performed a series of synthetic tests in order to estimate the resolution and robustness of the solutions. Real data inversion has been carried out using 3 different subsets: i active data; ii passive data; and iii joint dataset. Active database is composed by a total of 16,950 air-gun shots during 1 month and passive database includes 452 local and regional earthquakes recorded during 4 months. This large dataset provides a high ray density within the study region. The combination of active and passive seismic data, together with the high quality of the database, permits to obtain a new tomographic approach of the region under study never done before. An additional user-guide of PARTOS software is provided in order to facilitate the implementation for new users.

Environmental Information for the U.S. Next Generation Air Transportation System (NextGen)

Science.gov (United States)

Murray, J.; Miner, C.; Pace, D.; Minnis, P.; Mecikalski, J.; Feltz, W.; Johnson, D.; Iskendarian, H.; Haynes, J.

2009-09-01

It is estimated that weather is responsible for approximately 70% of all air traffic delays and cancellations in the United States. Annually, this produces an overall economic loss of nearly 40B. The FAA and NASA have determined that weather impacts and other environmental constraints on the U.S. National Airspace System (NAS) will increase to the point of system unsustainability unless the NAS is radically transformed. A Next Generation Air Transportation System (NextGen) is planned to accommodate the anticipated demand for increased system capacity and the super-density operations that this transformation will entail. The heart of the environmental information component that is being developed for NextGen will be a 4-dimensional data cube which will include a single authoritative source comprising probabilistic weather information for NextGen Air Traffic Management (ATM) systems. Aviation weather constraints and safety hazards typically comprise meso-scale, storm-scale and microscale observables that can significantly impact both terminal and enroute aviation operations. With these operational impacts in mind, functional and performance requirements for the NextGen weather system were established which require significant improvements in observation and forecasting capabilities. This will include satellite observations from geostationary and/or polar-orbiting hyperspectral sounders, multi-spectral imagers, lightning mappers, space weather monitors and other environmental observing systems. It will also require improved in situ and remotely sensed observations from ground-based and airborne systems. These observations will be used to better understand and to develop forecasting applications for convective weather, in-flight icing, turbulence, ceilings and visibility, volcanic ash, space weather and the environmental impacts of aviation. Cutting-edge collaborative research efforts and results from NASA, NOAA and the FAA which address these phenomena are summarized

The GenABEL Project for statistical genomics.

Science.gov (United States)

Karssen, Lennart C; van Duijn, Cornelia M; Aulchenko, Yurii S

2016-01-01

Development of free/libre open source software is usually done by a community of people with an interest in the tool. For scientific software, however, this is less often the case. Most scientific software is written by only a few authors, often a student working on a thesis. Once the paper describing the tool has been published, the tool is no longer developed further and is left to its own device. Here we describe the broad, multidisciplinary community we formed around a set of tools for statistical genomics. The GenABEL project for statistical omics actively promotes open interdisciplinary development of statistical methodology and its implementation in efficient and user-friendly software under an open source licence. The software tools developed withing the project collectively make up the GenABEL suite, which currently consists of eleven tools. The open framework of the project actively encourages involvement of the community in all stages, from formulation of methodological ideas to application of software to specific data sets. A web forum is used to channel user questions and discussions, further promoting the use of the GenABEL suite. Developer discussions take place on a dedicated mailing list, and development is further supported by robust development practices including use of public version control, code review and continuous integration. Use of this open science model attracts contributions from users and developers outside the "core team", facilitating agile statistical omics methodology development and fast dissemination.

Genética, performance física humana e doping genético: o senso comum versus a realidade científica

Directory of Open Access Journals (Sweden)

Rodrigo Gonçalves Dias

2011-02-01

Full Text Available Atletas de elite são reconhecidos como fenômenos esportivos e o potencial para atingir níveis superiores de performance no esporte está parcialmente sob o controle de genes. A excelência atlética é essencialmente multifatorial e determinada por complexas interações entre fatores ambientais e genéticos. Existem aproximadamente 10 milhões de variantes genéticas dispersas por todo o genoma humano e uma parcela destas variantes têm demonstrado influenciar a responsividade ao treinamento físico. Os fenótipos de performance física humana parecem ser altamente poligênicos e alguns estudos têm comprovado a existência de raras combinações genotípicas em atletas. No entanto, os mecanismos pelos quais genes se interagem para amplificar a performance física são desconhecidos. O conhecimento sobre os genes que influenciam a treinabilidade somado ao potencial uso indevido dos avanços da terapia gênica, como a possível introdução de genes em células de atletas, fez surgir o termo doping genético, um novo e censurado método de amplificação da performance física, além dos limites fisiológicos. Aumentos na hipertrofia muscular esquelética e nos níveis de hematócrito estão sendo conseguidos através da manipulação da expressão de genes específicos, mas a grande parte das impressionáveis alterações foi obtida em experimentação com animais de laboratório. A compreensão dos resultados científicos envolvendo genética, performance física humana e doping genético é uma difícil tarefa. Com o propósito de evitar a contínua má interpretação e propagação de conceitos errôneos, esta revisão, intencionalmente, vem discutir as evidências científicas produzidas até o momento sobre o tema, permitindo a compreensão do atual "estado da arte"

Quantificação da divergência genética entre acessos de goibeira por meio da estratégia Ward-MLM

Directory of Open Access Journals (Sweden)

Bianca Machado Campos

2013-06-01

Full Text Available O presente trabalho teve como objetivo quantificar a divergência genética entre 138 acessos de goiabeira procedentes do banco de germoplasma da Universidade Estadual do Norte Fluminense Darcy Ribeiro (UENF, com base em descritores morfológicos, agronômicos e físico-químicos, por meio do procedimento Ward - Modified Location Model (MLM. Para tanto, foram avaliados 13 descritores, sendo cinco qualitativos (coloração da polpa, superfície do fruto, formato do fruto ao final do pedúnculo, largura do pescoço e uniformidade da cor da polpa e oito quantitativos (massa média do fruto, diâmetro longitudinal do fruto, diâmetro transversal do fruto, rendimento da polpa, teor de sólidos solúveis totais, acidez do fruto, relação teor de sólidos solúveis totais e acidez do fruto e teor de ácido ascórbico. Detectou-se ampla variabilidade genética pelos dados morfológicos, agronômicos e físico-químicos nos 138 acessos de goiaba. Pelo procedimento da função da verossimilhança, determinou-se oito o número ideal de grupos, com um valor de incremento de 67,51. O grupo III foi considerado o mais distante, enquanto os grupos I, II, IV, V e VI, os mais próximos. O procedimento Ward-MLM é uma ferramenta útil para detectar divergência genética e agrupar os acessos utilizando, simultaneamente, variáveis qualitativas e quantitativas.

Polimorfismo Val108/158Met en el gen dopaminérgico catecol-o-metil transferasa (COMT en una población mixta peruana y su importancia para los estudios neuropsiquiátricos

Directory of Open Access Journals (Sweden)

Doris Huerta

2007-12-01

Full Text Available Introducción: El gen dopaminérgico catecol-o-metil transferasa (COMT, tiene un polimorfismo funcional Val108/158Met que da lugar a variantes de la enzima que cataliza la o-metilación de las catecolaminas activas, participando en el metabolismo de las drogas y neurotransmisores, como la L-dopa, norepinefrina, epinefrina y dopamina y, por consiguiente, puede asociarse a condiciones neuropsiquiátricas. Objetivos: Determinar las frecuencias genotípicas y alélicas del polimorfismo Val108/158Met del gen COMT en sujetos saludables de una población mixta peruana y establecer las implicancias para el estudio genético de enfermedades y otras condiciones neuropsiquiátricas. Diseño: Estudio descriptivo, observacional, transversal. Lugar: Centro de Investigación de Bioquímica y Nutrición ‘Alberto Guzmán Barrón’. Facultad de Medicina, Universidad Nacional Mayor de San Marcos. Participantes: Ciento seis personas, hombres y mujeres, clínicamente saludables, sin enfermedades neurológicas ni mentales u otra patología similar, voluntarios con consentimiento informado, sin relación de parentesco, todos residentes en Lima, cuyas edades fluctuaban entre los 18 y 50 años. Intervenciones: Extracción del ADN genómico a partir de células de epitelio bucal, según metodología estándar. Amplificación mediante la PCR con primers específicos y digestión con la enzima de restricción NlaIII. Detección de fragmentos de restricción de longitud polimórfica (RFLP por electroforesis en gel de poliacrilamida al 6%, teñido con nitrato de plata. Principales medidas de resultados: Frecuencias genotípicas y alélicas del gen COMT en población mixta peruana. Resultados: Se encontró las frecuencias genotípicas Met/Met=0,0661, Val/Met=0,5094 y Val/Val=0,4245, siendo la distribución consistente con el equilibrio de Hardy-Weinberg (X² =3,0317, g.l.=1, p >0,05. Las frecuencias alélicas encontradas fueron alelo Val=0,68 y el alelo Met=0

Genes and proteins of Escherichia coli (GenProtEc).

Science.gov (United States)

Riley, M; Space, D B

1996-01-01

GenProtEc is a database of Escherichia coli genes and their gene products, classified by type of function and physiological role and with citations to the literature for each. Also present are data on sequence similarities among E.coli proteins with PAM values, percent identity of amino acids, length of alignment and percent aligned. The database is available as a PKZip file by ftp from mbl.edu/pub/ecoli.exe. The program runs under MS-DOS on IMB-compatible machines. GenProtEc can also be accessed through the World Wide Web at URL http://mbl.edu/html/ecoli.html.

Reflexo da interação genótipo x ambiente sobre o melhoramento genético de feijão

OpenAIRE

Pereira, Thayse Cristine Vieira; Schmit, Rodolfo; Haveroth, Eduardo José; Melo, Rita Carolina de; Coimbra, Jefferson Luís Meirelles; Guidolin, Altamir Frederico; Backes, Rogério Luiz

2015-01-01

RESUMO: O objetivo foi avaliar os componentes da variância fenotípica e estimar a influência da interação genótipo*ambiente no rendimento de grãos em feijão. Os componentes da variância fenotípica foram estimados pelo método da máxima verossimilhança restrita e do melhor preditor linear não viesado (REML/BLUP), juntamente com o espaço de inferência específico. As avaliações foram realizadas nas safras agrícolas de 2006/07 a 2011/12 no município de Lages/SC. Durante o período, 104 genótipos fo...

ANALISIS SEKUEN GEN GLUTATION PEROKSIDASE (GPX1 SEBAGAI DETEKSI STRES OKSIDATIF AKIBAT INFEKSI MYCOBACTERIUM TUBERCULOSIS

Directory of Open Access Journals (Sweden)

Ari Yuniastuti

2013-02-01

Full Text Available Glutation merupakan antioksidan yang berperan dalam fungsi imun, dan diekspresikan secara genetik oleh urutan gen yang membentuk protein enzim Glutation Peroxidase (GPx1. Bila ekspresi gen berubah maka terjadi perubahan fungsi glutation dan kerentanan terhadap stress oksidatif. Metode yang digunakan adalah Kasus-kontrol. Sampel yang digunakan adalah sampel darah. Kelompok kasus adalah sampel darah pasien tuberkulosis paru sedangkan kelompok kontrol adalah sampel darah orang sehat. Pemeriksaan gen Glutation peroxidase (GPx1 menggunakan metode Polymerase Chain Reaction (PCR untuk melihat pita DNA pada pasien tuberkulosis par serta elektroforesis produk PCR-RFLP gen GPx1 kelompok sampel tuberkulosis. Hasil penelitian menunjukkan bahwa tidak terdapat hubungan yang bermakna antara polimorfisme gen GPx1 (p=0,365 pasein tuberkulois dengan individu sehat, sehingga tidak dapat digunakan sebagai alat deteksi kerentanan terhadap stress oksidatif pada pasien tuberkulosis. Perlu penelitian lanjutan yang menggunakan sampel lebih besar dan populasi etnik yang berbeda.

A survey on the VXIbus and validity analyses for instrumentation and control in NPPs

International Nuclear Information System (INIS)

Kwon, Kee Choon; Park, Won Man

1997-06-01

This document presents the technical status of the VXIbus system and its interface. VMEbus, while developed as a backplane for Motorola processors, can be used for data acquisition, control and other instrumentation applications. The VXIbus and its associated standard for form, fit, and electrical interface have simplified the process of putting together automated instrumentation systems. The VXIplug and play system alliance was founded in 1993, the alliance's charter to improve the effectiveness of VXI-based solutions by increasing ease-of-use and improving the interoperability of mainframes, computers, instrumentations, and software through open, multivendor standards and practices. This technical report surveys surveys the instrumentation and control in NPPs apply to the VXI-based instruments which are studied expendability, interoperability, maintainability and other features. (author). 10 refs., 4 tabs., 25 figs

Polimorfismos del gen BoLA-DRB3.2* en ganado criollo colombiano

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Darwin Hernández H.

2013-10-01

Full Text Available Objetivo. Caracterizar el polimorfismo del gen BoLA-DRB3.2* en las razas bovinas criollas y colombianas. Materiales y métodos. En 360 muestras de ADN de ocho razas bovinas criollas (Blanco Orejinegro, Casanareño, Costeño con Cuernos, Chino Santandereano, Caqueteño, Hartón del Valle, Romosinuano y San Martinero, dos razas sintéticas Colombianas (Lucerna y Velásquez y dos razas foráneas (Brahman y Holstein se evaluó el polimorfismo del gen BoLA-DRB3.2 mediante técnicas moleculares (PCR-RFLP; se calculó el número promedio de alelos (NPA, las frecuencias, la heterocigocidad esperada (He y observada (Ho, el equilibrio de Hardy-Weinberg, la estructura genética y los valores de FST y FIS. Resultados. El NPA fue 14.6 ± 3.8 siendo Caqueteño la raza con mayor NPA (25 y el menor el Chino Santandereano (10. Se encontraron 41 alelos BoLA-DRB3.2* los más frecuentes fueron *28, *37, *24, *23, *20, *27, *8, *16, *39 (0.17, 0.11, 0.10, 0.09, 0.09, 0.07, 0.07 y 0.06 respectivamente. Se encontró alta diversidad genética (He = 0.878 con mayor valor en Caqueteño (0.96 y menor en San Martinero (0.81. Todas las razas se encontraron en equilibrio de Hardy-Weinberg, se encontraron valores altamente significativos de diferenciación genética (FST= 0.044 y de coeficiente de endogamia (FIS = 0.249. Conclusiones. El ganado criollo colombiano posee alto polimorfismo del gen BoLA-DRB3.2* representado en los altos valores de NPA y diversidad génetica.

Variabilidade genética da produção anual da seringueira: estimativas de parâmetros genéticos e estudo de interação genótipo x ambiente Genetic variability of rubber tree annual yielding: estimates of genetic parameters and study of genotype x environment interaction

Directory of Open Access Journals (Sweden)

Paulo de Souza Gonçalves

1990-01-01

Full Text Available Selecionaram-se dezenove genótipos de seringueira (Hevea brasiliensis Muell. Arg. considerados como os melhores em vigor e produção em uma população de pés francos estabelecidos no campo de ensaios da Estação Experimental de Pindorama, com o objetivo de estudar a variabilidade genética e ambiental e a interação genótipo x ambiente sobre a produção durante cinco anos. Com base na análise da variância anual e conjunta, estimaram-se parâmetros genéticos para produção, na tentativa de quantificar o ganho genético com a seleção, e as correlações genéticas e fenotfpicas das produções ano a ano. Os resultados das análises da variância dentro de anos mostraram efeitos significativos para genótipos, sendo os efeitos da interação genótipo x ambiente altamente significativos. As estimativas de herdabilídade, no sentido amplo, ao nível de médias de parcelas, foram altas, com amplitude de 0,57 a 0,77, respectivamente, para o segundo e quinto ano de produção. As maiores percentagens de ganho genético foram obtidas no primeiro e quinto ano de produção, 39,03 e 27,57 respectivamente. Correlações genéticas e fenotípicas entre anos de sangria foram altas e significativas. Os altos valores de herdabilidade e ganho genético para o primeiro ano de sangria indicam que a seleção massal conduzida nesta fase proporciona, efetivamente, maior ganho na seleção.Nineteen rubber trees (Hevea brasiliensis Muell. Arg. considered as the best in growth and yield performance, were selected from a mature seedling population in the experimental field at the Pindorama Experiment Station of the "Instituto Agronômico de Campinas", São Paulo State, Brazil. Studies were carried out aiming to assess the annual environmental influence on genetic variation in five years of yielding. Components of variance were estimated from these analyses in an attempt to quantify genotype x environment interactions. The results of the analysis of

Avaliação genética de touros usando produção em lactações completas ou parciais projetadas: 3. Confiabilidade e ganhos genéticos

Directory of Open Access Journals (Sweden)

Melo Cláudio Manoel Rodrigues de

2000-01-01

Full Text Available Para estudar a viabilidade de se usarem produções em lactações parciais, projetadas, na avaliação do mérito genético de touros, foram utilizadas 4595 lactações de 2254 vacas, filhas de 145 touros de 1618 matrizes, distribuídas em 18 rebanhos, com partos entre 1980 e 1997. A partir de 91, 151, 211 ou 241 dias de lactação, projetaram-se 10, 30, 50 ou 70% das lactações, para a duração da lactação observada e para 305 dias. As estimativas dos parâmetros genéticos foram obtidas pelo sistema MTDFREML. Incluíram-se no modelo, independente da característica, efeitos fixos de rebanho-ano, época de parto e idade da vaca ao parto, com termos linear e quadrático, considerando-se efeitos aleatórios de animal, efeito permanente de ambiente e erro. A média das confiabilidades, obtida por meio das produções estimadas (PE, variou de 0,60 a 0,67, utilizando-se P305 igual a 0,60. O ganho genético anual pela seleção dos touros utilizando as PE foi, em média, 24,27% maior que o ganho genético anual da P305, quando as lactações foram projetadas para a duração da lactação observada, e 25,65% superior, quando as lactações foram projetadas para P305. As confiabilidades obtidas, bem como os ganhos genéticos anuais estimados nas avaliações genéticas, usando as PE, foram semelhantes àquelas obtidas para a produção de leite até 305 dias.

Prevalencia de bacterias Gram negativas portadoras del gen blaKPC en hospitales de Colombia

Directory of Open Access Journals (Sweden)

Robinson Pacheco

2014-04-01

Full Text Available Introducción. Las enzimas carbapenemasas de tipo KPC tienen gran capacidad de diseminación, son causantes de epidemias y se asocian a mayor mortalidad y estancia hospitalaria. En Colombia se han venido reportando cada vez más desde 2007, pero se desconoce la prevalencia hospitalaria. Objetivo. Estimar la prevalencia hospitalaria del gen blaKPC. Materiales y métodos. Se evaluó la presencia del gen blaKPC y su ‘clonalidad’ en aislamientos de enterobacterias y Pseudomonas aeruginosa de pacientes hospitalizados. Resultados. De los 424 aislamientos evaluados durante el periodo de estudio, 273 cumplieron con criterios de elegibilidad, 31,1 % fue positivo para el gen blaKPC y, al ajustar por ‘clonalidad’, la positividad fue de 12,8 %. El gen blaKPC se encontró con mayor frecuencia en Klebsiella pneumoniae seguido de P. aeruginosa y otras enterobacterias. A pesar de que la unidad de cuidados intensivos aportó el mayor número de aislamientos, no se encontró un patrón más prevalente del gen blaKPC en las ellas que en las otras salas. El aparato respiratorio fue el sitio anatómico de origen con la mayor prevalencia. No se presentó estacionalidad en la frecuencia de los aislamientos portadores del gen blaKPC. Conclusión. Este estudio reveló la alta prevalencia del gen blaKPC en diferentes microorganismos aislados en varias instituciones hospitalarias del país. La extraordinaria capacidad de propagación del gen blaKPC, las dificultades del diagnóstico y la limitada disponibilidad de antibióticos plantean la apremiante necesidad de fortalecer los sistemas de vigilancia epidemiológica y ajustar oportunamente las políticas institucionales de uso racional de antibióticos con el fin de contener su diseminación a otras instituciones de salud del país.

Contribuciones de Sir Roland Fisher a la Estadística Genética

Directory of Open Access Journals (Sweden)

Jaime Cuadros

2004-11-01

Full Text Available Sir Ronald Fisher (18901962 fue profesor de genética y muchas de sus innovaciones estadísticas encontraron expresión en el desarrollo de metodología en estadística genética. Sin embargo, mientras sus contribuciones en estadística matemática son fácilmente identificadas, en genética de poblaciones compartió su supremacía con Sewall Wright (1889 1988 y J. S. S. Haldane (1892 1965. Este documento muestra algunas de las mejores contribuciones de Fisher a las bases de la estadística genética, y sus interacciones con Wright y Haldane, los cuales contribuyeron al desarrollo del tema. Con la tecnología moderna, tanto la metodología la estadística como la información genética están cambiando. No obstante, muchos de los trabajos de Fisher permanecen relevantes, y pueden aun servir como una base para investigaciones futuras en el análisis estadístico de datos de DNA. El trabajo de este autor refleja su visión del papel de Ia estadística en Ia inferencia científica expresada en 1949

Concept research on general passive system

International Nuclear Information System (INIS)

Han Xu; Yang Yanhua; Zheng Mingguang

2009-01-01

This paper summarized the current passive techniques used in nuclear power plants. Through classification and analysis, the functional characteristics and inherent identification of passive systems were elucidated. By improving and extending the concept of passive system, the general passive concept was proposed, and space and time relativity was discussed and assumption of general passive system were illustrated. The function of idealized general passive system is equivalent with the current passive system, but the design of idealized general passive system is more flexible. (authors)

Study on Instrument Fault Detection using OLM Techniques for PHM Application in NPPs

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Hwan; Park, Gee Yong; Kim, Jung Taek; Hur, Seop [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

The diagnosis system is relatively being mature owing to many research. Among the various models, this paper introduces some On-Line Monitoring (OLM) models for instrument health monitoring and review applicability on NPPs. In recent years, many researchers are being focused on the prognostics which is predicting the future failure of instruments or equipment by using the status monitoring data. By using the prognostic techniques, we can expect a lot of advantages such as ease of control, power optimization, or optimal use of maintenance resources. And we have performed the test for detecting fault of safety-critical instruments and analyzed the fault detection sensitivity for various instrument failure modes using OLM techniques. OLM techniques using data-driven based model such AAKR or AANN can be useful tools for securing integrity of safety-critical instrument that should always keep healthy conditions for the plant safety.

Caracterização e estimativa da variabilidade genética de genótipos de cebola Characterization and estimation of genetic variability of onion genotypes

Directory of Open Access Journals (Sweden)

Gerson Henrique Wamser

2012-06-01

Full Text Available Este trabalho teve como objetivo caracterizar genótipos de cebola cultivados em Santa Catarina e estimar a variabilidade genética existente entre os mesmos. Para isto foram avaliados quinze genótipos de cebola em dois ambientes, Ituporanga e Lages. O delineamento utilizado foi de blocos casualizados, com três repetições em cada ambiente. Foram avaliados o comprimento do pseudocaule; número de folhas por pseudocaule; diâmetro do pseudocaule; diâmetro do bulbo; altura do bulbo; peso do bulbo; relação altura:diâmetro do bulbo; produção total de bulbos; formato do bulbo; porcentagem de florescimento e porcentagem de bulbos podres. Os dados foram submetidos à análise de variância multivariada. Houve efeito significativo para a interação genótipos x ambientes, fato que causou diferenças nos valores de dissimilaridade em cada local. Foi elaborada uma matriz de dissimilaridade utilizando a distância de Mahalanobis. Os caracteres morfológicos e agronômicos utilizados foram suficientes para caracterizar os genótipos, indicando que os programas de melhoramento dispõem de uma ampla base genética para o desenvolvimento de novas cultivares.This study aimed to characterize onion genotypes grown in Santa Catarina state, Brazil and to estimate their genetic variability. Fifteen onion genotypes were evaluated in two locations, Ituporanga and Lages. The experimental design was of randomized blocks with three replications in each environment. We evaluated the length of the pseudostem, number of leaves per pseudostem, stem diameter, bulb diameter, height of the bulb, bulb weight, height:diameter ratio; total production of bulbs, bulb shape, flowering percentage and percentage of rotten bulbs. The data were subjected to multivariate analysis of variance. The results showed significant effects for genotype-environment interaction, fact that was reflected in the values of dissimilarity in each location. A matrix of dissimilarity was prepared

GeoBoost: accelerating research involving the geospatial metadata of virus GenBank records.

Science.gov (United States)

Tahsin, Tasnia; Weissenbacher, Davy; O'Connor, Karen; Magge, Arjun; Scotch, Matthew; Gonzalez-Hernandez, Graciela

2018-05-01

GeoBoost is a command-line software package developed to address sparse or incomplete metadata in GenBank sequence records that relate to the location of the infected host (LOIH) of viruses. Given a set of GenBank accession numbers corresponding to virus GenBank records, GeoBoost extracts, integrates and normalizes geographic information reflecting the LOIH of the viruses using integrated information from GenBank metadata and related full-text publications. In addition, to facilitate probabilistic geospatial modeling, GeoBoost assigns probability scores for each possible LOIH. Binaries and resources required for running GeoBoost are packed into a single zipped file and freely available for download at https://tinyurl.com/geoboost. A video tutorial is included to help users quickly and easily install and run the software. The software is implemented in Java 1.8, and supported on MS Windows and Linux platforms. gragon@upenn.edu. Supplementary data are available at Bioinformatics online.

Surface Passivation in Empirical Tight Binding

OpenAIRE

He, Yu; Tan, Yaohua; Jiang, Zhengping; Povolotskyi, Michael; Klimeck, Gerhard; Kubis, Tillmann

2015-01-01

Empirical Tight Binding (TB) methods are widely used in atomistic device simulations. Existing TB methods to passivate dangling bonds fall into two categories: 1) Method that explicitly includes passivation atoms is limited to passivation with atoms and small molecules only. 2) Method that implicitly incorporates passivation does not distinguish passivation atom types. This work introduces an implicit passivation method that is applicable to any passivation scenario with appropriate parameter...

The Development of the Genital Psoriasis Sexual Frequency Questionnaire (GenPs-SFQ) to Assess the Impact of Genital Psoriasis on Sexual Health.

Science.gov (United States)

Gottlieb, Alice B; Kirby, Brian; Ryan, Caitriona; Naegeli, April N; Burge, Russel; Potts Bleakman, Alison; Anatchkova, Milena D; Cather, Jennifer

2018-03-01

Patient-reported outcome measures (PROs) exist for psoriasis but not genital psoriasis (GenPs). This cross-sectional, qualitative study in patients with moderate-to-severe GenPs was conducted to support development of a PRO for measuring the impact of GenPs on sexual activity and to establish content validity. The impacts of GenPs were identified in a literature review. Findings from the literature review were discussed with clinicians, and then patients with GenPs were interviewed. From the literature review, 52 articles, 44 abstracts, and 41 clinical trials met predefined search criteria. Of these, 11 concepts emerged as having theoretical support for use as measurable impacts of psoriasis symptoms on patients; these concepts included sexual functioning and general health-related quality of life (HRQoL). These concepts were confirmed and expanded upon by two clinicians who routinely care for patients with GenPs. Interviews were then conducted with GenPs patients (n = 20) to discuss the impact of GenPs on their HRQoL. Eighty percent of patients reported that GenPs impacted sexual frequency. The two-item GenPs Sexual Frequency Questionnaire (GenPs-SFQ) was developed to assess limitations on sexual activity frequency because of GenPs. Cognitive debriefing with an additional 50 patients with GenPs confirmed the utility and understandability of the GenPs-SFQ. The GenPs-SFQ may have utility in clinical trials involving GenPs patients and in routine clinical practice. Eli Lilly and Company. Plain language summary available for this article.

Discusión: Explicaciones genéticas y psicológicas de la esquizofrenia. Bases genéticas de la esquizofrenia: "Nurture vrs Nature

Directory of Open Access Journals (Sweden)

Henriette Raventós-Vorst

2003-01-01

Full Text Available El presente artículo revisa la evidencia científica que muestra la heredabilidad de la esquizofrenia, su forma de herencia compleja y la posible heterogeneidad genética y ambiental. Se presentan las regiones cromosómicas que han sido ligadas a la enfermedad y algunos de los genes candidatos. El objetivo es presentar los resultados más importantes en el campo de la investigación genética de la enfermedad. Aunque se acepta que factores ambientales deben estar presentes en la etiopatogenia de la enfermedad, no se profundiza en ellos. Finalmente, se comenta el modelo lamarquiano sugerido por el Prof.. Bolaños. El fin es transmitir que en la actualidad no hay contradicción entre el modelo biologista o psicológico que explicaban esta enfermedad. La concepción moderna une ambos modelos: se considera una enfermedad del neurodesarrollo en la que participan factores genéticos, factores epigenéticos y noxas ambientales, incluyendo los factores psicosociales.

SALOME PLATFORM and TetGen for Polyhedral Mesh Generation

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang Yong; Park, Chan Eok; Kim, Shin Whan [KEPCO E and C Company, Inc., Daejeon (Korea, Republic of)

2014-05-15

SPACE and CUPID use the unstructured mesh and they also require reliable mesh generation system. The combination of CAD system and mesh generation system is necessary to cope with a large number of cells and the complex fluid system with structural materials inside. In the past, a CAD system Pro/Engineer and mesh generator Pointwise were evaluated for this application. But, the cost of those commercial CAD and mesh generator is sometimes a great burden. Therefore, efforts have been made to set up a mesh generation system with open source programs. The evaluation of the TetGen has been made in focusing the application for the polyhedral mesh generation. In this paper, SALOME will be evaluated for the efforts in conjunction with TetGen. In section 2, review will be made on the CAD and mesh generation capability of SALOME. SALOME and TetGen codes are being integrated to construct robust polyhedral mesh generator. Edge removal on the flat surface and vertex reattachment to the solid are two challenging tasks. It is worthwhile to point out that the Python script capability of the SALOME should be fully utilized for the future investigation.

Genes and proteins of Escherichia coli K-12 (GenProtEC).

Science.gov (United States)

Riley, M

1997-01-01

GenProtEC is a database of Escherichia coli genes and their gene products, classified by type of function and physiological role and with citations to the literature for each. Also present are data on sequence similarities amongE.coliproteins with PAM values, percent identity of amino acids, length of alignment and percent aligned. GenProtEC can also be accessed through the World Wide Web at URL http://mbl.edu/html/ecoli.html .

Passive Education

Science.gov (United States)

Bojesen, Emile

2018-01-01

This paper does not present an advocacy of a passive education as opposed to an active education nor does it propose that passive education is in any way 'better' or more important than active education. Through readings of Maurice Blanchot, Jacques Derrida and B.S. Johnson, and gentle critiques of Jacques Rancière and John Dewey, passive…

Perspective decisions of WWER nuclear fuel: Implementation at Russian NPPs

International Nuclear Information System (INIS)

Molchanov, V.

2003-01-01

The scientific and technical policy pursued by JSC TVEL has managed to create a new generation of fuel assembly design on the basis of solutions tested at various units of Russian NPPs - Kola NPP, Kalinin NPP, Unit 1, Balakovo NPP Unit 1. The requirements set for the new generation nuclear fuel for WWER are: 1) High fuel burnup - up to 70 MWxdays/kgU; 2) Extended operation cycle - up to 6 years; 3) Increase of uranium charge to the core; 4) Increased lateral stability - bow not more than 7 mm; 5) High level of operating reliability - fuel rod leakage not worse than 10-5 1/year; 6) Demountable fuel assembly design. Post-irradiation examination results of fuel assemblies discharged from WWER-1000 reactors demonstrate that fuel rods have substantial reserve in general characteristics including that of dealing with planned burnup. In order to meet the requirements, trials are started for: implementation of rigid skeleton (WWER-1000); fuel column length extension (WWER-1000 and WWER-440); increase of UO 2 charge (WWER-1000 and WWER-440); enhancing of operational reliability and demountable design. It is concluded that the Russian nuclear fuel for WWER-type reactors is competitive and enables the implementation of state-of-the-art cost effective fuel cycles

Enhanced Understanding of High Energy Arcing Fault Phenomena in NPPs

Energy Technology Data Exchange (ETDEWEB)

Park, Jong Seuk; Kim, Me Kyoung; Lee, Sang Kyu [KINS, Daejeon (Korea, Republic of)

2016-05-15

This study reviews the recent HEAF events in nuclear power plants (NPPs) and investigates the HEAF phenomena with the experiment data performed at KEMA supported by OECD/NEA HEAF project. High Energy Arcing Fault (HEAF) can occur in an electrical components or systems through an arc path to ground and has the potential to cause extensive damage to the equipment involved. The intense radiant heat produced by the arc can cause significant damage or even destructions of equipment and can injure people. Affected components include a specific high-energy electrical devices, such as switch gears, load centers, bus bars/ducts, transformers, cables, etc., operating mainly on voltage levels of more than 380V but the voltage levels in NUREG/CR-6580 is more than 440. As stated before, HEAF may cause the significant damage to adjacent facilities as well as the equipment involved. Quantitative estimation of the equipment damage, determining the damage area, and predicting the secondary fire after initiating HEAF event should be further studied in depth. Draft test report produced by KEMA does not give comprehensive understanding of the HEAF phenomena. It is expected that a detail information of slug calorimeter and the test data to show the HEAF characteristics will be given in the final test reports.

Variabilidad genética de la respuesta inflamatoria: I. Polimorfismo -511 C/T en el gen IL1β en diferentes subpoblaciones peruanas

Directory of Open Access Journals (Sweden)

Óscar Acosta

2012-07-01

Full Text Available El polimorfismo -511 citosina/timina (-511 C/T en la región promotora del gen interleuquina 1 beta (IL1β estα implicado en la producciσn diferencial de la citoquina y por tanto puede estar asociado a la respuesta inmuno-inflamatoria en obesidad, dislipidemias, cardiopatías, cáncer, infecciones, y el tratamiento con nutrientes y fármacos. Objetivos: Establecer la distribución de frecuencias de los genotipos y alelos del polimorfismo -511 C/T del gen IL1β en diferentes subpoblaciones peruanas. Diseño: Estudio descriptivo, observacional, transversal. Instituciones: Centro de Investigación de Bioquímica y Nutrición e Instituto de Medicina Tropical D.A. Carrión, Facultad de Medicina, UNMSM y Centro de Genética y Biología Molecular, Facultad de Medicina, USMP, Lima, Perú. Participantes: Pobladores peruanos. Intervenciones: Extracción de ADN genómico a partir de muestras sanguíneas o epitelio bucal según metodología estándar, de 168 individuos de 9 grupos subpoblacionales: 23 mestizos de Lima, 33 amazónicos (20 de Pucallpa y 13 de Amazonas y 112 andinos (12 de Ancash, 10 de Cajamarca, 18 de Huarochirí-Lima, 25 de Puno-Taquile, 25 de Puno-Uros y 22 de Puno-Anapia. Análisis del polimorfismo -511 C/T mediante la técnica de PCR/RFLP, con primers específicos y digestión con la enzima de restricción AvaI, detectándose los fragmentos por electroforesis en geles de agarosa al 2% y tinción con bromuro de etidio. Principales medidas de resultados: Frecuencias genotípicas y alélicas del gen IL1β. Resultados: Se encontró las siguientes frecuencias genotípicas CC=0,024; CT=0,369 y TT=0,607, consistentes con el equilibrio de Hardy-Weinberg; y las frecuencias alélicas fueron alelo C=0,208 y aleloT= 0,792. La frecuencia del alelo T, considerado el mutante, fue muy alta en los Uros de Puno (0.940 y más baja en los mestizos de Lima (0.609. La comparación de las frecuencias genotípicas (TT versus CT+CC y alélicas (T versus C

Improvement of Steam Generator Reliability for GEN-IV SFR

Energy Technology Data Exchange (ETDEWEB)

Kim, Seong O; Kim Se Yun; Kim, Seok Hoon; Eoh, Jae Hyuk; Lee, Hyeong Yeon; Choi, Byung Seon

2005-11-15

The R and D items performed in this study were selected from the R and D task of ' Reliability improvement of Steam Generator' of GEN-IV SFR Component Design and BOP. Since this project deals with one of the most important issues for a GEN-IV SFR system, it needs to enhance the domestic technical backgrounds associated with the corresponding R and D items even for a very short period by 2005. This study provides the R and D results for i) Development of assessment methodology for dissimilar metal weld and ii) Development of multi-dimensional simulation methodology for a SWR event in a SFR steam generator.

Improvement of Steam Generator Reliability for GEN-IV SFR

International Nuclear Information System (INIS)

Kim, Seong O; Kim Se Yun; Kim, Seok Hoon; Eoh, Jae Hyuk; Lee, Hyeong Yeon; Choi, Byung Seon

2005-11-01

The R and D items performed in this study were selected from the R and D task of ' Reliability improvement of Steam Generator' of GEN-IV SFR Component Design and BOP. Since this project deals with one of the most important issues for a GEN-IV SFR system, it needs to enhance the domestic technical backgrounds associated with the corresponding R and D items even for a very short period by 2005. This study provides the R and D results for i) Development of assessment methodology for dissimilar metal weld and ii) Development of multi-dimensional simulation methodology for a SWR event in a SFR steam generator

Hydrogenation of passivated contacts

Energy Technology Data Exchange (ETDEWEB)

Nemeth, William; Yuan, Hao-Chih; LaSalvia, Vincenzo; Stradins, Pauls; Page, Matthew R.

2018-03-06

Methods of hydrogenation of passivated contacts using materials having hydrogen impurities are provided. An example method includes applying, to a passivated contact, a layer of a material, the material containing hydrogen impurities. The method further includes subsequently annealing the material and subsequently removing the material from the passivated contact.

Epidemiologia genética: epidemiologia, genética ou nenhuma das anteriores?

Directory of Open Access Journals (Sweden)

Aguinaldo Gonçalves

1990-12-01

Full Text Available No esforço de contribuir para melhor entendimento da identidade da Epidemiologia Genética, são revistas sua concepção, campo de atuação, métodos e técnicas pertinentes e algumas instâncias de aplicação. Entendendo-a como a área de interesse dos fatores genéticos das doenças e suas interações ambientais, apresenta-se seu campo de atuação como constituído por dois segmentos: um descritivo, que lida com conhecimento da distribuição de tais afecções em famílias e populações, seu impacto a nível do coletivo e sua vigilância epidemiológica, bem como o estudo de seus determinantes; o segundo, caracterizado pela intervenção, refere-se às respectivas medidas preventivas. Em que pese possível limitação pela não-consideração de todas as situações existentes, particular atenção é destinada à revisão de métodos e técnicas que possam ser convergentemente aplicados, a partir de procedimentos genéticos e epidemiológicos. Entre eles, destacam-se como estudos de casos tanto metodologias laboratoriais (como os dermatóglifos quanto quantitativos, como cálculo de herdabilidade e análise multivariada. Alguns objetos de estudo são tomados como instância de aplicação, por contarem com investigações específicas em nosso meio: a hanseníase, o hidrargirismo e a esquizofrenia.In an attempt to contribute to a better undestanding of the identity of Genetic Epidemiology, we review its conception, its field of influence, its appropriate methods and techniques and, at last, some of its applications. Genetic Epidemiology involves the study of genetic factors acting on diseases and on their environmental interactions. These includes two major areas: a descriptive one, related to the distribution of such conditions in families and populations, to the epidemiologic surveillance and to the study of determinants; and another characterized by intervention, which is related to preventive measures. Because of the dificulty in

Variabilidad genética en Prosopis ferox (Mimosaceae

Directory of Open Access Journals (Sweden)

Alicia D. Burghardt

2004-01-01

Full Text Available Prosopis ferox (Mimosaceae es una especie arbustiva o arbórea espinosa que se distribuye desde el Sur de Bolivia hasta el noroeste de la Argentina. En la provincia de Jujuy se encuentra a grandes alturas (entre los 2400 y los 3700 m s.m.. Existe una gran variabilidad morfológica, especialmente en cuanto a las dimensiones del fruto y la cantidad de semillas por fruto, ambas características importantes debido al uso de esta planta como forraje. Con el objeto de verificar si existe además variabilidad genética, se realizó un estudio electroforético de proteínas seminales de árboles procedentes de distintas localidades de la provincia de Jujuy. Los patrones polipeptídicos obtenidos por SDS-PAGE presentaron en total 26 bandas. Cada población se caracterizó por sus patrones de presencia-ausencia de bandas, habiéndose encontrado variabilidad intrapoblacional (polimorfismo en algunas de ellas, siendo otras genéticamente homogéneas. Los índices polimórficos en poblaciones de P. ferox son comparables a los obtenidos previamente en P. ruscifolia. La variabilidad genética interpoblacional hallada por medio del estudio electroforético de las proteínas seminales hace suponer la existencia de ecotipos

Use of FPGA to face electronic component obsolescence in software based safety I and C in NPPS

International Nuclear Information System (INIS)

Hadj, Abdellah; Bach, Julien; Esmenjaud, Claude; Daumas, Frederic; Salauen, Patrick

2010-01-01

In order to extend the life time of their Nuclear Power Plants (NPPs), most utilities are looking for ways to implement the renovation of their existing Instrumentation and Control (I and C) systems. When the I and C to modernize is software based, three paths can be considered: - to keep the legacy microprocessor and limit refurbishment to the associated hardware (i.e. the I/O boards, memories and the CPU board itself), - to move to another I and C platform based on another microprocessor, - to move to a non microprocessor based I and C platform. Software based I and C provide strong advantages such as flexibility and ability to implement advanced functions, however the complexity and the decreasing life time of nowadays microprocessors, mainly developed for the needs of the personal computer market, makes difficult their use and licensing for safety digital I and C systems. Solutions based on re-engineering of legacy microprocessors, or use of microprocessors dedicated to critical application need to be considered. In order to share a prospective vision of the future of I and C systems in NPPs, Electricite de France (EDF) Research and Development division and Rolls-Royce have launched a three year cooperation program on the use of the ASIC/FPGA technology in safety I and C systems. The first step of this program addresses the ability of the ASIC/FPGA technology to provide replacement solutions for former microprocessors taking as example the replacement of the Motorola MC6800 microprocessor. This paper presents the development of an IP cloning the Motorola MC6800 microprocessor, suitable for use in the refurbishment of safety I and C equipment based on this microprocessor. (authors)

Nitrato-complexes of Y(III), La(III), Ce(III), Pr(III), Nd(III), Sm(III), Gd(III), Tb(III), Dy(III) and Ho(III) with 2-(2'-pyridyl) benzimidazole

Energy Technology Data Exchange (ETDEWEB)

Mishra, A; Singh, M P; Singh, V K

1982-05-01

The nitrato-complexes, (Y(PyBzH)/sub 2/(NO/sub 3/)/sub 2/)NO/sub 3/.H/sub 2/O and Nd, Sm, Gd, Tb, Dy, Ho ; n=1-3, m=0-0.5 ; PyBzh=2-(2 -pyridyl)benzimidazole) are formed on interaction of the ligand with metal nitrates in ethanol. The electrical conductance values (116-129 ohm/sup -1/cm/sup 2/mol/sup -1/) suggest 1:1 electrolyte-nature of the complexes. Magnetic moment values of Ce(2.53 B.M.), Pr(3.62 B.M.), Nd(3.52 B.M.), Sm(1.70 B.M.), Gd(8.06 B.M.), Tb(9.44 B.M.), Dy(10.56 B.M.) and Ho(10.51 B.M.) in the complexes confirm the positive state of the metals. Infrared evidences are obtained for the existance of both coordinated (C/sub 2/v) and uncoordinated (D/sub 3/h) nitrate groups. Electronic absorption spectra of Pr(III)-, Nd(III)-, Sm(III)-, Tb(III)-, Dy(III)- and Ho(III)-complexes have been analysed in the light of LSJ terms.

Nitrato-complexes of Y(III), La(III), Ce(III), Pr(III), Nd(III), Sm(III), Gd(III), Tb(III), Dy(III) and Ho(III) with 2-(2'-pyridyl) benzimidazole

International Nuclear Information System (INIS)

Mishra, A.; Singh, M.P.; Singh, V.K.

1982-01-01

The nitrato-complexes, [Y(PyBzH) 2 (NO 3 ) 2 ]NO 3 .H 2 O and Nd, Sm, Gd, Tb, Dy, Ho ; n=1-3, m=0-0.5 ; PyBzh=2-(2 -pyridyl)benzimidazole] are formed on interaction of the ligand with metal nitrates in ethanol. The electrical conductance values (116-129 ohm -1 cm 2 mol -1 ) suggest 1:1 electrolyte-nature of the complexes. Magnetic moment values of Ce(2.53 B.M.), Pr(3.62 B.M.), Nd(3.52 B.M.), Sm(1.70 B.M.), Gd(8.06 B.M.), Tb(9.44 B.M.), Dy(10.56 B.M.) and Ho(10.51 B.M.) in the complexes confirm the terpositive state of the metals. Infrared evidences are obtained for the existance of both coordinated (C 2 v) and uncoordinated (D 3 h) nitrate groups. Electronic absorption spectra of Pr(III)-, Nd(III)-, Sm(III)-, Tb(III)-, Dy(III)- and Ho(III)-complexes have been analysed in the light of LSJ terms. (author)

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

International Nuclear Information System (INIS)

Lee, Seungmin; Seong, Poonghyun; Kim, Jonghyun

2013-01-01

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

III-V-on-silicon solar cells reaching 33% photoconversion efficiency in two-terminal configuration

Science.gov (United States)

Cariou, Romain; Benick, Jan; Feldmann, Frank; Höhn, Oliver; Hauser, Hubert; Beutel, Paul; Razek, Nasser; Wimplinger, Markus; Bläsi, Benedikt; Lackner, David; Hermle, Martin; Siefer, Gerald; Glunz, Stefan W.; Bett, Andreas W.; Dimroth, Frank

2018-04-01

Silicon dominates the photovoltaic industry but the conversion efficiency of silicon single-junction solar cells is intrinsically constrained to 29.4%, and practically limited to around 27%. It is possible to overcome this limit by combining silicon with high-bandgap materials, such as III-V semiconductors, in a multi-junction device. Significant challenges associated with this material combination have hindered the development of highly efficient III-V/Si solar cells. Here, we demonstrate a III-V/Si cell reaching similar performances to standard III-V/Ge triple-junction solar cells. This device is fabricated using wafer bonding to permanently join a GaInP/GaAs top cell with a silicon bottom cell. The key issues of III-V/Si interface recombination and silicon's weak absorption are addressed using poly-silicon/SiOx passivating contacts and a novel rear-side diffraction grating for the silicon bottom cell. With these combined features, we demonstrate a two-terminal GaInP/GaAs//Si solar cell reaching a 1-sun AM1.5G conversion efficiency of 33.3%.

GenRGenS: Software for Generating Random Genomic Sequences and Structures

OpenAIRE

Ponty , Yann; Termier , Michel; Denise , Alain

2006-01-01

International audience; GenRGenS is a software tool dedicated to randomly generating genomic sequences and structures. It handles several classes of models useful for sequence analysis, such as Markov chains, hidden Markov models, weighted context-free grammars, regular expressions and PROSITE expressions. GenRGenS is the only program that can handle weighted context-free grammars, thus allowing the user to model and to generate structured objects (such as RNA secondary structures) of any giv...

Upgrading safety of NPPs with RBMK-1000 reactors by implementation of the first priority measures and activities

International Nuclear Information System (INIS)

1996-01-01

After the accident at the Chernobyl Unit 4 reactor, extensive debates were in place about the future of nuclear power industry, its safety and the role of nuclear power in human life. The major conclusion drawn from those discussions is that the energy demands and ecological problems could not be resolved without further development of nuclear industry. However, the continued development of nuclear power industry, first and foremost, should rest on a wide range of actions aimed at assuring the quality of design and construction of new NPPs, the quality of operation of the existing plants and by means of their backfitting. 1 ref., 3 figs, 1 tab

Frecuencia de algunas enfermedades genéticas en Neuropediatría

Directory of Open Access Journals (Sweden)

Tatiana Zaldívar Vaillant

2012-12-01

Full Text Available Introducción: las enfermedades neurológicas en Pediatría son diversas y obedecen a un gran número de causas: infecciosas, genéticas, metabólicas y degenerativas, entre otras. El diagnóstico genético, dentro del método clínico en Neurología, está relacionado con el diagnóstico etiológico. Existen muy pocas publicaciones que reflejen la frecuencia de las enfermedades neurogenéticas como grupo etiológico. Objetivo: describir la frecuencia de algunas enfermedades neuropediátricas en la Consulta de Neurogenética del Instituto de Neurología y Neurocirugía. Métodos: se realizó una investigación descriptiva y prospectiva en el periodo 2008-2010. Se clasificó a los pacientes por grupos etarios, y se calculó el porcentaje de frecuencia para la atrofia muscular espinal de la infancia, la distrofia muscular tipo Duchenne/Becker, las lesiones estáticas del sistema nervioso central de causa prenatal genética, y para la clasificación de los grupos según tipo de herencia. Resultados: el universo de estudio estuvo conformado por 161 pacientes, 72,6 % del sexo masculino, para una razón de la variable sexo de 2,5. Los escolares fueron mayoría (37,8 %, y la edad promedio 5 años. La distrofia muscular tipo Duchenne fue la enfermedad más frecuente (24,8 %. El 41,40 % clasificó en la herencia autosómica recesiva. Los resultados coinciden con lo reportado en la literatura. Conclusiones: las enfermedades neuromusculares hereditarias, y las lesiones estáticas del sistema nervioso central de causa prenatal genética, son las más frecuentes de solicitud de asesoramiento genético en un servicio de Neurogenética.

Passive safety; Passive Sicherheit

Energy Technology Data Exchange (ETDEWEB)

Rueckert, J. [Skoda Auto a.s., Mlada Boleslav (Czech Republic). Interieurentwicklung und Versuche; Hau, M. [Skoda Auto a.s., Mlada Boleslav (Czech Republic). Koordination der Fahrzeugsicherung

2004-05-01

The specifications for passive safety are partly based on the legal requirements for all export markets combined with the strict internal standards of Volkswagen Group. The Euro NCAP tests and their precisely defined testing methods using the new point assessment are very important. (orig.)

Active-passively mode-locked dye laser for diagnosis of laser-produced plasmas

International Nuclear Information System (INIS)

Teng, Y.L.; Fedosejevs, R.; Sigel, R.

1981-03-01

In this report an active-passively mode-locked, flashlamp-pumped dye laser for diagnosis of laser-produced plasmas is described. This dye laser system used as a pulsed light source for high-speed photography of laser-target experiments was synchronized to the ASTERIX III iodine laser pulse with better than 100 ps accuracy. The single pulse energy was 10 μJ, pulse duration less than 10 ps. In 111 shots clear shadowgrams were obtained during a total of 151 target shots, i.e. the system worked well in 74% of the shots. (orig.)

The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

International Nuclear Information System (INIS)

Demetri, K. J.; Leipner, C. I.; Marshall, M. L.

2015-09-01

The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

Energy Technology Data Exchange (ETDEWEB)

Demetri, K. J.; Leipner, C. I.; Marshall, M. L., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2015-09-15

The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

Passive House Solutions

Energy Technology Data Exchange (ETDEWEB)

Strom, I.; Joosten, L.; Boonstra, C. [DHV Sustainability Consultants, Eindhoiven (Netherlands)

2006-05-15

PEP stands for 'Promotion of European Passive Houses' and is a consortium of European partners, supported by the European Commission, Directorate General for Energy and Transport. In this working paper an overview is given of Passive House solutions. An inventory has been made of Passive House solutions for new build residences applied in each country. Based on this, the most common basic solutions have been identified and described in further detail, including the extent to which solutions are applied in common and best practice and expected barriers for the implementation in each country. An inventory per country is included in the appendix. The analysis of Passive House solutions in partner countries shows high priority with regard to the performance of the thermal envelope, such as high insulation of walls, roofs, floors and windows/ doors, thermal bridge-free construction and air tightness. Due to the required air tightness, special attention must be paid to indoor air quality through proper ventilation. Finally, efficient ((semi-)solar) heating systems for combined space and DHW heating still require a significant amount of attention in most partner countries. Other basic Passive House solutions show a smaller discrepancy with common practice and fewer barriers have been encountered in partner countries. In the next section, the general barriers in partner countries have been inventoried. For each type of barrier a suggested approach has been given. Most frequently encountered barriers in partner countries are: limited know-how; limited contractor skills; and acceptation of Passive Houses in the market. Based on the suggested approaches to overcoming barriers, this means that a great deal of attention must be paid to providing practical information and solutions to building professionals, providing practical training to installers and contractors and communication about the Passive House concept to the market.

Some aspects of nuclear fuel use at Ukrainian NPPs during last two years

International Nuclear Information System (INIS)

Bilodid, Y.; Shevchenko, I.; Ieremenko, M.; Ovdiienko, I.

2015-01-01

For many years SSTC NRS actively participates in licensing of fuel reloading and in the implementation of new nuclear fuel types at the nuclear power plants in Ukraine. Results of the nuclear fuel use for last years are presented in the paper. The results are based on NPP documentation submitted for licensing to the regulating body of Ukraine and based on our estimations and independent calculations. The first part of the paper contains a brief characteristic of the fuel cycles at Ukrainian NPPs. Types of loaded fuel are described also. Experience of new fuel type implementation is presented (Westinghouse FA and TVSA-12 for WWER-1000 reactors). The next part of the paper presents a new regulatory document under development and further new fuel implementation (WWER-1000 reactors). The last part of the paper describes some issues with fuel use. (authors) Keywords: WWER, TVSA, TVSA-12, TVS-W, TVS-WR, Westinghouse, NPP

StateGEN/StateNET - A structured method to perform route comparisons

International Nuclear Information System (INIS)

Cashwell, J.W.; Erickson, C.M.

1989-01-01

StateGEN/StateNET is a modeling structure and routing algorithm designed expressly to address the needs of state and local governments to perform analyses of routing alternatives. StateGEN/StateNET is designed to permit the user to construct a network and assign attributes of interest to the network on a personal computer (PC). The completed network is then transferred via a modem to the TRANSNET system and the preferred route is determined based upon attribute weights assigned by the user. This modeling structure permits the state or local government to perform a routing analysis, such as that required by the US Department of Transportation (DOT) for Highway Route-Controlled Quantity shipments of radioactive materials, with a minimum of resources. StateGEN/StateNET provides a computerized version of the DOT guidelines or allows the user to structure their own network parameters. Sandia National Laboratories (SNL) is the Department of Energy (DOE) lead organization for transportation research and development. The DOE Office of Defense Programs has been the prime sponsor of development of models and associated databases used to analyze the impacts of the transportation of radioactive materials. The routing algorithms used in StateGEN/StateNET were based on the existing models on TRANSNET, a system which was developed to enable outside users to access analytical codes and associated data developed for the DOE

StateGEN/StateNET--A structured method to perform route comparisons

International Nuclear Information System (INIS)

Cashwell, J.W.; Erickson, C.M.

1989-01-01

StateGEN/StateNET is a modelling structure and routing algorithm designed expressly to address the needs of state and local governments to perform analyses of routing alternatives. StateGEN/StateNET is designed to permit the user to construct a network and assign attributes of interest to the network on a personal computer (PC). The completed network is then transferred via a modem to the TRANSNET system (Cashwell, 1989) and the preferred route is determined based upon attribute weights assigned by the user. This modelling structure permits the state or local to perform a routing analysis, such as that required by the US Department of Transportation (DOT) for Highway Route-Controlled Quantity shipments of radioactive materials, with a minimum of resources. StateGEN/StateNET provides a computerized version of the DOT guidelines (Cashwell, 1989) or allows the user to structure their own network parameters. Sandia national Laboratories (SNL) is the Department of Energy's (DOE) lead organization for transportation research and development. The DOE Office of Defense Programs has been the prime sponsor of development of models and associated databases used to analyze the impacts of the transportation of radioactive materials. The routing algorithms used in StateGEN/StateNET were based on the existing models on TRANSNET, a system which was developed to enable outside users to access analytical codes and associated data developed for the DOE. 2 refs

Bohunice NPPs - Part of the Slovak's economy (sustainable) development

International Nuclear Information System (INIS)

Dobak, Dobroslav

2001-01-01

Of the total consumption of electricity in Slovakia, 42% was generated in nuclear power plant units in 1999. Slovakia operates 6 units with a WWER 440 nuclear reactors, 4 of them are at Bohunice site and 2 at Mochovce. The Nuclear Regulatory Authority of SR is not the only regulatory body controlling nuclear activity. Both - the system of nuclear activities regulation in Slovakia as well as the approach to Nuclear Safety enhancement of the operator were positively judged by IAEA and WENRA. In 1993 -Slovakia has accepted the commitments of the UN Convention on Climate Changes, including a reduction of greenhouse gases to 1990 levels by the year 2000. Moreover, as an internal target Slovakia has set the reaching of the ,'Toronto Objective', i.e. 20% reduction in CO x emissions through the year 2005 as compared to 1988. Taking into account the actual situation as well as natural conditions for some renewable sources utilisation, the target won't be reached without nuclear energy. The nuclear energy is free of emissions, does not burn oxygen, and with the share of production in Slovakia will remain significant contributor. To the environment protection it contributes also by replacing fossil heat plants with heat delivery for the region. In case of radiological wastes the environment protection is ensured by very strict system of control, evidence, treatment and repository. To conclude, Bohunice NPPs were, are and will remain very important part of the Slovak's economy, creating conditions for its (sustainable) development

THE USE OF PASSIVE SOLAR HEATING SYSTEMS AS PART OF THE PASSIVE HOUSE

Directory of Open Access Journals (Sweden)

Bryzgalin Vladislav Viktorovich

2018-05-01

Full Text Available Subject: systems of passive solar heating, which can, without the use of engineering equipment, capture and accumulate the solar heat used for heating buildings. Research objectives: study of the possibility to reach the passive house standard (buildings with near zero energy consumption for heating in climatic conditions of Russia using the systems of passive solar heating in combination with other solutions for reduction of energy costs of building developed in the past. Materials and methods: search and analysis of literature, containing descriptions of various passive solar heating systems, examples of their use in different climatic conditions and the resulting effect obtained from their use; analysis of thermophysical processes occurring in these systems. Results: we revealed the potential of using the solar heating systems in the climatic conditions of parts of the territories of the Russian Federation, identified the possibility of cheaper construction by the passive house standard with the use of these systems. Conclusions: more detailed analysis of thermophysical and other processes that take place in passive solar heating systems is required for creation of their computational models, which will allow us to more accurately predict their effectiveness and seek the most cost-effective design solutions, and include them in the list of means for achieving the passive house standard.

Ganho de seleção no melhoramento genético intrapopulacional do maracujazeiro-amarelo

Directory of Open Access Journals (Sweden)

Willian Krause

2012-01-01

Full Text Available O objetivo deste trabalho foi estimar o ganho de seleção associado a características agronômicas de importância no melhoramento intrapopulacional do maracujazeiro-amarelo. O experimento foi realizado em campo, no Município de Terra Nova do Norte, MT, com a avaliação de 111 famílias de irmãos completos (FIC e seis cultivares comerciais, utilizadas como testemunhas. Utilizou-se o delineamento de blocos ao acaso, com três repetições e quatro plantas por parcela. Foram avaliadas as seguintes características: produtividade, comprimento, diâmetro e peso médio dos frutos, percentagem e peso de polpa, espessura de casca e teor de sólidos solúveis. Para verificar a existência de variabilidade genética entre os genótipos, estimaram-se os parâmetros genéticos da população com base na média das famílias. Os 30 genótipos com o menor valor da soma de postos, de acordo com o índice de seleção de Mulamba & Mock, foram selecionados para estimar os ganhos genéticos. Observaram-se altos valores médios para as características e parâmetros genéticos avaliados nas 26 FIC e nas quatro testemunhas selecionadas. O uso do índice de seleção proporciona ganhos genéticos positivos em produtividade, percentagem e peso de polpa, comprimento, diâmetro e peso de frutos, e espessura de casca.

Coeficiente de repetibilidade e parâmetros genéticos em capim-elefante

Directory of Open Access Journals (Sweden)

Marcelo Cavalcante

2012-04-01

Full Text Available O objetivo deste trabalho foi determinar os coeficientes de repetibilidade de caracteres morfofisiológicos em genótipos de capim-elefante (Pennisetum spp., a partir de dados obtidos durante seis ciclos de avaliação. Foram estimados: número mínimo de medições e parâmetros genéticos. Utilizou-se o delineamento experimental de blocos ao acaso, em arranjo de parcelas subdivididas, com quatro níveis de N (controle, 30, 60 e 90 kg ha‑1 por corte e 16 genótipos de Pennisetum (11 híbridos interespecíficos e cinco cultivares. Os ciclos consistiram de avaliações em 2010 (21/4, 19/7 e 28/9 e 2011 (6/1, 7/4 e 3/8. Os coeficientes de repetibilidade foram de média‑alta magnitude para todas as variáveis, o que indica que houve regularidade entre as medidas repetidas. Para as variáveis massa de forragem, altura da planta, comprimento e largura da folha, diâmetro do colmo, clorose e índice de área foliar, três ciclos de avaliação são suficientes para obter R² de 90%, pela análise de componentes principais. Para o comprimento do entrenó, o mínimo de sete avaliações é necessário para predizer o valor real dos genótipos. Os parâmetros genéticos das variáveis massa de forragem, comprimento e largura da folha, diâmetro do colmo e clorose foliar são de alta magnitude, o que favorece a seleção de genótipos superiores de Pennisetum.

Teleport Generation 3 (Teleport Gen 3)

Science.gov (United States)

2016-03-01

for high- throughput multi-band and multimedia connectivity from deployed locations to DISN and DoD Information Network (DoDIN) information sources and...2016 Major Automated Information System Annual Report Teleport Generation 3 (Teleport Gen 3) Defense Acquisition Management Information Retrieval...Program Information 4 Responsible Office 4 References 4 Program Description 5 Business Case 6 Program Status 8 Schedule 9

Divergência entre genótipos de soja, cultivados em várzea irrigada

Directory of Open Access Journals (Sweden)

Elonha Rodrigues dos Santos

2011-12-01

Full Text Available A divergência genética é um dos mais importantes parâmetros avaliados por melhoristas de plantas, na fase inicial de um programa de melhoramento genético. Diante disso, objetivou-se com este trabalho avaliar, por meio de técnicas multivariadas, a divergência genética entre 48 genótipos de soja, cultivados em várzea irrigada no Estado do Tocantins, com o intuito de identificar as combinações mais promissoras para produzir recombinações superiores, tanto destinados a produção de óleo e farelo, como do grupo especial, destinados ao consumo humano. O experimento foi conduzido no município de Formoso do Araguaia, TO, em cultivo de várzea irrigada na entressafra de 2010. O delineamento experimental foi o de blocos ao acaso, com quatro repetições. Verificou-se variabilidade entre os genótipos testados. Os resultados dos métodos de agrupamento de Tocher, UPGMA e Variáveis Canônicas foram concordantes entre si e detectaram quatro grupos distintos. As seguintes hibridações são promissoras para produção de grãos de soja destinados a óleo e farelo: M-Soy 8766, M-Soy 9144, A 7002 e M-Soy 9056 com Amaralina e cruzamentos entre M-Soy 8766, M-Soy 9144 e Amaralina com BRSMG 790A, BRS 257, BRS 216 e BRS 213 e são indicados visando a genótipos de soja especiais para alimentação humana.

On the origin of the photocurrent of electrochemically passivated p-InP(100) photoelectrodes.

Science.gov (United States)

Goryachev, Andrey; Gao, Lu; van Veldhoven, René P J; Haverkort, Jos E M; Hofmann, Jan P; Hensen, Emiel J M

2018-05-15

III-V semiconductors such as InP are highly efficient light absorbers for photoelectrochemical (PEC) water splitting devices. Yet, their cathodic stability is limited due to photocorrosion and the measured photocurrents do not necessarily originate from H2 evolution only. We evaluated the PEC stability and activation of model p-InP(100) photocathodes upon photoelectrochemical passivation (i.e. repeated surface oxidation/reduction). The electrode was subjected to a sequence of linear potential scans with or without intermittent passivation steps (repeated passivation and continuous reduction, respectively). The evolution of H2 and PH3 gases was monitored by online electrochemical mass spectrometry (OLEMS) and the Faradaic efficiencies of these processes were determined. Repeated passivation led to an increase of the photocurrent in 0.5 M H2SO4, while continuous reduction did not affect the photocurrent of p-InP(100). Neither H2 nor PH3 formation increased to the same extent as the photocurrent during the repeated passivation treatment. Surface analysis of the spent electrodes revealed substantial roughening of the electrode surface by repeated passivation, while continuous reduction left the surface unaltered. On the other hand, photocathodic conditioning performed in 0.5 M HCl led to the expected correlation between photocurrent increase and H2 formation. Ultimately, the H2 evolution rates of the photoelectrodes in H2SO4 and HCl are comparable. The much higher photocurrent in H2SO4 is due to competing side-reactions. The results emphasize the need for a detailed evaluation of the Faradaic efficiencies of all the involved processes using a chemical-specific technique like OLEMS. Photo-OLEMS can be beneficial in the study of photoelectrochemical reactions enabling the instantaneous detection of small amounts of reaction by-products.

Passivation of electrically active centers by Hydrogen and Lithium in Semiconductors

CERN Multimedia

2002-01-01

The hyperfine technique of Perturbed Angular Correlation Spectroscopy (PAC) has proven to be excellently suited for the microscopic investigation of impurity complexes in semiconductors. But this method is seriously limited by the small number of chemically different isotopes which are suitable for PAC measurements and represent electrically active centers in semiconductors. This bottleneck can be widely overcome by the ISOLDE facility which provides a great variety of shortliving PAC isotopes. The probe atom $^{111m}$Cd, provided by ISOLDE opened the first successful access to PAC investigations of III-V compounds and enabled also the first PAC experiments on double acceptors in silicon and germamum. \\\\ \\\\ At the new ISOLDE facility our experiments were concentrated on the passivation of electrically active centres by hydrogen and lithium in Si, Ge and III-V compounds. Experiments on $^{111m}$Cd in Ge revealed the formation of two different acceptor hydrogen and two different acceptor lithium complexes respe...

Université de Genève | Séminaire de physique corpusculaire | 13 November

CERN Multimedia

2013-01-01

Dark Matter searches in IceCube, Dr Carlos De Los Heros, Uppsala University.   Wednesday 13 November 2013, 11:15 a.m. Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: The IceCube Neutrino Observatory at the South Pole is the world's largest neutrino telescope. It instruments a kilometer cube of ice with more than 5000 optical sensors that detect the Cherenkov light emitted by secondary particles produced in neutrino-nucleon interactions in the ice. Covering a wide range of neutrino energies, from 10s of GeVs to PeVs, its physics program is extremely rich. The talk will focus on dark matter searches. In many models, dark matter gravitationally concentrated at the center of the Sun or the galactic center can self-annihilate to standard model particles, producing a flux of neutrinos from the decays of the annihilation products. IceCube can look for such neutrino flux, and competitive limits on the dark matter-nucleon cross section and on the dark m...

Université de Genève | Séminaire de physique corpusculaire | 2 octobre

CERN Multimedia

2013-01-01

Dark Matter Indirect Detection: status circa 10/2013, Dr Marco Cirelli, Saclay.   Mercredi 2 octobre 2013, 11h15 Science III, Auditoire 1S081 Boulevard d’Yvoy, 1211 Genève 4 Abstract: Dark Matter constitutes more that 80% of the total amount of matter in the Universe, yet almost nothing is known about its nature. A powerful investigation technique is that of searching for the products of annihilations of Dark Matter particles in the galactic halo, on top of the ordinary cosmic rays. Recent data from satellite and balloon experiments have reported unexpected excesses in the measured fluxes of charged cosmic rays, which have been interpreted as a possible first direct evidence for Dark Matter. If this is the case, which DM models and candidates can explain these anomalies and what do they imply for future searches? What are the constraints from other measurements (such as those in gamma rays or neutrinos) and from cosmology? And what is in store for the near future in this fi...

Passive solar construction handbook

Energy Technology Data Exchange (ETDEWEB)

Levy, E.; Evans, D.; Gardstein, C.

1981-08-01

Many of the basic elements of passive solar design are reviewed. The unique design constraints presented in passive homes are introduced and many of the salient issues influencing design decisions are described briefly. Passive solar construction is described for each passive system type: direct gain, thermal storage wall, attached sunspace, thermal storage roof, and convective loop. For each system type, important design and construction issues are discussed and case studies illustrating designed and built examples of the system type are presented. Construction details are given and construction and thermal performance information is given for the materials used in collector components, storage components, and control components. Included are glazing materials, framing systems, caulking and sealants, concrete masonry, concrete, brick, shading, reflectors, and insulators. The Load Collector Ratio method for estimating passive system performance is appended, and other analysis methods are briefly summarized. (LEW)

Caracteres clínico-patológicos y perfil genético en el carcinoma colorrectal

Directory of Open Access Journals (Sweden)

Florencia Perazzo

2013-10-01

Full Text Available El cáncer colorrectal es el tercer cáncer más frecuente en hombres y el segundo más frecuente en mujeres, con una incidencia mundial aproximada de 1.2 millones de casos nuevos por año. Nuestro objetivo primario fue estudiar la relación existente entre las características clínico-histológicas en individuos con cáncer colorrectal y el estado mutacional de los codones 12 y 13 del gen KRAS (7 mutaciones validadas, con el fin de hallar un marcador histopatológico para los tumores mutados. El objetivo secundario fue determinar cuántos pacientes tenían mutaciones adicionales en los codones 15 y 61 del gen KRAS y 600 del gen BRAF que podrían modificar el fenotipo tumoral. Fueron seleccionados 60 individuos con cáncer colorrectal (30 wild-type y 30 con mutaciones validadas en los codones 12 y 13 del gen KRAS. Se amplificaron y secuenciaron del gen KRAS los exones 2 y 3, y del gen BRAF el exón 15. La información recolectada se examinó mediante un análisis descriptivo, análisis univariado y/o análisis multivariado, según correspondiese. En conclusión, no se encontró relación entre las características clínico-histológicas de los tumores de individuos con diagnóstico de cáncer colorrectal y el estado mutacional de los codones 12 y 13 del gen KRAS. No hallamos un marcador histopatológico para los tumores mutados. En pacientes con adenocarcinomas colorrectales avanzados y KRAS wild-type resulta de interés considerar el estudio del codón 600 del gen BRAF.

A Security Assessment Approach with Graded Importance Score of Security Controls and Asset Consequence for I and C Systems in Operating NPPs

Energy Technology Data Exchange (ETDEWEB)

Lee, Sooill; Kim, Yong Sik; Moon, Insun; Lee, Euijong [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

This paper introduces a security assessment approach with graded importance score of security controls and the asset consequence through an asset and risk analysis to manage the security levels in operating NPPs (Nuclear Power Plants). Whereas, those are being exposed to various types of new and existing cyber threats, vulnerabilities and risks which significantly increase the likelihood that those could be compromised. U.S. NRC(United States Nuclear Regulatory Commission) and KINAC(Korea Institute of Nuclear Nonproliferation And Control) request the cyber security plan by establishing the cyber security program through assessing and managing the potential for adverse effect on safety, security and emergency preparedness functions so as to provide high assurance that critical functions are properly protected from the cyber-attack. This paper shows the security assessment approach with graded importance score of security controls and the asset consequence. It could lead to manage the security levels consistent with the purpose of defense in- depth strategy based on regulatory rule as well as internal risk-based self-assessment. Also, this management of the security level may make effect of encouraging the installation of high ranked countermeasures in order to rapidly increase the security level. Proposed approach could be conducted for the pilot test on the model plants with each reactor type of operating NPPs.

A Security Assessment Approach with Graded Importance Score of Security Controls and Asset Consequence for I and C Systems in Operating NPPs

International Nuclear Information System (INIS)

Lee, Sooill; Kim, Yong Sik; Moon, Insun; Lee, Euijong

2016-01-01

This paper introduces a security assessment approach with graded importance score of security controls and the asset consequence through an asset and risk analysis to manage the security levels in operating NPPs (Nuclear Power Plants). Whereas, those are being exposed to various types of new and existing cyber threats, vulnerabilities and risks which significantly increase the likelihood that those could be compromised. U.S. NRC(United States Nuclear Regulatory Commission) and KINAC(Korea Institute of Nuclear Nonproliferation And Control) request the cyber security plan by establishing the cyber security program through assessing and managing the potential for adverse effect on safety, security and emergency preparedness functions so as to provide high assurance that critical functions are properly protected from the cyber-attack. This paper shows the security assessment approach with graded importance score of security controls and the asset consequence. It could lead to manage the security levels consistent with the purpose of defense in- depth strategy based on regulatory rule as well as internal risk-based self-assessment. Also, this management of the security level may make effect of encouraging the installation of high ranked countermeasures in order to rapidly increase the security level. Proposed approach could be conducted for the pilot test on the model plants with each reactor type of operating NPPs

Alimentos Transgénicos : Organismos Genéticamente Modificados (OGM)

OpenAIRE

Martín López, Jimena

2016-01-01

Los alimentos transgénicos son aquellos que proceden de un organismo modificado genéticamente. La introducción de este tipo de productos en nuestra dieta es un tema que genera controversia ya que en muchos casos no se conoce con exactitud los efectos que esta modificación puede tener en el ser humano. A lo largo de las páginas de este trabajo se explica la historia de la aparición de estos organismos gracias a procedimientos de ingeniería genética, en los que se modifican fragmentos de su ADN...

Surface-related reduction of photoluminescence in GaAs quantum wires and its recovery by new passivation

International Nuclear Information System (INIS)

Shiozaki, Nanako; Anantathanasarn, Sanguan; Sato, Taketomo; Hashizume, Tamotsu; Hasegawa, Hideki

2005-01-01

Etched GaAs quantum wires (QWRs) and selectively grown (SG) QWRs were fabricated, and dependence of their photoluminescence (PL) properties on QWR width (W) and QWR distance to surface (d) were investigated. PL intensity greatly reduced with reduction of W and d, due to non-radiative recombination through surface states. Surface passivation by growing a Si interface control layer (Si-ICL) on group III-terminated surfaces greatly improved PL properties

Reactor core and passive safety systems descriptions of a next generation pressure tube reactor - mechanical aspects

Energy Technology Data Exchange (ETDEWEB)

Yetisir, M.; Gaudet, M.; Rhodes, D.; Hamilton, H.; Pencer, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

Canada has been developing a channel-type supercritical water-cooled nuclear reactor concept, often called the Canadian SCWR. The objective of this reactor concept is to meet the technology goals of the Generation IV International Forum (GIF) for the next generation nuclear reactor development, which include enhanced safety features (inherent safe operation and deploying passive safety features), improved resource utilization, sustainable fuel cycle, and greater proliferation resistance than Generation III nuclear reactors. The Canadian SCWR core concept consists of a high-pressure inlet plenum, a separate low-pressure heavy water moderator contained in a calandria vessel, and 336 pressure tubes surrounded by the moderator. The reactor uses supercritical water as a coolant, and a direct steam power cycle to generate electricity. The reactor concept incorporates advanced safety features such as passive core cooling, long-term decay heat rejection to the environment and fuel melt prevention via passive moderator cooling. These features significantly reduce core damage frequency relative to existing nuclear reactors. This paper presents a description of the design concepts for the Canadian SCWR core, reactor building layout and the plant layout. Passive safety concepts are also described that address containment and core cooling following a loss-of coolant accident, as well as long term reactor heat removal at station blackout conditions. (author)

Age-Related Degradation of Nuclear Power Plant Structures and Components

International Nuclear Information System (INIS)

Braverman, J.; Chang, T.-Y.; Chokshi, N.; Hofmayer, C.; Morante, R.; Shteyngart, S.

1999-01-01

This paper summarizes and highlights the results of the initial phase of a research project on the assessment of aged and degraded structures and components important to the safe operation of nuclear power plants (NPPs). A review of age-related degradation of structures and passive components at NPPs was performed. Instances of age-related degradation have been collected and reviewed. Data were collected from plant generated documents such as Licensing Event Reports, NRC generic communications, NUREGs and industry reports. Applicable cases of degradation occurrences were reviewed and then entered into a computerized database. The results obtained from the review of degradation occurrences are summarized and discussed. Various trending analyses were performed to identify which structures and components are most affected, whether degradation occurrences are worsening, and what was the most common aging mechanisms. The paper also discusses potential aging issues and degradation-susceptible structures and passive components which would have the greatest impact on plant risk

Crescimento de genótipos de frangos tipo caipira

Directory of Open Access Journals (Sweden)

R. C. Veloso

2015-10-01

Full Text Available RESUMOObjetivou-se com este trabalho comparar o padrão de crescimento, mediante ajustes das respectivas curvas de crescimento por modelos não lineares, bem como estudar o desenvolvimento de cortes de carcaça em relação ao peso da carcaça em diferentes genótipos de frangos tipo caipira. Foram utilizados 840 pintos de um dia, machos, distribuídos em delineamento inteiramente ao acaso, dos seguintes genótipos da linhagem Redbro: Caboclo, Carijó, Colorpak, Gigante Negro, Pesadão Vermelho, Pescoço Pelado e Tricolor. As aves foram alojadas em 28 boxes, sendo 30 aves/boxe, em galpão de alvenaria com acesso a um piquete de 45m², com quatro repetições. O peso corporal individual dos frangos foi medido ao nascer, aos 14, 28, 42, 56, 70 e 84 dias de idade. Para a determinação das curvas de crescimento do peso corporal das aves, os dados coletados foram avaliados por meio dos modelos não lineares: Brody, Gompertz, Logístico, Richards e von Bertalanffy. Foi empregado o PROC NLIN do SAS, utilizando-se o método interativo de Gauss-Newton. Os critérios usados para escolha do modelo de melhor ajuste da curva de crescimento foram o coeficiente de determinação, o desvio padrão assintótico, o desvio médio absoluto dos resíduos e o índice assintótico. As análises para obtenção dos coeficientes alométricos foram realizadas por meio do PROC GLM do SAS para os genótipos Carijó, Colorpak, Pesadão Vermelho, Pescoço Pelado e Tricolor. Foram avaliados os pesos da carcaça, do peito, das coxas, das sobrecoxas, das pernas e das asas das aves abatidas aos 85 dias de idade. Apenas as equações propostas por Gompertz, von Bertalanffy e Logístico atingiram a convergência, e o modelo proposto por von Bertalanffy foi o mais adequado para descrever o crescimento dos genótipos de frangos caipiras. Todos os cortes avaliados apresentaram crescimento tardio em relação ao peso da carcaça em genótipos de frangos tipo caipira.

Innovative fission reactors for this century

International Nuclear Information System (INIS)

Minguez, E.

2007-01-01

It is well known that global trends indicate a rebirth of nuclear energy due to several items: the climate change and the use of energies that emits CO 2 , the cost and dependence of gas and oil, the new innovative reactors which are competitive, safer, and sustainable and can support the Kyoto Protocol. The Advanced Reactors have safer systems than those developed in the Generation II, which demonstrates that are sustainable for the present and nuclear industry has also developed new concepts for the future which also will be sustainable. Now the new power plants that have being constructed are classified in the Generation III. Several units of this technology are in operation in Japan and other countries of the Pacific. Europe is now constructing the first unit in Finland (Olkilouto) with European technology: the European Pressurized Reactor (EPR). France has announced the beginning of the construction of an EPR in Flamanville next year. In 2000, several countries with advanced nuclear technology established the Generation IV International Forum (GIF) to develop and demonstrate nuclear energy systems that offer advantages in the following areas: sustainability, economics, safety and reliability and proliferation resistance and physical protection. These new systems will be deployed commercially after 2030. Six innovative concepts are under research, and the aim is not only produce electricity, but also hydrogen using the operational conditions of several concepts. Developed countries with NPPs in operation have strategies for the future of the nuclear energy. For the short term is to extend the operation of the NPPs until 60 years, or alternatively construction of new units of Generation III, to substitute those closed for decommissioning, keeping the percentage of contribution to the electricity generated. Between the period 2030-50, the solution is to operate the new innovative systems of the Generation IV, which uses the passive concept, and in the second part

Surface Passivation in Empirical Tight Binding

Science.gov (United States)

He, Yu; Tan, Yaohua; Jiang, Zhengping; Povolotskyi, Michael; Klimeck, Gerhard; Kubis, Tillmann

2016-03-01

Empirical Tight Binding (TB) methods are widely used in atomistic device simulations. Existing TB methods to passivate dangling bonds fall into two categories: 1) Method that explicitly includes passivation atoms is limited to passivation with atoms and small molecules only. 2) Method that implicitly incorporates passivation does not distinguish passivation atom types. This work introduces an implicit passivation method that is applicable to any passivation scenario with appropriate parameters. This method is applied to a Si quantum well and a Si ultra-thin body transistor oxidized with SiO2 in several oxidation configurations. Comparison with ab-initio results and experiments verifies the presented method. Oxidation configurations that severely hamper the transistor performance are identified. It is also shown that the commonly used implicit H atom passivation overestimates the transistor performance.

Transformação genética em espécies florestais.

Directory of Open Access Journals (Sweden)

Claudia Studart-Guimarães

2010-08-01

Full Text Available A transformação genética, que compreende a introdução de genes exógenos de forma controlada no genoma de uma célula vegetal e posterior regeneração da planta transgênica, tem contribuído com os programas de melhoramento genético de plantas pela obtenção de genótipos com novas características de interesse. O melhoramento de espécies florestais é limitado por características intrínsecas a tais espécies, como a altura dos indivíduos e o ciclo longo de vida. A transformação genética constitui, portanto, uma alternativa para a obtenção de espécies florestais com características desejáveis em um menor espaço de tempo. Plantas transgênicas com resistência a determinadas pragas, com melhor qualidade de madeira, maior produção de biomassa, tolerância a herbicidas, entre outras características de interesse, já foram obtidas para diferentes espécies florestais de importância econômica como álamo, eucalipto e pinheiros em geral. Este trabalho mostra a importância da transformação genética, associada a outras técnicas biotecnológicas no melhoramento de espécies florestais, as técnicas de transformação mais utilizadas e as características que já foram introduzidas nessas espécies pela transformação.

Reporte de familias con neurofibromatosis y otras enfermedades genéticas

OpenAIRE

Orraca Castillo, Miladys; Licourt Otero, Deysi; Sánchez Álvarez de La Campa, Ana Isabel

2011-01-01

La neurofibromatosis tipo 1, es una enfermedad genética que primariamente afecta el desarrollo y crecimiento celular del sistema nervioso, clínicamente se caracteriza por máculas café con leche, neurofibromas, pecas en regiones no expuestas al sol, nódulos de Lisch, lesiones óseas y glioma óptico. En el presente trabajo se describen dos familias, en las cuales algunos individuos padecen esta enfermedad y otros miembros de la misma familia muestran una diferente enfermedad genética. La coexist...

Inventering av Suldalslågen. Produksjonspotensial for sjøvandrende laksefisk

OpenAIRE

Foldvik, Anders; Pettersen, Oskar

2017-01-01

Foldvik, A. & Pettersen, O. 2017. Inventering av Suldalslågen. Produksjonspotensial for sjøvandrende laksefisk. - NINA Kortrapport 75, 18 s. Reguleringen av Suldalslågen til kraftproduksjon har hatt negative effekter for habitat for laksefisk, blant annet i form av sedimentering og begroing av substratet. Disse prosessene har blitt forsøkt motvirket ved å ha en serie med spyleflommer på over 200 m3/s om høsten. På oppdrag fra Statkraft inverterte NINA oppvekst- og gyteforhold for laks i Su...

Passive-solar construction handbook

Energy Technology Data Exchange (ETDEWEB)

Levy, E.; Evans, D.; Gardstein, C.

1981-02-01

Many of the basic elements of passive solar design are reviewed. Passive solar construction is covered according to system type, each system type discussion including a general discussion of the important design and construction issues which apply to the particular system and case studies illustrating designed and built examples of the system type. The three basic types of passive solar systems discussed are direct gain, thermal storage wall, and attached sunspace. Thermal performance and construction information is presented for typical materials used in passive solar collector components, storage components, and control components. Appended are an overview of analysis methods and a technique for estimating performance. (LEW)

Passivity and passivity breakdown of 304L stainless steel in hot and concentrated nitric acid

International Nuclear Information System (INIS)

Gillard-Tcharkhtchi, Elsa

2014-01-01

The objective of this study is to characterize the oxidation behavior of 304L stainless steel (SS) in representative conditions of spent nuclear fuel reprocessing, i.e. in hot and concentrated nitric acid. In these conditions the SS electrochemical potential is in the passive domain and its corrosion rate is low. However when the media becomes more aggressive, the potential may be shifted towards the trans-passive domain characterized with a high corrosion rate. Passivity and passivity breakdown in the trans-passive domain are of a major interest for the industry. So as to characterize these phenomenons, this work was undertaken with the following representative conditions: a 304L SS from an industrial sheet was studied, the media was hot and concentrated HNO 3 , long term tests were performed. First, the surface of an immersed 304L SS was characterized with several complementary techniques from the micro to the nanometer scale. Then oxidation kinetics was studied in the passive and in the trans-passive domain. The oxidation behavior was studied thanks to weight loss determination and surface analysis. Finally, oxidation evolution as a function of the potential was studied from the passive to the trans-passive domain. In particular, this allowed us to obtain the anodic curve of 304L SS in hot and concentrated and to define precisely the 304L SS limits of in such conditions. (author) [fr

TrayGen: Arranging objects for exhibition and packaging

KAUST Repository

Yang, Yongliang; Huang, Qixing

2013-01-01

We present a framework, called TrayGen, to generate tray designs for the exhibition and packaging of a collection of objects. Based on principles from shape perception and visual merchandising, we abstract a number of design guidelines on how