Gen IV. Technical and economical aspects

International Nuclear Information System (INIS)

Kaluzny, Y.; Legee, F.

2010-01-01

In this presentation author deals with development of nuclear reactor type of Generation IV. He concluded that: - Nuclear energy is competitive with regards to the other generation sources; Its competitiveness also increases with CO 2 cost. Considering the nuclear cost breakdown of LWR reactors, it turns out that the uranium is currently not in the range of a threshold for FBR deployment; - The global balance of uranium supply and demand and also innovation required to fulfil GEN IV objectives would probably imply the emergence of fast reactor competitiveness after the turn of the mid-century; - We shall need fast reactors in the coming decade.

The status of proliferation resistance evaluation methodology development in GEN IV international forum

International Nuclear Information System (INIS)

Inoue, Naoko; Kawakubo, Yoko; Seya, Michio; Suzuki, Mitsutoshi; Kuno, Yusuke; Senzaki, Masao

2010-01-01

The Generation IV Nuclear Energy Systems International Forum (GIF) Proliferation Resistance and Physical Protection Working Group (PR and PP WG) was established in December 2002 in order to develop the PR and PP evaluation methodology for GEN IV nuclear energy systems. The methodology has been studied and established by international consensus. The PR and PP WG activities include development of the measures and metrics; establishment of the framework of PR and PP evaluation, the demonstration study using Example Sodium Fast Reactor (ESFR), which included the development of three evaluation approaches; the Case Study using ESFR and four kinds of threat scenarios; the joint study with GIF System Steering Committees (SSCs) of the six reactor design concepts; and the harmonization study with the IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). This paper reviews the status of GIF PR and PP studies and identifies the challenges and directions for applying the methodology to evaluate future nuclear energy systems in Japan. (author)

Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations [ANIMMA--2015-IO-98

Energy Technology Data Exchange (ETDEWEB)

Jammes, C.; Filliatre, P.; De Izarra, G. [CEA, DEN, DER, Instrumentation, Sensors and Dosimetry Laboratory, Cadarache, F-13108 Saint-Paul-lez-Durance, (France); Elter, Zs.; Pazsit, I. [Chalmers University of Technology, Department of Applied Physics, Division of Nuclear Engineering, SE-412 96 Goteborg, (Sweden); Verma, V.; Hellesen, C.; Jacobsson, S. [Division of Applied Nuclear Physics, Uppsala University, Box 516, SE-75120 Uppsala, (Sweden); Hamrita, H.; Bakkali, M. [CEA, DRT, LIST, Sensors and Electronic Architecture Laboratory, Saclay, F-91191 Gif Sur Yvette, (France); Chapoutier, N.; Scholer, A-C.; Verrier, D. [AREVA NP, 10 rue Juliette Recamier F-69456 Lyon, (France); Cantonnet, B.; Nappe, J-C. [PHONIS France S.A.S, Nuclear Instrumentation, Avenue Roger Roncier, B.P. 520, F-19106 Brive Cedex, (France); Molinie, P.; Dessante, P.; Hanna, R.; Kirkpatrick, M.; Odic, E. [Supelec, Department of Power and Energy System, F-91192 Gif Sur Yvette, (France); Jadot, F. [CEA, DEN, DER, ASTRID Project Group, Cadarache, F-13108 Saint-Paul-lez-Durance, (France)

2015-07-01

The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on high temperature fission chambers installed in the reactor vessel and capable of operating over a wide-range neutron flux. The definition of such a system is presented and the technological solutions are justified with the use of simulation and experimental results. (authors)

GEN IV reactors: Where we are, where we should go

International Nuclear Information System (INIS)

Locatelli, G.; Mancini, M.; Todeschini, N.

2012-01-01

GEN IV power plants represent the mid-long term option of the nuclear sector. International literature proposes many papers and reports dealing with these reactors, but there is an evident difference of type and shape of information making impossible each kind of detailed comparison. Moreover, authors are often strongly involved in some particular design; this creates many difficulties in their super-partes position. Therefore it is necessary to put order in the most relevant information to understand strengths and weaknesses of each design and derive an overview useful for technicians and policy makers. This paper presents the state-of the art for GEN IV nuclear reactors providing a comprehensive literature review of the different designs with a relate taxonomy. It presents the more relevant references, data, advantages, disadvantages and barriers to the adoptions. In order to promote an efficient and wide adoption of GEN IV reactors the paper provides the pre-conditions that must be accomplished, enabling factors promoting the implementation and barriers limiting the extent and intensity of its implementation. It concludes outlying the state of the art of the most important R and D areas and the future achievements that must be accomplished for a wide adoption of these technologies. (authors)

Multi-criteria methodology to design a sodium-cooled carbide-fueled Gen-IV reactor

International Nuclear Information System (INIS)

Stauff, N.

2011-01-01

Compared with earlier plant designs (Phenix, Super-Phenix, EFR), Gen IV Sodium-cooled Fast Reactor requires improved economics while meeting safety and non-proliferation criteria. Mixed Oxide (U-Pu)O 2 fuels are considered as the reference fuels due to their important and satisfactory feedback experience. However, innovative carbide (U-Pu)C fuels can be considered as serious competitors for a prospective SFR fleet since carbide-fueled SFRs can offer another type of optimization which might overtake on some aspects the oxide fuel technology. The goal of this thesis is to reveal the potentials of carbide by designing an optimum carbide-fueled SFR with competitive features and a naturally safe behavior during transients. For a French nuclear fleet, a 1500 MW(e) break-even core is considered. To do so, a multi-physic approach was developed taking into account neutronics, fuel thermo-mechanics and thermal-hydraulic at a pre-design stage. Simplified modeling with the calculation of global neutronic feedback coefficients and a quasi-static evaluation was developed to estimate the behavior of a core during overpower transients, loss of flow and/or loss of heat removal transients. The breakthrough of this approach is to provide the designer with an overall view of the iterative process, emphasizing the well-suited innovations and the most efficient directions that can improve the SFR design project.This methodology was used to design a core that benefits from the favorable features of carbide fuels. The core developed is a large carbide-fueled SFR with high power density, low fissile inventory, break-even capability and forgiving behaviors during the un-scrammed transients studied that should prevent using expensive mitigate systems. However, the core-peak burnup is unlikely to significantly exceed 100 MWd/kg because of the large swelling of the carbide fuel leading to quick pellet-clad mechanical interaction and the low creep capacity of carbide. Moderate linear power fuel

Multi-scale approach to the modeling of fission gas discharge during hypothetical loss-of-flow accident in gen-IV sodium fast reactor

Energy Technology Data Exchange (ETDEWEB)

Behafarid, F.; Shaver, D. R. [Rensselaer Polytechnic Inst., Troy, NY (United States); Bolotnov, I. A. [North Carolina State Univ., Raleigh, NC (United States); Jansen, K. E. [Univ. of Colorado, Boulder, CO (United States); Antal, S. P.; Podowski, M. Z. [Rensselaer Polytechnic Inst., Troy, NY (United States)

2012-07-01

The required technological and safety standards for future Gen IV Reactors can only be achieved if advanced simulation capabilities become available, which combine high performance computing with the necessary level of modeling detail and high accuracy of predictions. The purpose of this paper is to present new results of multi-scale three-dimensional (3D) simulations of the inter-related phenomena, which occur as a result of fuel element heat-up and cladding failure, including the injection of a jet of gaseous fission products into a partially blocked Sodium Fast Reactor (SFR) coolant channel, and gas/molten sodium transport along the coolant channels. The computational approach to the analysis of the overall accident scenario is based on using two different inter-communicating computational multiphase fluid dynamics (CMFD) codes: a CFD code, PHASTA, and a RANS code, NPHASE-CMFD. Using the geometry and time history of cladding failure and the gas injection rate, direct numerical simulations (DNS), combined with the Level Set method, of two-phase turbulent flow have been performed by the PHASTA code. The model allows one to track the evolution of gas/liquid interfaces at a centimeter scale. The simulated phenomena include the formation and breakup of the jet of fission products injected into the liquid sodium coolant. The PHASTA outflow has been averaged over time to obtain mean phasic velocities and volumetric concentrations, as well as the liquid turbulent kinetic energy and turbulence dissipation rate, all of which have served as the input to the core-scale simulations using the NPHASE-CMFD code. A sliding window time averaging has been used to capture mean flow parameters for transient cases. The results presented in the paper include testing and validation of the proposed models, as well the predictions of fission-gas/liquid-sodium transport along a multi-rod fuel assembly of SFR during a partial loss-of-flow accident. (authors)

A Qualitative Assessment of Diversion Scenarios for a GEN IV Example Sodium Fast Reactor Using the GEN IV PR and PP Methodology

Energy Technology Data Exchange (ETDEWEB)

Zentner, M.D.; Coles, G.A. [PNNL, P.O. Box 999, 902 Battelle Boulvard, Richland, WA 99336 (United States); Therios, I.U. [Argonne National Lab. - ANL (United States)

2009-06-15

An experts working group was created in 2002 by The Generation IV International Forum for the purpose of developing an internationally accepted methodology for assessing the proliferation resistance of a nuclear energy system (NES) and its individual elements. A two year case study was performed by the working group using this methodology to assess the proliferation resistance of a hypothetical NES called the Example Sodium Fast Reactor (ESFR). This work demonstrates how the PR and PP methodology can be used to provide important information to designers at various levels of details, including pre-conceptual design stage. The study analyzes the response of the ESFR entire nuclear energy system to different proliferation and theft strategies. The challenges considered comprise concealed diversion, concealed misuse and abrogation strategies. This paper describes the work done in performing a qualitative assessment of potential concealed diversion scenarios from the ESFR, and includes an evaluation of the potential effect of changes in the conversion ratio on diversion strategies. (authors)

Overview of nuclear safety activities performed by JRC-IE on Gen IV fast reactor concepts

Energy Technology Data Exchange (ETDEWEB)

Tsige-Tamirat, H.; Ammirabile, L.; D' Agata, E.; Fuetterer, M.; Ranguelova, V. [European Commission, Joint Research Centre, Institute for Energy, Westerduinweg 3, 1755LE Petten (Netherlands)

2010-07-01

The European Strategic Energy Technology (SET) Plan recognizes the need to develop new energy technologies, in order to reduce greenhouse gas emissions and secure energy supply in Europe. Besides renewable energy and improved energy efficiency, a new generation of nuclear power plants and innovative nuclear power applications can play a significant role to achieve this goal. The JRC Institute for Energy 'Safety of Future Nuclear Reactors' (SFNR) Unit is engaged in experimental research, numerical simulation and modelling, scientific, feasibility and engineering studies on innovative nuclear reactor systems. This also represents a significant EURATOM contribution to the Generation IV International Forum. Its activities deal with, among others, the performance assessment of innovative fuels and materials, development of new reactor core concepts and safety solutions, and knowledge management and preservation. Special attention is given to fast reactor concepts, namely the sodium (SFR) and lead (LFR) cooled reactors. Recognizing the maturity of the SFR technology, the European Sustainable Nuclear Energy Technology Platform (SNETP) considers a prototype SFR to be built as a next-step towards the deployment of a first-of-a-kind Gen IV SFR. This paper gives an overview of current research preformed at JRC-IE with emphasis on the work performed in the Collaborative Project on European Sodium Fast Reactor (CP-ESFR) within the European Commission's Seventh Framework Program. (authors)

Overview of nuclear safety activities performed by JRC-IE on Gen IV fast reactor concepts

International Nuclear Information System (INIS)

Tsige-Tamirat, H.; Ammirabile, L.; D'Agata, E.; Fuetterer, M.; Ranguelova, V.

2010-01-01

The European Strategic Energy Technology (SET) Plan recognizes the need to develop new energy technologies, in order to reduce greenhouse gas emissions and secure energy supply in Europe. Besides renewable energy and improved energy efficiency, a new generation of nuclear power plants and innovative nuclear power applications can play a significant role to achieve this goal. The JRC Institute for Energy 'Safety of Future Nuclear Reactors' (SFNR) Unit is engaged in experimental research, numerical simulation and modelling, scientific, feasibility and engineering studies on innovative nuclear reactor systems. This also represents a significant EURATOM contribution to the Generation IV International Forum. Its activities deal with, among others, the performance assessment of innovative fuels and materials, development of new reactor core concepts and safety solutions, and knowledge management and preservation. Special attention is given to fast reactor concepts, namely the sodium (SFR) and lead (LFR) cooled reactors. Recognizing the maturity of the SFR technology, the European Sustainable Nuclear Energy Technology Platform (SNETP) considers a prototype SFR to be built as a next-step towards the deployment of a first-of-a-kind Gen IV SFR. This paper gives an overview of current research preformed at JRC-IE with emphasis on the work performed in the Collaborative Project on European Sodium Fast Reactor (CP-ESFR) within the European Commission's Seventh Framework Program. (authors)

Fuel research for subcritical and critical GEN-IV systems cooled by heavy liquid metal

International Nuclear Information System (INIS)

Sobolev, V.; Verwerft, M.

2009-01-01

The participation of the Belgian Nuclear Research Centre SCK-CEN in the worldwide GEN-IV research can be considered as an opportunity. Today's GEN-IV research at SCK-CEN is mainly driven by the interests of the project MYRRHA (Multipurpose hYbrid Research Reactor for High-tech Applications). The main goal of this project is to build at SCK-CEN in Mol a new generation fast spectrum, subcritical, research and materials testing reactor MYRRHA driven by a high-energy proton accelerator. This GEN-IV MTR is cooled by heavy liquid metal (Pb-Bi) and will be used for the ADS concept demonstration, testing and qualification of new fuels, transmutation targets and innovative materials. On the European scale, MYRRHA is integrated in the Euratom FP6 Integrated Project (IP) EUROTRANS (EUROpean research programme for TRANSmutation of high level nuclear waste in an accelerator driven system), as the small-scale experimental machine for transmutation demonstration called XT-ADS. Last but not least, this experimental facility will also demonstrate the technological feasibility of the LFR (Lead-cooled Fast Reactor) GEN-IV concept; in EU the LFR design studies are performed in the framework of the Euratom FP6 ELSY (European Lead-cooled SYstem) project, where SCK-CEN is a partner. Among the research needed to ensure a safe and reliable operation of the MYRRHA/XT ADS reactor, the development and qualification of fuel and cladding materials have been recognized as one of the main key issues to be addressed

Materials for generation-IV nuclear reactors

International Nuclear Information System (INIS)

Alvarez, M. G.

2009-01-01

Materials science and materials development are key issues for the implementation of innovative reactor systems such as those defined in the framework of the Generation IV. Six systems have been selected for Generation IV consideration: gas-cooled fast reactor, lead-cooled fast reactor, molten salt-cooled reactor, sodium-cooled fast reactor, supercritical water-cooled reactor, and very high temperature reactor. The structural materials need to resist much higher temperatures, higher neutron doses and extremely corrosive environment, which are beyond the experience of the current nuclear power plants. For this reason, the first consideration in the development of Generation-IV concepts is selection and deployment of materials that operate successfully in the aggressive operating environments expected in the Gen-IV concepts. This paper summarizes the Gen-IV operating environments and describes the various candidate materials under consideration for use in different structural applications. (author)

JRC-IE's research of safety of Gen IV systems

International Nuclear Information System (INIS)

Tsige-Tamirat, H.; Ranguelova, V.; Feutterer, M.; Ammirabile, L.; Carlsson, J.; D'Agata, E.; Laurie, M.; Magallon, D.

2010-01-01

The Institute for Energy (IE), one of the seven scientific Institutes of the Joint Research Centre (JRC) of the European Commission, has the mission to provide scientific and technical support for the conception, development, implementation and monitoring of community policies related to energy. To accomplish its mission, IE performs research in the areas of renewable energies, safety and sustainability of nuclear energy for current and future reactor systems, energy technic/economic assessment, and security of energy supply. The Generation IV International Forum (GIF) is a cooperative international endeavour organized to carry out R and D needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems and support the progress towards their realization. The EU, represented by EURATOM and with the JRC as implementing agent, is working together with other GIF partners to perform pre-competitive R and D on key technologies to be implemented in future nuclear systems. IE is engaged in experimental research, simulation and modeling, scientific, feasibility and engineering studies on innovative nuclear reactor systems needed to support the EURATOM contribution to GEN IV initiative, in particular in assessment of innovative fuels and materials, development of new reactor core concepts and safety solutions and knowledge management and preservation. IE's research activities on Generation IV reactor systems are focused on the assessment of the potential of such systems to meet long term EU energy needs with respect to economical advantages, enhanced safety, sustainability, and proliferation resistance. IE participates in international collaborations and has bilateral research cooperation both with European and non-European partners. This paper gives an overview of IE's current research activities on the Gen IV reactor systems related to safety. (authors)

Thermal stability study for candidate stainless steels of GEN IV reactors

International Nuclear Information System (INIS)

Simeg Veternikova, J.; Degmova, J.; Pekarcikova, M.; Simko, F.; Petriska, M.; Skarba, M.; Mikula, P.; Pupala, M.

2016-01-01

Highlights: • Thermal resistance of advanced stainless steels were observed at 1000 °C. • GEN IV candidate steels were confronted to classic AISI steels. • ODS AISI 316 has weaker thermal resistance than classic AISI steel. • Ferritic ODS steels and NF 709 has better thermal resistance than AISI steels. - Abstract: Candidate stainless steels for GEN IV reactors were investigated in term of thermal and corrosion stability at high temperatures. New austenitic steel (NF 709), austenitic ODS steel (ODS 316) and two ferritic ODS steels (MA 956 and MA 957) were exposed to around 1000 °C in inert argon atmosphere at pressure of ∼8 MPa. The steels were further studied in a light of vacancy defects presence by positron annihilation spectroscopy and their thermal resistance was confronted to classic AISI steels. The thermal strain supported a creation of oxide layers observed by scanning electron microscopy (SEM).

Thermal stability study for candidate stainless steels of GEN IV reactors

Energy Technology Data Exchange (ETDEWEB)

Simeg Veternikova, J., E-mail: jana.veternikova@stuba.sk [Institute of Nuclear and Physical Engineering, Faculty of Electrical and Information Technology, Slovak University of Technology, Ilkovicova 3, 812 19 Bratislava (Slovakia); Degmova, J. [Institute of Nuclear and Physical Engineering, Faculty of Electrical and Information Technology, Slovak University of Technology, Ilkovicova 3, 812 19 Bratislava (Slovakia); Pekarcikova, M. [Institute of Materials Science, Faculty of Materials Science and Technology, Slovak University of Technology, Paulinska 16, 917 24 Trnava (Slovakia); Simko, F. [Department of Molten Salts, Institute of Inorganic Chemistry, Slovak Academy of Sciences, Dubravska cesta 9, 845 36 Bratislava (Slovakia); Petriska, M. [Institute of Nuclear and Physical Engineering, Faculty of Electrical and Information Technology, Slovak University of Technology, Ilkovicova 3, 812 19 Bratislava (Slovakia); Skarba, M. [Slovak University of Technology, Vazovova 5, 812 43 Bratislava (Slovakia); Mikula, P. [Institute of Nuclear and Physical Engineering, Faculty of Electrical and Information Technology, Slovak University of Technology, Ilkovicova 3, 812 19 Bratislava (Slovakia); Pupala, M. [Department of Molten Salts, Institute of Inorganic Chemistry, Slovak Academy of Sciences, Dubravska cesta 9, 845 36 Bratislava (Slovakia)

2016-11-30

Highlights: • Thermal resistance of advanced stainless steels were observed at 1000 °C. • GEN IV candidate steels were confronted to classic AISI steels. • ODS AISI 316 has weaker thermal resistance than classic AISI steel. • Ferritic ODS steels and NF 709 has better thermal resistance than AISI steels. - Abstract: Candidate stainless steels for GEN IV reactors were investigated in term of thermal and corrosion stability at high temperatures. New austenitic steel (NF 709), austenitic ODS steel (ODS 316) and two ferritic ODS steels (MA 956 and MA 957) were exposed to around 1000 °C in inert argon atmosphere at pressure of ∼8 MPa. The steels were further studied in a light of vacancy defects presence by positron annihilation spectroscopy and their thermal resistance was confronted to classic AISI steels. The thermal strain supported a creation of oxide layers observed by scanning electron microscopy (SEM).

Gen IV Materials Handbook Functionalities and Operation

International Nuclear Information System (INIS)

Ren, Weiju

2009-01-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Gen IV Materials Handbook Functionalities and Operation

Energy Technology Data Exchange (ETDEWEB)

Ren, Weiju [ORNL

2009-12-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

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

Reactor physics challenges in GEN-IV reactor design

Energy Technology Data Exchange (ETDEWEB)

Driscoll, Michael K.; Hejzlar, Pavel [Massachusetts Institute of Technology, MA (United States)

2005-02-15

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

Reactor physics challenges in GEN-IV reactor design

International Nuclear Information System (INIS)

Driscoll, Michael K.; Hejzlar, Pavel

2005-01-01

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources

Structural materials for Gen-IV nuclear reactors: Challenges and opportunities

Science.gov (United States)

Murty, K. L.; Charit, I.

2008-12-01

Generation-IV reactor design concepts envisioned thus far cater toward a common goal of providing safer, longer lasting, proliferation-resistant and economically viable nuclear power plants. The foremost consideration in the successful development and deployment of Gen-IV reactor systems is the performance and reliability issues involving structural materials for both in-core and out-of-core applications. The structural materials need to endure much higher temperatures, higher neutron doses and extremely corrosive environment, which are beyond the experience of the current nuclear power plants. Materials under active consideration for use in different reactor components include various ferritic/martensitic steels, austenitic stainless steels, nickel-base superalloys, ceramics, composites, etc. This paper presents a summary of various Gen-IV reactor concepts, with emphasis on the structural materials issues depending on the specific application areas. This paper also discusses the challenges involved in using the existing materials under both service and off-normal conditions. Tasks become increasingly complex due to the operation of various fundamental phenomena like radiation-induced segregation, radiation-enhanced diffusion, precipitation, interactions between impurity elements and radiation-produced defects, swelling, helium generation and so forth. Further, high temperature capability (e.g. creep properties) of these materials is a critical, performance-limiting factor. It is demonstrated that novel alloy and microstructural design approaches coupled with new materials processing and fabrication techniques may mitigate the challenges, and the optimum system performance may be achieved under much demanding conditions.

Safeguards Licensing Aspects of a Future Gen IV Test Facility - a Case Study

International Nuclear Information System (INIS)

Lindell, M. Aberg; Grape, S.; Hakansson, A.; Svaerd, S. Jacobsson

2010-01-01

The scope of this study covers safeguards licensing aspects of a possible future Gen IV demonstration facility. As a basis for the investigation, the facility was assumed to be located in Sweden, comprising a lead-cooled fast reactor and a reprocessing plant with fuel fabrication. The aim has been to identify safeguards requirements that may be set by the IAEA and the Swedish Radiation Safety Authority, and also to suggest how the safeguards system could be implemented in practice. The changed usage and handling of nuclear fuel, as compared to that of today, has been examined in order to determine how today's safeguards measures can be modified and extended to meet the needs of the demonstration facility. This work is part of GENIUS, the Swedish Gen IV research and development programme, which emphasizes lead-cooled fast reactors. (author)

Generation-IV nuclear reactors, SFR concept

International Nuclear Information System (INIS)

Dufour, P.

2010-01-01

In this presentation author deals with development of sodium-cooled fast reactors and lead-cooled fast reactors. He concluded that: - SFR is a proved concept that has never achieved industrial deployment; - The GEN IV objectives need to reconsider the design of both the core and the reactor design : innovations are being analysed; Future design will benefit from considerable feedback of design, licensing, construction and operation of PX, SPX, etc.

Development of basic key technologies for Gen IV SFR

International Nuclear Information System (INIS)

Kim, Yeongil; Kim, Sungoh; Choi, Sukgi

2012-04-01

The advanced concepts, for the breakeven reactor(1,200MWe) and TRU burner(600MWe), were defined to satisfy the technology goals of Generation IV nuclear systems. Based on the advanced design concepts, a conceptual design of the demonstration SFR has been developed using the available licensing technology. The conceptual core design has been developed for the TRU burner in which an initial core is fueled with less than 20wt% enriched U235, and finally transformed to a self-recycled TRU core. The passive decay heat removal circuit ensuring reactor safety even in case of loss of emergency power has been developed and minimization of a reactor vessel and simplification of reactor internals have been conducted in the conceptual design. For development of advanced technologies, control logics for various power levels and the optimal design concept of heat exchanger applicable to supercritical CO 2 Brayton cycle as an energy conversion system was developed. A novel under-sodium waveguide sensor and a prototype under-sodium inspection system have been developed for under-sodium viewing of in-vessel structures submerged in an opaque liquid sodium. The fabrication technology of fuel slugs using the advanced fuel slug casting system was developed, and U-Zr alloy fuel rods were fabricated and examined. And a HT 9 cladding tube was manufactured using the developed cladding tube fabrication technology. For development of basic technologies, the cross section adjustment code ATCROSS and the MATRA-LMR code with HCFs have been developed to reduce core design uncertainties. The SIE ASME-NH computer program to evaluate high temperature structural design for 60 years design life, and the safety analysis code MARS-LMR with thermal-hydraulic and reactivity feedback models have been developed and validated. In addition, the sodium impurity measurement and control technology, the sodium water reaction event propagation model to predict the sodium leak propagation in a steam generator, and

The safety R and D for GEN-IV reactors in the European nuclear energy technology platform strategic research agenda

International Nuclear Information System (INIS)

Bruna, G.

2009-01-01

In the fall 2007 EC launched the Sustainable Nuclear Energy Technology Platform (SNE-TP). The SNE-TP governing board set-up three working groups (WG): 1) Strategic Research Agenda (SRA) WG, in charge of drafting road-maps to support research, development and demonstration for current and future NPPs; 2) Deployment Strategy (DS) WG, in charge of defining the research road-map implementation and 3) Education, Training and Knowledge management (ETKM) WG, which was aimed at issuing proposal to reinforce European education and attract young in the nuclear field. The SRA WG was mandated to prepare the SRA vision document based on the preliminary road-map sketched in the document published by the Commission earlier in 2007. The SRA WG was originally organized in 5 sub-groups covering specific topics (1) GEN II and III, III+, including Advanced LWR, 2) Advanced Fuel Cycle for waste minimization and resource optimization; 3) GEN IV Fast Systems (SFR, LFR, GFR, ADS); 4) GEN IV (V) HTR and non-electricity-production applications; 5) New Nuclear Large Research Infrastructures) and 5 other sub-groups dealing with more generic cross-cutting research activities applicable to many specific topics, namely: 1) Structural material research; 2) modeling, simulation and methods, including physical data and tools and means for qualification and validation; 3) Reactor Safety, including severe accidents and human factor; 4) Advanced Driver and Minor Actinide Fuels: science and properties; 5) Pre-normative Research, Codes and Standards.The present paper is mainly aimed at summarizing the content of the SRA Safety sub-chapter focusing on GEN-IV aspects

ASTRID, Generation IV advanced sodium technological reactor for industrial demonstration

International Nuclear Information System (INIS)

Gauche, F.

2013-01-01

ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) is an integrated technology demonstrator designed to demonstrate the operability of the innovative choices enabling fast neutron reactor technology to meet the Generation IV criteria. ASTRID is a sodium-cooled fast reactor with an electricity generating power of 600 MWe. In order to meet the generation IV goals, ASTRID will incorporate the following decisive innovations: -) an improved core with a very low, even negative void coefficient; -) the possible installation of additional safety devices in the core. For example, passive anti-reactivity insertion devices are explored; -) more core instrumentation; -) an energy conversion system with modular steam generators, to limit the effects of a possible sodium-water reaction, or sodium-nitrogen exchangers; -) considerable thermal inertia combined with natural convection to deal with decay heat; -)elimination of major sodium fires by bunkerization and/or inert atmosphere in the premises; -) to take into account off-site hazards (earthquake, airplane crash,...) right from the design stage; -) a complete rethink of the reactor architecture in order to limit the risk of proliferation. ASTRID will also include systems for reducing the length of refueling outages and increasing the burn-up and the duration of the cycle. In-service inspection, maintenance and repair are also taken into account right from the start of the project. The ASTRID prototype should be operational by about 2023. (A.C.)

Methodology for Extraction of Remaining Sodium of Used Sodium Containers

International Nuclear Information System (INIS)

Jung, Minhwan; Kim, Jongman; Cho, Youngil; Jeong, Jiyoung

2014-01-01

Sodium used as a coolant in the SFR (Sodium-cooled Fast Reactor) reacts easily with most elements due to its high reactivity. If sodium at high temperature leaks outside of a system boundary and makes contact with oxygen, it starts to burn and toxic aerosols are produced. In addition, it generates flammable hydrogen gas through a reaction with water. Hydrogen gas can be explosive within the range of 4.75 vol%. Therefore, the sodium should be handled carefully in accordance with standard procedures even though there is a small amount of target sodium remainings inside the containers and drums used for experiment. After the experiment, all sodium experimental apparatuses should be dismantled carefully through a series of draining, residual sodium extraction, and cleaning if they are no longer reused. In this work, a system for the extraction of the remaining sodium of used sodium drums has been developed and an operation procedure for the system has been established. In this work, a methodology for the extraction of remaining sodium out of the used sodium container has been developed as one of the sodium facility maintenance works. The sodium extraction system for remaining sodium of the used drums was designed and tested successfully. This work will contribute to an establishment of sodium handling technology for PGSFR. (Prototype Gen-IV Sodium-cooled Fast Reactor)

Developing new nuclear curricula for GEN IV needs

International Nuclear Information System (INIS)

Ghitescu, P.; Pavel, G.L.

2014-01-01

States who wish to start and develop a nuclear program must take into consideration a strong proven strategy for developing a sustainable program. A complete nuclear research program must include: a good national strategy and support on the topic; strong research laboratories supported by good personnel; education component to provide sustainable and qualified workforce; national/international interest from stakeholders and governments and a well informed society. New demonstrators are foreseen for the next period to be built in Europe and skilled supporting personnel is strongly needed. Current situation in nuclear higher education with perspective will be analysed. EURATOM strongly supports development of multidisciplinary co-operational projects in order to built such novel initiatives. An example of such program supported by European Commission, ARCADIA, will be given. The project is based on the cooperation of a large number of participants all over Europe and the main purpose is to develop a road-map for Gen IV reactor. (authors)

Report and analysis on 'PR and PP evaluation. Example sodium fast reactor full system case study'

International Nuclear Information System (INIS)

Sagara, Hiroshi; Inoue, Naoko; Kawakubo, Yoko; Watahiki, Masaru

2011-01-01

The Generation IV (GEN IV) Nuclear Energy Systems International Forum (GIF) Proliferation Resistance and Physical Protection Working Group (PRPP WG) was established in December 2002 in order to develop the PR and valuation methodology for GEN IV nuclear energy systems. In the final report of 'PR and PP Evaluation: Example Sodium Fast Reactor (ESFR) Full System Case Study,' issued in October 2009, the demonstration study of PR and PP evaluation with the qualitative approach are summarized using ESFR with four scenario threats. The present paper reviews and analyzes some results of the ESFR case study, and identifies the challenges and direction for the PR and PP evaluation methodology with quantitative approach. (author)

Native pyroglutamation of huwentoxin-IV: a post-translational modification that increases the trapping ability to the sodium channel.

Science.gov (United States)

Rong, Mingqiang; Duan, Zhigui; Chen, Juliang; Li, Jianglin; Xiao, Yuchen; Liang, Songping

2013-01-01

Huwentoxin-IV (HWTX-IV), a tetrodotoxin-sensitive (TTX-s) sodium channel antagonist, is found in the venom of the Chinese spider Ornithoctonus huwena. A naturally modified HWTX-IV (mHWTX-IV), having a molecular mass 18 Da lower than HWTX-IV, has also been isolated from the venom of the same spider. By a combination of enzymatic fragmentation and MS/MS de novo sequencing, mHWTX-IV has been shown to have the same amino acid sequence as that of HWTX-IV, except that the N-terminal glutamic acid replaced by pyroglutamic acid. mHWTX-IV inhibited tetrodotoxin-sensitive voltage-gated sodium channels of dorsal root ganglion neurons with an IC50 nearly equal to native HWTX-IV. mHWTX-IV showed the same activation and inactivation kinetics seen for native HWTX-IV. In contrast with HWTX-IV, which dissociates at moderate voltage depolarization voltages (+50 mV, 180000 ms), mHWTX-IV inhibition of TTX-sensitive sodium channels is not reversed by strong depolarization voltages (+200 mV, 500 ms). Recovery of Nav1.7current was voltage-dependent and was induced by extreme depolarization in the presence of HWTX-IV, but no obvious current was elicited after application of mHWTX-IV. Our data indicate that the N-terminal modification of HWTX-IV gives the peptide toxin a greater ability to trap the voltage sensor in the sodium channel. Loss of a negative charge, caused by cyclization at the N-terminus, is a possible reason why the modified toxin binds much stronger. To our knowledge, this is the first report of a pyroglutamic acid residue in a spider toxin; this modification seems to increase the trapping ability of the voltage sensor in the sodium channel.

Native pyroglutamation of huwentoxin-IV: a post-translational modification that increases the trapping ability to the sodium channel.

Directory of Open Access Journals (Sweden)

Mingqiang Rong

Full Text Available Huwentoxin-IV (HWTX-IV, a tetrodotoxin-sensitive (TTX-s sodium channel antagonist, is found in the venom of the Chinese spider Ornithoctonus huwena. A naturally modified HWTX-IV (mHWTX-IV, having a molecular mass 18 Da lower than HWTX-IV, has also been isolated from the venom of the same spider. By a combination of enzymatic fragmentation and MS/MS de novo sequencing, mHWTX-IV has been shown to have the same amino acid sequence as that of HWTX-IV, except that the N-terminal glutamic acid replaced by pyroglutamic acid. mHWTX-IV inhibited tetrodotoxin-sensitive voltage-gated sodium channels of dorsal root ganglion neurons with an IC50 nearly equal to native HWTX-IV. mHWTX-IV showed the same activation and inactivation kinetics seen for native HWTX-IV. In contrast with HWTX-IV, which dissociates at moderate voltage depolarization voltages (+50 mV, 180000 ms, mHWTX-IV inhibition of TTX-sensitive sodium channels is not reversed by strong depolarization voltages (+200 mV, 500 ms. Recovery of Nav1.7current was voltage-dependent and was induced by extreme depolarization in the presence of HWTX-IV, but no obvious current was elicited after application of mHWTX-IV. Our data indicate that the N-terminal modification of HWTX-IV gives the peptide toxin a greater ability to trap the voltage sensor in the sodium channel. Loss of a negative charge, caused by cyclization at the N-terminus, is a possible reason why the modified toxin binds much stronger. To our knowledge, this is the first report of a pyroglutamic acid residue in a spider toxin; this modification seems to increase the trapping ability of the voltage sensor in the sodium channel.

Gen IV Materials Handbook Functionalities and Operation (2B) Handbook Version 2.0

International Nuclear Information System (INIS)

Ren, Weiju

2011-01-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Gen IV Materials Handbook Functionalities and Operation (4A) Handbook Version 4.0

Energy Technology Data Exchange (ETDEWEB)

Ren, Weiju [ORNL

2013-09-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Gen IV Materials Handbook Functionalities and Operation (2B) Handbook Version 2.0

Energy Technology Data Exchange (ETDEWEB)

Ren, Weiju [ORNL

2011-08-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Indirect complexometric determination of thorium(IV) using sodium fluoride as masking agent

International Nuclear Information System (INIS)

Sreekumar, N.V.; Nazareth, R.A.; Narayana, B.; Hegde, P.; Manjunatha, B.R.

2002-01-01

A complexometric method for the determination of thorium(IV) in presence of other metal ions based on the selective masking ability of sodium fluoride towards thorium is described. Thorium(IV) present in a given sample solution is first complexed with a known excess of EDTA and the surplus EDTA is titrated against bismuth nitrate solution at pH 2-3 using xylenol orange as indicator. A known excess of sodium fluoride (5 %) is then added and the EDTA released from the Th-EDTA complex is titrated against standard bismuth nitrate solution. Reproducible and accurate results are obtained for 5 mg to 280 mg of thorium with relative errors ±0.65 % and standard deviations /leq 0.75 mg. The interference of various ions was studied. (author)

Study on high temperature design methodology of heat-resistant materials for GEN-IV systems

Energy Technology Data Exchange (ETDEWEB)

Ryu, Woo Seog; Kim, D. W.; Kim, S. H.; Kim, W. G.; Kim, J. H.; Park, D. G.; Yoon, J. H.; Lee, H. Y.; Hing, J. H

2005-08-15

Analysis of the existing high temperature design and assessment codes such as US(ASME-NH,Draft Code Case for Alloy 617), France(RCC-MR), UK(R5), Japan(BDS/DDS/FDS) for Gen IV reactor structure has been carried out. In addition the scope and fields for research and development is needed in the future have been defined. For assessing the high temperature creep cracks, time dependent fracture mechanics (TDFM) parameters of the C and Ct were analyzed. The creep propagation data were obtained from the creep crack growth tests for type 316LN stainless steels, and creep crack growth testing machine for Gen-IV system up to 950 .deg. C was set up. Damage mechanism and causes for creep-fatigue were investigated. The difference between prediction creep-fatigue life and experimental life were investigated. Material properties for analysis creep-fatigue damage were recommended. The assessment procedure (Draft) on creep-fatigue crack initiation has been developed based on the technical appendix A16 of French RCC-MR code. Ultrasonic wave signal against creep ruptured specimens of type 316LN stainless steel was obtained. It was identified that creep damage can be evaluated by ultrasonic method. The NDT techniques evaluated include Barkhausen noise, magnetic hysteresis parameters, positron annihilation, X-ray diffraction and small angle neutron scattering. Experimental procedure and evaluation method of material integrity were developed through the fracture toughness test of Cr-Mo steel.

Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR with PBO Reflector

Directory of Open Access Journals (Sweden)

Chihyung Kim

2016-04-01

Full Text Available The Korean Prototype Gen-IV sodium-cooled fast reactor (PGSFR is supposed to be loaded with a relatively-costly low-enriched U fuel, while its envisaged transuranic fuels are not available for transmutation. In this work, the U-enrichment reduction by improving the neutron economy is pursued to save the fuel cost. To improve the neutron economy of the core, a new reflector material, PbO, has been introduced to replace the conventional HT9 reflector in the current PGSFR core. Two types of PbO reflectors are considered: one is the conventional pin-type and the other one is an inverted configuration. The inverted PbO reflector design is intended to maximize the PbO volume fraction in the reflector assembly. In addition, the core radial configuration is also modified to maximize the performance of the PbO reflector. For the baseline PGSFR core with several reflector options, the U enrichment requirement has been analyzed and the fuel depletion analysis is performed to derive the equilibrium cycle parameters. The linear reactivity model is used to determine the equilibrium cycle performances of the core. Impacts of the new PbO reflectors are characterized in terms of the cycle length, neutron leakage, radial power distribution, and operational fuel cost.

Analysis of a Spanish energy scenario with Generation IV nuclear reactors

International Nuclear Information System (INIS)

Ochoa, Raquel; Jimenez, Gonzalo; Perez-Martin, Sara

2013-01-01

Highlights: • Spanish energy scenario for the hypothetical deployment of Gen-IV SFR reactors. • Availability of national resources is assessed, considering SFR’s breeding. • An assessment of the impact of transmuting MA on the final repository. • SERPENT code with own pre- and post-processing tools were employed. • The employed SFR core design is based on the specifications of the CP-ESFR. - Abstract: The advantages of fast-spectrum reactors consist not only of an efficient use of fuel through the breeding of fissile material and the use of natural or depleted uranium, but also of the potential reduction of the amount of actinides such as americium and neptunium contained in the irradiated fuel. The first aspect means a guaranteed future nuclear fuel supply. The second fact is key for high-level radioactive waste management, because these elements are the main responsible for the radioactivity of the irradiated fuel in the long term. The present study aims to analyze the hypothetical deployment of a Gen-IV Sodium Fast Reactor (SFR) fleet in Spain. A nuclear fleet of fast reactors would enable a fuel cycle strategy different than the open cycle, currently adopted by most of the countries with nuclear power. A transition from the current Gen-II to Gen-IV fleet is envisaged through an intermediate deployment of Gen-III reactors. Fuel reprocessing from the Gen-II and Gen-III Light Water Reactors (LWR) has been considered. In the so-called advanced fuel cycle, the reprocessed fuel used to produce energy will breed new fissile fuel and transmute minor actinides at the same time. A reference case scenario has been postulated and further sensitivity studies have been performed to analyze the impact of the different parameters on the required reactor fleet. The potential capability of Spain to supply the required fleet for the reference scenario using national resources has been verified. Finally, some consequences on irradiated final fuel inventory are assessed

Environmental sensitivity studies for Gen-IV roadmap DUPIC scenario

International Nuclear Information System (INIS)

Jeong, Chang Joon

2004-03-01

The environmental effect of the DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors) fuel cycle, which is considered as one of the partial recycle scenario in Gen-IV roadmap, has been analyzed by using the dynamic analysis method. Through the parametric calculations for the DUPIC fuel cycle deployment time and the fraction of the DUPIC reactors, the environmental effects of the fuel cycle for important parameters such as the amount of spent fuel and the combined amounts of plutonium and minor actinides were estimated and compared to those of the once-through LWR fuel cycle. The results of the sensitivity calculations showed that an early deployment of the DUPIC fuel cycle with a high DUPIC reactor fraction can reduce the accumulation of spent fuel by up to 40%. More important is the associated reduction in the combined amount of plutonium and minor actinides, which may reduce the key repository parameter (long term decay heat). Therefore it is expected that favorable environmental effects will be the outcome of the implementation of the DUPIC fuel cycle

A Qualitative Assessment Of Diversion Scenarios For A Example Sodium Fast Reactor Using The Gen IV PR And PP Methodology

International Nuclear Information System (INIS)

Zentner, Michael D.

2008-01-01

A working group was created in 2002 by the Generation IV International Forum (GIF) for the purpose of developing an internationally accepted methodology for assessing the Proliferation Resistance of a nuclear energy system (NES) and its individual elements. A two year case study is being performed by the experts group using this methodology to assess the proliferation resistance of a hypothetical NES called the Example Sodium Fast Reactor (ESFR). This work demonstrates how the PR and PP methodology can be used to provide important information at various levels of details to NES designers, safeguard administrators and decision makers. The study analyzes the response of the complete ESFR nuclear energy system to different proliferation and theft strategies. The challenges considered include concealed diversion, concealed misuse and 'break out' strategies. This paper describes the work done in performing a qualitative assessment of concealed diversion scenarios from the ESFR.

Environmental sensitivity studies for Gen-IV roadmap fast reactor scenario

International Nuclear Information System (INIS)

Jeong, Chang Joon

2004-03-01

The environmental effect of the self-sufficient fast reactor scenario, which is considered as one of the full fissile plutonium and transuranic recycle scenario in Gen-IV roadmap, has been analyzed by using the dynamic analysis method. Through the parametric calculations for the fast reactor deployment time and capacity, the environmental effects of the fuel cycle for important parameters such as the amount of spent fuel and the combined amounts of plutonium and minor actinides were estimated and compared to those of the once-through LWR fuel cycle. The results of the sensitivity calculations showed that an early deployment of the fast reactor with a high capacity can reduce the accumulation of spent fuel by up to 37%. Furthermore, the recycling of plutonium and minor actinides can reduce the key repository parameter (long term decay heat). Therefore the favorable environmental effects can be expected with the implementation of the symbiotic fast reactor scenario

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.

Status of the French R/D program on the severe accident issue to develop Gen IV SFRs - 15373

International Nuclear Information System (INIS)

Serre, F.; Bertrand, F.; Journeau, C.; Suteau, C.; Verwaede, D.; Schmitt, D.; Farges, B.

2015-01-01

The ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demonstration) is a technological demonstrator designed by the CEA with its industrial partners, with very high levels of requirements. In the ASTRID project, the safety objectives are to prevent core melting, in particular by the development of an innovative core with complementary safety prevention devices, and to enhance the reactor resistance to severe accident by design. To mitigate the consequences of hypothetical core melting situations, specific dispositions or mitigation devices will be added to the core and to the reactor. It is also required to provide a robust safety demonstration (with high level of confidence). Therefore a new approach for severe accident issue has been defined: to the well-known 'lines of defense' method, a 'lines of mitigation' method is added. To meet these ASTRID, or future SFR, requirements, a large R/D program was launched in the Severe Accident domain, with a large number of partners. This paper will present the status of the CEA R/D related to the SFR Severe Accident issue, the collaboration framework (with industrial partners and R/D foreign organizations), and the future R/D plans to support the ASTRID project and possible developments for future Gen IV commercial SFR. (authors)

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

A Qualitative Assessment of Diversion Scenarios for an Example Sodium Fast Reactor Using the GEN IV PR and PP Methodology

International Nuclear Information System (INIS)

Zentner, Michael D.; Coles, Garill A.; Therios, Ike

2012-01-01

FAST REACTORS;NUCLEAR ENERGY;NUCLEAR MATERIALS MANAGEMENT;PROLIFERATION;SAFEGUARDS;THEFT; A working group was created in 2002 by the Generation IV International Forum (GIF) for the purpose of developing an internationally accepted methodology for assessing the Proliferation Resistance of a nuclear energy system (NES) and its individual elements. A two year case study is being performed by the experts group using this methodology to assess the proliferation resistance of a hypothetical NES called the Example Sodium Fast Reactor (ESFR). This work demonstrates how the PR and PP methodology can be used to provide important information at various levels of details to NES designers, safeguard administrators and decision makers. The study analyzes the response of the complete ESFR nuclear energy system to different proliferation and theft strategies. The challenges considered include concealed diversion, concealed misuse and 'break out' strategies. This paper describes the work done in performing a qualitative assessment of concealed diversion scenarios from the ESFR.

Selective complexometric determination of titanium(IV) using sodium potassium tartrate or ascorbic acid as masking agent

International Nuclear Information System (INIS)

Sreekumar, N.V.; Bhat, N.G.; Narayana, B.; Nazareth, R.A.; Hegde, P.; Manjunatha, B.R.

2003-01-01

A simple, rapid and accurate complexometric method is proposed for the determination of titanium(IV) where sodium potassium tartrate or ascorbic acid were used as masking agents. In the presence of diverse metal ions, titanium is first complexed with excess of EDTA and surplus EDTA is then titrated at pH 5-6 with zinc sulfate, xylenol orange being used as indicator. An excess of 5 % aqueous sodium potassium tartrate is then added to displace the complexed EDTA from the Ti-EDTA complex quantitatively, which is titrated with zinc sulfate. Also, ascorbic acid may be used as the releasing agent. The methods work well in the range 1-53 mg of Ti(IV) for sodium potassium tartrate with relative errors ± 0.28 % and standard deviations 0.16 mg. For ascorbic acid the range is 1.00-30.00 mg of Ti(IV) with relative errors of ± 0.40 % and standard deviations of 0.05 mg. (author)

GIF (Gen-IV International Forum) Symposium 2009. Proceedings

International Nuclear Information System (INIS)

2009-01-01

The objective of this symposium is to give a well documented state of the art of the initiative and to report and discuss the most significant technical progress and evolution in the different areas during these last ten years. Another significant objective is to provide a forum for an open and hopefully lively discussion of the perspectives, priorities and challenges for the next few years, accounting for a rapidly evolving environment. The symposium has been organized into three sessions that have dealt with the following issues: -) Generation IV International Forum (GIF): 10 years of achievements and the path forward, -) Methodology Overviews and Focus on Applications, -) Very High Temperature Reactor (VHTR), -) Gas-cooled Fast Reactor (GFR), -) Super-Critical Water-cooled Reactor (SCWR), -) Lead-cooled Fast Reactor (LFR), -) Molten Salt Reactor (MSR), -) Sodium-cooled Fast Reactor (SFR), -) International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) and its potential synergy with GIF, and -) GIF priority objectives for the next 5 years

Gen IV International Forum - GIF, 2010 Annual Report

International Nuclear Information System (INIS)

Anon.

2011-01-01

The Generation IV International Forum (GIF), created in 2000 to foster international collaboration at a detailed level of actual R and D, is a cooperative international endeavor, organized to develop the research necessary to test the feasibility and performance capabilities of fourth generation nuclear systems, with the goal of making such systems deployable in large numbers around 2030. Since its beginning, GIF members stated the following goals for the fourth generation of nuclear power plants when compared to previous generations: a) improve sustainability (including effective fuel utilization and minimization of waste); b) improve economics (competitiveness with respect to other energy sources); c) improve safety and reliability (e.g. no need for offsite emergency response); and d) improve proliferation resistance and physical protection. After an in-depth analysis of the different available concepts, whatever their level of development, the Forum selected six concepts as the most promising, and decided to focus R and D on these systems: - the very-high-temperature reactor (VHTR); - the sodium-cooled fast reactor (SFR); - the supercritical-water-cooled reactor (SCWR); - the gas-cooled fast reactor (GFR); - the lead-cooled fast reactor (LFR); - the molten salt reactor (MSR). Active members of the GIF are Canada, Euratom, France, Japan, People's Republic of China, Republic of Korea, Republic of South Africa, Russian Federation, Switzerland and the United States. Altogether, they represent around 90% of the world installed nuclear capacity for producing electricity, and all key technology holders. The forum is led by the policy group, where all members are represented, and currently chaired by Japan since December 2009, assisted by vice-chairs from France and United States. The year 2010 has seen some important achievements and decisions regarding these six systems. For example, two sodium-cooled fast reactors (re)started this year: Monju in Japan restarted after

Experimental investigation of solid sodium-water reaction: tests results and phenomenological analysis

International Nuclear Information System (INIS)

Daudin, K.; Beauchamp, F.; Proust, C.

2014-01-01

Sodium-Water Reaction (SWR) is an issue one has to be capable to deal with for the next generation of nuclear reactors (SFR for GEN IV). The background of these experiments is the improvement of safety demonstration regarding SWR in an open volume. This experimental campaign is conducted at the CEA Cadarache inside a cylindrical reactor filled with inert gas. The sodium is inside a loading pot and water comes into contact by immersion. SWR and its physical effects are followed by different pressure and temperature sensors. The results show a limit to the overpressure increasing sodium mass. Global assessment of physical effects of SWR contributes to put forward the relative nature of phenomena with geometric configuration, and the importance of scale effects. (authors)

Instrumentation and Control Systems for Sodium thermal hydraulic Experiment Loop for Finned-tube sodium-to-Air heat exchanger (SELFA)

Energy Technology Data Exchange (ETDEWEB)

Kim, Byeong Yeon; Kim, Hyung Mo; Cho, Youn Gil; Kim, Jong Man; Ko, Yung Joo; Kang, Byeong Su; Jung, Min Hwan; Jeong, Ji Young [KAERI, Daejeon (Korea, Republic of)

2016-05-15

A forced-draft sodium-to-air heat exchanger (FHX) is a part of decay heat removal system (DHRS) in Prototype Gen-IV Sodium-cooled fast reactor (PGSFR), which is being developed at Korea Atomic Energy Research Institute (KAERI). Sodium thermal hydraulic Experiment Loop for Finned-tube sodium-to-Air heat exchanger (SELFA) is a test facility for verification and validation of the design code for a forced-draft sodium-to-air heat exchanger (FHX). In this paper, we have provided design and fabrication features for the instrumentation and control systems of SELFA. In general, the instrumentation systems and control systems are coupled for measurement and control of process variables. Instrumentation systems have been designed for investigating thermal-hydraulic characteristics of FHX and control systems have been designed to control the main components (e.g. electromagnetic pumps, heaters, valves etc.) required for test in SELFA. In this paper, we have provided configurations of instrumentation and control systems for Sodium thermal hydraulic Experiment Loop for Finned-tube sodium-to-Air heat exchanger (SELFA). The instrumentation and control systems of SELFA have been implemented based on the expected operation ranges and lesson learned from operational experience of 'Sodium integral effect test loop for safety simulation and assessment-1' (STELLA-1)

Summary of Structural Concept Development and High Temperature Structural Integrity Evaluation Technology for a Gen-IV SFR

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae Han; Joo, Young Sang; Lee, Hyeong Yeon (and others)

2008-04-15

The economic improvement is a hot issue as one of Gen IV nuclear plant goals. It requires many researches and development works to meet the goal by securing the same level of plant safety. One of the key research items is the increase of the plant capacity with the minimum number of components and loops. Through the successful conceptual design experience for the KALIMER-600, the structural design study for a 1200MWe large capacity of sodium-cooled fast reactor has been performed to achieve the above plant size effects. The component number and reactor structural sizing were determined based on the core and fluid system design information. Several researches were performed to reduce the construction cost of NSSS in structural point of view, for example, a simplified component arrangement, concept proposals of integrated components, a high temperature LBB application technology, and an innovative in-service inspection (ISI) tool, and a computer program development of the ASME-NH design procedure of the class 1 structure and component under high temperature over 500 .deg. C. The IHTS piping arrangement was also proposed to minimize the length through the properly locating the SG and pump by 126m. Further studies of these concepts are required to confirm on the fabricability and the structural integrity for the operating and design loads. The proposed concepts will be optimized to a unified conceptual design through several trade-off studies.

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

Minor actinides transmutation potential: state of art for GEN IV sodium cooled fast reactors

International Nuclear Information System (INIS)

Buiron, Laurent

2015-01-01

In the frame of the R and D program relative to the 1991 French act on nuclear waste management, fast neutron systems have shown relevant characteristics that meet both requirements on sustainable resources management and waste minimization. They also offer flexibility by mean of burner or breeder configurations allowing mastering plutonium inventory without significant impact on core safety. From the technological point of view, sodium cooled fast reactor are considered in order to achieve mean term industrial deployment. The present document summaries the main results of R and D program on minor actinides transmutation in sodium fast reactor since 2006 following recommendation of the first part of the 1991 French act. Both homogeneous and heterogeneous management achievable performances are presented for 'evolutionary' SFR V2B core as well as low void worth CFV core for industrial scale configurations (1500 MWe). Minor actinides transmutation could be demonstrated in the ASTRID reactor with the following configurations: - a 2%vol Americium content for the homogeneous mode, - a 10%vol Americium content for the heterogeneous mode, without any substantial modification of the main core safety parameters and only limited impacts on the associated fuel cycle (manufacturing issues are not considered here). In order to achieve such goal, a wide range of experimental irradiations driven by transmutation scenarios have to be performed for both homogeneous and heterogeneous minor actinides management. (author) [fr

R and D Trends For The Future Sodium Fast Reactors In France

International Nuclear Information System (INIS)

Dufour, Ph.; Anzieu, P.; Lecarpentier, D.; Serpantie, JP.

2006-01-01

The sodium fast reactors are the natural Generation IV candidate, thanks to their strong potential for incineration and/or breeding that allow drastic fissile materials economy and fission waste products recycling or transmutation. The question is now to make evolve the existing or past projects of reactors to systems fully compatible with Generation IV objectives, in particular with regard to the economy, durability and safety. This work must be achieved in an international frame which requires a sharing of the objectives and will allow, in the long term, the sharing of the activities. However, in order to ensure the overall coherence of the various development programs defined within the Gen-IV framework, it is necessary to define a new SFR development plan based on the experience gained in France (Phenix, Superphenix) and Europe, in the EFR project. The commonly agreed SFR system issues to be improved or further investigated are its capital cost, safety issues (sodium risks, core criticality accidents), and in-service inspection and maintenance technology. (authors)

Preliminary conceptual design of the secondary sodium circuit-eliminated JSFR (Japan Sodium Fast Reactor) adopting a supercritical CO2 turbine system (1). Sodium/CO2 heat exchanger

International Nuclear Information System (INIS)

Kisohara, Naoyuki; Sakamoto, Yoshihiko; Kotake, Shoji

2014-09-01

Research and development of the supercritical CO 2 (S-CO 2 ) cycle turbine system is underway in various countries for further improvement of the safety and economy of sodium-cooled fast reactors. The Component Design and Balance-Of-Plant (CD and BOP) of the Generation IV International Nuclear Forum (Gen-IV) has addressed this study, and their analytical and experimental results have been discussed between the relevant countries. JAEA, who is a member of the CD and BOP, has performed a design study of an S-CO 2 gas turbine system applied to the Japan Sodium-cooled Fast Reactor (JSFR). In this study, the S-CO 2 cycle turbine system was directly connected to the primary sodium system of the JSFR to eliminate the secondary sodium circuit, aiming for further economical improvement. This is because there is no risk of sodium-water reaction in the S-CO 2 cycle turbine system of SFRs. The Na/CO 2 heat exchanger is one of the key components for the secondary sodium system eliminated SFR, and this report describes its structure and the safety in case of CO 2 leak. A Printed Circuit Heat Exchanger (PCHE), which has a greater heat transfer performance, is employed to the heat exchanger. Another advantage of the PCHE is to limit the area affected by a leak of CO 2 because of its partitioned flow path structure. A SiC/SiC ceramic composite material is used for the PCHE to prevent crack growth and to reduce thermal stress. The Na/CO 2 heat exchanger has been designed in such a way that a number of small heat transfer modules are combined in the vessel in consideration of manufacture and repair. The primary sodium pump is installed in the center of the heat exchanger vessel. CO 2 leak events in the heat exchanger have been also evaluated, and it revealed that no significant effect has arisen on the core or the primary sodium boundary. (author)

Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations

International Nuclear Information System (INIS)

Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Bruna, Giovanni; Hache, Georges; Repussard, Jacques

2012-01-01

The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

Key Factors for the Linkage Strategy between R and D and Commercialization for Gen-ΙV

International Nuclear Information System (INIS)

Lee, Kyoungmi; Hong, Jung Suk

2013-01-01

The Fukushima nuclear disaster has leaded to enhance the safety and the cost-effectiveness of technology for the future so that advanced countries such as United Sates and France have concerned about a next generation nuclear power plant, Gen-IV(Generation-IV Reactor). Considering various characteristics of nuclear R and D, it is necessary to have more elaborated strategies for the effective development of the next generation of nuclear technology. In this study, we suggest 5 key factors for the successful commercialization of Gen-IV by analyzing the distinct characteristics of nuclear R and D with Gen-IV and CSF(Critical Success Factor)s of several cases in these field and conducting the FGI(Focus Group Interview). Considering these results, we could find and suggest some important points for further strategy for Gen-IV. That is, following five key factors for the linkage improvement between R and D and commercialization of Gen-IV should be considered: the participation of nuclear power plant operators from the beginning, the establishment of consistent and comprehensive plan/roadmap/detailed strategy, the technology development based on global energy issues and international cooperation, the stable and clear funding plans for long-term projects, the cooperation of relative ministries. Gen-IV system is getting a positive response in that it accompanies long-term R and D plans in Korea. We think that the standard of Gen-IV would lead the next generation of nuclear industry if the proper strategy for the cooperation between the private sector and the regulation from the beginning. Moreover, we expect that this study will facilitate its development process from R and D to commercialization

Key Factors for the Linkage Strategy between R and D and Commercialization for Gen-ΙV

Energy Technology Data Exchange (ETDEWEB)

Lee, Kyoungmi; Hong, Jung Suk [Korean Institute of S and T Evaluation and Planning, Seoul (Korea, Republic of)

2013-05-15

The Fukushima nuclear disaster has leaded to enhance the safety and the cost-effectiveness of technology for the future so that advanced countries such as United Sates and France have concerned about a next generation nuclear power plant, Gen-IV(Generation-IV Reactor). Considering various characteristics of nuclear R and D, it is necessary to have more elaborated strategies for the effective development of the next generation of nuclear technology. In this study, we suggest 5 key factors for the successful commercialization of Gen-IV by analyzing the distinct characteristics of nuclear R and D with Gen-IV and CSF(Critical Success Factor)s of several cases in these field and conducting the FGI(Focus Group Interview). Considering these results, we could find and suggest some important points for further strategy for Gen-IV. That is, following five key factors for the linkage improvement between R and D and commercialization of Gen-IV should be considered: the participation of nuclear power plant operators from the beginning, the establishment of consistent and comprehensive plan/roadmap/detailed strategy, the technology development based on global energy issues and international cooperation, the stable and clear funding plans for long-term projects, the cooperation of relative ministries. Gen-IV system is getting a positive response in that it accompanies long-term R and D plans in Korea. We think that the standard of Gen-IV would lead the next generation of nuclear industry if the proper strategy for the cooperation between the private sector and the regulation from the beginning. Moreover, we expect that this study will facilitate its development process from R and D to commercialization.

Conceptual Design on Primary Control Rod Drive Mechanism of a Prototype Gen-IV SFR

International Nuclear Information System (INIS)

Lee, Jae Han; Koo, Gyeong Hoi

2013-01-01

This paper describes the key concept of the drive mechanism, and suggests a required motor power and reducer gears to meet the functional design requirements, and a seismic response analysis of CRDM housing is performed to check its structural integrity. An AC servo motor is selected as a CRA driving power because it uses permanent magnets and is brushless type while DC motor needs a brush and a coil rotates. The control shim motor size is constrained by a housing diameter of 250mm. The driving system has several design requirements. To calculate the motor power, the drive shaft torque is needed. One part of the drive shaft has a lead screw, driving by a ball-nut. The ball screw driver torque (Tr) is calculated by some equations as follow; A servo motor with a nominal power of 100W, a nominal torque of 0.32 N-m (max. 0.48N-m) is selected considering a safety margin. Its diameter is about 50mm. The fast drive-in motor needs a strong power to insert enforcedly the stuck CRA into core within a required time. The motor sizes are calculated by the same procedure. The diameters are in the range of 80mm to 110mm by the insertion time (10 ∼ 24 seconds). The prototype Gen-IV SFR (sodium-cooled Fast Reactor) is of 150MWe capacity. The reactor has six primary control rod assemblies(CRAs). The primary control rod is used for power control, burn-up compensation and reactor shutdown in response to demands from the plant control or protection systems. The control rod drive mechanism (CRDM) consists of the drive motor assembly, the driveline, and its housing. The driveline consists of three concentric members of a drive shaft, a tension tube, and a position indicator rod, and it connects the drive motor assembly to the CRA. Main issue is that these many driving parts shall be enclosed within a limited housing diameter because the available pitch of CRDMs is limited by 300mm

Conceptual Design on Primary Control Rod Drive Mechanism of a Prototype Gen-IV SFR

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae Han; Koo, Gyeong Hoi [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

This paper describes the key concept of the drive mechanism, and suggests a required motor power and reducer gears to meet the functional design requirements, and a seismic response analysis of CRDM housing is performed to check its structural integrity. An AC servo motor is selected as a CRA driving power because it uses permanent magnets and is brushless type while DC motor needs a brush and a coil rotates. The control shim motor size is constrained by a housing diameter of 250mm. The driving system has several design requirements. To calculate the motor power, the drive shaft torque is needed. One part of the drive shaft has a lead screw, driving by a ball-nut. The ball screw driver torque (Tr) is calculated by some equations as follow; A servo motor with a nominal power of 100W, a nominal torque of 0.32 N-m (max. 0.48N-m) is selected considering a safety margin. Its diameter is about 50mm. The fast drive-in motor needs a strong power to insert enforcedly the stuck CRA into core within a required time. The motor sizes are calculated by the same procedure. The diameters are in the range of 80mm to 110mm by the insertion time (10 ∼ 24 seconds). The prototype Gen-IV SFR (sodium-cooled Fast Reactor) is of 150MWe capacity. The reactor has six primary control rod assemblies(CRAs). The primary control rod is used for power control, burn-up compensation and reactor shutdown in response to demands from the plant control or protection systems. The control rod drive mechanism (CRDM) consists of the drive motor assembly, the driveline, and its housing. The driveline consists of three concentric members of a drive shaft, a tension tube, and a position indicator rod, and it connects the drive motor assembly to the CRA. Main issue is that these many driving parts shall be enclosed within a limited housing diameter because the available pitch of CRDMs is limited by 300mm.

Current status of NPP generation IV

International Nuclear Information System (INIS)

Yohanes Dwi Anggoro; Dharu Dewi; Nurlaila; Arief Tris Yuliyanto

2013-01-01

Today development of nuclear technology has reached the stage of research and development of Generation IV nuclear power plants (advanced reactor systems) which is an innovative development from the previous generation of nuclear power plants. There are six types of power generation IV reactors, namely: Very High Temperature Reactor (VHTR), Sodium-cooled Fast Reactor (SFR), Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), and Super Critical Water-cooled Reactor (SCWR). The purpose of this study is to know the development of Generation IV nuclear power plants that have been done by the thirteen countries that are members of the Gen IV International Forum (GIF). The method used is review study and refers to various studies related to the current status of research and development of generation IV nuclear power. The result of this study showed that the systems and technology on Generation IV nuclear power plants offer significant advances in sustainability, safety and reliability, economics, and proliferation resistance and physical protection. In addition, based on the research and development experience is estimated that: SFR can be used optimally in 2015, VHTR in 2020, while NPP types GFR, LFR, MSR, and SCWR in 2025. Utilization of NPP generation IV said to be optimal if fulfill the goal of NPP generation IV, such as: capable to generate energy sustainability and promote long-term availability of nuclear fuel, minimize nuclear waste and reduce the long term stewardship burden, has an advantage in the field of safety and reliability compared to the previous generation of NPP and VHTR technology have a good prospects in Indonesia. (author)

Preliminary conceptual design of the secondary sodium circuit-eliminated JSFR (Japan Sodium Fast Reactor) adopting a supercritical CO2 turbine system (2). Turbine system and plant size

International Nuclear Information System (INIS)

Kisohara, Naoyuki; Sakamoto, Yoshihiko; Kotake, Shoji

2014-09-01

Research and development of the supercritical CO 2 (S-CO 2 ) cycle turbine system is underway in various countries for further improvement of the safety and economy of sodium-cooled fast reactors. The Component Design and Balance-Of-Plant (CD and BOP) of the Generation IV International Nuclear Forum (Gen-IV) has addressed this study, and their analytical and experimental results have been discussed between the relevant countries. JAEA, who is a member of the CD and BOP, has performed a design study of an S-CO 2 gas turbine system applied to the Japan Sodium-cooled Fast Reactor (JSFR). In this study, the S-CO 2 cycle turbine system was directly connected to the primary sodium system of the JSFR to eliminate the secondary sodium circuit, aiming for further economical improvement. This is because there is no risk of sodium-water reaction in the S-CO 2 cycle turbine system of SFRs. This report describes the system configuration, heat/mass balance, and main components of the S-CO 2 turbine system, based on the JSFR specifications. The layout of components and piping in the reactor and turbine buildings were examined and the dimensions of the buildings were estimated. The study has revealed that the reactor and turbine buildings could be reduced by 7% and 40%, respectively, in comparison with those in the existing JSFR design with the secondary sodium circuit employing the steam turbine. The cycle thermal was also calculated as 41.9-42.3%, which is nearly the same as that of the JSFR with the water/steam system. (author)

Progress of thermal hydraulic evaluation methods and experimental studies on a sodium-cooled fast reactor and its safety in Japan

Energy Technology Data Exchange (ETDEWEB)

Kamide, Hideki, E-mail: kamide.hideki@jaea.go.jp; Ohshima, Hiroyuki, E-mail: ohshima.hiroyuki@jaea.go.jp; Sakai, Takaaki, E-mail: sakai.takaaki@jaea.go.jp; Tanaka, Masaaki, E-mail: tanaka.masaaki@jaea.go.jp

2017-02-15

Highlights: • Thermal hydraulic issues for safety design criteria of sodium cooled fast reactors. • Measurement of velocity data in a subchannel surrounded by wire wrapped fuel-pins. • Statistical evaluation of core hot spot temperature during natural circulation. • Simulation of dynamics of molten fuel pool in a core disruptive accident. • V&V procedure of a multi-dimensional thermal hydraulic code on thermal striping. - Abstract: In the framework of the Generation-IV International Forum, the safety design criteria (SDC) incorporating safety-related R&D results on innovative technologies and lessons learned from Fukushima Dai-ichi nuclear power plants accident has been established to provide the set of general criteria for the safety designs of structures, systems and components of Generation-IV Sodium-cooled Fast Reactors (Gen-IV SFRs). A number of thermal-hydraulic evaluations are necessary to meet the concept of the criteria in the design studies of Gen-IV SFRs. This paper focuses on four kinds of thermal-hydraulic issues associated with the SDC, i.e., fuel subassembly thermal-hydraulics, natural circulation decay heat removal, core disruptive accidents, and thermal striping. Progress of evaluation methods on these issues is shown with activities on verification and validation (V&V) and experimental studies towards commercialization of SFR in Japan. These evaluation methods are planned to be eventually integrated into a comprehensive numerical simulation system that can be applied to all possible phenomena in SFR systems and that can be expected to become an effective tool for the development of human resource and the handing our knowledge and technologies down.

Stability of i.v. admixture containing metoclopramide, diphenhydramine hydrochloride, and dexamethasone sodium phosphate in 0.9% sodium chloride injection.

Science.gov (United States)

Kintzel, Polly E; Zhao, Ting; Wen, Bo; Sun, Duxin

2014-12-01

The chemical stability of a sterile admixture containing metoclopramide 1.6 mg/mL, diphenhydramine hydrochloride 2 mg/mL, and dexamethasone sodium phosphate 0.16 mg/mL in 0.9% sodium chloride injection was evaluated. Triplicate samples were prepared and stored at room temperature without light protection for a total of 48 hours. Aliquots from each sample were tested for chemical stability immediately after preparation and at 1, 4, 8, 24, and 48 hours using liquid chromatography-tandem mass spectrometry (LC-MS/MS) analysis. Metoclopramide, diphenhydramine hydrochloride, and dexamethasone sodium phosphate were selectively monitored using multiple-reaction monitoring. Samples were diluted differently for quantitation using three individual LC-MS/MS methods. To determine the drug concentration of the three compounds in the samples, three calibration curves were constructed by plotting the peak area or the peak area ratio versus the concentration of the calibration standards of each tested compound. Apixaban was used as an internal standard. Linearity of the calibration curve was evaluated by the correlation coefficient r(2). Constituents of the admixture of metoclopramide 1.6 mg/mL, diphenhydramine hydrochloride 2 mg/mL, and dexamethasone sodium phosphate 0.16 mg/mL in 0.9% sodium chloride injection retained more than 90% of their initial concentrations over 48 hours of storage at room temperature without protection from light. The observed variability in concentrations of these three compounds was within the limits of assay variability. An i.v. admixture containing metoclopramide 1.6 mg/mL, diphenhydramine hydrochloride 2 mg/mL, and dexamethasone sodium phosphate 0.16 mg/mL in 0.9% sodium chloride injection was chemically stable for 48 hours when stored at room temperature without light protection. Copyright © 2014 by the American Society of Health-System Pharmacists, Inc. All rights reserved.

ASTRID: Advanced Sodium Technological Reactor for Industrial Demonstration

International Nuclear Information System (INIS)

Vasile, A.

2012-01-01

Conclusions: • R&D results [CEA-AREVA-EDF] obtained from 2007 to 2009 have contributed to ASTRID mid 2010 choice of options; • ASTRID has the objective to demonstrate at the industrial scale progress in the identified domains of SFR weakness (safety, operability, economy). and to perform transmutation demonstrations; • A lot of improvements are related to safety; • The first very important milestone is 2012 (June 2006 French Act on wastes management): – ASTRID pre-conceptual design studies: 2010-2012; – First investment cost evaluation; – First safety Authorities advice on the orientations for ASTRID safety; • With the ASTRID program funded by the French government, France has the opportunity to develop a GEN IV Sodium Fast Reactor

Overview of materials R and D for fusion and Gen-4

Energy Technology Data Exchange (ETDEWEB)

Kohyama, A. [Kyoto Univ., lnstitute of Advanced Energy (Japan); Tavassoli, F.; Carre, F.; Billot, P. [CEA Saclay, 91 - Gif sur Yvette (France); Zinide, S. [Oak Ridge National Laboratory, Materials Science and Technology Div., AK TN (United States)

2007-07-01

Full text of publication follows: In view of the growing need for energy, the risk of exhaustion of fossil fuel and the problem of global warming, the nuclear energy is receiving added attention as a realistic and viable advanced solution. International collaborations on Generation IV (Gen-IV) fission reactors and on ITER and DEMO fusion reactors are developing. This is particularly the case in the sector of materials, where they hold the key to success of these systems. The international community has recognized and planned its materials R and D work for Fusion and Gen-IV reactors with the following considerations: 1- The time allotted to materials R and D is short and may not allow development of totally new materials. 2- Activities required, to cover existing materials variations and service conditions necessary for reactor design, are very time consuming. 3- The work to be done must build upon the existing knowledge of materials and avoid duplications. Although ITER for fusion and Generation four International Forum (GIF) for Gen-IV are important international collaborative programs, they are insufficient to meet all the national energy policies of the participating countries. This paper provides an overview of the materials R and D carried out for fusion and Gen-IV reactors at international and national levels. Materials programs discussed include both cross-cutting and reactor specific actions, where major tasks can be defined as: + Cross-cutting materials tasks: - materials for high temperature service; - materials with neutron damage tolerance; - materials behavior analysis and modeling; - high temperature design methodology. + Reactor specific materials tasks: - very high temperature alloys; - carbon, high temperature ceramics and their composites; - materials compatibilities. Starting with a brief introduction of materials R and D strategies, ITER and Broader Approach (BA), overall activities for fusion and GIF for Gen-IV will be reviewed. Domestic

Innovative technologies on fuel assemblies cleaning for sodium fast reactors: First considerations on cleaning process

International Nuclear Information System (INIS)

Simon, N.; Lorcet, H.; Beauchamp, F.; Guigues, E.; Lovera, P.; Fleche, J. L.; Lacroix, M.; Carra, O.; Dechelette, F.; Prele, G.; Rodriguez, G.

2012-01-01

Within the framework of Sodium Fast Reactor development, innovative fuel assembly cleaning operations are investigated to meet the GEN IV goals of safety and of process development. One of the challenges is to mitigate the Sodium Water Reaction currently used in these processes. The potential applications of aqueous solutions of mineral salts (including the possibility of using redox chemical reactions) to mitigate the Sodium Water Reaction are considered in a first part and a new experimental bench, dedicated to this study, is described. Anhydrous alternative options based on Na/CO 2 interaction are also presented. Then, in a second part, a functional study conducted on the cleaning pit is proposed. Based on experimental feedback, some calculations are carried out to estimate the sodium inventory on the fuel elements, and physical methods like hot inert gas sweeping to reduce this inventory are also presented. Finally, the implementation of these innovative solutions in cleaning pits is studied in regard to the expected performances. (authors)

Innovative technologies on fuel assemblies cleaning for sodium fast reactors: First considerations on cleaning process

Energy Technology Data Exchange (ETDEWEB)

Simon, N.; Lorcet, H.; Beauchamp, F.; Guigues, E. [CEA, DEN, DTN Cadarache, F-13108 Saint-Paul-lez-Durance (France); Lovera, P.; Fleche, J. L. [CEA, DEN, DPC Saclay, F-91191 Gif-sur-Yvette (France); Lacroix, M. [CEA, DEN, DTN Cadarache, F-13108 Saint-Paul-lez-Durance (France); Carra, O. [AREVA / NP, 10 Rue Juliette Recamier, 69003 Lyon (France); Dechelette, F. [CEA, DEN, DTN Cadarache, F-13108 Saint-Paul-lez-Durance (France); Prele, G. [EDF/SEPTEN, 12-14 avenue Dutrievoz, 69628 Villeurbane Cedex (France); Rodriguez, G. [CEA, DEN, DTN Cadarache, F-13108 Saint-Paul-lez-Durance (France)

2012-07-01

Within the framework of Sodium Fast Reactor development, innovative fuel assembly cleaning operations are investigated to meet the GEN IV goals of safety and of process development. One of the challenges is to mitigate the Sodium Water Reaction currently used in these processes. The potential applications of aqueous solutions of mineral salts (including the possibility of using redox chemical reactions) to mitigate the Sodium Water Reaction are considered in a first part and a new experimental bench, dedicated to this study, is described. Anhydrous alternative options based on Na/CO{sub 2} interaction are also presented. Then, in a second part, a functional study conducted on the cleaning pit is proposed. Based on experimental feedback, some calculations are carried out to estimate the sodium inventory on the fuel elements, and physical methods like hot inert gas sweeping to reduce this inventory are also presented. Finally, the implementation of these innovative solutions in cleaning pits is studied in regard to the expected performances. (authors)

Improvement of Sodium Neutronic Nuclear Data for the Computation of Generation IV Reactors

International Nuclear Information System (INIS)

Archier, P.

2011-01-01

The safety criteria to be met for Generation IV sodium fast reactors (SFR) require reduced and mastered uncertainties on neutronic quantities of interest. Part of these uncertainties come from nuclear data and, in the particular case of SFR, from sodium nuclear data, which show significant differences between available international libraries (JEFF-3.1.1, ENDF/B-VII.0, JENDL-4.0). The objective of this work is to improve the knowledge on sodium nuclear data for a better calculation of SFR neutronic parameters and reliable associated uncertainties. After an overview of existing 23 Na data, the impact of the differences is quantified, particularly on sodium void reactivity effects, with both deterministic and stochastic neutronic codes. Results show that it is necessary to completely re-evaluate sodium nuclear data. Several developments have been made in the evaluation code Conrad, to integrate new nuclear reactions models and their associated parameters and to perform adjustments with integral measurements. Following these developments, the analysis of differential data and the experimental uncertainties propagation have been performed with Conrad. The resolved resonances range has been extended up to 2 MeV and the continuum range begins directly beyond this energy. A new 23 Na evaluation and the associated multigroup covariances matrices were generated for future uncertainties calculations. The last part of this work focuses on the sodium void integral data feedback, using methods of integral data assimilation to reduce the uncertainties on sodium cross sections. This work ends with uncertainty calculations for industrial-like SFR, which show an improved prediction of their neutronic parameters with the new evaluation. (author) [fr

Report on generation IV technical working group 3 : liquid metal reactors

International Nuclear Information System (INIS)

Lineberry, M. J.; Rosen, S. L.; Sagayama, Y.

2002-01-01

This paper reports on the first round of R and D roadmap activities of the Generation IV (Gen IV) Technical Working Group (TWG) 3, on liquid metal-cooled reactors. Liquid metal coolants give rise to fast spectrum systems, and thus the reactor systems considered in this TWG are all fast reactors. Gas-cooled fast reactors are considered in the context of TWG 2. As is noted in other Gen IV papers, this first round activity is termed ''screening for potential'', and includes collecting the most complete set of liquid metal reactor/fuel cycle system concepts possible and evaluating the concepts against the Gen IV principles and goals. Those concepts or concept groups that meet the Gen IV principles and which are deemed to have reasonable potential to meet the Gen IV goals will pass to the next round of evaluation. Although we sometimes use the terms ''reactor'' or ''reactor system'' by themselves, the scope of the investigation by TWG 3 includes not only the reactor systems, but very importantly the closed fuel recycle system inevitably required by fast reactors. The response to the DOE Request for Information (RFI) on liquid metal reactor/fuel cycle systems from principal investigators, laboratories, corporations, and other institutions, was robust and gratifying. Thirty three liquid metal concept descriptions, from eight different countries, were ultimately received. The variation in the scope, depth, and completeness of the responses created a significant challenge for the group, but the TWG made a very significant effort not to screen out concepts early in the process

Nordic Nuclear Materials Forum for Generation IV Reactors

Energy Technology Data Exchange (ETDEWEB)

Anghel, C. (Studsvik Nuclear AB, Nykoeping (Sweden)); Penttilae, S. (Technical Research Centre of Finland, VTT (Finland))

2010-03-15

A network for material issues for Generation IV nuclear power has been initiated within the Nordic countries. The objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) are to put the basis of a sustainable forum for Gen IV issues, especially focussing on fuels, cladding, structural materials and coolant interaction. Other issues include reactor physics, dynamics and diagnostics, core and fuel design. The present report summarizes the work performed during the year 2009. The efforts made include identification of organisations involved in Gen IV issues in the Nordic countries, update of the forum website, http://www.studsvik.se/GenerationIV, and investigation of capabilities for research within the area of Gen IV. Within the NOMAGE4 project a seminar on Generation IV Nuclear Energy Systems has been organized during 15-16th of October 2009. The aim of the seminar was to provide a forum for exchange of information, discussion on future research needs and networking of experts on Generation IV reactor concepts. As an outcome of the NOMAGE4, a few collaboration project proposals have been prepared/planned in 2009. The network was welcomed by the European Commission and was mentioned as an exemplary network with representatives from industries, universities, power companies and research institutes. NOMAGE4 has been invited to participate to the 'European Energy Research Alliance, EERA, workshop for nuclear structural materials' http://www.eera-set.eu/index.php?index=41 as external observers. Future plans include a new Nordic application for continuation of NOMAGE4 network. (author)

Nordic Nuclear Materials Forum for Generation IV Reactors

International Nuclear Information System (INIS)

Anghel, C.; Penttilae, S.

2010-03-01

A network for material issues for Generation IV nuclear power has been initiated within the Nordic countries. The objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) are to put the basis of a sustainable forum for Gen IV issues, especially focussing on fuels, cladding, structural materials and coolant interaction. Other issues include reactor physics, dynamics and diagnostics, core and fuel design. The present report summarizes the work performed during the year 2009. The efforts made include identification of organisations involved in Gen IV issues in the Nordic countries, update of the forum website, http://www.studsvik.se/GenerationIV, and investigation of capabilities for research within the area of Gen IV. Within the NOMAGE4 project a seminar on Generation IV Nuclear Energy Systems has been organized during 15-16th of October 2009. The aim of the seminar was to provide a forum for exchange of information, discussion on future research needs and networking of experts on Generation IV reactor concepts. As an outcome of the NOMAGE4, a few collaboration project proposals have been prepared/planned in 2009. The network was welcomed by the European Commission and was mentioned as an exemplary network with representatives from industries, universities, power companies and research institutes. NOMAGE4 has been invited to participate to the 'European Energy Research Alliance, EERA, workshop for nuclear structural materials' http://www.eera-set.eu/index.php?index=41 as external observers. Future plans include a new Nordic application for continuation of NOMAGE4 network. (author)

Design Evaluation of Thermal-hydraulic Test Facility for a Finned-tube Sodium-to-Air Heat Exchanger

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyungmo; Kim, Byeong-Yeon; Ko, Yung Joo; Cho, Youngil; Kim, Jong-Man; Son, Seok-Kwon; Jo, Youngchul; Kang, Byeong Su; Jung, Minhwan; Eoh, Jaehyuk; Lee, Hyeong-Yeon; Jeong, Ji-Young [KAERI, Daejeon (Korea, Republic of)

2016-05-15

This paper introduces the recent progress of overall design phase for the SELFA facility and deals with basic thermal-hydraulic design parameters and its design validation as well. For more reliable design of the safety-grade decay heat removal system (DHRS) in PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor), two kinds of sodium-to-air heat exchangers have been employed in the system as an ultimate heat sink. One is a natural draft sodium-to-air heat exchanger (AHX) with helically-coiled sodium tubes, and the other is a forced draft sodium-to-air heat exchanger (FHX) with finned tubes with a straight-type arranged. Since the FHX is normally operated in an active mode with a forced air draft conditions, its performance should be verified for any anticipated operating conditions. To validate the test section design, evaluations of both thermal-hydraulic and mechanical design have been carried out, and some new concepts or devices were newly employed to replicate the prototypic conditions as closely as possible.

Conversion of actinide solutions for the production of MA bearing fuels for Gen IV fast reactor systems

International Nuclear Information System (INIS)

Fernandez, A.; McGinley, J.; Somers, J.

2008-01-01

The conversion of the solution to solid for fuels containing minor actinides for accelerator driven systems or Gen IV fast reactors cannot be made by conventional ammonia or oxalate precipitation as is the case in today's reprocessing plant. The small particle size and concomitant dust that is produced in subsequent processing steps will not permit use of these processes on industrial scale. Innovation is needed to avoid dust generating powders, and indeed to simplify the processes themselves. Two such processing routes have been developed at the JRC-ITU. The sol gel route has been used to produce fuel containing Am and Np for the SUPERFACT, TRABANT and other irradiation experiments. The infiltration process has also been established and fuels have been produced for the FUTURIX and HELIOS experiments. (authors)

Conversion of actinide solutions for the production of MA bearing fuels for Gen IV fast reactor systems

Energy Technology Data Exchange (ETDEWEB)

Fernandez, A.; McGinley, J.; Somers, J. [European Commission, Joint Research Centre, Institute for Transuranium Elements P.O.Box 2340, Karlsruhe, D-76125 (Germany)

2008-07-01

The conversion of the solution to solid for fuels containing minor actinides for accelerator driven systems or Gen IV fast reactors cannot be made by conventional ammonia or oxalate precipitation as is the case in today's reprocessing plant. The small particle size and concomitant dust that is produced in subsequent processing steps will not permit use of these processes on industrial scale. Innovation is needed to avoid dust generating powders, and indeed to simplify the processes themselves. Two such processing routes have been developed at the JRC-ITU. The sol gel route has been used to produce fuel containing Am and Np for the SUPERFACT, TRABANT and other irradiation experiments. The infiltration process has also been established and fuels have been produced for the FUTURIX and HELIOS experiments. (authors)

Conceptual core designs for a 1200 MWe sodium cooled fast reactor

International Nuclear Information System (INIS)

Joo, H. K.; Lee, K. B.; Yoo, J. W.; Kim, Y. I.

2008-01-01

The conceptual core design for a 1200 MWe sodium cooled fast reactor is being developed under the framework of the Gen-IV SFR development program. To this end, three core concepts have been tested during the development of a core concept: a core with an enrichment split fuel, a core with a single-enrichment fuel with a region-wise varying clad thickness, and a core with a single-enrichment fuel with non-fuel rods. In order to optimize a conceptual core configuration which satisfies the design targets, a sensitivity study of the core design parameters has been performed. Two core concepts, the core with an enrichment-split fuel and the core with a single-enrichment fuel with a region-wise varying clad thickness, have been proposed as the candidates of the conceptual core for a 1200 MWe sodium cooled fast reactor. The detailed core neutronic, fuel behavior, thermal, and safety analyses will be performed for the proposed candidate core concepts to finalize the core design concept. (authors)

Development of the Sodium-cooled Fast Reactor R and D and Technology Monitoring System

International Nuclear Information System (INIS)

Lee, Dong Uk; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

2008-01-01

This study presents a R and D performance monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. The prime goal of this system is to furnish project manager with reliable and accurate information of status of progress, performance and resource allocation, and attain traceability and visibility of project implementation for effective project management. In this study, the work breakdown structure, the related schedule and the expected outputs were established to derive the interfaces between projects and the above parameters was loaded PCs. The R and D performance monitoring system is composed of about 750 R and D activities within 'Development of Basic Key Technologies for Gen IV SFR' project in 2007. The Microsoft Project Professional software was used to monitor the progress, evaluate the results and analyze the resource distribution to activities

Development of the Sodium-cooled Fast Reactor R and D and Technology Monitoring System

Energy Technology Data Exchange (ETDEWEB)

Lee, Dong Uk; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

2008-01-15

This study presents a R and D performance monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. The prime goal of this system is to furnish project manager with reliable and accurate information of status of progress, performance and resource allocation, and attain traceability and visibility of project implementation for effective project management. In this study, the work breakdown structure, the related schedule and the expected outputs were established to derive the interfaces between projects and the above parameters was loaded PCs. The R and D performance monitoring system is composed of about 750 R and D activities within 'Development of Basic Key Technologies for Gen IV SFR' project in 2007. The Microsoft Project Professional software was used to monitor the progress, evaluate the results and analyze the resource distribution to activities.

Enhanced radiation resistance through interface modification of nano-structured steels for Gen IV in-core applications

International Nuclear Information System (INIS)

Jang, Jinsung; Kang, Suk Hoon; Kim, Min Chul

2013-06-01

This project is to increase radiation tolerance of candidate alloys for Gen IV core component through the optimization of grain size and grain boundary characteristics. The focus is on nanocrystalline metal alloys with a fcc crystal structure. The long-term goal is to design and develop bulk nanostructured austenitic steels with enhanced void swelling resistance and substantial ductility, and to enhance their creep resistance at elevated temperatures via grain boundary engineering. An austenitic stainless steel, HT-UPS (high temperature ultra-fine precipitates strengthened) was developed at ORNL, and is expected to show enhanced void swelling resistance through the trapping of point defects at nanometer-sized carbides. Reducing the grain size and increasing the fraction-induced point defects (due to the increased sink area of the grain boundaries), to make bubble nucleation at the boundaries less likely (by reducing the fraction of high-energy boundaries), and to improve the strength and ductility under radiation by producing a higher density of nanometer sized carbides on the boundaries

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

Energy Technology Data Exchange (ETDEWEB)

William E. Kastenberg; Edward Blandford; Lance Kim

2009-03-31

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

International Nuclear Information System (INIS)

Kastenberg, William E.; Blandford, Edward; Kim, Lance

2009-01-01

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public

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.

Gating transitions in the selectivity filter region of a sodium channel are coupled to the domain IV voltage sensor.

Science.gov (United States)

Capes, Deborah L; Arcisio-Miranda, Manoel; Jarecki, Brian W; French, Robert J; Chanda, Baron

2012-02-14

Voltage-dependent ion channels are crucial for generation and propagation of electrical activity in biological systems. The primary mechanism for voltage transduction in these proteins involves the movement of a voltage-sensing domain (D), which opens a gate located on the cytoplasmic side. A distinct conformational change in the selectivity filter near the extracellular side has been implicated in slow inactivation gating, which is important for spike frequency adaptation in neural circuits. However, it remains an open question whether gating transitions in the selectivity filter region are also actuated by voltage sensors. Here, we examine conformational coupling between each of the four voltage sensors and the outer pore of a eukaryotic voltage-dependent sodium channel. The voltage sensors of these sodium channels are not structurally symmetric and exhibit functional specialization. To track the conformational rearrangements of individual voltage-sensing domains, we recorded domain-specific gating pore currents. Our data show that, of the four voltage sensors, only the domain IV voltage sensor is coupled to the conformation of the selectivity filter region of the sodium channel. Trapping the outer pore in a particular conformation with a high-affinity toxin or disulphide crossbridge impedes the return of this voltage sensor to its resting conformation. Our findings directly establish that, in addition to the canonical electromechanical coupling between voltage sensor and inner pore gates of a sodium channel, gating transitions in the selectivity filter region are also coupled to the movement of a voltage sensor. Furthermore, our results also imply that the voltage sensor of domain IV is unique in this linkage and in the ability to initiate slow inactivation in sodium channels.

The generation IV nuclear reactor systems - Energy of future

International Nuclear Information System (INIS)

Ohai, Dumitru; Jianu, Adrian

2006-01-01

Ten nations joined within the Generation IV International Forum (GIF), agreeing on a framework for international cooperation in research. Their goal is to develop future-generation nuclear energy systems that can be licensed, constructed, and operated in an economically competitive way while addressing the issues of safety, proliferation, and other public perception concerns. The objective is for the Gen IV systems to be available for deployment by 2030. Using more than 100 nuclear experts from its 10 member nations, the GIF has developed a Gen IV Technology Roadmap to guide the research and development of the world's most advanced, efficient and safe nuclear power systems. The Gen IV Technology Roadmap calls for extensive research and development of six different potential future reactor systems. These include water-cooled, gas-cooled, liquid metal-cooled and nonclassical systems. One or more of these reactor systems will provide the best combination of safety, reliability, efficiency and proliferation resistance at a competitive cost. The main goals for the Gen IV Nuclear Energy Systems are: - Provide sustainable energy generation that meets clean air objectives and promotes long-term availability of systems and effective fuel use for worldwide energy production; - Minimize and manage their nuclear waste and noticeably reduce the long-term stewardship burden in the future, improving the protection of public health and the environment; - Increase the assurance that these reactors are very unattractive and the least desirable route for diversion or theft of weapons-usable materials, and provide increased protection against acts of terrorism; - Have a clear life-cycle cost advantage over other energy sources; - Have a level of financial risk comparable to other energy projects; - Excel in safety and reliability; - Have a low likelihood and degree of reactor core damage. (authors)

Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations. Published on September 24, 2012

International Nuclear Information System (INIS)

Couturier, Jean; Bruna, Giovanni; Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Hache, Georges

2012-01-01

The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

Association between continuous peripheral i.v. infusion of 3% sodium chloride injection and phlebitis in adults.

Science.gov (United States)

Meng, Lina; Nguyen, Cherwyn M; Patel, Samit; Mlynash, Michael; Caulfield, Anna Finley

2018-03-01

One institution's experience with use of peripheral i.v. (PIV) catheters for prolonged infusions of 3% sodium chloride injection at rates up to 100 mL/hr is described. A prospective, observational, 13-month quality assurance project was conducted at an academic medical center to evaluate frequencies of patient and catheter phlebitis among adult inpatients who received both an infusion of 3% sodium chloride injection for a period of ≥4 hours through a dedicated PIV catheter and infusions of routine-care solutions (RCSs) through separate PIV catheters during the same hospital stay. Sixty patients received PIV infusions through a total of 291 catheters during the study period. The majority of patients (78%) received infusions of 3% sodium chloride injection for intracranial hypertension, with 30% receiving such infusions in the intensive care unit. Phlebitis occurred in 28 patients (47%) during infusions of 3% sodium chloride and 26 patients (43%) during RCS infusions ( p = 0.19). Catheter phlebitis occurred in 73 catheters (25%), with no significant difference in the frequencies of catheter phlebitis with infusion of 3% sodium chloride versus RCSs (30% [32 of 106 catheters]) versus 22% [41 of 185 catheters]), p = 0.16). Patient and catheter phlebitis rates were not significantly different with infusions of 3% sodium chloride injection versus RCSs, suggesting that an osmolarity cutoff value of 900 mOsm/L for peripheral infusions of hypertonic saline solutions may not be warranted. Copyright © 2018 by the American Society of Health-System Pharmacists, Inc. All rights reserved.

Nordic forum for generation IV reactors, status and activities in 2012

International Nuclear Information System (INIS)

Van Nieuwenhove, R.; Lauritzen, B.; Nonboel, E.

2012-12-01

The Nordic-Gen4 (continuation from NOMAGE4) seminar was this year hosted by DTU Nutech at Risoe, Denmark. The seminar was well attended (49 participants from 12 countries). The presentations covered many aspects in Gen-IV reactor research and gave a good overview of the activities within this field at the various institutes and universities. The present report contains book of abstracts. The individual Power Point presentations are indexed in INIS and may be found at http://nordic-gen4.org/seminars/nordic-gen4-riso-2012-2/ (LN)

Nordic forum for generation IV reactors, status and activities in 2012

Energy Technology Data Exchange (ETDEWEB)

Van Nieuwenhove, R. [Institutt for Energiteknikk, OECD Halden Reactor Project, Kjeller (Norway); Lauritzen, B.; Nonboel, E. [Technical Univ. of Denmark. DTU Nutech, Roskilde (Denmark)

2012-12-15

The Nordic-Gen4 (continuation from NOMAGE4) seminar was this year hosted by DTU Nutech at Risoe, Denmark. The seminar was well attended (49 participants from 12 countries). The presentations covered many aspects in Gen-IV reactor research and gave a good overview of the activities within this field at the various institutes and universities. The present report contains book of abstracts. The individual Power Point presentations are indexed in INIS and may be found at http://nordic-gen4.org/seminars/nordic-gen4-riso-2012-2/ (LN)

Common molecular determinants of tarantula huwentoxin-IV inhibition of Na+ channel voltage sensors in domains II and IV.

Science.gov (United States)

Xiao, Yucheng; Jackson, James O; Liang, Songping; Cummins, Theodore R

2011-08-05

The voltage sensors of domains II and IV of sodium channels are important determinants of activation and inactivation, respectively. Animal toxins that alter electrophysiological excitability of muscles and neurons often modify sodium channel activation by selectively interacting with domain II and inactivation by selectively interacting with domain IV. This suggests that there may be substantial differences between the toxin-binding sites in these two important domains. Here we explore the ability of the tarantula huwentoxin-IV (HWTX-IV) to inhibit the activity of the domain II and IV voltage sensors. HWTX-IV is specific for domain II, and we identify five residues in the S1-S2 (Glu-753) and S3-S4 (Glu-811, Leu-814, Asp-816, and Glu-818) regions of domain II that are crucial for inhibition of activation by HWTX-IV. These data indicate that a single residue in the S3-S4 linker (Glu-818 in hNav1.7) is crucial for allowing HWTX-IV to interact with the other key residues and trap the voltage sensor in the closed configuration. Mutagenesis analysis indicates that the five corresponding residues in domain IV are all critical for endowing HWTX-IV with the ability to inhibit fast inactivation. Our data suggest that the toxin-binding motif in domain II is conserved in domain IV. Increasing our understanding of the molecular determinants of toxin interactions with voltage-gated sodium channels may permit development of enhanced isoform-specific voltage-gating modifiers.

Development of Basic Key Technologies for Gen IV SFR Safety Evaluation

International Nuclear Information System (INIS)

Jeong, Hae Yong; Kwon, Young Min; Kim, Tae Woon; Park, Soo Yong; Suk, Soo Dong; Lee, Kwi Lim; Lee, Yong Bum; Chang, Won Pyo; Ha, Kwi Seok; Hahn, Sang Hoon

2010-07-01

Safety issues and design requirements on control rod worth were identified through the evaluation of safety design characteristics and the preliminary safety evaluation. This results will be taken into account for the conceptual design studies of the demonstration reactor in the next stage. The Level-1 Pasa has been performed and a quantitative Cdf value was produced for the selected design from the several candidates. The inherent safety characteristics of the selected design were evaluated through the DBE and ATWS analyses. A surrogate material for Tru has been selected which is applicable to the study of liquidus/solidus temperature test for the metallic fuel containing Tru. A methodology for the regression analysis with surrogate material has been developed and valuable data on metal fuel liquidus/solidus temperature have been measured. A simple mechanistic model describing a bending of subassemblies has been formulated based on the foreign test data and existing models. Its applicability has been evaluated for the Phenix design. New criteria of the core damage for the SFR PSA were identified. The list of initiating events, system response event tree, and core response event tree, which constitute a PSA methodology for an SFR, have been introduced. By developing the SFR PIRT, phenomenological model features, which have to be satisfied in a safety code, were defined and the PIRT results were applied to the design of the PDRC test facility. Bases for a safety evaluation methodology for the SFR DBEs have been also prepared. A draft version of the topical report on the code for local fault analysis has been completed. Since 2007, the MARS-LMR code has been developed and assessments for model validation with the test data from EBR-II and Phenix reactor have been continued. The code has been applied to the evaluation of passive safety of a conceptual design of Gen IV SFR

New Materials for NGNP/Gen IV

International Nuclear Information System (INIS)

Swindeman, Robert W.; Marriott, Douglas L.

2009-01-01

The bounding conditions were briefly summarized for the Next Generation Nuclear Plant (NGNP) that is the leading candidate in the Department of Energy Generation IV reactor program. Metallic materials essential to the successful development and proof of concept for the NGNP were identified. The literature bearing on the materials technology for high-temperature gas-cooled reactors was reviewed with emphasis on the needs identified for the NGNP. Several materials were identified for a more thorough study of their databases and behavioral features relative to the requirements ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NH.

Evaluation of a sodium-water reaction event caused by steam generator tubes break in the prototype generation IV sodium-cooled fast reactor

Energy Technology Data Exchange (ETDEWEB)

Ahn, Sang June; Ha, Kwi Seok; Chang, Won Pyo; Kang, Seok Hun; Lee, Kwi Lim; Choi, Chi Woong; Lee, Seung Won; Yoo, Jin; Jeong, Jae Ho; Jeong, Tae Kyeong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-08-15

The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. Sodium has chemical characteristics that allow it to violently react with materials such as a water or steam. When a sodium–water reaction (SWR) occurs due to leakage or breakage of steam generator tubes, high-pressure waves and corrosive reaction products are produced, which threaten the structural integrity of the components of the intermediate heat-transfer system (IHTS) and the safety of the primary heat-transfer system (PHTS). In the PGSFR, SWR events are included in the design-basis event. This event should be analyzed from the viewpoint of the integrities of the IHTS and fuel rods. To evaluate the integrity of the IHTS based on the consequences of the SWR, the behaviors of the generated high-pressure waves are analyzed at the major positions of a failed IHTS loop using a sodium–water advanced analysis method-II code. The integrity of the fuel rods must be consistently maintained below the safety acceptance criteria to avoid the consequences of the SWR. The integrity of the PHTS is evaluated using the multidimensional analysis of reactor safety-liquid metal reactor code to model the whole plant.

A Review of PSA Technology Applications according to the Development of Sodium-cooled Fast Reactors in the World

International Nuclear Information System (INIS)

Kim, Tae Woon; Lee, Yong Bum; Jung, Hae Yong; Kim, Sang Ji; Hahn, Do Hee; Yang, Joon Eon

2008-12-01

The international nuclear societies request to perform Probabilistic Safety Assessment (PSA) according to the development of Gen IV Sodium-cooled Fast Reactors (SFR). One of the major tasks of the PSA is to identify various sequences of events which could lead to the release of radioactivity. However, due to the limited operating and SFR PSA experiences, it will be difficult to derive and to quantify core damage frequency for SFR under development in Korea, so called KALIMER. Hence, in this report, the foreign PSA results, such as USA and Japan, are analyzed based on the obtained documents. Finally an approach on how to perform PSA for KALIMER is suggested

Policy-induced market introduction of Generation IV reactor systems

International Nuclear Information System (INIS)

Heek, Aliki Irina van; Roelofs, Ferry

2011-01-01

Almost 10 years ago the U.S. Department of Energy (DOE) started the Generation IV Initiative (GenIV) with 9 other national governments with a positive ground attitude towards nuclear energy. Some of these Generation IV systems, like the fast reactors, are nearing the demonstration stage. The question on how their market introduction will be implemented becomes increasingly urgent. One main topic for future reactor technologies is the treatment of radioactive waste products. Technological solutions to this issue are being developed. One possible process is the transformation of long-living radioactive nuclides into short living ones; a process known as transmutation, which can be done in a nuclear reactor only. Various Generation IV reactor concepts are suitable for this process, and of these systems most experience has been gained with the sodium-cooled fast reactor (SFR). However, both these first generation SFR plants and their Generation IV successors are designed as electricity generating plants, and therefore supposed to be commercially viable in the electricity markets. Various studies indicate that the generation costs of a combined LWR-(S)FR nuclear generating park (LWR: light water reactor) will be higher than that of an LWR-only park. To investigate the effects of the deployment of the different reactors and fuel cycles on the waste produced, resources used and costs incurred as a function of time, a dynamic fuel cycle assessment is performed. This study will focus on the waste impact of the introduction of a fraction of fast reactors in the European nuclear reactor park with a cost increase as described in the previous paragraph. The nuclear fuel cycle scenario code DANESS is used for this, as well as the nuclear park model of the EU-27 used for the previous study. (orig.)

Assessment of Application Example for a Sodium Fire Extinguishing Facility using Safety Control of Dangerous Substances Act

International Nuclear Information System (INIS)

Jung, Minhwan; Jeong, Ji-Young; Kim, Jongman

2014-01-01

Sodium is under regulation of four kinds of laws including the Safety Control of Dangerous Substances Act and it is under categorized as Class 3(pyrophoric material, water-prohibiting substance). To obtain a license for a sodium experiment facility, the codes and regulations must be satisfied in the Safety Control of Dangerous Substance Act. However, there are some parts that need to be discussed in related regulations in the Safety Control of Dangerous Substance Act because there are differences with the actual features of sodium. To apply for an actual sodium facility, it is necessary to give a supplementary explanation regarding the regulations. The objective of this study is to assess the application example of a sodium experiment facility using the above mentioned laws and to propose the necessity of an amendment for conventional laws in regard to fire extinguishing systems and agents. In this work, an application example of a sodium experiment facility using the Safety Control of Dangerous Substances Act, and the necessity of amending the existing laws in regard to fire extinguishing systems including the agent used, was assessed. The safest standard was applied for cases in which the consideration of a sodium fire is not mentioned in conventional regulations. For the construction of the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor), the described regulations in this work should be reviewed and improved carefully by the fire safety regulatory body

A Comparative Study of the Efficacy of IV Dexketoprofen, Lornoxicam, and Diclophenac Sodium on Postoperative Analgesia and Tramadol Consumption in Patients Receiving Patient-Controlled Tramadol.

Science.gov (United States)

Kılıçkaya, Refika; Güleç, Ersel; Ünlügenç, Hakkı; Gündüz, Murat; Işık, Geylan

2015-06-01

This study was designed to compare the effects of dexketoprofen, lornoxicam, and diclophenac sodium on postoperative analgesia and tramadol consumption in patients receiving postoperative patient-controlled tramadol after a major abdominal surgery. Eighty patients were randomized to receive one of the four study drugs. Patients in group dexketoprofen (DT) received IV 50 mg dexketoprofen, group lornoxicam (LR) received IV 8 mg lornoxicam, group diclophenac sodium (DS) received 75 mg IV diclophenac sodium and group saline (S) received 0.9% saline in 2 mL syringes, 20 min before the end of anaesthesia. A standardized (1 mg kg(-1)) dose of tramadol was routinely administered to all patients as the loading dose at the end of surgery. Postoperatively, whenever patients requested, they were allowed to use a tramadol patient-controlled analgesia device giving a bolus dose (0.2 mg kg(-1)) of tramadol. Pain, discomfort, and sedation scores, cumulative tramadol consumption, supplemental meperidine requirement, and side effects were recorded. Visual rating scale and patient discomfort scores were significantly lower in DT, LR and DS groups compared to those in in group S (pdexketoprofen to patient-controlled tramadol resulted in lower pain scores, smaller tramadol consumption, less rescue supplemental analgesic requirement, and fewer side effects compared with the tramadol alone group.

Thermodynamic Data to Model the Interaction Between Coolant and Fuel in Gen IV Sodium Cooled Fast Reactors

International Nuclear Information System (INIS)

Dinsdale, Alan; Gisby, John; Davies, Hugh; Konings, Rudy; Benes, Ondrej

2013-06-01

Understanding the behaviour of nuclear fuels in various environments is vital to the design and safe operation of nuclear reactors. While this is true if the reactor is operating within its design specification, it is even more so if accidents occur and the fuel is exposed to unexpected temperatures, pressures or chemical environments. It is clearly hazardous and costly to explore all such scenarios experimentally and therefore it is necessary to undertake modelling where possible using well-grounded theoretical approaches. This paper will show examples of where calculations of chemical and phase equilibria have been applied successfully to the long term storage of nuclear waste, phase formation during core meltdown and prediction of fission product release into the atmosphere. It will also highlight the development of thermodynamic data carried out during the European Metrology Research Project Metrofission required to model the potential interaction between the coolant, nuclear fuel, containment materials and atmosphere of a sodium cooled fast reactor. (authors)

Generation IV SFR Nuclear Reactors: Under-Sodium Repair for ASTRID

International Nuclear Information System (INIS)

Baque, F.; Chagnot, C.; Bruguiere, L.; Augem, J.M.; Delalande, V.; Sibilo, J.

2013-06-01

For non-removable components of the future ASTRID prototype, repair operations will be performed in a gas environment. If the faulty area is located under the sodium free level, the gas-tight system will have to contain the inspection and repair tools and to protect them from the surrounding liquid sodium. Concerning repair tools, the unique laser tool has been selected for future SFRs: the repair scenario for in-sodium structures will first involve removing the sodium (after bulk draining), then machining and finally welding. Concerning conventional tools (brush or gas blower for sodium removal, milling machine for machining and TIG for welding for which its feasibility was demonstrated in the 1990's) are still considered as a back-up solution. In-pile examination or repair requires robotic carriers. These carriers have to be compatible with the sodium environment: either in the cover-gas plenum or in gas after sodium draining, or even under liquid sodium. This R and D programme has been divided into nine parts in order to provide an overall design of the required robotic carriers and to develop technological solutions for their components: detailed definition for SFR carrier needs (access to internal structures, possible defects to be detected/repaired), definition and specifications of carrier architecture (depending on inspection and repair scenarios), in-sodium leak-tightness of carrier components, carrier material compatibility with sodium, temperature resistance (200 deg. C), irradiation resistance (depending on the location of the main vessel), gas-tight bell for operations under liquid sodium, carrier positioning control in liquid sodium, development, validation and qualification of technological solutions, for future SFRs, and worldwide benchmark regarding the previous areas of investigation. (authors)

Seletividade de herbicidas a genótipos de cana-de-açúcar Herbicide selectivity to sugarcane genotypes

Directory of Open Access Journals (Sweden)

L Galon

2009-12-01

Full Text Available A cultura da cana-de-açúcar, por ter desenvolvimento inicial lento até 60 dias após a emergência, apresenta pouca capacidade competitiva com as plantas daninhas. Por isso, o uso de herbicidas nesse período é prática comum no canavial. No entanto, há variação entre genótipos de cana-de-açúcar na tolerância a herbicidas. Os genótipos pouco tolerantes podem ser intoxicados e, em alguns casos, ocorre redução da produtividade da cana-deaçúcar. Neste trabalho, avaliou-se a tolerância de três genótipos aos herbicidas ametryn, trifloxysulfuron-sodium e à mistura comercial desses, em 0,0, 0,5, 1,0 e 3,0 vezes a dose comercial recomendada. O experimento foi realizado em ambiente protegido. Foi empregado o delineamento experimental inteiramente casualizado, com quatro repetições. Os tratamentos constaram dos genótipos SP80-1816, RB855113 e RB867515, combinados aos herbicidas ametryn, trifloxysulfuron-sodium e ametryn + trifloxysulfuron-sodium, nas doses de 0, 0,5, 1,0 e 3,0 vezes a dose comercial recomendada pelo fabricante. A intoxicação das plantas (% foi avaliada aos 14, 28 e 42 dias após a aplicação dos herbicidas (DAT. As outras variáveis aferidas aos 80 dias após a brotação das gemas foram: área foliar e massa da matéria seca da parte aérea. Em geral, os genótipos SP80-1816 e RB85513 foram menos tolerantes aos herbicidas ametryn, trifloxysulfuron-sodium e à mistura formulada de ametryn + trifloxysulfuron-sodium do que o RB867515 em todas as doses. Eles apresentaram elevados índices de intoxicação aos 14, 28 e 42 dias após a aplicação dos herbicidas. Concluiu-se que o genótipo RB855113 foi o mais sensível aos herbicidas, seguido pelo SP80-1816, sendo o RB867515 o mais tolerante.Due to a slow initial development up to 60 days after emergence, sugarcane shows little competitive capacity over weeds. Thus, the use of herbicides during this period is a common practice in the sugarcane crop. However, there is

Thermal analysis of supercritical CO2 power cycles: Assessment of their suitability to the forthcoming sodium fast reactors

International Nuclear Information System (INIS)

Pérez-Pichel, G.D.; Linares, J.I.; Herranz, L.E.; Moratilla, B.Y.

2012-01-01

Highlights: ► This paper investigates the potential use of S-CO 2 cycles in SFRs. ► A wide range of configurations have been explored. ► It is feasible to reach a thermal efficiency as high as 43.5%. ► A sensitivity analysis together with an exergy study have been done. ► Potential use in SFRs of recompression S-CO 2 cycles for their balance of plant. - Abstract: Sodium fast reactors (SFRs) potential to meet Gen. IV requirements is broadly acknowledged worldwide. The scientific and technological experience accumulated by operating test reactors and, even, by running commercial reactors, makes them be considered as the closest Gen. IV option in the near future. In the past their balance of plant has been always based on Rankine cycles. This paper investigates the potential use of supercritical recompression CO 2 cycles (S-CO 2 ) in SFRs on the basis of the working parameters foreseen within the European Sodium Fast Reactor (ESFR) project. A wide range of configurations have been explored, from the simplest one to combined cycles (with organic Rankine cycles, ORC), and a comparison has been set in terms of thermal efficiency. As a result, it has been found out that the most basic configuration could reach a thermal efficiency as high as 43.31%, which is comparable to that obtained through super-critical Rankine cycles proposed elsewhere. A sensitivity analysis together with an exergy study of this configuration, pointed the pre-cooler and IHX Na–CO 2 as key components in the cycle performance. These results highlight a main conclusion: the potential use in SFRs of recompression S-CO 2 cycles for their balance of plant, whenever a sound and extensive database is built-up on S-CO 2 turbo-machinery and IHX performance.

Tarantula huwentoxin-IV inhibits neuronal sodium channels by binding to receptor site 4 and trapping the domain ii voltage sensor in the closed configuration.

Science.gov (United States)

Xiao, Yucheng; Bingham, Jon-Paul; Zhu, Weiguo; Moczydlowski, Edward; Liang, Songping; Cummins, Theodore R

2008-10-03

Peptide toxins with high affinity, divergent pharmacological functions, and isoform-specific selectivity are powerful tools for investigating the structure-function relationships of voltage-gated sodium channels (VGSCs). Although a number of interesting inhibitors have been reported from tarantula venoms, little is known about the mechanism for their interaction with VGSCs. We show that huwentoxin-IV (HWTX-IV), a 35-residue peptide from tarantula Ornithoctonus huwena venom, preferentially inhibits neuronal VGSC subtypes rNav1.2, rNav1.3, and hNav1.7 compared with muscle subtypes rNav1.4 and hNav1.5. Of the five VGSCs examined, hNav1.7 was most sensitive to HWTX-IV (IC(50) approximately 26 nM). Following application of 1 microm HWTX-IV, hNav1.7 currents could only be elicited with extreme depolarizations (>+100 mV). Recovery of hNav1.7 channels from HWTX-IV inhibition could be induced by extreme depolarizations or moderate depolarizations lasting several minutes. Site-directed mutagenesis analysis indicated that the toxin docked at neurotoxin receptor site 4 located at the extracellular S3-S4 linker of domain II. Mutations E818Q and D816N in hNav1.7 decreased toxin affinity for hNav1.7 by approximately 300-fold, whereas the reverse mutations in rNav1.4 (N655D/Q657E) and the corresponding mutations in hNav1.5 (R812D/S814E) greatly increased the sensitivity of the muscle VGSCs to HWTX-IV. Our data identify a novel mechanism for sodium channel inhibition by tarantula toxins involving binding to neurotoxin receptor site 4. In contrast to scorpion beta-toxins that trap the IIS4 voltage sensor in an outward configuration, we propose that HWTX-IV traps the voltage sensor of domain II in the inward, closed configuration.

Updated Generation IV Reactors Integrated Materials Technology Program Plan, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Halsey, William [Lawrence Livermore National Laboratory (LLNL); Hayner, George [Idaho National Laboratory (INL); Katoh, Yutai [ORNL; Klett, James William [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Stoller, Roger E [ORNL; Wilson, Dane F [ORNL

2005-12-01

The Department of Energy's (DOE's) Generation IV Nuclear Energy Systems Program will address the research and development (R&D) necessary to support next-generation nuclear energy systems. Such R&D will be guided by the technology roadmap developed for the Generation IV International Forum (GIF) over two years with the participation of over 100 experts from the GIF countries. The roadmap evaluated over 100 future systems proposed by researchers around the world. The scope of the R&D described in the roadmap covers the six most promising Generation IV systems. The effort ended in December 2002 with the issue of the final Generation IV Technology Roadmap [1.1]. The six most promising systems identified for next generation nuclear energy are described within the roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor - SCWR and the Very High Temperature Reactor - VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor - GFR, the Lead-cooled Fast Reactor - LFR, and the Sodium-cooled Fast Reactor - SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides, and may provide an alternative to accelerator-driven systems. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural materials needed to ensure their safe and reliable operation. Accordingly, DOE has identified materials as one of the focus areas for Gen IV technology development.

Small angle neutron scattering study of nano sized microstructure in Fe-Cr ODS steels for gen IV in-core applications.

Science.gov (United States)

Han, Young-Soo; Mao, Xiadong; Jang, Jinsung

2013-11-01

The nano-sized microstructures in Fe-Cr oxide dispersion strengthened steel for Gen IV in-core applications were studied using small angle neutron scattering. The oxide dispersion strengthened steel was manufactured through hot isostatic pressing with various chemical compositions and fabrication conditions. Small angle neutron scattering experiments were performed using a 40 m small angle neutron scattering instrument at HANARO. Nano sized microstructures, namely, yttrium oxides and Cr-oxides were quantitatively analyzed by small angle neutron scattering. The yttrium oxides and Cr-oxides were also observed by transmission electron microscopy. The microstructural analysis results from small angle neutron scattering were compared with those obtained by transmission electron microscopy. The effects of the chemical compositions and fabrication conditions on the microstructure were investigated in relation to the quantitative microstructural analysis results obtained by small angle neutron scattering. The volume fraction of Y-oxide increases after fabrication, and this result is considered to be due to the formation of non-stochiometric Y-Ti-oxides.

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors. (3) Progress of component design

International Nuclear Information System (INIS)

Enuma, Yasuhiro; Kawasaki, Nobuchika; Orita, Junichi; Eto, Masao; Miyagawa, Takayuki

2015-01-01

In the frame work of generation IV international forum (GIF), safety design criteria (SDC) and safety design guideline (SDG) for the generation IV sodium-cooled fast reactors have been developing in the circumstance of worldwide deployment of SFRs. JAEA, JAPC, MFBR have been investigating design study for JSFR to satisfy SDC in the feasibility study of SDG for Sodium-cooled Fast Reactor (SFR). In addition to the safety measures, maintainability, reparability and manufacturability are taken into account in the JSFR design study. This paper describes the design of main components. Enlargement of the access route for the inspection devices and addition of the access routes were carried out for the reactor structure. The pump-integrated IHX (pump/IHX) was modified for the primary heat exchanger (PHX), which was installed for the decay heat removal in the IHX at the upper plenum, to be removable for improved repair and maintenance. For the steam generator (SG), protective wall tube type design is under investigation as an option with less R and D risks. (author)

Effect of Reflector Material on the Neutronic Characteristics of the Small Sodium-cooled Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Yun, Sung Hwan; Baek, Min Ho; Yoo, Jae Woon; Kim, Sang Ji [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

The sodium-cooled fast reactor (SFR) has been chosen as a candidate for the Gen-IV Nuclear Energy Systems Initiative due to the advantages in utilization of uranium resources and reduction of radioactive wastes. Recently, the uranium blanket concept is omitted for a purpose of the non-proliferation, hence the reflector material plays a more important role in reactor core design. Moreover, especially in the Korean prototype SFR, the initial core should startup with low-enriched uranium ({<=} 20 w/o) for 100 {approx} 150 MWe power. This restriction causes significant difficulties to achieve sufficient excess reactivity. Thus, in this paper, core characteristic studies of various reflector materials (HT9, BeO, MgO, and ZrH{sub 1.6}) are performed to enhance the initial core excess reactivity

Discussion on safety analysis approach for sodium fast reactors

International Nuclear Information System (INIS)

Hong, Soon Joon; Choo, Yeon Joon; Suh, Nam Duk; Shin, Ahn Dong; Bae, Moo Hoon

2012-01-01

Utilization of nuclear energy is increasingly necessary not only because of the increasing energy consumption but also because of the controls on greenhouse emissions against global warming. To keep step with such demands, advanced reactors are now world widely under development with the aims of highly economical advances, and enhanced safety. Recently, further elaborating is encouraged on the research and development program for Generation IV (GEN IV) reactors, and in collaboration with other interested countries through the Generation IV International Forum (GIF). Sodium cooled Fast Reactor (SFR) is a strong contender amongst the GEN IV reactor concepts. Korea also takes part in that program and plans to construct demonstration reactor of SFR. SFR is under the development for a candidate of small modular reactors, for example, PRISM (Power Reactor Innovative Small Module). Understanding of safety analysis approach has also advanced by the demand of increasing comprehensive safety requirement. Reviewing the past development of the licensing and safety basis in the advanced reactors, such approaches seemed primarily not so satisfactory because the reference framework of licensing and safety analysis approach in the advanced reactors was always the one in water reactors. And, the framework is very plant specific one and thereby the advanced reactors and their frameworks don't look like a well assorted couple. Recently as a result of considerable advances in probabilistic safety assessment (PSA), risk informed approaches are increasingly applied together with some of the deterministic approaches like as the ones in water reactors. Technology neutral framework (TNF) can be said to be the utmost works of such risk informed approaches, even though an intensive assessment of the applicability has not been sufficiently accomplished. This study discusses the viable safety analysis approaches for the urgent application to the construction of pool type SFR. As discussed in

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

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.

The Atalante facility at CEA/Marcoule: towards Gen IV systems fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Bordier, Gilles; Warin, Dominique; Masson, Michel [CEA/Marcoule Direction, BP 17171 - 30207 - Bagnols-sur-Ceze Cedex (France)

2008-07-01

The Atalante facility is a complete set of 18 hot labs and 9 shielded cells devoted to the research and development on fuel cycle. The activities correspond to 4 major sectors of nuclear research: -) to support the operation of actual reprocessing plants with the aim of adapting the head of the process to the increase of the spend fuel burn-up and to different types of new burnt fuels to be reprocessed (including MOX, USi or UMo fuels); -) to develop the COEX{sup TM} process that jointly manages uranium and plutonium from the dissolution of spent fuel to the production of UPuO{sub 2} powder and the fabrication of MOX fuel pellets; -) to prepare the recycling of minor actinides (MA) by partitioning or by grouped actinide extraction, and by MA bearing fuel fabrication; -) to study the long term behavior of high level waste conditioning matrices and especially self irradiation and leaching of vitrified waste. The first hot lab of Atalante was operated in 1992, the process shielded cell (CBP) in 2003 and the last LN1 lab in 2005, while at the same time a large scale demonstration test on the DIAMEX-SANEX MA partitioning process was performed. Now some new challenges involve further necessary evolutions of the facility. Some are related to safety assessment and operating flexibility; the major evolutions will come from new scientific goals and research programs. Furthermore, minor actinides materials irradiation tests in fast reactors will be prepared in the framework of a large international cooperation (GACID program) and need the production of significant amounts of MA bearing mixed U-Pu oxide compounds in new hot labs and shielded cells equipment. The major new research tools are presented and we highlight how Atalante is a unique facility which brings a real opportunity to reinforce the European and international scientific cooperation in order to prepare the next Gen IV fuel cycle. (authors)

The Atalante facility at CEA/Marcoule: towards Gen IV systems fuel cycle

International Nuclear Information System (INIS)

Bordier, Gilles; Warin, Dominique; Masson, Michel

2008-01-01

The Atalante facility is a complete set of 18 hot labs and 9 shielded cells devoted to the research and development on fuel cycle. The activities correspond to 4 major sectors of nuclear research: -) to support the operation of actual reprocessing plants with the aim of adapting the head of the process to the increase of the spend fuel burn-up and to different types of new burnt fuels to be reprocessed (including MOX, USi or UMo fuels); -) to develop the COEX TM process that jointly manages uranium and plutonium from the dissolution of spent fuel to the production of UPuO 2 powder and the fabrication of MOX fuel pellets; -) to prepare the recycling of minor actinides (MA) by partitioning or by grouped actinide extraction, and by MA bearing fuel fabrication; -) to study the long term behavior of high level waste conditioning matrices and especially self irradiation and leaching of vitrified waste. The first hot lab of Atalante was operated in 1992, the process shielded cell (CBP) in 2003 and the last LN1 lab in 2005, while at the same time a large scale demonstration test on the DIAMEX-SANEX MA partitioning process was performed. Now some new challenges involve further necessary evolutions of the facility. Some are related to safety assessment and operating flexibility; the major evolutions will come from new scientific goals and research programs. Furthermore, minor actinides materials irradiation tests in fast reactors will be prepared in the framework of a large international cooperation (GACID program) and need the production of significant amounts of MA bearing mixed U-Pu oxide compounds in new hot labs and shielded cells equipment. The major new research tools are presented and we highlight how Atalante is a unique facility which brings a real opportunity to reinforce the European and international scientific cooperation in order to prepare the next Gen IV fuel cycle. (authors)

Boron-bearing Influences of 9Cr-0.5Mo-2W-V-Nb Ferritic/Martensitic Steels for a SFR Fuel Cladding

International Nuclear Information System (INIS)

Baek, Jong-Hyuk; Han, Chang-Hee; Kim, Woo-Gon; Kim, Sung-Ho; Lee, Chan-Bock

2008-01-01

Currently the principal materials in a SFR (sodium-cooled fast reactor) of Gen-IV nuclear system are considering stainless steels (e.g. austenitic steels and ferritic/martensitic steels) for pressure boundary and structural applications in the primary circuit (cladding, duct, cold and hot leg piping, and pressure vessel). There are sound technical justifications for these material selections, and the adoption of these stainless steels for a wide range of nuclear and non-nuclear applications has generated much industrial technology and experience. However, there are strong incentives to develop advanced materials, especially cladding, for the Gen-IV SFR. The Gen-IV SFR is to have a considerable increase in safety and be economically competitive when compared with the conventional water reactors. To accomplish these objectives, the development of the fuel cladding material should be set forth as a premise because its integrity is directly related to those of the reactor system as well as the fuel in the Gen-IV SFR. Since last year, a R and D program was launched to develop the improved ferritic/martensitic steel for the Gen-IV SFR fuel cladding. Categories of materials considered in the program included 8 - 12% Cr ferritic/ martensitic steels. A strong recommendation was made for the development of a high strength steel equivalent to or superior to ASTM Gr.92 steel to offset the difficulties encountered with commercial available steels of the 8 - 12% Cr group. That is, since fuel cladding in the Gen-IV SFR would operate under higher temperatures than 600 .deg. C, contacting with liquid sodium, and be irradiated by neutrons to as high as 200dpa, the cladding should thus sustain both superior irradiation and temperature stabilities during an operational life. The newly developed advanced steel should overcome the severe drawback; mechanical properties, especially creep, are deteriorated at a higher temperature over 600 .deg. C. In this study, as one of the composition

Project planning of Gen-IV sodium cooled fast reactor technology

Energy Technology Data Exchange (ETDEWEB)

Yoo, Jaewoon; Joo, H. K.; Cho, C. H.; Kim, Y. G.; Lee, D. U.; Jin, M. W.

2013-05-15

The project program will be established to shorten the design schedule by sharing the design man power and experimental facility, and by introducing the proven technology through international collaboration and the project plan including preliminary specific design, technology validation and fuel design validation plan will be more detail by reviewing the plan at the International Technical Review Meeting (ITRM). Periodic project progress review meeting will be held to find the technical issues and to resolve them. The results of the progress review meeting will be reflected into the final assessment of research project. The project progress review meeting will be held every quarter and external expert will also participate in the meeting. In parallel with the PGSFR development, innovative small modular SFR will be developed aiming to the international nuclear market. The system and component technologies of both system can be shared but innovative concept will be implemented into the design. Ultra long life core design concept and supercritical CO{sub 2} Brayton cycle will be considered as the innovative concept for enhancing the plant economy and safety.

Project planning of Gen-IV sodium cooled fast reactor technology

International Nuclear Information System (INIS)

Yoo, Jaewoon; Joo, H. K.; Cho, C. H.; Kim, Y. G.; Lee, D. U.; Jin, M. W.

2013-05-01

The project program will be established to shorten the design schedule by sharing the design man power and experimental facility, and by introducing the proven technology through international collaboration and the project plan including preliminary specific design, technology validation and fuel design validation plan will be more detail by reviewing the plan at the International Technical Review Meeting (ITRM). Periodic project progress review meeting will be held to find the technical issues and to resolve them. The results of the progress review meeting will be reflected into the final assessment of research project. The project progress review meeting will be held every quarter and external expert will also participate in the meeting. In parallel with the PGSFR development, innovative small modular SFR will be developed aiming to the international nuclear market. The system and component technologies of both system can be shared but innovative concept will be implemented into the design. Ultra long life core design concept and supercritical CO 2 Brayton cycle will be considered as the innovative concept for enhancing the plant economy and safety

Hydride generation atomic fluorescence spectrometric determination of As, Bi, Sb, Se(IV) and Te(IV) in aqua regia extracts from atmospheric particulate matter using multivariate optimization

International Nuclear Information System (INIS)

Moscoso-Perez, Carmen; Moreda-Pineiro, Jorge; Lopez-Mahia, Purificacion; Muniategui-Lorenzo, Soledad; Fernandez-Fernandez, Esther; Prada-Rodriguez, Dario

2004-01-01

A highly sensitive and simple method, based on hydride generation and atomic fluorescence detection, has been developed for the determination of As, Bi, Sb, Se(IV) and Te(IV) in aqua regia extracts from atmospheric particulate matter samples. Atmospheric particulates matter was collected on glass fiber filters using a medium volume sampler (PM1 particulate matter). Two-level factorial designs have been used to optimise the hydride generation atomic fluorescence spectrometry (HG-AFS) procedure. The effects of several parameters affecting the hydride generation efficiency (hydrochloric acid, sodium tetrahydroborate and potassium iodide concentrations and flow rates) have been evaluated using a Plackett-Burman experimental design. In addition, parameters affecting the hydride measurement (delay, analysis and memory times) have been also investigated. The significant parameters obtained (sodium tetrahydroborate concentration, sodium tetrahydroborate flow rate and analysis time for As; hydrochloric acid concentration and sodium tetrahydroborate flow rate for Se(IV); and sodium tetrahydroborate concentration and sodium tetrahydroborate flow rate for Te(IV)) have been optimized by using 2 n + star central composite design. Hydrochloric acid concentration and sodium tetrahydroborate flow rate were the significant parameters obtained for Sb and Bi determination, respectively. Using a univariate approach these parameters were optimized. The accuracy of methods have been verified by using several certified reference materials: SRM 1648 (urban particulate matter) and SRM 1649a (urban dust). Detection limits in the range of 6 x 10 -3 to 0.2 ng m -3 have been achieved. The developed methods were applied to several atmospheric particulate matter samples corresponding to A Coruna city (NW Spain)

Generation IV SFR Nuclear Reactors: Under Sodium Robotics for ASTRID

International Nuclear Information System (INIS)

Jouan-de-Kervenoael, T.; Rey, F.; Baque, F.

2013-06-01

For non-removable components of the future ASTRID prototype, repair operations will be performed in a gas environment. If the faulty area is located under the sodium free level, the gas-tight system will have to contain the inspection and repair tools and to protect them from the surrounding liquid sodium. Concerning repair tools, the unique laser tool has been selected for future SFRs: the repair scenario for in-sodium structures will first involve removing the sodium (after bulk draining), then machining and finally welding. Concerning conventional tools (brush or gas blower for sodium removal, milling machine for machining and TIG for welding for which its feasibility was demonstrated in the 1990's) are still considered as a back-up solution. The maintenance of future ASTRID nuclear reactor prototype (inspection, repair) will be performed during shut down periods with some robotic carriers which have to be introduced within the main vessel, in primary 200 deg. C sodium coolant with argon gas cover. Inspection campaigns will be 20 days long. These robots (or carriers) will allow bringing inspection and repairing tools up to concerned components and structures. The needed degrees of freedom associated to these operations will be assumed either directly by the carrier itself or by specifics lower end carrier device for accurate local positioning. Several carriers will be designed, well adapted to specific needs: type of maintenance operation and location of inspection and repair sites. Feedback experience was gained during Superphenix SFR operation with the MIR robot which allowed to successfully make the Non Destructive Examination of main vessel welding joints, the carrier being outside bulk sodium. Operating conditions for the ASTRID robots will be harder from those of the MIR robot: temperature ranging from 180 deg. C to 200 deg. C, radiation dose ranging from 105 to 106 Gy, but mainly direct immersion within liquid sodium coolant. At the design phase of

Corrosion of structural materials for Generation IV systems

International Nuclear Information System (INIS)

Balbaud-Celerier, F.; Cabet, C.; Courouau, J.L.; Martinelli, L.; Arnoux, P.

2009-01-01

The Generation IV International Forum aims at developing future generation nuclear energy systems. Six systems have been selected for further consideration: sodium-cooled fast reactor (SFR), gas-cooled fast reactor (GFR), lead-cooled fast reactor (LFR), molten salt reactor (MSR), supercritical water-cooled reactor (SCWR) and very high temperature reactor (VHTR). CEA, in the frame of a national program, of EC projects and of the GIF, contributes to the structural materials developments and research programs. Particularly, corrosion studies are being performed in the complex environments of the GEN IV systems. As a matter of fact, structural materials encounter very severe conditions regarding corrosion concerns: high temperatures and possibly aggressive chemical environments. Therefore, the multiple environments considered require also a large diversity of materials. On the other hand, the similar levels of working temperatures as well as neutron spectrum imply also similar families of materials for the various systems. In this paper, status of the research performed in CEA on the corrosion behavior of the structural material in the different environments is presented. The materials studied are either metallic materials as austenitic (or Y, La, Ce doped) and ferrito-martensitic steels, Ni base alloys, ODS steels, or ceramics and composites. In all the environments studied, the scientific approach is identical, the objective being in all cases the understanding of the corrosion processes to establish recommendations on the chemistry control of the coolant and to predict the long term behavior of the materials by the development of corrosion models. (author)

ASAMPSA2 best-practices guidelines for L2 PSA development and applications. Volume 3 - Extension to Gen IV reactors

International Nuclear Information System (INIS)

Bassi, C.; Bonneville, H.; Brinkman, H.; Burgazzi, L.; Polidoro, F.; Vincon, L.; Jouve, S.

2010-01-01

The main objective assigned to the Work Package 4 (WP4) of the 'ASAMPSA2' project (EC 7. FPRD) consist in the verification of the potential compliance of L2PSA guidelines based on PWR/BWR reactors (which are specific tasks of WP2 and WP3) with Generation IV representative concepts. Therefore, in order to exhibit potential discrepancies between LWRs and new reactor types, the following work was based on the up-to-date designs of: - The European Fast Reactor (EFR) which will be considered as prototypical of a pool-type Sodium-cooled Fast Reactor (SFR); - The ELSY design for the Lead-cooled Fast Reactor (LFR) technology; - The ANTARES project which could be representative of a Very-High Temperature Reactor (VHTR); - The CEA 2400 MWth Gas-cooled Fast Reactor (GFR). (authors)

Spectroscopy study of ceramic pigments based on Ce(IV)-Pr(IV) oxide

International Nuclear Information System (INIS)

Furtado, L.; Toma, H.E.

1991-01-01

The synthesis and spectroscopic properties of a series of cerium(IV)-praseodimium(IV) oxide pigments are reported. The pigments exhibit brick-red colours and are suitable for ceramic applications because of their high temperature stability. Electronic absorption spectra of the pigments suspended in a gel matrix of polyvinyl alcohol-sodium tetradecaborate mixture, consists of broad band with gaussian components at 372 and 472nm. These bands are described to charge -transfer transitions from the occupied oxygen p-orbitals to the empty f levels of the lanthanides. (author)

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].

Effect of Proton Irradiation on the Corrosion Behaviors of Ferritic/Martensitic Steel in Liquid Metal Environment

Energy Technology Data Exchange (ETDEWEB)

Lee, Jeonghyeon; Kim, Tae Yong; Kim, Ji Hyun [UNIST, Ulsan (Korea, Republic of)

2016-10-15

Liquid metal fast breeder reactors (LMFBRs) such as sodium-cooled fast reactor (SFR) and lead-cooled fast reactor (LFR) are the candidates of GEN-IV nuclear energy systems. Among various liquid metals that can be used as primary coolant material, sodium is a world widely used coolant for GEN-IV reactors. In this study, as-received Gr.92 and irradiated Gr.92 specimen in the oxygen-saturated liquid sodium were examined at high temperature for 300h. The microstructure results reveal the information of the effect of irradiation and effect of the chrome concentration in specimen. From the SRIM result, penetration distance of 40 μm in stainless steel and nominal sample thickness of 30 μm was used to avoid the damage peak and any proton implantation and From the microstructural evaluation, chromium-rich zones existed under the surface of the both of non-irradiated and irradiated materials. The irradiated materials showed chromium-rich zones with larger depths than the non-irradiated specimens.

Advanced Computational Materials Science: Application to Fusion and Generation IV Fission Reactors (Workshop Report)

Energy Technology Data Exchange (ETDEWEB)

Stoller, RE

2004-07-15

The ''Workshop on Advanced Computational Materials Science: Application to Fusion and Generation IV Fission Reactors'' was convened to determine the degree to which an increased effort in modeling and simulation could help bridge the gap between the data that is needed to support the implementation of these advanced nuclear technologies and the data that can be obtained in available experimental facilities. The need to develop materials capable of performing in the severe operating environments expected in fusion and fission (Generation IV) reactors represents a significant challenge in materials science. There is a range of potential Gen-IV fission reactor design concepts and each concept has its own unique demands. Improved economic performance is a major goal of the Gen-IV designs. As a result, most designs call for significantly higher operating temperatures than the current generation of LWRs to obtain higher thermal efficiency. In many cases, the desired operating temperatures rule out the use of the structural alloys employed today. The very high operating temperature (up to 1000 C) associated with the NGNP is a prime example of an attractive new system that will require the development of new structural materials. Fusion power plants represent an even greater challenge to structural materials development and application. The operating temperatures, neutron exposure levels and thermo-mechanical stresses are comparable to or greater than those for proposed Gen-IV fission reactors. In addition, the transmutation products created in the structural materials by the high energy neutrons produced in the DT plasma can profoundly influence the microstructural evolution and mechanical behavior of these materials. Although the workshop addressed issues relevant to both Gen-IV and fusion reactor materials, much of the discussion focused on fusion; the same focus is reflected in this report. Most of the physical models and computational methods

In silico, in vitro and in vivo analyses of dipeptidyl peptidase IV inhibitory activity and the antidiabetic effect of sodium caseinate hydrolysate.

Science.gov (United States)

Hsieh, Cheng-Hong; Wang, Tzu-Yuan; Hung, Chuan-Chuan; Jao, Chia-Ling; Hsieh, You-Liang; Wu, Si-Xian; Hsu, Kuo-Chiang

2016-02-01

The frequency (A), a novel in silico parameter, was developed by calculating the ratio of the number of truncated peptides with Xaa-proline and Xaa-alanine to all peptide fragments from a protein hydrolyzed with a specific protease. The highest in vitro DPP-IV inhibitory activity (72.7%) was observed in the hydrolysate of sodium caseinate by bromelain (Cas/BRO), and the constituent proteins of bovine casein also had relatively high A values (0.10-0.17) with BRO hydrolysis. 1CBR (the <1 kDa fraction of Cas/BRO) showed the greatest in vitro DPP-IV inhibitory activity of 77.5% and was used for in vivo test by high-fat diet-fed and low-dose streptozotocin-induced diabetic rats. The daily administration of 1CBR for 6 weeks was effective to improve glycaemic control in diabetic rats. The results indicate that the novel in silico method has the potential as a screening tool to predict dietary proteins to generate DPP-IV inhibitory and antidiabetic peptides.

Thermal analysis of supercritical CO{sub 2} power cycles: Assessment of their suitability to the forthcoming sodium fast reactors

Energy Technology Data Exchange (ETDEWEB)

Perez-Pichel, G.D., E-mail: gdp@icai.es [Rafael Marino Chair on New Energy Technologies, Comillas Pontifical University, Madrid (Spain); Linares, J.I. [Rafael Marino Chair on New Energy Technologies, Comillas Pontifical University, Madrid (Spain); Herranz, L.E.; Moratilla, B.Y. [Unit of Nuclear Safety Research, CIEMAT, Madrid (Spain)

2012-09-15

Highlights: Black-Right-Pointing-Pointer This paper investigates the potential use of S-CO{sub 2} cycles in SFRs. Black-Right-Pointing-Pointer A wide range of configurations have been explored. Black-Right-Pointing-Pointer It is feasible to reach a thermal efficiency as high as 43.5%. Black-Right-Pointing-Pointer A sensitivity analysis together with an exergy study have been done. Black-Right-Pointing-Pointer Potential use in SFRs of recompression S-CO{sub 2} cycles for their balance of plant. - Abstract: Sodium fast reactors (SFRs) potential to meet Gen. IV requirements is broadly acknowledged worldwide. The scientific and technological experience accumulated by operating test reactors and, even, by running commercial reactors, makes them be considered as the closest Gen. IV option in the near future. In the past their balance of plant has been always based on Rankine cycles. This paper investigates the potential use of supercritical recompression CO{sub 2} cycles (S-CO{sub 2}) in SFRs on the basis of the working parameters foreseen within the European Sodium Fast Reactor (ESFR) project. A wide range of configurations have been explored, from the simplest one to combined cycles (with organic Rankine cycles, ORC), and a comparison has been set in terms of thermal efficiency. As a result, it has been found out that the most basic configuration could reach a thermal efficiency as high as 43.31%, which is comparable to that obtained through super-critical Rankine cycles proposed elsewhere. A sensitivity analysis together with an exergy study of this configuration, pointed the pre-cooler and IHX{sub Na-CO{sub 2}} as key components in the cycle performance. These results highlight a main conclusion: the potential use in SFRs of recompression S-CO{sub 2} cycles for their balance of plant, whenever a sound and extensive database is built-up on S-CO{sub 2} turbo-machinery and IHX performance.

A Study on the Planning of Technology Development and Research for Generation IV Nuclear Energy Systems

Energy Technology Data Exchange (ETDEWEB)

Chang, Moon Hee; Kim, H. R.; Kim, H. J. and others

2005-08-15

This study aimed at the planning the domestic technology development of the Gen IV and the formulating the international collaborative project contents and executive plan for 'A Validity Assessment and Policies of the R and D of Generation IV Nuclear Energy Systems'. The results of the study include follows; - Survey of the technology state in the fields of the Gen IV system specific technologies and the common technologies, and the plans of the international collaborative research - Drawing up the executive research and development plan by the experts of the relevant technology field for the systems which Korean will participate in. - Formulating the effective conduction plan of the program reflecting the view of the experts from the industry, the university and the research institute. - Establishing the plan for estimation of the research fund and the manpower for the efficient utilization of the domestic available resources. This study can be useful material for evaluating the appropriateness of the Korea's participation in the international collaborative development of the Gen IV, and can be valuably utilized to establish the strategy for the effective conduction of the program. The executive plan of the research and development which was produced in this study will be used to the basic materials for the establishing the guiding direction and the strategic conduction of the program when the research and development is launched in the future.

Effects of Ta addition on the Microstructural and Mechanical Properties of 9Cr-0.5Mo-2W F/M Steels for a SFR Fuel Cladding

International Nuclear Information System (INIS)

Baek, Jong-Hyuk; Han, Chang-Hee; Kim, Tae-Kyu; Kim, Sung-Ho; Lee, Chan-Bock

2007-01-01

Today twenty fission reactors provide about 40% of the domestic electricity supply. The world-wide distribution of some nuclear reactors will be aging and will need replacement and enhancement to both keep pace with and to take up a large share of the growing world-wide electricity demand. A new generation (Gen IV) of nuclear plant concepts has become the focus of international advanced reactor activity. Gen IV nuclear systems embodies greater improvements and innovative advances in technology over earlier ones. The Gen IV systems are to have a considerable increase in safety and be economically competitive when compared with the existed commercial reactors. In particular, the systems should produce a significantly reduced volume of nuclear wastes. From this point of view, sodium-cooled Fast Reactor (SFR) is strongly considered as a future nuclear energy system in Korea

Physical properties of liquid sodium

International Nuclear Information System (INIS)

Alberdi Primicia, J.; Martinez Piquer, T.A.

1977-01-01

The molten sodium has been the more accepted coolant for the first generation of FBR, by this reason the knowledge of its technology is needed for the development of the next LMFBR. A series of necessary data for designing sodium liquid systems are given. Tables and graphics about the most important physical sodium properties between 1200-1400 degC are gathered. The results have been obtained from equations that relate the properties with temperature using a Fortran IV program. (author) [es

Development of reliable analytical method for extraction and separation of thorium(IV) by Cyanex 272 in kerosene

International Nuclear Information System (INIS)

Madane, N.S.; Mohite, B.S.

2011-01-01

A simple and selective spectrophotometric method has been developed for the extraction and separation of thorium(IV) from sodium salicylate media using Cyanex 272 in kerosene. Thorium(IV) was quantitatively extracted by 5 x 10 -4 M Cyanex 272 in kerosene from 1 x 10 -5 M sodium salicylate medium. The extracted thorium(IV) was stripped out quantitatively from the organic phase with 4.0 M hydrochloric acid and determined spectrophotometrically with arsenazo(III) at 620 nm. The effect of concentrations of sodium salicylate, extractant, diluents, metal ion and strippants has been studied. Separation of thorium(IV) from other elements was achieved from binary as well as multicomponent mixtures such as uranium(VI), strontium(II), rubidium(I), cesium(I), potassium(I), Sodium(I), lithium(I), lead(II), barium(II), beryllium(II) etc. Using this method separation and determination of thorium(IV) in geological and real samples has been carried out. The method is simple, rapid and selective with good reproducibility (approximately ±2%). (author)

Development of Basic Key Technologies for Gen IV SFR

International Nuclear Information System (INIS)

Han, Do Hee; Kim, Young In; Won, Byung Chool

2008-11-01

Technical specifications such as power capacity, type of core, clad alloy, clad barrier material, number of loops, type of SG tube have been evaluated and a optimal design concept has been identified to satisfy the technology goals of Generation IV nuclear systems. The concept for breakeven design is featured by the heat capacity of 1,200 MWe, enrichment-separated core, 2-loop, double-walled SG tube, and a long-life sensor system for in-service inspection

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...

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...

Metal fuel development and verification for prototype generation- IV Sodium- Cooled Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Chan Bock; Cheon, Jin Sik; Kim, Sung Ho; Park, Jeong Yong; Joo, Hyung Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR) to be built by 2028. U-Zr fuel is a driver for the initial core of the PGSFR, and U -transuranics (TRU)-Zr fuel will gradually replace U-Zr fuel through its qualification in the PGSFR. Based on the vast worldwide experiences of U-Zr fuel, work on U-Zr fuel is focused on fuel design, fabrication of fuel components, and fuel verification tests. U-TRU-Zr fuel uses TRU recovered through pyroelectrochemical processing of spent PWR (pressurized water reactor) fuels, which contains highly radioactive minor actinides and chemically active lanthanide or rare earth elements as carryover impurities. An advanced fuel slug casting system, which can prevent vaporization of volatile elements through a control of the atmospheric pressure of the casting chamber and also deal with chemically active lanthanide elements using protective coatings in the casting crucible, was developed. Fuel cladding of the ferritic-martensitic steel FC92, which has higher mechanical strength at a high temperature than conventional HT9 cladding, was developed and fabricated, and is being irradiated in the fast reactor.

Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Directory of Open Access Journals (Sweden)

Chan Bock Lee

2016-10-01

Full Text Available Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR to be built by 2028. U–Zr fuel is a driver for the initial core of the PGSFR, and U–transuranics (TRU–Zr fuel will gradually replace U–Zr fuel through its qualification in the PGSFR. Based on the vast worldwide experiences of U–Zr fuel, work on U–Zr fuel is focused on fuel design, fabrication of fuel components, and fuel verification tests. U–TRU–Zr fuel uses TRU recovered through pyroelectrochemical processing of spent PWR (pressurized water reactor fuels, which contains highly radioactive minor actinides and chemically active lanthanide or rare earth elements as carryover impurities. An advanced fuel slug casting system, which can prevent vaporization of volatile elements through a control of the atmospheric pressure of the casting chamber and also deal with chemically active lanthanide elements using protective coatings in the casting crucible, was developed. Fuel cladding of the ferritic–martensitic steel FC92, which has higher mechanical strength at a high temperature than conventional HT9 cladding, was developed and fabricated, and is being irradiated in the fast reactor.

Economic, energy and GHG emissions performance evaluation of a WhisperGen Mk IV Stirling engine μ-CHP unit in a domestic dwelling

International Nuclear Information System (INIS)

Conroy, G.; Duffy, A.; Ayompe, L.M.

2014-01-01

Highlights: • The performance of a Stirling engine MK IV micro-CHP unit was evaluated in a domestic dwelling in Ireland. • The performance of the micro-CHP was compare to that of a condensing gas boiler. • The micro-CHP unit resulted in an annual cost saving of €180 compared to the condensing gas boiler. • Electricity imported from the grid decreased by 20.8% while CO 2 emissions decreased by 16.1%. • The micro-CHP unit used 2889 kW h of gas more than the condensing gas boiler during one year of operation. - Abstract: This paper presents an assessment of the energy, economic and greenhouse gas emissions performances of a WhisperGen Mk IV Stirling engine μ-CHP unit for use in a conventional house in the Republic of Ireland. The energy performance data used in this study was obtained from a field trial carried out in Belfast, Northern Ireland during the period June 2004–July 2005 by Northern Ireland Electricity and Phoenix Gas working in collaboration with Whispertech UK. A comparative performance analysis between the μ-CHP unit and a condensing gas boiler revealed that the μ-CHP unit resulted in an annual cost saving of €180 with an incremental simple payback period of 13.8 years when compared to a condensing gas boiler. Electricity imported from the grid decreased by 20.8% while CO 2 emissions decreased by 16.1%. The μ-CHP unit used 2889 kW h of gas more than the condensing gas boiler

Studies on sorption of plutonium on inorganic exchangers from sodium carbonate medium

Energy Technology Data Exchange (ETDEWEB)

Pius, I C; Charyulu, M M; Sivaramakrishnan, C K [Fuel Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India); Venkataramani, B [Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

Sorption of Pu(IV) from sodium carbonate medium has been investigated by using different inorganic exchangers alumina, silica gel and hydrous titanium oxide. Distribution ratios of Pu(IV) for its sorption on these exchangers from sodium carbonate medium were found to be sufficiently high indicating the suitability of these exchangers for the removal of Pu(IV). The presence of uranium and dibutyl phosphate do not have any effect on distribution ratio. The 10% Pu(IV) breakthrough capacities for above exchangers have been determined with 5 ml bed at a flow rate of 30 ml/hour. (author). 4 refs., 2 tabs.

Objective Provision Tree (OPT) in sodium cooled fast reactors; Objective Provision Tree (OPT) en reactores rapidos refrigerados por sodio. Aplicacion a la funcion de seguridad de evacuacion de calor residual

Energy Technology Data Exchange (ETDEWEB)

Queral, C.; Montero-Mayorga, J.; Gonzalez-Cadelo, J.

2013-07-01

Application to the safety function of residual heat removal As part of the project {sup S}afety Assessment for Reactor of GEN-IV (SARGEN IV) has been implemented the methodology ISAM from the IAEA to the safety assessment of new sodium reactor designs. Within the ISAM, a new tool to facilitate this assessment is the Objective Provision Tree (OPT) which documents the provisions necessary for each of the levels of defense in depth, as well as for each critical function of security. Due to the design innovations that have sodium reactors, the evaluation of safety and licensing of these reactors requires special considerations. In this work we have analyzed the mechanisms of failure of the safety function concerning the evacuation of waste heat, and have been proposed different provisions for each of the first three levels of defense in depth. The main result of this work is reflected in the elaboration of the OPTs, one for each of the first three levels of defense in depth for the safety of evacuation of residual heat function. These trees represent in a schematic way the provisions necessary to comply with the objectives of each level which are respectively: 1) deviations from normal operation, 2) control of abnormal operation and fault detection and 3) incidental control.

Material properties of Grade 91 steel at elevated temperature and their comparison with a design code

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyeong Yeon; Kim, Woo Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Han Sang; Kim, Yun Jae [Korea Univ., Seoul (Korea, Republic of)

2013-10-15

In this study, the material properties of tensile strength, creep properties, and creep crack growth model for Gr.91 steel at elevated temperature were obtained from material tests at KAERI, and the test data were compared with those of the French elevated temperature design code, RCC-MRx. The conservatism of the material properties in the French design code is highlighted. Mod.9Cr-1Mo (ASME Grade 91; Gr.91) steel is widely adopted as candidate material for Generation IV nuclear systems as well as for advanced thermal plants. In a Gen IV sodium-cooled fast reactor of the PGSFR (Prototype Gen IV Sodium-cooled Fast Reactor) being developed by KAERI (Korea Atomic Energy Research Institute), Gr.91 steel is selected as the material for the steam generator, secondary piping, and decay heat exchangers. However, as this material has a relatively shorter history of usage in an actual plant than austenitic stainless steel, there are still many issues to be addressed including the long-term creep rupture life extrapolation and ratcheting behavior with cyclic softening characteristics.

Preparation of UO_2 Fine Particle by Hydrolysis of Uranium(IV) Alkoxide

OpenAIRE

Satoh, Isamu; Takahashi, Mitsuyuki; Miura, Shigeyuki

1997-01-01

Fine particles of uranium(IV) dioxides were obtained by hydrolysis of uranium(IV) ethoxide which was synthesized by reacting uranium tetrachloride with sodium ethoxide. The monodispersed submicrometer particles were confirmed by SEM observation.

JSFR design progress related to development of safety design criteria for Generation IV sodium-cooled fast reactors. (1) Overview

International Nuclear Information System (INIS)

Kamide, Hideki; Ando, Masato; Ito, Takaya

2015-01-01

JAEA, JAPC and MFBR have been conducting design study for the Japan Sodium-cooled Fast Reactor (JSFR), which is a design concept aiming at future commercial use as sustainable electric power source. As the result of the design study and R and D activity related the innovative technologies incorporated in the design in the Fast Reactor Cycle Technology Development (FaCT) project up to 2010, basic design concept of JSFR was established and its development process to the commercialization including construction and operation of a demonstration version of JSFR was outlined. JSFR is a looptype next generation sodium-cooled fast reactor (SFR), which is aiming at achieving development targets of Generation IV reactors concerning sustainability, safety and reliability, economics and proliferation resistance and physical protection by introducing the innovative technologies such as shortened high-chromium steel piping. The output power is assumed for the design study as 1,500 MWe for the commercial version and 750 MWe for the demonstration version. In FaCT phase I up to 2010, in order to evaluate feasibility to achieve the development targets, the design study has been conducted on the main components and systems. Since 2011, in order to contribute to the development of safety design criteria (SDC) and safety design guideline (SDG), which include the lessons learned from the TEPCO's Fukushima Dai-ichi nuclear power plants accident, in the frame work of Generation IV International Forum (GIF), the design study is focusing on the design measures against severe external events such as earthquake and tsunami. At the same time, the design study is going into detail and paying much attention to the maintenance and repair to make surer its feasibility. This paper summarizes the design concept of the demonstration version of JSFR in which progress of design work was incorporated for the safety issues on SDC and SDG of a SFR. (author)

A Study on planning of promotion for international collaborative development of Generation IV Nuclear Energy Systems

International Nuclear Information System (INIS)

Hee, Chang Moon; Yang, M. S.; Ha, J. J.

2006-06-01

Korea has participated in the international collaboration programs for the development of future nuclear energy systems driven by the countries holding advanced nuclear technology and Korea and U. S. have cooperated in the INERI. This study is mainly at developing the plan for participation in the collaborative development of the Gen IV, searching the participation strategy for INERI and the INPRO, and the international cooperation in these programs. Contents and scope of the study for successful achievement are as follows; - Investigation and analysis of international and domestic trends related to advanced nuclear technologies - Development of the plan for collaborative development of the Gen IV and conducting the international cooperation activities - Support for the activities related to I-NERI between Korea and U. S. and conducting the international cooperation - International cooperation activities for the INPRO This study can be useful for planning the research plan and setting up of the strategy of integrating the results of the international collaboration and the domestic R and D results by combining the Gen IV and the domestic R and D in the field of future nuclear technology. Furthermore, this study can contribute to establishing the effective foundation and broadening the cooperation activities not only with the advanced countries for acquisition of the advanced technologies but also with the developing countries for the export of the domestic nuclear energy systems

Problems of technology and corrosion in sodium coolant and cover gas

International Nuclear Information System (INIS)

Kuenstler, K.; Ullmann, H.

1977-07-01

The meeting encloses the following themes: (i) Reactions in the system sodium-steel-cover gas (ii) Corrosion behaviour of structural and cladding materials (iii) Determination of impurities in sodium and cover gas (iv) Technology of sodium and cover gas (v) Testing equipments (vi) Safety problems

Domain IV voltage-sensor movement is both sufficient and rate limiting for fast inactivation in sodium channels.

Science.gov (United States)

Capes, Deborah L; Goldschen-Ohm, Marcel P; Arcisio-Miranda, Manoel; Bezanilla, Francisco; Chanda, Baron

2013-08-01

Voltage-gated sodium channels are critical for the generation and propagation of electrical signals in most excitable cells. Activation of Na(+) channels initiates an action potential, and fast inactivation facilitates repolarization of the membrane by the outward K(+) current. Fast inactivation is also the main determinant of the refractory period between successive electrical impulses. Although the voltage sensor of domain IV (DIV) has been implicated in fast inactivation, it remains unclear whether the activation of DIV alone is sufficient for fast inactivation to occur. Here, we functionally neutralize each specific voltage sensor by mutating several critical arginines in the S4 segment to glutamines. We assess the individual role of each voltage-sensing domain in the voltage dependence and kinetics of fast inactivation upon its specific inhibition. We show that movement of the DIV voltage sensor is the rate-limiting step for both development and recovery from fast inactivation. Our data suggest that activation of the DIV voltage sensor alone is sufficient for fast inactivation to occur, and that activation of DIV before channel opening is the molecular mechanism for closed-state inactivation. We propose a kinetic model of sodium channel gating that can account for our major findings over a wide voltage range by postulating that DIV movement is both necessary and sufficient for fast inactivation.

Comparison of In-Vessel Shielding Design Concepts between Sodium-cooled Fast Burner Reactor and the Sodium-cooled Fast Breeder Reactor

International Nuclear Information System (INIS)

Yun, Sunghwan; Kim, Sang Ji

2015-01-01

In this study, quantities of in-vessel shields were derived and compared each other based on the replaceable shield assembly concept for both of the breeder and burner SFRs. Korean Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR) like SFR was used as the reference reactor and calculation method reported in the reference was used for shielding analysis. In this paper, characteristics of in-vessel shielding design were studied for the burner SFR and breeder SFR based on the replaceable shield assembly concept. An in-vessel shield to prevent secondary sodium activation (SSA) in the intermediate heat exchangers (IHXs) is one of the most important structures for the pool type Sodium-cooled Fast Reactor (SFR). In our previous work, two in-vessel shielding design concepts were compared each other for the burner SFR. However, a number of SFRs have been designed and operated with the breeder concept, in which axial and radial blankets were loaded for fuel breeding, during the past several decades. Since axial and radial blanket plays a role of neutron shield, comparison of required in-vessel shield amount between the breeder and burner SFRs may be an interesting work for SFR designer. Due to the blanket, the breeder SFR showed better performance in axial neutron shielding. Hence, 10.1 m diameter reactor vessel satisfied the design limit of SSA at the IHXs. In case of the burner SFR, due to more significant axial fast neutron leakage, 10.6 m diameter reactor vessel was required to satisfy the design limit of SSA at the IHXs. Although more efficient axial shied such as a mixture of ZrH 2 and B 4 C can improve shielding performance of the burner SFR, additional fabrication difficulty may mitigate the advantage of improved shielding performance. Therefore, it can be concluded that the breeder SFR has better characteristic in invessel shielding design to prevent SSA at the IHXs than the burner SFR in the pool-type reactor

Estimación de parámetros genéticos para características productivas y reproductivas en los sistemas doble propósito del trópico bajo colombiano

Directory of Open Access Journals (Sweden)

A. P. Galeano

2010-01-01

Full Text Available Con el objetivo de estimar los componentes de varianza, las heredabilidades, repetibilidades y correlaciones genéticas y fenotípicas para la producción de leche por lactancia (PL, el peso al destete (PD, el intervalo entre partos (IEP y el Índice de Vaca (IV, de las hembras bovinas manejadas en los sistemas de producción de doble propósito del trópico bajo colombiano, se analizaron los registros productivos y reproductivos de 1.687 vacas registradas en la Asociación Colombiana de Criadores de Ganado en Doble Propósito (Asodoble, durante el periodo comprendido entre 1998 y 2007. Se empleó un modelo animal mixto que incluyó los efectos fijos del grupo contemporáneo (finca-sexo-época-año, la composición racial, y la duración de la lactancia como covariable; así como los efectos genéticos aleatorios del animal, el medio ambiente permanente y el residual. Las heredabilidades estimadas para IEP (0,04 y PD (0,11 fueron bajas, y moderadas para PL (0,35 e IV (0,24, respectivamente. La repetibilidad estimada para IEP fue baja (0,08, y para PL (0,41 e IV (0,31 moderada; en el caso de PD este valor fue igual a la heredabilidad (0,11. Las correlaciones genéticas y fenotípicas obtenidas entre PL y PD con respecto a IEP fueron positivas, y se determinó una asociación genética negativa entre PL y PD. Los resultados demostraron que el IV es un buen indicador, desde el punto de vista genético, de la eficiencia productiva y reproductiva de los animales manejados en estos sistemas productivos.

Thermometric titration of thorium with EDTA in the presence of large excess of neutral sodium salts.

Science.gov (United States)

Doi, K

1980-11-01

The thermometric titration of Th(IV) in the presence of neutral sodium salts, sulphuric acid or acetic acid with EDTA has been studied. The effect of each on the observed heat values for the titration is discussed. For sodium perchlorate media, DeltaH values of -9 and -21 kJ/mole have been estimated for the formation of the Th(IV)-EDTA chelate at mu --> 0 and mu = 0.5 (NaClO(4)), respectively. The -DeltaH values increase steadily with increase in concentration of sodium perchlorate up to at least 3M. For the titration of Th(IV) in the presence of a large excess of sodium nitrate the use of sodium iodide as a masking reagent has been examined: large amounts of Bi and Cu(II) are masked and a masking effect is observed for small amounts of Ni.

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...

Separation of uranium(V I) from binary solution mixtures with thorium(IV), zirconium(IV) and cerium(III) by foaming

International Nuclear Information System (INIS)

Shakir, K.; Aziz, M.; Benyamin, K.

1992-01-01

Foam separation has been investigated for the removal of uranium(V I), thorium(IV), zirconium(IV) and cerium(III) from dilute aqueous solutions at pH values ranging from about I to about II. Sodium laurel sulphate (Na L S) and acetyl trimethyl ammonium bromide (CTAB), being a strong anionic and a strong cationic surfactants, were used as collectors. The results indicate that Na L S can efficiently remove thorium(IV), zirconium(IV) and cerium(III) but not uranium(V I). CTAB, on the other hand, can successfully float only uranium(V I) and zirconium(IV). These differences in flotation properties of the different cations could be used to establish methods for the separation of uranium(V I) from binary mixtures with thorium(IV), zirconium(IV) or cerium(III). The results are discussed in terms of the hydrolytic behaviour of the tested cations and properties of used collectors.2 fig., 1 tab

Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials

Energy Technology Data Exchange (ETDEWEB)

Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Katoh, Yutai [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Wilson, Dane F [ORNL

2008-08-01

Since 2002, the Department of Energy's (DOE's) Generation IV Nuclear Energy Systems (Gen IV) Program has addressed the research and development (R&D) necessary to support next-generation nuclear energy systems. The six most promising systems identified for next-generation nuclear energy are described within this roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor-SCWR and the Very High Temperature Reactor-VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor-GFR, the Lead-cooled Fast Reactor-LFR, and the Sodium-cooled Fast Reactor-SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides and may provide an alternative to accelerator-driven systems. At the inception of DOE's Gen IV program, it was decided to significantly pursue five of the six concepts identified in the Gen IV roadmap to determine which of them was most appropriate to meet the needs of future U.S. nuclear power generation. In particular, evaluation of the highly efficient thermal SCWR and VHTR reactors was initiated primarily for energy production, and evaluation of the three fast reactor concepts, SFR, LFR, and GFR, was begun to assess viability for both energy production and their potential contribution to closing the fuel cycle. Within the Gen IV Program itself, only the VHTR class of reactors was selected for continued development. Hence, this document will address the multiple activities under the Gen IV program that contribute to the development of the VHTR. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of

Thermometric titration of thorium with EDTA in the presence of large excess of neutral sodium salts

International Nuclear Information System (INIS)

Doi, K.

1980-01-01

The thermometric titration of Th(IV) in the presence of neutral sodium salts, sulphuric acid or acetic acid with EDT has been studied. The effect of each on the observed heat values for the titration is discussed. For sodium perchlorate media, ΔH values of -9 and -21 kJ/mole have been estimated for the formation of the Th(IV)-EDTA chelate at μ → 0 and μ = 0.5 (NaClO 4 ), respectively. The -ΔH values increase steadily with increase in concentration of sodium perchlorate up to at least 3M. For the titration of Th(IV) in the presence of a large excess of sodium nitrate the use of sodium iodide as a masking reagent has been examined: large amounts of Bi and Cu(II) are masked and a masking effect is observed for small amounts of Ni. (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.

Allium cepa L. Response to Sodium Selenite (Se(IV)) Studied in Plant Roots by a LC-MS-Based Proteomic Approach.

Science.gov (United States)

Karasinski, Jakub; Wrobel, Kazimierz; Corrales Escobosa, Alma Rosa; Konopka, Anna; Bulska, Ewa; Wrobel, Katarzyna

2017-05-17

Liquid chromatography-high-resolution mass spectrometry was used for the first time to investigate the impact of Se(IV) (10 mgSe L -1 as sodium selenite) on Allium cepa L. root proteome. Using MaxQuant platform, more than 600 proteins were found; 42 were identified based on at least 2 razor + unique peptides, score > 25, and were found to be differentially expressed in the exposed versus control roots with t-test difference > ±0.70 (p roots. Different abundances of proteins involved in transcriptional regulation, protein folding/assembly, cell cycle, energy/carbohydrate metabolism, stress response, and antioxidant defense were found in the exposed vs nonexposed roots. New evidence was obtained on the alteration of sulfur metabolism due to S-Se competition in A. cepa L. which, together with the original analytical approach, is the main scientific contribution of this study. Specifically, proteins participating in assimilation and transformation of both elements were affected; formation of volatile Se compounds seemed to be favored. Changes observed in methionine cycle suggested that Se(IV) stress might repress methylation capability in A. cepa L., potentially limiting accumulation of Se in the form of nonprotein methylated species and affecting adversely transmethylation-dependent signaling pathways.

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...

Bolivian Rhinotragini IV: Paraeclipta gen. nov. (Coleoptera, Cerambycidae, new species and new combinations

Directory of Open Access Journals (Sweden)

Robin O. S. Clarke

2011-01-01

Full Text Available Paraeclipta gen. nov. is described to allocate five new species, and ten transferred from Eclipta Bates, 1873: P. cabrujai sp. nov.; P. clementecruzi sp. nov.; P. melgarae sp. nov.; P. tomhacketti sp. nov.; P. moscosoi sp. nov.; P. bicoloripes (Zajciw, 1965, comb. nov.; P. croceicornis (Gounelle, 1911, comb. nov.; P. flavipes (Melzer, 1922, comb. nov.; P. jejuna (Gounelle, 1911, comb. nov.; P. kawensis (Peñaherrera-Leiva & Tavakilian, 2004, comb. nov.; P. longipennis (Fisher, 1947, comb. nov.; P. rectipennis (Zajciw, 1965, comb. nov.; P. soumourouensis (Tavakilian & Peñaherrera-Leiva, 2003, comb. nov.; P. tenuis (Burmeister, 1865, comb. nov.; and P. unicoloripes (Zajciw, 1965, comb. nov. The Bolivian species are illustrated. A key to their identification and host flower records are provided.

Investigation of steel--sodium--iron shields

International Nuclear Information System (INIS)

Oblow, E.M.; Maerker, R.E.

1978-01-01

An analysis of experimental data from 21 fast reactor shield configurations containing steel, sodium, and iron were made as part of a study of the upper axial shielding needs of the Clinch River Breeder Reactor. The measured data were analyzed using both one- and two-dimensional discrete ordinates transport codes and several cross section libraries based on ENDF/B-IV data with group structures of 51 and 171 neutron groups. One-dimensional sensitivity studies using the 171 group library and ENDF/B-IV covariance files for sodium and iron data were used to determine the sensitivities of the measured data to multigroup cross sections and to estimate uncertainties in the calculated results. Results indicate that the standard 51-group design cross section library could be expected to predict the measurements to within 30% over 12 decades of attenuation although a few of the deepest penetration configurations showed disagreements as large as a factor of three. The sensitivity results revealed very high sensitivity of the measurements to total cross section minima and cross sections from 5 to 10 MeV in sodium and iron in the deep penetration configurations. As a result, large uncertainties in the calculated results arose from small uncertainties in the cross section data. These results indicate the need for better measurements of the total cross section minima in sodium, especially around 300 keV

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...

Synthesis and evaluation of artificial antigens for astragaloside IV

Directory of Open Access Journals (Sweden)

Sheng-lan Yu

Full Text Available The objective of this study was to produce artificial antigens for astragaloside IV that could be used to prepare antibodies against astragaloside IV screened in Radix astragali (Astragalus membranaceus (Fisch Bunge, Fabaceae and its preparations, using an indirect ELISA. Astragaloside IV was coupled to carrier proteins, bovine serum albumin and ovalbumin using the sodium periodate method and was then evaluated using SDS-PAGE, MALDI-TOF MS and animal immunizations. The coupling ratio of astragaloside IV to bovine serum albumin ratio was determined to be thirteen, and the indirect ELISA demonstrated that three groups of mice immunized with astragaloside IV-bovine serum albumin produced anti-astragaloside IV- bovine serum albumin-specific antibody, with a minimum serum titer of 1:9600. A method for synthesizing highly immunogenic astragaloside IV artificial antigens was successfully developed thus indicating its feasibility in the establishment of a fast immunoassay for astragaloside IV content determination in Radix astragali and its products.

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...

NOMAGE4 activities 2011. Part I, Nordic Nuclear Materials Forum for Generation IV Reactors: Status and activities in 2011

International Nuclear Information System (INIS)

Van Nieuwenhove, R.

2012-01-01

A network for materials issues has been initiated in 2009 within the Nordic countries. The original objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) were to form the basis of a sustainable forum for Gen-IV issues, especially focusing on fuels, cladding, structural materials and coolant interaction. Over the last years, other issues such as reactor physics, thermal hydraulics, safety and waste have gained in importance (within the network) and therefore the scope of the forum has been enlarged and a more appropriate and more general name, NORDIC-GEN4, has been chosen for the forum. Further, the interaction with non-Nordic countries (such as The Netherlands (JRC, NRG) and Czech Republic (CVR)) will be increased. Within the NOMAGE4 project, a seminar was organized by IFE-Halden during 31 October - 1 November 2011. The seminar attracted 65 participants from 12 countries. The seminar provided a forum for exchange of information, discussion on future research reactor needs and networking of experts on Generation IV reactor concepts. The participants could also visit the Halden reactor site and the workshop. (Author)

NOMAGE4 activities 2011. Part I, Nordic Nuclear Materials Forum for Generation IV Reactors: Status and activities in 2011

Energy Technology Data Exchange (ETDEWEB)

Van Nieuwenhove, R. (Institutt for Energiteknikk, OECD Halden Reactor Project (Norway))

2012-01-15

A network for materials issues has been initiated in 2009 within the Nordic countries. The original objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) were to form the basis of a sustainable forum for Gen-IV issues, especially focusing on fuels, cladding, structural materials and coolant interaction. Over the last years, other issues such as reactor physics, thermal hydraulics, safety and waste have gained in importance (within the network) and therefore the scope of the forum has been enlarged and a more appropriate and more general name, NORDIC-GEN4, has been chosen for the forum. Further, the interaction with non-Nordic countries (such as The Netherlands (JRC, NRG) and Czech Republic (CVR)) will be increased. Within the NOMAGE4 project, a seminar was organized by IFE-Halden during 31 October - 1 November 2011. The seminar attracted 65 participants from 12 countries. The seminar provided a forum for exchange of information, discussion on future research reactor needs and networking of experts on Generation IV reactor concepts. The participants could also visit the Halden reactor site and the workshop. (Author)

Status of the design and safety project for the sodium-cooled fast reactor as a generation IV nuclear energy system

International Nuclear Information System (INIS)

Niwa, Hajime; Fiorini, Gian-Luigi; Sim, Yoon-Sub; Lennox, Tom; Cahalan, James E.

2005-01-01

The Design and Safety Project Management Board (DSPMB) was established under the Sodium Cooled Fast Reactor (SFR) System Steering Committee (SSC) in the Generation IV international Forum. The DSPMB will promote collaborative R and D activities on reactor core design, and safety assessment for candidate systems, and also integrate these results together with those from other PMBs such as advanced fuel and component to a whole fast reactor system in order to develop high performance systems that will satisfy the goals of Generation IV nuclear energy systems. The DSPMB has formulated the present R and D schedules for this purpose. Two SFR concepts were proposed: a loop-type system with primarily a MOX fuel core and a pool-type system with a metal fuel core. Study of innovative systems and their evaluation will also be included. The safety project will cover both the safety assessment of the design and the preparation of the methods/tools to be used for the assessment. After a rather short viability phase, the project will move to the performance phase for development of performance data and design optimization of conceptual designs. This paper describes the schedules, work packages and tasks for the collaborative studies of the member countries. (author)

Estimación de parámetros genéticos para características productivas y reproductivas en los sistemas doble propósito del trópico bajo colombiano

Directory of Open Access Journals (Sweden)

A. P. Galeano

2010-06-01

Full Text Available Con el objetivo de estimar los componentes de varianza, las heredabilidades, repetibilidadesy correlaciones genéticas y fenotípicas para la producción de leche por lactancia(PL, el peso al destete (PD, el intervalo entre partos (IEP y el Índice de Vaca (IV,de las hembras bovinas manejadas en los sistemas de producción de doble propósitodel trópico bajo colombiano, se analizaron los registros productivos y reproductivosde 1.687 vacas registradas en la Asociación Colombiana de Criadores de Ganado enDoble Propósito (Asodoble, durante el periodo comprendido entre 1998 y 2007. Seempleó un modelo animal mixto que incluyó los efectos fijos del grupo contemporáneo(finca-sexo-época-año, la composición racial, y la duración de la lactancia comocovariable; así como los efectos genéticos aleatorios del animal, el medio ambientepermanente y el residual. Las heredabilidades estimadas para IEP (0,04 y PD (0,11fueron bajas, y moderadas para PL (0,35 e IV (0,24, respectivamente. La repetibilidadestimada para IEP fue baja (0,08, y para PL (0,41 e IV (0,31 moderada; en el casode PD este valor fue igual a la heredabilidad (0,11. Las correlaciones genéticas y fenotípicasobtenidas entre PL y PD con respecto a IEP fueron positivas, y se determinóuna asociación genética negativa entre PL y PD. Los resultados demostraron que el IVes un buen indicador, desde el punto de vista genético, de la eficiencia productiva yreproductiva de los animales manejados en estos sistemas productivos.

Fast reactor development and worldwide cooperation in Generation-IV International Forum

International Nuclear Information System (INIS)

Sagayama, Yutaka

2013-01-01

Objectives of Gen-IV systems development: Goals: Four challenging technology goals have been defined to be applied to innovative nuclear reactor concepts in the 21st century: 1) Safety and Reliability (safe and reliable operation, no offsite emergency response); 2) Sustainability (effective fuel utilization, minimization of nuclear waste); 3) Proliferation Resistance & Physical Protection (to assure unattractive and the least desirable route for diversion or theft of weapons-usable materials, and provide increased physical protection against acts of terrorism); 4) Economic Competitiveness (life-cycle cost advantage over other energy resources). Phase: Each Generation-IV reactor system is one of three stages. 1) Viability Phase; 2) Performance Phase; 3) Demonstration Phase. Target: Commercial Deployment is expected around 2030s or beyond

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

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...

Liquid-liquid extraction/separation of platinum(IV) and rhodium(III) from acidic chloride solutions using tri-iso-octylamine

Energy Technology Data Exchange (ETDEWEB)

Lee, Jin-Young, E-mail: jinlee@kigam.re.kr [Metals Recovery Department, Minerals Resources Research Division, Korea Institute of Geoscience and Mineral Resources (KIGAM), 92 Gahangno, Yuesong-gu, Daejeon 305-350 (Korea, Republic of); Rajesh Kumar, J., E-mail: rajeshkumarphd@rediffmail.com [Metals Recovery Department, Minerals Resources Research Division, Korea Institute of Geoscience and Mineral Resources (KIGAM), 92 Gahangno, Yuesong-gu, Daejeon 305-350 (Korea, Republic of); Kim, Joon-Soo; Park, Hyung-Kyu; Yoon, Ho-Sung [Metals Recovery Department, Minerals Resources Research Division, Korea Institute of Geoscience and Mineral Resources (KIGAM), 92 Gahangno, Yuesong-gu, Daejeon 305-350 (Korea, Republic of)

2009-08-30

Liquid-liquid extraction/separation of platinum(IV) and rhodium(III) from acidic chloride solutions was carried out using tri-iso-octylamine (Alamine 308) as an extractant diluted in kerosene. The percentage extraction of platinum(IV) and rhodium(III) increased with increase in acid concentration up to 8 mol L{sup -1}. However, at 10 mol L{sup -1} HCl concentration, the extraction behavior was reversed, indicating the solvation type mechanism during extraction. The quantitative extraction of {approx}98% platinum(IV) and 36% rhodium(III) was achieved with 0.01 mol L{sup -1} Alamine 308. The highest separation factor (S.F. = 184.7) of platinum(IV) and rhodium(III) was achieved with 0.01 mol L{sup -1} Alamine 308 at 1.0 mol L{sup -1} of hydrochloric acid concentration. Alkaline metal salts like sodium chloride, sodium nitrate, sodium thiocyanate, lithium chloride, lithium nitrate, potassium chloride and potassium thiocyanate used for the salting-out effect. LiCl proved as best salt for the extraction of platinum(IV). Temperature effect demonstrates that the extraction process is exothermic. Hydrochloric acid and thiourea mixture proved to be better stripping reagents when compared with other mineral acids and bases.

Identificación de mutaciones puntuales del gen de la 21-hidroxilasa en pacientes afectados con hiperplasia suprarrenal congénita.

Directory of Open Access Journals (Sweden)

Dora Fonseca

2005-06-01

Full Text Available lntroducción. La hiperplasia suprarrenal congénita es un trastorno autosómico recesivo debido a la inadecuada secreción de cortisol. Mas del 95% de los casos de hiperplasia suprarrenal congénita son causados por defectos del gen de la 21 hidroxilasa, CYP21A2 . Las manifestaciones clínicas incluyen la forma clásica y la forma no clásica. Objetivos. Determinar la frecuencia de las mutaciones puntuales P30L, IVS2-12AIC-G, Del 8pb, I172N, cluster Ex 6, V281L, Q318X, R356W y P453S en pacientes con hiperplasia suprarrenal congénita. Materiales y métodos. Se estudiaron 58 pacientes, de los cuales, 48 fueron clásicos y 10 no clásicos. Mediante PCR alelo-especifica y ACRS (Amplified Creation Restriction Sites, se analizaron 9 mutaciones puntuales del gen CYP21A2 y se determinó la frecuencia en la población analizada. Resultados. Los alelos afectados se identificaron en el 82,8% de los cromosomas. Las mutaciones mas frecuentes fueron: IVS2-12AIC-G (26,7%, Q318X (21,5%, V281L (12,1% e I172N (12,1%. Conclusiones. Las mutaciones mas frecuentes en Colombia son similares a las de otros países del mundo, excepto para Q318X que presentó una mayor frecuencia, pero similar a la de otros países latinoamericanos. Este hallazgo y la existencia de 17,2% de alelos no identificados puede indicar diferencia entre el acervo genético de las poblaciones. En la forma clásica perdedora de sal predominaron las mutaciones Q318X e IVS2-12AIC-G; en la virilizante simple, IVS2-12AIC-G e I172N y en la no clásica , V281L, lo cual esta relacionado con el grado de actividad enzimática. En la forma no clásica, se encontraron alelos severos en el 66,7% de los casos, lo que determina el riesgo de tener hijos afectados con la forma grave virilizante simple o perdedora de sal. Los resultados reportados permiten ofrecer asesoramiento genético y diagnóstico prenatal.

Efferent pathways in sodium overload-induced renal vasodilation in rats.

Directory of Open Access Journals (Sweden)

Nathalia O Amaral

Full Text Available Hypernatremia stimulates the secretion of oxytocin (OT, but the physiological role of OT remains unclear. The present study sought to determine the involvement of OT and renal nerves in the renal responses to an intravenous infusion of hypertonic saline. Male Wistar rats (280-350 g were anesthetized with sodium thiopental (40 mg. kg(-1, i.v.. A bladder cannula was implanted for collection of urine. Animals were also instrumented for measurement of mean arterial pressure (MAP and renal blood flow (RBF. Renal vascular conductance (RVC was calculated as the ratio of RBF by MAP. In anesthetized rats (n = 6, OT infusion (0.03 µg • kg(-1, i.v. induced renal vasodilation. Consistent with this result, ex vivo experiments demonstrated that OT caused renal artery relaxation. Blockade of OT receptors (OXTR reduced these responses to OT, indicating a direct effect of this peptide on OXTR on this artery. Hypertonic saline (3 M NaCl, 1.8 ml • kg(-1 b.wt., i.v. was infused over 60 s. In sham rats (n = 6, hypertonic saline induced renal vasodilation. The OXTR antagonist (AT; atosiban, 40 µg • kg(-1 • h(-1, i.v.; n = 7 and renal denervation (RX reduced the renal vasodilation induced by hypernatremia. The combination of atosiban and renal denervation (RX+AT; n = 7 completely abolished the renal vasodilation induced by sodium overload. Intact rats excreted 51% of the injected sodium within 90 min. Natriuresis was slightly blunted by atosiban and renal denervation (42% and 39% of load, respectively, whereas atosiban with renal denervation reduced sodium excretion to 16% of the load. These results suggest that OT and renal nerves are involved in renal vasodilation and natriuresis induced by acute plasma hypernatremia.

Improved modelling of sodium-spray fires and sodium-combustion aerosol chemical evolution - 15488

International Nuclear Information System (INIS)

Mathe, E.; Kissane, M.; Petitprez, D.

2015-01-01

In the context of the Generation IV Initiative, the consequences of a severe-accident in sodium-cooled fast reactor (SFR) must be studied. Being pyrophoric, sodium will burn upon contact with air in a containment creating toxic aerosols and we must take into account these fire aerosols when assessing the source term. We have developed a numerical simulation named NATRAC to calculate the mass of aerosols produced during a spray fire in a SFR severe accident. The results show that the mass of oxide aerosols can involve more than 60% of the ejected sodium. In a second part we have developed a numerical simulation named STARK based on the Cooper model that models the physico-chemical transformations of the aerosols. However, this model has never been validated and the literature does not permit to do so. In these conditions, we have designed and performed our own experiment ESSTIA to obtain the missing values of the parameters that govern Cooper model. The modified Cooper model we propose with the new parameters reproduces correctly the ESSTIA experimental data. The only parameter that has not yet been measured is the tortuosity of the sodium-fire aerosols surface layers. A dedicated experiment using real sodium-fire aerosols could eliminate any doubts about the uncertainty of the proposed Cooper model

Seletivicty of eucalyptus genotypes to herbicides rates / Seletividade de genótipos de eucalipto a doses de herbicidas

Directory of Open Access Journals (Sweden)

Siumar Pedro Tironi

2010-09-01

Full Text Available The aim of this work was to quantify the herbicide selectivity applied at post-emergence of eucalyptus in different rates. The experiment was conducted in greenhouse conditions in the period from January to March 2007 at the Faculdade de Agronomia Eliseu Maciel in Universidade Federal de Pelotas – Capão do Leão-RS. Experimental design was completely randomized, with four replications. Treatments were in a factorial scheme: factor A - eucalyptus genotypes (E. globulus e E. saligna, factor B - herbicides (isoxaflutole, oxyfluorfen, bispyribac-sodium and sethoxydim+diclosulam, and factor C – rates of the registered average for weed control (0, 50, 100, 150 e 200%. Phytotoxicity, height, stem diameter and dry matter were evaluated. E. globulus genotype was more sensitive to herbicides than E. saligna. The mixture of the herbicides sethoxydim plus diclosulam showed potential to be used in eucalyptus. Bispyribac-sodium herbicide was the most toxic and isoxaflutole was the most selective to the studied genotypes.O objetivo deste trabalho foi quantificar a seletividade de herbicidas aplicados em pós-emergência na cultura do eucalipto em função de diferentes doses. O experimento foi realizado em casa de vegetação, pertencente a Faculdade de Agronomia Eliseu Maciel da Universidade Federal de Pelotas, no Município de Capão do Leão – RS, no período de janeiro a março de 2007. O delineamento experimental utilizado foi completamente casualizado, com quatro repetições. Os tratamentos foram arranjados em esquema fatorial, onde o fator A testou genótipos de eucalipto (E. globulus e E. saligna, o fator B comparou quatro herbicidas (isoxaflutole, oxyfluorfen, bispyribac-sodium e sethoxydim+diclosulam e o fator C doses (0, 50, 100, 150 e 200% da dose média registrada para controle de plantas daninhas. As variáveis avaliadas foram fitotoxicidade, estatura, diâmetro do caule e matéria seca da parte aérea das plantas de eucalipto. O gen

[Effect of IV hydration with sodium bicarbonate on high-dose methotrexate disposition kinetics].

Science.gov (United States)

Tsuda, N; Goto, M; Konishi, H; Yamashina, H

1984-04-01

Following two-compartment kinetic analysis, the effect of loading of transfusion with sodium bicarbonate on methotrexate disposition was investigated in 13 cases with malignant tumor, being treated with high-dose methotrexate. The mean values of total body clearance, when administered at doses 50 mg and 100 mg per kg body weight, were 0.369 and 0.402 (l/h) per kg, respectively. No significant relationship was observed between alpha value and total amount of transfusion, of urine or dosage of sodium bicarbonate. The other kinetic parameters on elimination, beta value, K10 and total body clearance, did not also correlate with those values described above. These results suggest that the elimination profile of methotrexate show linear kinetics, and that massive administration of transfusion with sodium bicarbonate be not necessary if pH value of urine exceeds 7.0.

Mapping of sodium void worth and doppler effect for sodium-cooled fast reactor - 15458

International Nuclear Information System (INIS)

Krepel, J.; Pelloni, S.; Bortot, S.; Panadero, A.L.; Mikityuk, K.

2015-01-01

The sodium-cooled fast reactor (SFR) represents the reference and the most technologically mastered system among the Generation-IV reactors. Nevertheless, the sodium void worth in the fuel regions of SFR is usually positive. To overcome this safety drawback, low-void sodium-cooled fast spectrum core (CFV) was proposed by CEA. Such a CFV core is used in the frame of WP6 'Core safety' of the FP7 Euratom ESNII+ project as a reference SFR design. The overall sodium void effect is negative for the CFV core. Nevertheless, locally it is positive in the fuel region and negative in the sodium plenum. Similarly, also the Doppler effect is spatially dependent and it varies between the inner and outer fuel regions and between the middle and lower blankets. Accordingly, knowledge of the local distributions or actually mappings of the two safety-related parameters will be necessary, before safety assessment and transient analysis can be done. In this study these maps have been produced using the deterministic code ERANOS. The obtained mapping shows strong local dependency of both safety-related effects. A sensitivity of the void effect to the sodium plenum modeling was also demonstrated. The results may serve as an input for the transient analysis of the CFV core or as a cross-check for the Monte Carlo method based maps. (authors)

Analysis of Sodium-23 Data Cross-Sections for Coolant on Generation IV Reactor - SFR

International Nuclear Information System (INIS)

Suwoto; Zuhair

2009-01-01

The integral tests of sodium-23 neutron cross-sections for coolant contained in JENDL-3.3, ENDF/B-VII.0, BROND-2.2 and JEFF-3.1 files have been performed. Cross-sections analysis of sodium-23 such as total cross-sections, elastic scattering, in-elastic scattering and radiative capture cross-sections for several temperature i.e. 300K, 800K and 1500K. The sodium-23 total cross-sections analysis based on MAEKER, R.E. experimental result through Broomstick experiment calculation. Differences between among other evaluated nuclear data file for elastic scattering, in-elastic scattering and radiative capture cross-sections were done analyzed and compared to ENDF/B-VII.0 as standard reference. Analysis of total cross-sections sodium-23 through broomstick calculation show JENDL-3.3 file give the best result on C/E statistical average value is 1.1043 compared to another nuclear data files. Differences sodium-23 total cross-sections on JEFF-3.1 file for all temperature work specially for energy 40keV and 1MeV-2MeV is about 0.2%. Meanwhile, relative small differences on in-elastic total scattering cross-sections are shown for all temperatures are about ±0.1% in JENDL-3.3. On the other hand, BROND-2.2 file give ±6% higher on sodium-23 in-elastic total scattering cross sections for energy range 450keV-550keV. Clearly significant differences on sodium-23 radiative capture cross sections for BROND-2.2 file especially in energy 109.659keV is somewhat higher than 446%, otherwise JENDL-3.3 and JEFF-3.1 give 16% higher than ENDF/B-VII.0 file. Overall result show that JENDL-3.3, ENDFB-VII.0, BROND-2.2 and JEFF-3.1 have little bit differences in total, elastic scattering, in-elastic scattering total cross sections, except BROND-2.2 file due to radiative capture cross-sections with larger discrepancies. (author)

Development of Core Heat Removal Objective Provision Trees for Sodium-Cooled Fast Reactor Defense-in-Depth Evaluation

Energy Technology Data Exchange (ETDEWEB)

Yang, Huichang; Kang, Bongsuk; Lee, Youngho [TUEV Rheinland Korea Ltd., Seoul (Korea, Republic of); Suh, Namduk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

Based on the definition of Defense-in-Depth levels and safety functions for KALIMER sodium-cooled fast reactor, suggested in the reference and, OPTs for level 1, 2, and 3 defense-in-depth and core heat removal safety function, were developed and suggested in this paper. The purpose of this OPT is first to assure the defensein-depth design during the licensing of Sodium-Cooled Fast Reactors (SFR), but it will also contribute in evaluating the completeness of regulatory requirements under development by Korea Institute of Nuclear Safety (KINS). The challenges and mechanisms and provisions were briefly explained in this paper. Comparing the mechanisms and provisions with the requirements will contribute in identifying the missing requirements. Since the design of PGSFR (Prototype Gen-IV SFR) is not mature yet, the OPT is developed for KALIMER design. Developed OPTs in this study can be used for the identification of potential design vulnerabilities. When detailed identification of provisions in terms of design features were achieved through the next step of this study, it can contribute to the establishment of defensein-depth evaluation frame for the regulatory reviews for the licensing process. At this moment, the identified provisions have both aspects as requirements and design features already adopted in KALIMER design. In the next stage of this study, derived provisions to be adopted will be compared with the actual design features and findings can be suggested as recommendations for the safety improvement.

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)

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 5 Report: Generation IV Reactor Virtual Mockup Proof-of-Principle Study

International Nuclear Information System (INIS)

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-01-01

Task 5 report is part of a 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Created a virtual mockup of PBMR reactor cavity and discussed applications of virtual mockup technology to improve Gen IV design review, construction planning, and maintenance planning

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 5 Report: Generation IV Reactor Virtual Mockup Proof-of-Principle Study

Energy Technology Data Exchange (ETDEWEB)

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28

Task 5 report is part of a 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Created a virtual mockup of PBMR reactor cavity and discussed applications of virtual mockup technology to improve Gen IV design review, construction planning, and maintenance planning.

Solutions of group IV elements in liquid lithium

International Nuclear Information System (INIS)

Dadd, A.T.; Hubberstey, P.; Roberts, P.G.

1982-01-01

The solubilities of tin (0.00 = 22 Sn 5 . A simple thermochemical cycle is used to demonstrate that, whereas carbon dissolves endothermically in both liquid lithium and liquid sodium, the heavier Group IV elements dissolve exothermically. A similar cycle is used to derive solvation enthalpies (for the neutral gaseous species) for all Group IV elements in the two solvents. The trend in solvation enthalpy: C > Si > Ge > Sn > Pb is indicative of a diminishing affinity of solvent for solute and is attributed to the increasing metallic character of the solute as the Group is descended. (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.

Comparing the Effect of Intravenous Midazolam with Rectal Sodium Valproate in Controlling of Children with Refractory Status Epilepticus

Directory of Open Access Journals (Sweden)

T Mahmoudian

2006-01-01

Full Text Available Background: Refractory status epilepticus usually defined as a seizure lasting at least 60 minutes which is uncontrollable by Diazepam, Phenytoin, or Phenobarbital. The aim of this study was to compare the effect of interavenous Midazolam and rectal Sodium valproate in controlling refractory status epilepticus. Methods: In this case-control study; 76 children with (mean age of 37± 20 months with refractory status epilepticus were randomly divided into two groups to receive IV Midazolam and rectal Sodium Valproate. The effect of the two drugs were compared in control of seizure during first 20 minutes of treatment. Results: In 84.2 percent of children treated with IV Midazolam, the seizure was under control within 4.5 ± 0.5 minutes, while in 63 percent of those receiving Sodium Valproate, the seizure was completely controlled within 16.5 ± 0.8 minutes (P < 0.00001. Conclusion: The IV Midazolam was more effective than Sodium valproate, but the latter can be used in hospitals or pediatric emergency wards without ICU for controlling of refractory status epilepticus. Key words: refractory status epilepticus, midazolam, sodium valproate

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.

The natural scorpion peptide, BmK NT1 activates voltage-gated sodium channels and produces neurotoxicity in primary cultured cerebellar granule cells.

Science.gov (United States)

Zou, Xiaohan; He, Yuwei; Qiao, Jinping; Zhang, Chunlei; Cao, Zhengyu

2016-01-01

The scorpion Buthus martensii Karsch has been used in Traditional Chinese Medicine to treat neuronal diseases such as neuropathic pain, paralysis and epilepsy for thousands of years. Studies have demonstrated that scorpion venom is the primary active component. Although scorpion venom can effectively attenuate pain in the clinic, it also produces neurotoxic response. In this study, toxicity guided purification led to identify a mammalian toxin termed BmK NT1 comprising of 65 amino acid residues and an amidated C-terminus, a mature peptide encoded by the nucleotide sequence (GenBank No. AF464898). In contract to the recombinant product of the same nucleotide sequence, BmK AGAP, which displayed analgesic and anti-tumor effect, intravenous injection (i.v.) of BmK NT1 produced acute toxicity in mice with an LD50 value of 1.36 mg/kg. In primary cultured cerebellar granule cells, BmK NT1 produced a concentration-dependent cell death with an IC50 value of 0.65 μM (0.41-1.03 μM, 95% Confidence Intervals, 95% CI) which was abolished by TTX, a voltage-gated sodium channel (VGSC) blocker. We also demonstrated that BmK NT1 produced modest sodium influx in cerebellar granule cell cultures with an EC50 value of 2.19 μM (0.76-6.40 μM, 95% CI), an effect similar to VGSC agonist, veratridine. The sodium influx response was abolished by TTX suggesting that BmK NT1-induced sodium influx is solely through activation of VGSC. Considered these data together, we demonstrated that BmK NT1 activated VGSC and produced neurotoxicity in cerebellar granule cell cultures. Copyright © 2015 Elsevier Ltd. All rights reserved.

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.

Metal Oxide Decomposition In Hydrothermal Alkaline Sodium Phosphate Solutions

Energy Technology Data Exchange (ETDEWEB)

S.E. Ziemniak

2003-09-24

Alkaline hydrothermal solutions of sodium orthophosphate (2.15 < Na/P < 2.75) are shown to decompose transition metal oxides into two families of sodium-metal ion-(hydroxy)phosphate compounds. Equilibria for these reactions are quantified by determining phosphate concentration-temperature thresholds for decomposition of five oxides in the series: Ti(IV), Cr(III), Fe(III, II), Ni(II) and Zn(II). By application of a computational chemistry method General Utility Lattice Program (GULP), it is demonstrated that the unique non-whole-number Na/P molar ratio of sodium ferric hydroxyphosphate is a consequence of its open-cage structure in which the H{sup +} and excess Na{sup +} ions are located.

The tarantula toxins ProTx-II and huwentoxin-IV differentially interact with human Nav1.7 voltage sensors to inhibit channel activation and inactivation.

Science.gov (United States)

Xiao, Yucheng; Blumenthal, Kenneth; Jackson, James O; Liang, Songping; Cummins, Theodore R

2010-12-01

The voltage-gated sodium channel Na(v)1.7 plays a crucial role in pain, and drugs that inhibit hNa(v)1.7 may have tremendous therapeutic potential. ProTx-II and huwentoxin-IV (HWTX-IV), cystine knot peptides from tarantula venoms, preferentially block hNa(v)1.7. Understanding the interactions of these toxins with sodium channels could aid the development of novel pain therapeutics. Whereas both ProTx-II and HWTX-IV have been proposed to preferentially block hNa(v)1.7 activation by trapping the domain II voltage-sensor in the resting configuration, we show that specific residues in the voltage-sensor paddle of domain II play substantially different roles in determining the affinities of these toxins to hNa(v)1.7. The mutation E818C increases ProTx-II's and HWTX-IV's IC(50) for block of hNa(v)1.7 currents by 4- and 400-fold, respectively. In contrast, the mutation F813G decreases ProTx-II affinity by 9-fold but has no effect on HWTX-IV affinity. It is noteworthy that we also show that ProTx-II, but not HWTX-IV, preferentially interacts with hNa(v)1.7 to impede fast inactivation by trapping the domain IV voltage-sensor in the resting configuration. Mutations E1589Q and T1590K in domain IV each decreased ProTx-II's IC(50) for impairment of fast inactivation by ~6-fold. In contrast mutations D1586A and F1592A in domain-IV increased ProTx-II's IC(50) for impairment of fast inactivation by ~4-fold. Our results show that whereas ProTx-II and HWTX-IV binding determinants on domain-II may overlap, domain II plays a much more crucial role for HWTX-IV, and contrary to what has been proposed to be a guiding principle of sodium channel pharmacology, molecules do not have to exclusively target the domain IV voltage-sensor to influence sodium channel inactivation.

Tantalum-Addition Effect on Tensile and Creep Properties in 9Cr-0.5Mo-2W-V-Nb Steels

International Nuclear Information System (INIS)

Kim, Woo Gon; Kim, Sung Ho; Back, Jong Hyuk; Kim, Tae Kyu; Lee, Chan Bock

2011-01-01

Ferritic/martensitic steels (FMS) are being considered prospectively as cladding materials of a SFR fuel in Gen-IV nuclear systems. There are sound technical justifications for these material selections, and the adoption of the FM steels for a wide range of nuclear and non-nuclear applications has generated much industrial technology and experience. However, there are strong incentives to develop advanced materials, especially cladding, for a Gen-IV SFR. To develop an improved FM steel for the Gen-IV SFR fuel cladding in Korea, a R and D program has been progressed since 2007. Categories of materials considered in the program included 8∼12% Cr FM steels. A strong recommendation was made for the development of a high strength steel equivalent to or superior to ASTM Gr.92 steel (hereafter Gr. 92) to offset the difficulties encountered with commercial available high Cr (8∼12%) steels. Since the fuel cladding in a Gen-IV SFR would operate under higher temperatures than 600 .deg. C, contacting with liquid sodium, and be irradiated by neutrons to as high as 200dpa, the developed cladding should thus sustain both superior irradiation and temperature stabilities during its operational life. The newly developed advanced steel should also overcome severe drawbacks: mechanical properties, especially creep, are deteriorated at a higher temperature over 600 .deg. C. The aim of this study is to investigate the effect of Ta addition on the tensile and creep properties of the three alloys which are designed, manufactured and tested. Their properties are obtained and compared for developing new FM fuel cladding materials

Synthesis and reactivity of triscyclopentadienyl uranium (III) and (IV) complexes

International Nuclear Information System (INIS)

Berthet, J.C.

1992-01-01

The reactions of (RC 5 H 4 ) 3 U with R=trimethylsilylcyclopentadienyl or tertiobutylcyclopentadienyl are studied for the synthesis of new uranium organometallic compounds. Reactions with sodium hydride are first described uranium (III) anionic hydrides obtained are oxidized for synthesis of stable uranium (IV) organometallic hydrides. Stability of these compounds is discussed. Reactivity of these uranium (III) and (IV) hydrides are studied. Formation of new binuclear compounds with strong U-O and U-N bonds is examined and crystal structure are presented. Monocyclooctatetraenylic uranium complexes are also investigated

{sup 20}F power measurement for generation IV sodium fast reactors

Energy Technology Data Exchange (ETDEWEB)

Coulon, R.; Normand, S.; Michel, M.; Barbot, L.; Domenech, T.; Boudergui, K.; Bourbotte, J.M.; Kondrasovs, V.; Frelin-Labalme, A.M.; Hamrita, H. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, F-91191 Gif-sur-Yvette (France); BAN, G. [ENSICAEN, 6 Boulevard Marechal Juin, F-14050 Caen Cedex 4 (France); Barat, E.; Dautremer, T.; Montagu, T.; Carrel, F. [CEA, LIST, Laboratoire Modelisation Simulation et Systemes, F-91191 Gif-sur-Yvette (France); Brau, H.P. [ICSM, Centre de Marcoule, BP 17171 F-30207 Bagnols sur Ceze (France); Dumarcher, V. [AREVA NP, SET, F-84500 Bollene (France); Portier, J.L. [Centrale PHENIX, Centre de Marcoule, Groupe Essais Statistiques, F-30207 Bagnols sur Ceze (France); Jousset, P. [CEA, LIST, Laboratoire Capteurs Diamant, F-91191 Gif-sur-Yvette (France); Saurel, N. [CEA, DAM, Laboratoire Mesure de Dechets et Expertise, F-21120 Is-sur-Tille, France.F-84500 Bollene (France)

2010-07-01

The Phenix nuclear power plant has been a French Sodium Fast Reactor (SFR) prototype producing electrical power between 1973 and 2010. The power was monitored using ex-core neutron measurements. This kind of measurement instantly estimates the power but needs to be often calibrated with the heat balance thermodynamic measurement. Large safety and security margins have then been set not to derive above the nominal operating point. It is important for future SFR to reduce this margin and working closer to the nominal operating point. This work deals with the use of delayed gamma to measure the power. The main activation product contained in the primary sodium coolant is the {sup 24}Na which is not convenient for neutron flux measurement due to its long decay period. The experimental study done at the Phenix reactor shows that the use of {sup 20}F as power tagging agent gives a fast and accurate power measurement closed to the thermal balance measurement thanks to its high energy photon emission (1.634 MeV) and its short decay period (11 s). (authors)

Drop performance test of conceptually designed control rod assembly for prototype generation IV sodium-cooled fast reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Kyu; Lee, Jae Han; Kim, Hoe Woong; KIm, Sung Kyun; Kim, Jong Bum [Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-06-15

The control rod assembly controls reactor power by adjusting its position during normal operation and shuts down chain reactions by its free drop under scram conditions. Therefore, the drop performance of the control rod assembly is important for the safety of a nuclear reactor. In this study, the drop performance of the conceptually designed control rod assembly for the prototype generation IV sodium-cooled fast reactor that is being developed at the Korea Atomic Energy Research Institute as a next-generation nuclear reactor was experimentally investigated. For the performance test, the test facility and test procedure were established first, and several free drop performance tests of the control rod assembly under different flow rate conditions were then carried out. Moreover, performance tests under several types and magnitudes of seismic loading conditions were also conducted to investigate the effects of seismic loading on the drop performance of the control rod assembly. The drop time of the conceptually designed control rod assembly for 0% of the tentatively designed flow rate was measured to be 1.527 seconds, and this agrees well with the analytically calculated drop time. It was also observed that the effect of seismic loading on the drop time was not significant.

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

Étude de l'effet modérateur de sels sur la réaction sodium-eau, pour le "lavage" d'assemblages de combustible irradiés issus de réacteurs à caloporteur sodium

OpenAIRE

Lacroix , Marie

2014-01-01

Within the framework of the development of generation IV reactors one of the research tracks is related to the development of fast neutron reactors using fluid sodium heat transfer...; Dans le cadre du développement des réacteurs de génération IV, une des voies de recherche concerne le développement des réacteurs à neutron rapide à caloporteur sodium. Le CEA a pour projet la construction d'un prototype de réacteur de ce type appelé " ASTRID ". En réponse aux besoins de développement de ce pro...

Comparison of Core Performance with Various Oxide fuels on Sodium Cooled Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Choi, Jin Ha; Kim, Myung Hyun [Kyung Hee University, Yongin (Korea, Republic of)

2016-05-15

The system is called Prototype GenIV Sodium-cooled Fast Reactor (PGSFR). Ultimate goal of PGSFR is test for capability of TRU transmutation. Purpose of this study is test for evaluation of in-core performance and TRU transmutation performance by applying various oxide fuel loaded TRU. Fuel type of reference core is changed to uranium-based oxide fuel. Oxide fuel has a lot of experience through fuel fabrication and reactor operation. This study performed by compared and analyzed a core performance of various oxide fuels. (U,Pu)O{sub 2} and (U,TRU)O{sub 2} which various oxide fuel types are selected as extreme case for comparison with core performance and transmutation capability of TRU isotopes. Thorium-based fuel is known that it has good performance for burner reactor due to low proliferation characteristic. To check the performance of TRU incineration for comparison with uranium-based fuel on prototype SFR, Thorium-based fuel, (Th,U)O{sub 2}, (Th,Pu)O{sub 2} and (Th,TRU)O{sub 2}, is selected. Calculations of core performance for various oxide fuel are performed using the fast calculation tool, TRANSX / DANTSTS / REBUS-3. In this study, comparison of core performance and transmutation performance is conducted with various fuel types in a sodium-cooled fast reactor. Mixed oxide fuel with TRU can produce the energy with small amount of fissile material. However, the TRU fuel is confirmed to bring a potential decline of the safety parameters. In case of (Th,U)O2 fuel, the flux level in thermal neutron region becomes lower because of higher capture cross-section of Th-232 than U-238. However, Th-232 has difficulty in converting to TRU isotopes. Therefore, the TRU consumption mass is relatively high in mixed oxide fuel with thorium and TRU.

Comparison of Core Performance with Various Oxide fuels on Sodium Cooled Fast Reactor

International Nuclear Information System (INIS)

Choi, Jin Ha; Kim, Myung Hyun

2016-01-01

The system is called Prototype GenIV Sodium-cooled Fast Reactor (PGSFR). Ultimate goal of PGSFR is test for capability of TRU transmutation. Purpose of this study is test for evaluation of in-core performance and TRU transmutation performance by applying various oxide fuel loaded TRU. Fuel type of reference core is changed to uranium-based oxide fuel. Oxide fuel has a lot of experience through fuel fabrication and reactor operation. This study performed by compared and analyzed a core performance of various oxide fuels. (U,Pu)O_2 and (U,TRU)O_2 which various oxide fuel types are selected as extreme case for comparison with core performance and transmutation capability of TRU isotopes. Thorium-based fuel is known that it has good performance for burner reactor due to low proliferation characteristic. To check the performance of TRU incineration for comparison with uranium-based fuel on prototype SFR, Thorium-based fuel, (Th,U)O_2, (Th,Pu)O_2 and (Th,TRU)O_2, is selected. Calculations of core performance for various oxide fuel are performed using the fast calculation tool, TRANSX / DANTSTS / REBUS-3. In this study, comparison of core performance and transmutation performance is conducted with various fuel types in a sodium-cooled fast reactor. Mixed oxide fuel with TRU can produce the energy with small amount of fissile material. However, the TRU fuel is confirmed to bring a potential decline of the safety parameters. In case of (Th,U)O2 fuel, the flux level in thermal neutron region becomes lower because of higher capture cross-section of Th-232 than U-238. However, Th-232 has difficulty in converting to TRU isotopes. Therefore, the TRU consumption mass is relatively high in mixed oxide fuel with thorium and TRU.

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.

Generation IV reactors and the ASTRID prototype: lessons from the Fukushima accident

International Nuclear Information System (INIS)

Gauche, F.

2012-01-01

In France, the ASTRID prototype is an industrial demonstrator of a sodium-cooled fast neutron reactor (SFR), fulfilling the criteria for Generation IV reactors. ASTRID will meet safety requirements as stringent as for third generation reactors, and it takes into account lessons from the Fukushima accident. The objectives are to reinforce the robustness of the safety demonstration for all safety functions. ASTRID will feature an innovative core with a negative sodium void coefficient, it will take advantage of the large thermal inertia of SFR for decay heat removal, and will provide for a design either eliminating the sodium-water reaction, or guaranteeing no consequences for safety in case such reaction would take place. (author)

Objective Provision Trees of Reactivity Control Safety Function for Sodium-Cooled Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Kang, Bongsuk; Yang, Huichang [TUEV Rheinland Korea Ltd., Seoul (Korea, Republic of); Suh, Namduk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-05-15

The purpose of this OPT is first to assure the DiD design during the licensing of Sf, but it will also contribute in evaluating the completeness of regulatory requirements under development by Korea Institute of Nuclear Safety (KINS). Based on the definition of Defense-in-Depth (DiD) levels and safety functions for KALIMER Sodium-Cooled Fast Reactor (SFR), suggested in the reference and, Objective Provision Trees (OPTs) of reactivity control function for level 1, 2, 3 and 4 DiD were developed and suggested in this paper. The challenges and mechanisms and provisions were briefly explained in this paper. Comparing the mechanisms and provisions with the requirements will contribute in identifying the missing requirements. Since the design of Prototype Gen-IV Sf (PGSFR) is not mature yet, the OPT is developed for KALIMER design. Developed level 1 to 4 OPTs in this study can be used for the identification of potential design vulnerabilities. When detailed identification of provisions in terms of design features were achieved through the next step of this study, it can contribute to the establishment of defense-in-depth evaluation frame for the regulatory reviews for the licensing process. In the next stage of this study, other safety function will be researched and findings can be suggested as recommendations for the safety improvement.

Objective Provision Trees of Reactivity Control Safety Function for Sodium-Cooled Fast Reactor

International Nuclear Information System (INIS)

Kang, Bongsuk; Yang, Huichang; Suh, Namduk

2014-01-01

The purpose of this OPT is first to assure the DiD design during the licensing of Sf, but it will also contribute in evaluating the completeness of regulatory requirements under development by Korea Institute of Nuclear Safety (KINS). Based on the definition of Defense-in-Depth (DiD) levels and safety functions for KALIMER Sodium-Cooled Fast Reactor (SFR), suggested in the reference and, Objective Provision Trees (OPTs) of reactivity control function for level 1, 2, 3 and 4 DiD were developed and suggested in this paper. The challenges and mechanisms and provisions were briefly explained in this paper. Comparing the mechanisms and provisions with the requirements will contribute in identifying the missing requirements. Since the design of Prototype Gen-IV Sf (PGSFR) is not mature yet, the OPT is developed for KALIMER design. Developed level 1 to 4 OPTs in this study can be used for the identification of potential design vulnerabilities. When detailed identification of provisions in terms of design features were achieved through the next step of this study, it can contribute to the establishment of defense-in-depth evaluation frame for the regulatory reviews for the licensing process. In the next stage of this study, other safety function will be researched and findings can be suggested as recommendations for the safety improvement

Review on Korea Participation of Generation IV International Forum (GIF)

International Nuclear Information System (INIS)

Lee, Jewhan; Jeong, Ji-Young; Hahn, Dohee

2015-01-01

Generation IV International Forum (GIF) originates from US proposal of an initiative in 2000. The vision was to leapfrog LWR technology and collaborate with international partners to share R and D on advanced nuclear systems. Nine countries and EU joined the initiative and Gen IV concept was defined via technology goals and legal framework. Two years study with more than 100 experts worldwide has evaluated nearly 100 reactor designs and down selected six most promising concepts. In 2005, the first signatures on Framework Agreement were collected and the first research projects were defined in 2006. Korea is one of the founding members of GIF and actively participating in various areas. In 2013, TD was assigned to Korean expert and Korea is endeavoring to enhance the benefit of participation since this turning point. In this paper, pros and cons of engaging with GIF were briefly introduced and items to maximize the benefit were suggested

Review on Korea Participation of Generation IV International Forum (GIF)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jewhan; Jeong, Ji-Young; Hahn, Dohee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Generation IV International Forum (GIF) originates from US proposal of an initiative in 2000. The vision was to leapfrog LWR technology and collaborate with international partners to share R and D on advanced nuclear systems. Nine countries and EU joined the initiative and Gen IV concept was defined via technology goals and legal framework. Two years study with more than 100 experts worldwide has evaluated nearly 100 reactor designs and down selected six most promising concepts. In 2005, the first signatures on Framework Agreement were collected and the first research projects were defined in 2006. Korea is one of the founding members of GIF and actively participating in various areas. In 2013, TD was assigned to Korean expert and Korea is endeavoring to enhance the benefit of participation since this turning point. In this paper, pros and cons of engaging with GIF were briefly introduced and items to maximize the benefit were suggested.

The concepts of liquid metal of IV generation

International Nuclear Information System (INIS)

Carbonnier, J. L.

2005-01-01

The concepts of liquid metals, due to their large spectrum, show important possibility of sustainable development: two concepts of liquid metal (Sodium and Lead) were engaged in the frame of the IV generation. The reactors with sodium benefit from considerable background of experience and of important work on projects to aim at the price diminution and the increase of safety (EFR, JSFR). The commitment of Japan as a leader of this concept and the support by France allow to contemplate an industrial deployment from 2015. The lead reactors offer some advantages in the domain of safety but otherwise require a highly important research and development binded to the control of the corrosion, the perspective of deployment of this concept are more hypothetical

Safety design approach for JSFR toward the realization of GEN IV SFR

International Nuclear Information System (INIS)

Kubo, S.; Yamano, H.; Chikazawa, Y.; Shimakawa, Y.

2013-01-01

Conclusion: Safety Design Approach for JSFR: • Based on the safety design criteria for Generation-IV SFR • DECs, Situations practically eliminated and related design measures are identified and selected with due consideration of the safety features of SFR and the lessons learned from the TEPCO’s Fukushima Dai-ichi nuclear power plants accident Safety Design Concept of JSFR: • For failure to shutdown: Passive shutdown capability, Mitigation of core damage (Prevention of severe mechanical energy release, In-Vessel Retention) • For failure to remove heat: Prevention of significant core damage (Natural circulation DHR, Alternative cooling measures) • Containment: Prevention of sever dynamic loads by design measures (IVR, double boundary concept, inertization)

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

Organoclays obtaining starting up of clays sodium

International Nuclear Information System (INIS)

Silva, M.M. da; Mota, M.F.; Oliveira, G.C. de; Rodrigues, M.G.F.

2012-01-01

Clays have several applications in many areas of fields of technology, however, modification of these materials using organic compounds can be performed to obtain further hydrophobic materials, for applications in the adsorption of organic pollutants. This study aimed to analyze the effects of modifying two clays using sodium quaternary ammonium surfactants through ion exchange reaction process, in obtaining organoclays. The samples with sodium and organoclays were characterized by the techniques of X-ray diffraction (XRD), Infrared Spectroscopy in the region (IV), Gravimetric and Differential Thermal Analysis (DTA / TG) and organic adsorption tests. The results show that the process of obtaining organoclay is efficient, and materials have the potential for future applications in removing organic contaminants. (author)

Methylbutylmalonamide as an extractant for U(VI), Pu(IV), and Am(III)

International Nuclear Information System (INIS)

Nair, G.M.; Prabhu, D.R.; Mahajan, G.R.

1994-01-01

The unsymmetrical diamide methylbutylmalonamide has been synthesized and used in the extraction of U(VI), Pu(IV), and Am(III) in benzene medium. The distribution ratio for three cations was found to increase with increasing aqueous nitric acid concentration. U(VI) and Pu(IV) were found to be extracted as disolvates while Am(III) as a trisolvate. The thermodynamic parameters determined by the temperature variation method showed the extraction reactions to be mainly enthalphy-controlled. Am(III) was found to be back-extracted with dilute nitric acid, while Pu(IV) by dilute nitric acid - hydrofluoric acid mixture and U(VI) by dilute sodium carbonate solution. (author) 6 refs.; 3 figs.; 2 tabs

Sodium ferric gluconate (SFG) in complex with sucrose for IV infusion: bioequivalence of a new generic product with the branded product in healthy volunteers.

Science.gov (United States)

Baribeault, David

2011-08-01

Parenteral sodium ferric gluconate in complex (Ferrlecit [branded SFG]) is used to treat patients with iron deficiency anemia undergoing chronic hemodialysis and receiving supplemental epoetin. This comparative pharmacokinetic study (GeneraMedix, Inc., Study 17909) evaluates whether the recently approved generic product Nulecit (generic SFG) and the branded product Ferrlecit (branded SFG) are bioequivalent. In this open-label study, 240 healthy volunteers in a fasting state were assigned randomly to a single 10-min intravenous (IV) infusion of 125 mg of generic or branded SFG. Total and transferrin-bound iron concentrations were determined for the 36-h period after infusion and corrected for pretreatment levels. Maximum concentration (Cmax) and area under the concentration-time curve of 0 to 36 h (AUC[0-36]) were compared between the two products. Demonstration of bioequivalence required that the 90% confidence intervals of each parameter evaluated for generic SFG were within 80% to 125% of the corresponding values for branded SFG. Uncorrected and baseline-corrected mean serum concentrations of total serum iron during the 36-h assessment period were similar for generic and branded SFG. For total serum iron, the geometric mean ratios of corrected Cmax and AUC[0-36] were 100%. For transferrin-bound iron, the geometric mean ratios were 87% for corrected Cmax and 92% for corrected AUC[0-36]. All associated 90% confidence intervals were within the range of 80% to 125%. A new generic SFG in complex for IV infusion is bioequivalent to the branded SFG in complex for IV infusion. The generic SFG is AB rated by the FDA and considered therapeutically equivalent to the branded product.

Design and evaluation of a thorium (IV) selective optode

International Nuclear Information System (INIS)

Safavi, Afsaneh; Sadeghi, Marzieh

2006-01-01

A novel optical sensor has been proposed for sensitive determination of thorium (IV) ion in aqueous solutions. The thorium sensing membrane was prepared by incorporating 4-(p-nitrophenyl azo)-pyrocatechol (NAP) as ionophore in the plasticized PVC membrane containing tributyl phosphate (TBP) as plasticizer. The membrane responds to thorium ion by changing color reversibly from yellow to red-brown in glycine buffer solution at pH 3.5. The proposed sensor displays a linear range of 8.66 x 10 -6 -2.00 x 10 -4 M with a limit of detection of 6 x 10 -6 M. The response time of the optode was about 8.8-12.5 min, depending on the concentration of Th (IV) ions. The selectivity of optode to Th (IV) ions in glycine buffer is good. The sensor can readily be regenerated by exposure to a solution mixture of sodium fluoride and 5-sulfosalicylic acid (dihydrate) (0.01 M each). The optode is fully reversible. The proposed optode was applied to the determination of thorium (IV) in environmental water samples

Mapping the interaction site for the tarantula toxin hainantoxin-IV (β-TRTX-Hn2a) in the voltage sensor module of domain II of voltage-gated sodium channels.

Science.gov (United States)

Cai, Tianfu; Luo, Ji; Meng, Er; Ding, Jiuping; Liang, Songping; Wang, Sheng; Liu, Zhonghua

2015-06-01

Peptide toxins often have pharmacological applications and are powerful tools for investigating the structure-function relationships of voltage-gated sodium channels (VGSCs). Although a group of potential VGSC inhibitors have been reported from tarantula venoms, little is known about the mechanism of their interaction with VGSCs. In this study, we showed that hainantoxin-IV (β-TRTX-Hn2a, HNTX-IV in brief), a 35-residue peptide from Ornithoctonus hainana venom, preferentially inhibited rNav1.2, rNav1.3 and hNav1.7 compared with rNav1.4 and hNav1.5. hNav1.7 was the most sensitive to HNTX-IV (IC50∼21nM). In contrast to many other tarantula toxins that affect VGSCs, HNTX-IV at subsaturating concentrations did not alter activation and inactivation kinetics in the physiological range of voltages, while very large depolarization above +70mV could partially activate toxin-bound hNav1.7 channel, indicating that HNTX-IV acts as a gating modifier rather than a pore blocker. Site-directed mutagenesis indicated that the toxin bound to site 4, which was located on the extracellular S3-S4 linker of hNav1.7 domain II. Mutants E753Q, D816N and E818Q of hNav1.7 decreased toxin affinity for hNav1.7 by 2.0-, 3.3- and 130-fold, respectively. In silico docking indicated that a three-toed claw substructure formed by residues with close contacts in the interface between HNTX-IV and hNav1.7 domain II stabilized the toxin-channel complex, impeding movement of the domain II voltage sensor and inhibiting hNav1.7 activation. Our data provide structural details for structure-based drug design and a useful template for the design of highly selective inhibitors of a specific subtype of VGSCs. Copyright © 2014 Elsevier Inc. All rights reserved.

Comparative Evaluation of Tensile Strength in Die Stone Incorporated with Sodium and Calcium Hypochlorite as Disinfectants: An in vitro Study.

Science.gov (United States)

Pramodh, N R; Kumar, C N Vijay; Pradeep, M R; Naik, Ravi; Mahesh, C S; Kumari, Manju R

2017-12-01

The aim of this study was to evaluate the tensile strength of die stone incorporated with sodium and calcium hypochlorite as disinfectants. Two commercially available type IV die stone (Kalrock: Kalabhai Karson Pvt., Ltd and Pearlstone: Asian Chemicals) and two commercially available disinfectant solutions (sodium hypochlorite and calcium hypochlorite: Beachem Laboratory Chemical Private Limited, Chennai and Leo Chem Private Limited, Bengaluru) were used in this study, and the tensile strength was measured using Lloyd's Universal Testing Machine. The results show that incorporating the disinfecting solutions decreases the tensile strength of both products. The effect of decreasing tensile strength on type IV gypsum product is seen more in calcium hypochlorite when compared with sodium hypochlorite disinfecting solution, and the tensile strength of Kalrock specimens is higher than Pearlstone specimens after disinfecting with sodium hypochlorite and calcium hypochlorite solution. The statistical results also show significant results in all the groups when compared with the control group. The incorporation of sodium and calcium hypochlorite disinfecting solutions is not an encouraging method for both die materials as it reduces the tensile strength of type IV gypsum product. Tensile strength of Kalstone® die material is superior than Pearlstone® die material after mixing with sodium hypochlorite and calcium hypochlorite. According to the recommendations of Americans with Disability Act (ADA) and the Centers for Disease Control and Prevention, disinfecting the whole cast without or minimal changes in physical and mechanical properties was the motto of the study. The tensile strength in type IV gypsum product plays a most important role in retrieval of cast from impression, especially in narrow tooth preparation. This study reveals that incorporating method of disinfecting solutions is not recommended as it reduces the tensile strength.

Performance evaluation study of IHX-IV seal assembly

Energy Technology Data Exchange (ETDEWEB)

Padmakumar, G.; Venkatramanan, J.; Balasubramanian, V.; Prakash, V.; Vaidyanathan, G. [Indira Gandhi Centre for Atomic Research, Kalpakkam - 603102 (India); Konnur, M.S.; Ram Mohan, S.; Suresh, M.; Manikandan, S.; Rajesh, V. [Fluid Control Research Institute, Palakkad - 678 623 (India)

2005-07-01

Full text of publication follows: The construction of the 500 MWe Prototype Fast Breeder Reactor (PFBR) has commenced at IGCAR, Kalpakkam. PFBR has four intermediate Heat Exchangers (IHX) and two primary Sodium Pumps. The secondary circuits consist of two loops with each loop having one secondary pump, two intermediate heat exchangers, one surge tank and four steam generators. Primary circuit has both hot and cold sodium and is separated into hot and cold pools by Inner Vessel(IV). IHX forms the interface between the primary circuit and secondary circuit of PFBR. The IHX and pumps are supported from at the top in the roof slab and penetrate through the conical portion of inner vessel. Proper sealing arrangements are necessary to prevent leakage of hot sodium into the cold pool through the penetration. The Mechanical Seal is employed to minimize the leakage through the penetration. This seal arrangement can facilitate Differential radial and thermal expansion between IHX and IV stand pipe at the region of penetration Relative tilting between the axis of IHX and IV stand pipe Smooth installation during commissioning and easy removal during maintenance Minimizes the forces transmitted to IV The hydraulic simulation study, of the IHX - IV mechanical seal assembly was undertaken at the Fluid Control Research Institute, Palghat. The seal has two leakage paths viz. Axial and radial. The leakage depends on the contact pressure on the sealing surface and the head causing the leakage. High leakage flow may lead to damage of inner vessel and may affect the thermal efficiency of the IHX. CFD analysis of the geometry was done in detail. This was done for prototype and the model condition. The optimized design obtained using CFD was employed for experimental evaluation. In the experimental set up, the leakage characteristics was studied for varying axial and radial clearance that prevails during the various stages of operation of the seal assembly in the reactor. A 1/2 scaled

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!

Adult presentation of Bartter syndrome type IV with erythrocytosis.

Science.gov (United States)

Heilberg, Ita Pfeferman; Tótoli, Cláudia; Calado, Joaquim Tomaz

2015-01-01

Bartter syndrome comprises a group of rare autosomal-recessive salt-losing disorders with distinct phenotypes, but one unifying pathophysiology consisting of severe reductions of sodium reabsorption caused by mutations in five genes expressed in the thick ascending limb of Henle, coupled with increased urinary excretion of potassium and hydrogen, which leads to hypokalemic alkalosis. Bartter syndrome type IV, caused by loss-of-function mutations in barttin, a subunit of chloride channel CLC-Kb expressed in the kidney and inner ear, usually occurs in the antenatal-neonatal period. We report an unusual case of late onset presentation of Bartter syndrome IV and mild phenotype in a 20 years-old man who had hypokalemia, deafness, secondary hyperparathyroidism and erythrocytosis.

Isotopic exchange rate of sodium ions between hydrous metal oxides and aqueous solutions

International Nuclear Information System (INIS)

Inoue, Yasushi; Yamazaki, Hiromichi

1991-01-01

To elucidate the kinetics of ion-exchange reaction on hydrous metal oxide, the isotopic exchange rates of sodium ions between hydrous metal oxides such as hydrous tin (IV), niobium (V), zirconium (IV) and titanium (IV) oxides, and aqueous solutions were measured radiochemically and compared with each other. The rate of reaction cannot be understood by an unified view since the rate controlling step differs with the kind of exchangers. The rate constants relevant to each exchanger such as diffusion constants and their activation energies were also determined. (author)

β1 subunit stabilises sodium channel Nav1.7 against mechanical stress.

Science.gov (United States)

Körner, Jannis; Meents, Jannis; Machtens, Jan-Philipp; Lampert, Angelika

2018-06-01

The voltage-gated sodium channel Nav1.7 is a key player in neuronal excitability and pain signalling. In addition to voltage sensing, the channel is also modulated by mechanical stress. Using whole-cell patch-clamp experiments, we discovered that the sodium channel subunit β1 is able to prevent the impact of mechanical stress on Nav1.7. An intramolecular disulfide bond of β1 was identified to be essential for stabilisation of inactivation, but not activation, against mechanical stress using molecular dynamics simulations, homology modelling and site-directed mutagenesis. Our results highlight the role of segment 6 of domain IV in fast inactivation. We present a candidate mechanism for sodium channel stabilisation against mechanical stress, ensuring reliable channel functionality in living systems. Voltage-gated sodium channels are key players in neuronal excitability and pain signalling. Precise gating of these channels is crucial as even small functional alterations can lead to pathological phenotypes such as pain or heart failure. Mechanical stress has been shown to affect sodium channel activation and inactivation. This suggests that stabilising components are necessary to ensure precise channel gating in living organisms. Here, we show that mechanical shear stress affects voltage dependence of activation and fast inactivation of the Nav1.7 channel. Co-expression of the β1 subunit, however, protects both gating modes of Nav1.7 against mechanical shear stress. Using molecular dynamics simulation, homology modelling and site-directed mutagenesis, we identify an intramolecular disulfide bond of β1 (Cys21-Cys43) which is partially involved in this process: the β1-C43A mutant prevents mechanical modulation of voltage dependence of activation, but not of fast inactivation. Our data emphasise the unique role of segment 6 of domain IV for sodium channel fast inactivation and confirm previous reports that the intracellular process of fast inactivation can be

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…

Associations Between Genetic Variants of NADPH Oxidase-Related Genes and Blood Pressure Responses to Dietary Sodium Intervention: The GenSalt Study.

Science.gov (United States)

Han, Xikun; Hu, Zunsong; Chen, Jing; Huang, Jianfeng; Huang, Chen; Liu, Fangchao; Gu, Charles; Yang, Xueli; Hixson, James E; Lu, Xiangfeng; Wang, Laiyuan; Liu, De-Pei; He, Jiang; Chen, Shufeng; Gu, Dongfeng

2017-04-01

The aim of this study was to comprehensively test the associations of genetic variants of nicotinamide adenine dinucleotide phosphate (NADPH) oxidase-related genes with blood pressure (BP) responses to dietary sodium intervention in a Chinese population. We conducted a 7-day low-sodium intervention followed by a 7-day high-sodium intervention among 1,906 participants in rural China. BP measurements were obtained at baseline and each dietary intervention using a random-zero sphygmomanometer. Linear mixed-effect models were used to assess the additive associations of 63 tag single-nucleotide polymorphisms in 11 NADPH oxidase-related genes with BP responses to dietary sodium intervention. Gene-based analyses were conducted using the truncated product method. The Bonferroni method was used to adjust for multiple testing in all analyses. Systolic BP (SBP) response to high-sodium intervention significantly decreased with the number of minor T allele of marker rs6967221 in RAC1 (P = 4.51 × 10-4). SBP responses (95% confidence interval) for genotypes CC, CT, and TT were 5.03 (4.71, 5.36), 4.20 (3.54, 4.85), and 0.56 (-1.08, 2.20) mm Hg, respectively, during the high-sodium intervention. Gene-based analyses revealed that RAC1 was significantly associated with SBP response to high-sodium intervention (P = 1.00 × 10-6) and diastolic BP response to low-sodium intervention (P = 9.80 × 10-4). These findings suggested that genetic variants of NADPH oxidase-related genes may contribute to the variation of BP responses to sodium intervention in Chinese population. Further replication of these findings is warranted. © American Journal of Hypertension, Ltd 2017. All rights reserved. For Permissions, please email: journals.permissions@oup.com

Studies of binary cerium(IV)-praseodymium(IV) and cerium(IV)-terbium(IV) oxides as pigments for ceramic applications

International Nuclear Information System (INIS)

Furtado, L.M.L.

1991-01-01

It was investigated a series of pigments of general composition Ce 1-x Pr x O 2 , and Ce x Tb y O 2 , exhibiting radish and brown colors, respectively, and high temperature stability. The pigments were obtained by dissolving appropriate amounts of the pure lanthanide oxides in acids and precipitating the rare earths as mixed oxalates, which were isolated and calcined under air, at 1000 0 C. X-Ray powder diffractograms were consistent with a cubic structure for the pigments. Magnetic susceptibility measurements, using Gouy method, indicated the presence of Pr(IV) ions in the Ce 1-x Pr x O 2 pigments and of Terbium predominantly as Tb(III) ions in the Ce-tb mixed oxides. A new method, based on suspension of solid samples in PVA-STB gels (STB = sodium tetradecaborate), was employed for the measurements of the electronic spectra of the pigments. The thermal behaviour the pigments was investigated by the calcination of the oxalates in the temperature range of 500 to 1200 O C, from 10 to 60 minutes. (author)

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

Combustion of sodium in the open atmosphere

Energy Technology Data Exchange (ETDEWEB)

Morewith, H A; Johnson, R P; Nelson, C T; Otter, J M [Energy System Group, Rockwell International, Rockwell (United States)

1979-03-01

A series of sodium fire tests has been conducted in ambient air at a meteorological test site. This test series was designed to simulate hypothetical accidents which might occur in the heat transport system of an LMFBR. Measurements of concentration, agglomeration, fallout, and chemical species of the sodium combustion products were made as a function of downwind distance. In each of the first two tests, {approx}23 kg of 540 deg. C sodium was sprayed as a fan of 250-{mu}m sodium drops across the wind, from heights of 5 or 6 m. Each release took a few minutes. A dense sodium combustion product aerosol was formed, and quickly agglomerated to large (100 to 660 {mu}m) diameter particles. More than 50% of the aerosol mass fell out within several hundred meters of the release point. Two additional tests were performed by releasing sodium through 9.5-mm diameter jets at a height of 30 m. In each test, the sodium jet was aimed horizontally across the wind, and followed a downward parabolic trajectory, releasing burning sodium drops along its track. Again, close-in fallout due to large agglomerates was observed. A substantial amount of unburned sodium fell 30 m to the ground, where it burned. In a third type of test, sodium was burned for 60 min as pool in a 1.5m{sup 2} burn pan at 9 m/s wind velocity. Approximately 30% of the combustion products became airborne. Large agglomerates fell out as they moved downwind, depositing 1 kg/m{sup 2} at 1 m downwind from the edge of the pan. Chemical analysis of the samples indicated that the sodium fires produced mainly Na{sub 2}O, and that the conversion of NaOH was slow. Comparison were made with COMRADEX-IV code models, which are appropriate for calculating deposition and concentrations for downwind distances between 10{sup 2} and 10{sup 4} m. (author)

Combustion of sodium in the open atmosphere

International Nuclear Information System (INIS)

Morewith, H.A.; Johnson, R.P.; Nelson, C.T.; Otter, J.M.

1979-01-01

A series of sodium fire tests has been conducted in ambient air at a meteorological test site. This test series was designed to simulate hypothetical accidents which might occur in the heat transport system of an LMFBR. Measurements of concentration, agglomeration, fallout, and chemical species of the sodium combustion products were made as a function of downwind distance. In each of the first two tests, ∼23 kg of 540 deg. C sodium was sprayed as a fan of 250-μm sodium drops across the wind, from heights of 5 or 6 m. Each release took a few minutes. A dense sodium combustion product aerosol was formed, and quickly agglomerated to large (100 to 660 μm) diameter particles. More than 50% of the aerosol mass fell out within several hundred meters of the release point. Two additional tests were performed by releasing sodium through 9.5-mm diameter jets at a height of 30 m. In each test, the sodium jet was aimed horizontally across the wind, and followed a downward parabolic trajectory, releasing burning sodium drops along its track. Again, close-in fallout due to large agglomerates was observed. A substantial amount of unburned sodium fell 30 m to the ground, where it burned. In a third type of test, sodium was burned for 60 min as pool in a 1.5m 2 burn pan at 9 m/s wind velocity. Approximately 30% of the combustion products became airborne. Large agglomerates fell out as they moved downwind, depositing 1 kg/m 2 at 1 m downwind from the edge of the pan. Chemical analysis of the samples indicated that the sodium fires produced mainly Na 2 O, and that the conversion of NaOH was slow. Comparison were made with COMRADEX-IV code models, which are appropriate for calculating deposition and concentrations for downwind distances between 10 2 and 10 4 m. (author)

Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems

Energy Technology Data Exchange (ETDEWEB)

Vasudevan, Vijay [Univ. of Cincinnati, OH (United States); Carroll, Laura [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sham, Sam [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-04-06

This research project, which includes collaborators from INL and ORNL, focuses on the study of alloy 617 and alloy 800H that are candidates for applications as intermediate heat exchangers in GEN IV nuclear reactors, with an emphasis on the effects of grain size, grain boundaries and second phases on the creep properties; the mechanisms of dislocation creep, diffusional creep and cavitation; the onset of tertiary creep; and theoretical modeling for long-term predictions of materials behavior and for high temperature alloy design.

Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems

International Nuclear Information System (INIS)

Vasudevan, Vijay; Carroll, Laura; Sham, Sam

2015-01-01

This research project, which includes collaborators from INL and ORNL, focuses on the study of alloy 617 and alloy 800H that are candidates for applications as intermediate heat exchangers in GEN IV nuclear reactors, with an emphasis on the effects of grain size, grain boundaries and second phases on the creep properties; the mechanisms of dislocation creep, diffusional creep and cavitation; the onset of tertiary creep; and theoretical modeling for long-term predictions of materials behavior and for high temperature alloy design.

Comparative analysis of power conversion cycles optimized for fast reactors of generation IV; Analisis comparativo de ciclos de conversion de potencia optimizados para reactores rapidos de generacion IV

Energy Technology Data Exchange (ETDEWEB)

Perez Pichel, G. D.

2011-07-01

For the study, which is presented here, has been chosen as the specific parameters of each reactor, which are today the three largest projects within generation IV technology development: ESFR for the reactor's sodium, LEADER for the lead reactor's and finally, GoFastR in the case of reactor gas-cooled.

Innovative materials for GEN IV systems and transmutation facilities (cross-cutting research project GETMAT)

International Nuclear Information System (INIS)

Fazio, Concetta; Rieth, Michael; Gomez Briceno, Dolores; Gessi, Alessandro; Henry, Jean; Malerba, Lorenzo

2010-01-01

The objectives of the 'Generation IV and Transmutation Materials' (GETMAT) project is to contribute to the development, qualification and ranking of different types of ODS steels and to qualify Ferritic/Martensitic steels in a wide irradiation condition range. The experimental approach is complemented by the development of physical models with the aim to understand and improve the predictability of the materials performance. The GETMAT consortium is composed of fourteen Research centres, nine Universities and one Utility, from eleven European countries. The R and D tasks address (i) the materials availability, fabricability, weldability and their fundamental mechanical properties, (ii) their compatibility with aggressive coolants and development of corrosion protection methods; (iii) their performance under neutron irradiation, and (iv) starting from model alloys relevant for the two classes of alloys, the development and validation of physical models. The exploitation of results to potential end-users will occur through the 'GETMAT User Group', where exchange of information with the nuclear and steel industries, international (outside Europe) Research Organisations and engineers involved in the design of the new reactors, will occur. The exploitation of results to potential end-users will occur through the G ETMAT User Group , where exchange of information with the nuclear and steel industries, international (outside Europe) Research Organisations and engineers involved in the design of the new reactors, will occur

Caracterização genético-clínica de pacientes com fenilcetonúria no Estado de Alagoas = Genetic and clinical characterization of patients with phenylketonuria in Alagoas state, Brazil

Directory of Open Access Journals (Sweden)

Santos, Emerson Santana

2012-01-01

Conclusões: O genótipo V388M/IVS10nt11G>A foi o mais prevalente. Trinta por cento dos pacientes foram sintomáticos, provavelmente pela natureza das mutações, não adesão ao tratamento, tratamento inadequado e/ou diagnóstico tardio

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

Kinetics and mechanism of reduction of cerium(IV) by ascorbic acid

International Nuclear Information System (INIS)

Bhatt, K.; Nand, K.C.

1979-01-01

The reduction of cerium(IV) has been studied in sulfuric acid medium using ascorbic acid as the reductant. The rate is found to be function of both Ce(IV) and AH 2 concentrations. Sulfuric acid retards the rate and the inverse order with respect to sulfuric acid is unity. The addition of chloride, bisulfate and sulfate of sodium show negative salt effect and an increase in the dielectric constant of the medium shows an accelerating effect on the reaction rate. Arrhenius parameters have been evaluated. A mechanism involving intermediate formation of ascorbate radical (AH) is proposed and the derived rate law agrees well with the experimental observations. (author)

Fast reactor shield sensitivity studies for steel--sodium--iron systems

International Nuclear Information System (INIS)

Oblow, E.M.; Weisbin, C.R.

1977-01-01

A study was made of the adequacy of the current ENDF/B-IV sodium and iron neutron cross section data files for fast reactor shield design work. Experimental data from 21 fast reactor shield configurations containing large thicknesses of steel, sodium, and iron were analyzed with discrete ordinates calculations and sensitivity methods to assess the data files. This study represents the largest full-scale sensitivity analysis of benchmark quality experimental data to date. Included in the sensitivity studies were the results of the new cross section adjustment algorithms added to the FORSS code system. Conclusions were drawn about the need for more accurate data for sodium and iron elastic and discrete inelastic cross sections above 1 MeV and the values of the total cross section in the vicinity of important minima

J3Gen: A PRNG for Low-Cost Passive RFID

Directory of Open Access Journals (Sweden)

Jordi Herrera-Joancomartí

2013-03-01

Full Text Available Pseudorandom number generation (PRNG is the main security tool in low-cost passive radio-frequency identification (RFID technologies, such as EPC Gen2. We present a lightweight PRNG design for low-cost passive RFID tags, named J3Gen. J3Gen is based on a linear feedback shift register (LFSR configured with multiple feedback polynomials. The polynomials are alternated during the generation of sequences via a physical source of randomness. J3Gen successfully handles the inherent linearity of LFSR based PRNGs and satisfies the statistical requirements imposed by the EPC Gen2 standard. A hardware implementation of J3Gen is presented and evaluated with regard to different design parameters, defining the key-equivalence security and nonlinearity of the design. The results of a SPICE simulation confirm the power-consumption suitability of the proposal.

Comparison of elevated temperature design codes of ASME Subsection NH and RCC-MRx

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyeong-Yeon, E-mail: hylee@kaeri.re.kr

2016-11-15

Highlights: • Comparison of elevated temperature design (ETD) codes was made. • Material properties and evaluation procedures were compared. • Two heat-resistant materials of Grade 91 steel and austenitic stainless steel 316 are the target materials in the present study. • Application of the ETD codes to Generation IV reactor components and a comparison of the conservatism was conducted. - Abstract: The elevated temperature design (ETD) codes are used for the design evaluation of Generation IV (Gen IV) reactor systems such as sodium-cooled fast reactor (SFR), lead-cooled fast reactor (LFR), and very high temperature reactor (VHTR). In the present study, ETD code comparisons were made in terms of the material properties and design evaluation procedures for the recent versions of the two major ETD codes, ASME Section III Subsection NH and RCC-MRx. Conservatism in the design evaluation procedures was quantified and compared based on the evaluation results for SFR components as per the two ETD codes. The target materials are austenitic stainless steel 316 and Mod.9Cr-1Mo steel, which are the major two materials in a Gen IV SFR. The differences in the design evaluation procedures as well as the material properties in the two ETD codes are highlighted.

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...

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.

Comparative analysis of power conversion cycles optimized for fast reactors of generation IV

International Nuclear Information System (INIS)

Perez Pichel, G. D.

2011-01-01

For the study, which is presented here, has been chosen as the specific parameters of each reactor, which are today the three largest projects within generation IV technology development: ESFR for the reactor's sodium, LEADER for the lead reactor's and finally, GoFastR in the case of reactor gas-cooled.

Local anesthetics disrupt energetic coupling between the voltage-sensing segments of a sodium channel.

Science.gov (United States)

Muroi, Yukiko; Chanda, Baron

2009-01-01

Local anesthetics block sodium channels in a state-dependent fashion, binding with higher affinity to open and/or inactivated states. Gating current measurements show that local anesthetics immobilize a fraction of the gating charge, suggesting that the movement of voltage sensors is modified when a local anesthetic binds to the pore of the sodium channel. Here, using voltage clamp fluorescence measurements, we provide a quantitative description of the effect of local anesthetics on the steady-state behavior of the voltage-sensing segments of a sodium channel. Lidocaine and QX-314 shifted the midpoints of the fluorescence-voltage (F-V) curves of S4 domain III in the hyperpolarizing direction by 57 and 65 mV, respectively. A single mutation in the S6 of domain IV (F1579A), a site critical for local anesthetic block, abolished the effect of QX-314 on the voltage sensor of domain III. Both local anesthetics modestly shifted the F-V relationships of S4 domain IV toward hyperpolarized potentials. In contrast, the F-V curve of the S4 domain I was shifted by 11 mV in the depolarizing direction upon QX-314 binding. These antagonistic effects of the local anesthetic indicate that the drug modifies the coupling between the voltage-sensing domains of the sodium channel. Our findings suggest a novel role of local anesthetics in modulating the gating apparatus of the sodium channel.

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Final Report

International Nuclear Information System (INIS)

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-01-01

Final report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Mockups applied to design review of AP600/1000, Construction planning for AP 600, and AP 1000 maintenance evaluation. Proof of concept study also performed for GenIV PBMR models

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Final Report

Energy Technology Data Exchange (ETDEWEB)

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28

Final report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Mockups applied to design review of AP600/1000, Construction planning for AP 600, and AP 1000 maintenance evaluation. Proof of concept study also performed for GenIV PBMR models.

Extrapolation of ZPR sodium void measurements to the power reactor

International Nuclear Information System (INIS)

Beck, C.L.; Collins, P.J.; Lineberry, M.J.; Grasseschi, G.L.

1976-01-01

Sodium-voiding measurements of ZPPR assemblies 2 and 5 are analyzed with ENDF/B Version IV data. Computations include directional diffusion coefficients to account for streaming effects resulting from the plate structure of the critical assembly. Bias factors for extrapolating critical assembly data to the CRBR design are derived from the results of this analysis

Unsteady aspects of sodium-water reaction. Water clearing of sodium containing equipments

International Nuclear Information System (INIS)

Carnevali, Sofia

2012-01-01

Sodium fast Reactor (FSR) is one of the most promising nuclear reactor concepts in the frame of Generation IV Systems to be commercialised in the next decades. One important safety issue about this technology is the highly exothermal chemical reaction of sodium when brought in contact with liquid water. This situation is likely, in particular during decommissioning, when sodium needs to be firstly converted ('destroyed') into non-reactive species. This is achieved by water washing: the major products are then gaseous hydrogen and corrosive soda. Today, such operations are performed in confined chambers to mitigate the consequences of any possible abnormal conditions. It has for long been believed that the main safety problem was the combustion of hydrogen in the surrounding air despite some pioneering works suggested that even without air the reaction could be explosive. It is extremely important to clarify the phenomenology of sodium-water interactions since available knowledge does not allow a robust extrapolation of existing data/model to full scale plants. The primary objective of this work is to identify and assess the details of the phenomenology, especially at the sodium/water interface, to isolate the leading mechanisms and to propose a robust and innovative modelling approach. A large body of yet unreleased experimental data extracted from the files of the French Commissariat a l'Energie Atomique (CEA) was collated and analysed on the basis of 'explosion' physics. Some additional experiments were also performed to fill some gaps, especially about the kinetics of the reaction. The results strongly suggest that the fast expansion of gas producing a blast wave in certain conditions is a kind of vapour explosion. It also appears that any potential hydrogen-air explosion should be strongly mitigated by the large quantity of water vapour emanating also from the reaction zone. The limitations of existing modelling approaches are clearly

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

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.

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.

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

Eficiência de uso da água em genótipos de cana-de-açúcar submetidos à aplicação de herbicidas Water use efficiency in sugarcane genotypes submitted to herbicide application

Directory of Open Access Journals (Sweden)

L Galon

2010-12-01

Full Text Available Objetivou-se com este trabalho avaliar os efeitos de ametryn e trifloxysulfuronsodium, em aplicações isoladas ou em mistura, sobre as características associadas à eficiência do uso da água em genótipos de cana-de-açúcar. O delineamento experimental foi em blocos casualizados, com quatro repetições, em parcelas subdivididas. As parcelas foram compostas pelos herbicidas ametryn e trifloxysulfuron-sodium e pela mistura formulada de ametryn + trifloxysulfuron-sodium, aplicados aos 65 dias após o plantio, além de uma testemunha sem presença de plantas daninhas; e as subparcelas, pelos genótipos RB72454, RB835486, RB855113, RB867515, RB947520 e SP80-1816. Decorridos 15 dias da aplicação dos herbicidas, foram realizadas as avaliações de condutância estomática de vapores de água (Gs, gradiente entre temperatura da folha e do ar (ΔT e taxa de transpiração (E, sendo calculada ainda a eficiência do uso da água (WUE. Foi determinada também a matéria seca da parte aérea das plantas. O genótipo RB855113 foi o que apresentou maiores danos à eficiência do uso da água e transpiração, sendo, por isso, considerado o mais sensível aos herbicidas ametryn e trifloxysulfuron-sodium, enquanto os genótipos SP80-1816 e RB867515 estiveram entre os mais tolerantes. Condutância estomática, temperatura da folha, transpiração e eficiência de uso da água são características eficientes para identificar danos de herbicidas a plantas cultivadas, principalmente aqueles com efeito sobre a taxa fotossintética. Os genótipos de cana-de-açúcar avaliados diferiram quanto à sensibilidade aos herbicidas aplicados; as variedades SP80-1816 e RB867515 destacaram-se como as menos afetadas pelo ametryn e trifloxysulfuron-sodium, isolados ou em mistura, enquanto RB855113 foi a mais sensível.The objective of this study was to evaluate the effects of the herbicides ametryn and trifloxysulfuron-sodium, applied alone or in mixture, on the

Expert judgments about RD&D and the future of nuclear energy.

Science.gov (United States)

Anadón, Laura D; Bosetti, Valentina; Bunn, Matthew; Catenacci, Michela; Lee, Audrey

2012-11-06

Probabilistic estimates of the cost and performance of future nuclear energy systems under different scenarios of government research, development, and demonstration (RD&D) spending were obtained from 30 U.S. and 30 European nuclear technology experts. We used a novel elicitation approach which combined individual and group elicitation. With no change from current RD&D funding levels, experts on average expected current (Gen. III/III+) designs to be somewhat more expensive in 2030 than they were in 2010, and they expected the next generation of designs (Gen. IV) to be more expensive still as of 2030. Projected costs of proposed small modular reactors (SMRs) were similar to those of Gen. IV systems. The experts almost unanimously recommended large increases in government support for nuclear RD&D (generally 2-3 times current spending). The majority expected that such RD&D would have only a modest effect on cost, but would improve performance in other areas, such as safety, waste management, and uranium resource utilization. The U.S. and E.U. experts were in relative agreement regarding how government RD&D funds should be allocated, placing particular focus on very high temperature reactors, sodium-cooled fast reactors, fuels and materials, and fuel cycle technologies.

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.

Euratom contributions in Fast Reactor research programmes

International Nuclear Information System (INIS)

Fanghänel, Th.; Somers, J.

2013-01-01

The Sustainable Nuclear Initiative: • demonstrate long-term sustainability of nuclear energy; • demonstration reactors of Gen IV: •more efficient use of resources; • closed fuel cycle; • reduced proliferation risks; • enhanced safety features. • Systems pursued in Europe: • Sodium-cooled fast reactor SFR; • Lead-cooled fast reactor LFR; • Gas-cooled fast reactor GFR. Sustainable Nuclear Energy Technology Platform SNE-TP promotes research, development and demonstration of the nuclear fission technologies necessary to achieve the SET-Plan goals

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 ...

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.

Estudo do polimorfismo genético no gene p53 (códon 72 em câncer colorretal Role of the genetic polymorphism of p53 (codon 72 gene in colorectal cancer

Directory of Open Access Journals (Sweden)

Jacqueline Miranda de Lima

2006-03-01

Full Text Available RACIONAL: Polimorfismos genéticos são variações genéticas que podem ocorrer em seqüências codificadoras e não-codificadoras, levando a alterações qualitativas e/ou quantitativas das proteínas em questão. O p53 é o gene mais comumente alterado no câncer humano. O polimorfismo desse gene no códon 72 ocorre por substituição de uma base e tem sido associado a maior risco de câncer. OBJETIVO: Determinar a possível associação entre o polimorfismo no códon 72 (72 arginina/prolina do gene p53 e câncer colorretal. CASUÍSTICA E MÉTODOS: Foram avaliados em 100 pacientes com câncer colorretal e em 100 indivíduos sem câncer, pareados quanto ao sexo idade, o hábito de fumar, o etilismo e no grupo caso o estádio, o grau de diferenciação e a evolução da doença. O genótipo (72 arginina/prolina foi determinado por PCR, utilizando-se primers (seqüências de nucleotídeos específicos. RESULTADOS: O genótipo homozigoto arginina/arginina foi prevalente em 56% no grupo controle e em 58% no grupo caso. Não se observou diferença entre os dois grupos. No estádio IV este genótipo foi mais freqüente quando comparado ao estádio I (80% versus 14%. Não se observou diferença entre as variações do genótipo e fumo, álcool, evolução clínica ou grau de diferenciação. CONCLUSÃO: A prevalência do genótipo arginina/arginina foi a mais freqüente nos dois grupos. Não foi encontrada correlação entre maior risco de câncer e o polimorfismo no códon 72 prolina/arginina do gene p53. Apesar do pequeno número de doentes com câncer em estádio avançado (IV, estes tiveram maior prevalência do genótipo arginina/arginina.BACKGROUND: Polymorphisms are genetic variations that can occur in sequences of codons, leading to defective proteins. p53 is the most commonly gene affected in human cancer. The polymorphism of this gene occurs by a substitution of a base in codon 72 and may increase the risk of cancer. AIM: To investigate the

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....

Some observations concerning the direct titration of nitrite with cerium(IV)

International Nuclear Information System (INIS)

Muralikrishna, U.; Subrahmanyam, K.; Suryanarayana, M.V.S.; Krishnamurthy, M.

1983-01-01

Direct titration of nitrite with cerium(IV), with ferroin as indicator, is shown to give satisfactory results if the acidity is kept between 0.033 and 0.055 M at the end-point. Loss of nitrous acid owing to volatilization and decomposition is discussed. From 10 to 60 mg of sodium nitrite can be estimated with a standard deviation of 5 μg and an average error of 0.2%. (author)

Materials challenges supporting new sodium fast reactor designs

International Nuclear Information System (INIS)

Gelineau, O.; Goff, S. Dubiez-le; Dubuisson, Ph.; Dalle, F.; Blat, M.

2009-01-01

Sodium Fast Reactor is considered in France as the most mature technology of the different Generation IV systems. In the short-term the designing work is focused on the identification of the potential tracks to improve competitiveness, safety, efficiency and to reduce cost. In that frame the materials have a key role to play. This paper is focused on the new materials envisaged and on the Research and Development program launched in France by Areva NP, CEA and EDF in order to sustain the innovative design options: ferritic steels as candidates for exchangers, steam generators and possibly sodium circuits, optimization of materials and fabrication processes to improve safety and risk management, extension of material databases to take into account the 60 years life duration including irradiation and ageing effect. (author)

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.

Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations [ANIMMA--2015-IO-392

Energy Technology Data Exchange (ETDEWEB)

Jammes, C.; Filliatre, P.; Izarra, G. de [CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance (France); Elter, Zs. [CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance (France); Chalmers University of Technology, Department of Applied Physics, Division of Nuclear Engineering, SE-412 96 Goeteborg (Sweden); Verma, V. [CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance (France); Uppsala University, Division of Applied Nuclear Physics, Box 516, SE-75120 Uppsala (Sweden); Hamrita, H.; Bakkali, M. [CEA, DRT, LIST, Metrology, Instrumentation and Information Department, Saclay, 91191 Gif-sur-Yvette (France); Chapoutier, N.; Scholer, A.C.; Verrier, D. [AREVA NP, 10 rue Juliette Recamier F-69456 Lyon (France); Hellesen, C.; Jacobsson, S. [Uppsala University, Division of Applied Nuclear Physics, Box 516, SE-75120 Uppsala (Sweden); Pazsit, I. [Chalmers University of Technology, Department of Applied Physics, Division of Nuclear Engineering, SE-412 96 Goeteborg (Sweden); Cantonnet, B.; Nappe, J.C. [PHOTONIS France, Nuclear Instrumentation, 19100 Brive-la-Gaillarde (France); Molinie, P.; Dessante, P.; Hanna, R.; Kirkpatrick, M.; Odic, E. [Supelec, Energy Department, 3 rue Joliot-Curie, 91191 Gif-sur-Yvette (France)

2015-07-01

France has a long experience of about 50 years in designing, building and operating sodium-cooled fast reactors (SFR) such as RAPSODIE, PHENIX and SUPER PHENIX. Fast reactors feature the double capability of reducing nuclear waste and saving nuclear energy resources by burning actinides. Since this reactor type is one of those selected by the Generation IV International Forum, the French government asked, in the year 2006, CEA, namely the French Alternative Energies and Atomic Energy Commission, to lead the development of an innovative GEN-IV nuclear- fission power demonstrator. The major objective is to improve the safety and availability of an SFR. The neutron flux monitoring (NFM) system of any reactor must, in any situation, permit both reactivity control and power level monitoring from startup to full power. It also has to monitor possible changes in neutron flux distribution within the core region in order to prevent any local melting accident. The neutron detectors will have to be installed inside the reactor vessel because locations outside the vessel will suffer from severe disadvantages; radially the neutron shield that is also contained in the reactor vessel will cause unacceptable losses in neutron flux; below the core the presence of a core-catcher prevents from inserting neutron guides; and above the core the distance is too large to obtain decent neutron signals outside the vessel. Another important point is to limit the number of detectors placed in the vessel in order to alleviate their installation into the vessel. In this paper, we show that the architecture of the NFM system will rely on high-temperature fission chambers (HTFC) featuring wide-range flux monitoring capability. The definition of such a system is presented and the justifications of technological options are brought with the use of simulation and experimental results. Firstly, neutron-transport calculations allow us to propose two in-vessel regions, namely the above-core and under

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 ...

Coupling analysis of deformation and thermal-hydraulics in a FBR fuel pin bundle using BAMBOO and ASFRE-IV Codes

International Nuclear Information System (INIS)

Ito, Masahiro; Imai, Yasutomo; Uwaba, Tomoyuki; Ohshima, Hiroyuki

2004-03-01

The bundle-duct interaction may occur in sodium cooled wire-wrapped FBR fuel subassemblies in high burn-up conditions. JNC has been developing a bundle deformation analysis code BAMBOO (Behavior Analysis code for Mechanical interaction of fuel Bundle under On-power Operation), a thermal hydraulics analysis code ASFRE-IV (Analysis of Sodium Flow in Reactor Elements - ver. IV) and their coupling method as a simulation system for the evaluation on the integrity of deformed FBR fuel pin bundles. In this study, the simulation system was applied to a coupling analysis of deformation and thermal-hydraulics in the fuel pin-bundle under a steady-state condition just after startup for the purpose of the verification of the simulation system. The iterative calculations of deformation and thermal-hydraulics employed in the coupling analysis provided numerically unstable solutions. From the result, it was found that improvement of the coupling algorithm of BAMBOO and ASFRE-IV is necessary to reduce numerical fluctuations and to obtain better convergence by introducing such computational technique as the optimized under-relaxation method. (author)

Solubilities of sodium nitrate, sodium nitrite, and sodium aluminate in simulated nuclear waste

International Nuclear Information System (INIS)

Reynolds, D.A.; Herting, D.L.

1984-09-01

Solubilities were determined for sodium nitrate, sodium nitrite, and sodium aluminate in synthetic nuclear waste liquor. Solubilities were determined as a function of temperature and solution composition (concentrations of sodium hydroxide, sodium nitrate, sodium nitrite, and sodium aluminate). Temperature had the greatest effect on the solubilities of sodium nitrate and sodium nitrite and a somewhat lesser effect on sodium aluminate solubility. Hydroxide had a great effect on the solubilities of all three salts. Other solution components had minor effects. 2 references, 8 figures, 11 tables

Mechanism of sodium channel block by local anesthetics, antiarrhythmics, and anticonvulsants.

Science.gov (United States)

Tikhonov, Denis B; Zhorov, Boris S

2017-04-03

Local anesthetics, antiarrhythmics, and anticonvulsants include both charged and electroneutral compounds that block voltage-gated sodium channels. Prior studies have revealed a common drug-binding region within the pore, but details about the binding sites and mechanism of block remain unclear. Here, we use the x-ray structure of a prokaryotic sodium channel, NavMs, to model a eukaryotic channel and dock representative ligands. These include lidocaine, QX-314, cocaine, quinidine, lamotrigine, carbamazepine (CMZ), phenytoin, lacosamide, sipatrigine, and bisphenol A. Preliminary calculations demonstrated that a sodium ion near the selectivity filter attracts electroneutral CMZ but repels cationic lidocaine. Therefore, we further docked electroneutral and cationic drugs with and without a sodium ion, respectively. In our models, all the drugs interact with a phenylalanine in helix IVS6. Electroneutral drugs trap a sodium ion in the proximity of the selectivity filter, and this same site attracts the charged group of cationic ligands. At this position, even small drugs can block the permeation pathway by an electrostatic or steric mechanism. Our study proposes a common pharmacophore for these diverse drugs. It includes a cationic moiety and an aromatic moiety, which are usually linked by four bonds. © 2017 Tikhonov and Zhorov.

Increased renal sodium absorption by inhibition of prostaglandin synthesis during fasting in healthy man. A possible role of the epithelial sodium channels

Directory of Open Access Journals (Sweden)

Graffe Carolina C

2010-10-01

Full Text Available Abstract Background Treatment with prostaglandin inhibitors can reduce renal function and impair renal water and sodium excretion. We tested the hypotheses that a reduction in prostaglandin synthesis by ibuprofen treatment during fasting decreased renal water and sodium excretion by increased absorption of water and sodium via the aquaporin2 water channels and the epithelial sodium channels. Methods The effect of ibuprofen, 600 mg thrice daily, was measured during fasting in a randomized, placebo-controlled, double-blinded crossover study of 17 healthy humans. The subjects received a standardized diet on day 1, fasted at day 2, and received an IV infusion of 3% NaCl on day 3. The effect variables were urinary excretions of aquaporin2 (u-AQP2, the beta-fraction of the epithelial sodium channel (u-ENaCbeta, cyclic-AMP (u-cAMP, prostaglandin E2 (u-PGE2. Free water clearance (CH2O, fractional excretion of sodium (FENa, and plasma concentrations of vasopressin, angiotensin II, aldosterone, atrial-, and brain natriuretic peptide. Results Ibuprofen decreased u-AQP2, u-PGE2, and FENa at all parts of the study. During the same time, ibuprofen significantly increased u-ENaCbeta. Ibuprofen did not change the response in p-AVP, u-c-AMP, urinary output, and free water clearance during any of these periods. Atrial-and brain natriuretic peptide were higher. Conclusion During inhibition of prostaglandin synthesis, urinary sodium excretion decreased in parallel with an increase in sodium absorption and increase in u-ENaCbeta. U-AQP2 decreased indicating that water transport via AQP2 fell. The vasopressin-c-AMP-axis did not mediate this effect, but it may be a consequence of the changes in the natriuretic peptide system and/or the angiotensin-aldosterone system Trial Registration Clinical Trials Identifier: NCT00281762

Controlled release of diclofenac sodium through acrylamide grafted hydroxyethyl cellulose and sodium alginate.

Science.gov (United States)

Al-Kahtani, Ahmed A; Sherigara, B S

2014-04-15

To reinforce the hydroxyethyl cellulose for using it in biomedical and pharmaceutical applications as a drug delivery systems, the grafting of acrylamide onto hydroxyethyl cellulose (AAm-g-HEC) was achieved by Ce(IV) induced free radical polymerization. The AAm-g-HEC was then blended with sodium alginate (NaAlg) to prepare pH-sensitive interpenetrating network (IPN) microspheres (MPs) by emulsion-crosslinking method using glutaraldehyde (GA) as a crosslinking agent. The produced MPs are almost spherical in nature with smooth surfaces. Diclofenac sodium (DS), an anti-inflammatory drug, was successfully encapsulated into the MPs. The % encapsulation efficiency was found to vary between 54 and 67. The MPs were characterized by DSC, SEM and FTIR spectroscopy. In vitro release studies were carried out in simulated gastric fluid of pH 1.2 for 2h followed by simulated intestinal fluid of pH 7.4 at 37°C. The release data have been fitted to an empirical equation to investigate the diffusional exponent (n), which indicated that the release mechanism shifted from anomalous to the super Case-II transport. Copyright © 2014 Elsevier Ltd. All rights reserved.

Simplified modeling of liquid sodium medium with temperature and velocity gradient using real thermal-hydraulic data. Application to ultrasonic thermometry in sodium fast reactor

Energy Technology Data Exchange (ETDEWEB)

Massacret, N.; Jeannot, J. P. [DEN/DTN/STPA/LIET, CEA Cadarache, Saint Paul Lez Durance (France); Moysan, J.; Ploix, M. A.; Corneloup, G. [Aix-Marseille Univ, LMA UPR 7051 CNRS, site LCND, 13625 Aix-en-Provence (France)

2013-01-25

In the framework of the French R and D program for the Generation IV reactors and specifically for the sodium cooled fast reactors (SFR), studies are carried out on innovative instrumentation methods in order to improve safety and to simplify the monitoring of fundamental physical parameters during reactor operation. The aim of the present work is to develop an acoustic thermometry method to follow up the sodium temperature at the outlet of subassemblies. The medium is a turbulent flow of liquid sodium at 550 Degree-Sign C with temperature inhomogeneities. To understand the effect of disturbance created by this medium, numerical simulations are proposed. A ray tracing code has been developed with Matlab Copyright-Sign in order to predict acoustic paths in this medium. This complex medium is accurately described by thermal-hydraulic data which are issued from a simulation of a real experiment in Japan. The analysis of these results allows understanding the effects of medium inhomogeneities on the further thermometric acoustic measurement.

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...

Studies on extraction behaviour of U (VI) and Pu (IV) by Aliquat-336 encapsulated in microporous polymer beads

International Nuclear Information System (INIS)

Parikh, K.J.; Kedari, C.S.; Pandit, S.S.; Tripathi, S.C.; Dwivedi, C.; Singh, K.K.; Kumar, M.; Bajaj, P.N.

2009-01-01

Aliquat-336 encapsulated microporous polymeric beads (AEPB) were prepared to investigate their applicability for the solid-liquid extraction Pu (IV) from nitric acid solutions. Batch equilibration studies on the extractions of U (VI) and Pu (IV) from aqueous solutions using AEPB have been carried out at different concentrations of nitric acid and sodium nitrate. Extraction of Pu (IV) increases with increasing concentration of nitrate ions in the aqueous phase where as extraction of U (VI) remains less than 5% for all the aqueous conditions studied. Polymeric beads appeared to be less stable at higher nitric acid concentrations as the extraction of Pu (IV) was found to be lowered above 4 M HNO 3 concentration. The maximum Pu (IV) uptake by AEPB was 0.84 μg per mg of beads. Pu (IV)from loaded polymer can be back extracted using dilute nitric acid or ascorbic acid solution. (author)

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 ...

Potencial de vida útil pós-colheita de quatro genótipos de melão tipo Galia Potential of postharvest shelf life of four genotypes of Galia type melons

Directory of Open Access Journals (Sweden)

Patrícia Lígia Dantas de Morais

2004-12-01

Full Text Available Avaliou-se o potencial de vida útil pós-colheita de melões (Cucumis melo L. tipo Galia (genótipos Primal, Solarking, Total e Vicar. Utilizou-se o delineamento inteiramente casualizado em esquema fatorial 4 (genótipos x 4 (tempos de armazenamento: 0, 3, 6 e 9 dias, com três repetições. Os frutos foram colhidos no estádio de maturação IV (predominantemente amarelo e armazenados à temperatura de 20 ± 1ºC e umidade relativa de 50 ± 2%. O genótipo Solarking apresentou uma firmeza média de polpa superior aos demais, do inicio ao final do período de armazenamento. Em todos os genótipos, os valores de sólidos solúveis no início do armazenamento encontraram-se dentro da faixa aceitável para comercialização no mercado externo, havendo pouca variação com o decorrer do período de armazenamento. A aparência interna limitou o tempo de vida útil pós-colheita do genótipo Total em apenas seis dias. Os genótipos Solarking, Vicar e Primal apresentaram maior potencial na conservação pós-colheita, principalmente o híbrido Solarking, que chegou aos nove dias de armazenamento com boa aparência interna.The postharvest life span of Galia (genotypes Primal, Solarking, Total, and Vicar melons (Cucumis melo L. was evaluated by a four (genotypes x four (storage periods: 0, 3, 6, and 9 days factorial experiment, in a completely randomized design with three replications. The fruits were harvested at maturation stage IV (yellow color predominance, and stored under 20 ± 1ºC and HR 50 ± 2%. Solarking's average firmness was better than that of the other genotypes during the experimental period. At the beginning of the experiment all genotypes had soluble solids contents at the level (eight to ten percent required for exportation, with these levels varying slightly during storage. The internal aspect limited to six days the postharvest life span of genotype Total. Solarking, Vicar, and Primal showed great postharvest conservation potential

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.

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.

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 %

Extraction behaviour and mechanism of Pt(iv) and Pd(ii) by liquid-liquid extraction with an ionic liquid [HBBIm]Br.

Science.gov (United States)

Liu, Wenhui; Wang, Qi; Zheng, Yan; Wang, Shubin; Yan, Yan; Yang, Yanzhao

2017-06-06

In this study, a method of one-step separation and recycling of high purity Pd(ii) and Pt(iv) using an ionic liquid, 1-butyl-3-benzimidazolium bromate ([HBBIm]Br), was investigated. The effects of [HBBIm]Br concentration, initial metal concentration, and loading capacity of [HBBIm]Br were examined in detail. It was observed that [HBBIm]Br was a very effective extractant for selectively extracting Pd(ii) and precipitating Pt(iv). Through selectively extracting Pd(ii) and precipitating Pt(iv), each metal with high purity was separately obtained from mixed Pd(ii) and Pt(iv) multi-metal solution. The method of one-step separation of Pd(ii) and Pt(iv) is simple and convenient. The anion exchange mechanism between [HBBIm]Br and Pt(iv) was proven through Job's method and FTIR and 1 H NMR spectroscopies. The coordination mechanism between [HBBIm]Br and Pd(ii) was demonstrated via single X-ray diffraction and was found to be robust and distinct, as supported by the ab initio quantum-chemical studies. The crystals of the [PdBr 2 ·2BBIm] complex were formed first. Moreover, the influence of the concentrations of hydrochloric acid, sodium chloride, and sodium nitrate on the precipitation of Pt(iv) and extraction of Pd(ii) was studied herein. It was found that only the concentration of H + could inhibit the separation of Pt(iv) because H + could attract the anion PtCl 6 2- ; thus, the exchange (anion exchange mechanism) between the anions PtCl 6 2- and Br - was prevented. However, both the concentration of H + and Cl - can obviously inhibit the extraction of Pd(ii) because H + and Cl - are the reaction products and increasing their concentration can inhibit the progress of the reaction (coordination mechanism).

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.

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...

Dialysate sodium and sodium gradient in maintenance hemodialysis: a neglected sodium restriction approach?

OpenAIRE

Munoz Mendoza, Jair; Sun, Sumi; Chertow, Glenn M.; Moran, John; Doss, Sheila; Schiller, Brigitte

2011-01-01

Background. A higher sodium gradient (dialysate sodium minus pre-dialysis plasma sodium) during hemodialysis (HD) has been associated with sodium loading; however, its role is not well studied. We hypothesized that a sodium dialysate prescription resulting in a higher sodium gradient is associated with increases in interdialytic weight gain (IDWG), blood pressure (BP) and thirst.

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

Safety approach and research and development presentation for the selected systems of the International forum Generation IV

International Nuclear Information System (INIS)

Fiorini, G.L.

2003-01-01

This paper deals with the six projects of the Generation IV forum: Sodium Fast reactor, lead fast reactor, gas fast reactor, very high temperature reactor, supercritical water reactor, molten salt reactor. The technical objectives of the reactor safety and the design/evaluation approach are discussed. (A.L.B.)

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

Electroencephalographic Response to Sodium Nitrite May Predict Delayed Cerebral Ischemia After Severe Subarachnoid Hemorrhage.

Science.gov (United States)

Garry, Payashi S; Rowland, Matthew J; Ezra, Martyn; Herigstad, Mari; Hayen, Anja; Sleigh, Jamie W; Westbrook, Jon; Warnaby, Catherine E; Pattinson, Kyle T S

2016-11-01

Aneurysmal subarachnoid hemorrhage often leads to death and poor clinical outcome. Injury occurring during the first 72 hours is termed "early brain injury," with disruption of the nitric oxide pathway playing an important pathophysiologic role in its development. Quantitative electroencephalographic variables, such as α/δ frequency ratio, are surrogate markers of cerebral ischemia. This study assessed the quantitative electroencephalographic response to a cerebral nitric oxide donor (intravenous sodium nitrite) to explore whether this correlates with the eventual development of delayed cerebral ischemia. Unblinded pilot study testing response to drug intervention. Neuroscience ICU, John Radcliffe Hospital, Oxford, United Kingdom. Fourteen World Federation of Neurosurgeons grades 3, 4, and 5 patients (mean age, 52.8 yr [range, 41-69 yr]; 11 women). IV sodium nitrite (10 μg/kg/min) for 1 hour. Continuous electroencephalographic recording for 2 hours. The alpha/delta frequency ratio was measured before and during IV sodium nitrite infusion. Seven of 14 patients developed delayed cerebral ischemia. There was a +30% to +118% (range) increase in the alpha/delta frequency ratio in patients who did not develop delayed cerebral ischemia (p frequency ratio in those patients who did develop delayed cerebral ischemia (range, +11% to -31%) (p = 0.006, multivariate analysis accounting for major confounds). Administration of sodium nitrite after severe subarachnoid hemorrhage differentially influences quantitative electroencephalographic variables depending on the patient's susceptibility to development of delayed cerebral ischemia. With further validation in a larger sample size, this response may be developed as a tool for risk stratification after aneurysmal subarachnoid hemorrhage.

Gens Fera. The Wild men in the system of border decoration of the Bible of Wenceslas IV

Czech Academy of Sciences Publication Activity Database

Studničková, Milada

2014-01-01

Roč. 62, č. 3 (2014), s. 214-239 ISSN 0049-5123 R&D Projects: GA ČR GA13-39192S Institutional support: RVO:68378033 Keywords : book illumination * Bible of Wenceslas IV Subject RIV: AL - Art, Architecture, Cultural Heritage http://www.umeni-art.cz/admin/fileGet.aspx?v=issue-issue-2267-category-2268-paragraph-2269-pdf&l=cz

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...

Hepatic imaging in stage IV-S neuroblastoma

International Nuclear Information System (INIS)

Franken, E.A. Jr.; Smith, W.L.; Iowa Univ., Iowa City; Cohen, M.D.; Kisker, C.T.; Platz, C.E.

1986-01-01

Stage IV-S neuroblastoma describes a group of infants with tumor spread limited to liver, skin, or bone marrow. Such patients, who constitute about 25% of affected infants with neuroblastoma, may expect spontaneous tumor remission. We report 18 infants with Stage IV-S neuroblastoma, 83% of whom had liver involvement. Imaging investigations included Technetium 99m sulfur colloid scan, ultrasound, and CT. Two patterns of liver metastasis were noted: ill-defined nodules or diffuse tumor throughout the liver. Distinction of normal and abnormal liver with diffuse type metastasis could be quite difficult, particularly with liver scans. We conclude that patients with Stage IV-S neuroblastoma have ultrasound or CT examination as an initial workup, with nuclear medicine scans reserved for followup studies. (orig.)

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…

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.

An Antarctic hypotrichous ciliate, Parasterkiella thompsoni (Foissner) nov. gen., nov. comb., recorded in Argentinean peat-bogs: morphology, morphogenesis, and molecular phylogeny.

Science.gov (United States)

Küppers, Gabriela Cristina; Paiva, Thiago da Silva; Borges, Bárbara do Nascimento; Harada, Maria Lúcia; Garraza, Gabriela González; Mataloni, Gabriela

2011-05-01

The ciliate Parasterkiella thompsoni (Foissner, 1996) nov. gen., nov. comb. was originally described from Antarctica. In the present study, we report the morphology, morphogenesis during cell division, and molecular phylogeny inferred from the 18S-rDNA sequence of a population isolated from the Rancho Hambre peat bog, Tierra del Fuego Province (Argentina). The study is based on live and protargol-impregnated specimens. Molecular phylogeny was inferred from trees constructed by means of the maximum parsimony, neighbor joining, and Bayesian analyses. The interphase morphology matches the original description of the species. During the cell division, stomatogenesis begins with the de novo proliferation of two fields of basal bodies, each one left of the postoral ventral cirri and of transverse cirri, which later unify. Primordia IV-VI of the proter develop from disaggregation of cirrus IV/3, while primordium IV of the opisthe develops from cirrus IV/2 and primordia V and VI from cirrus V/4. Dorsal morphogenesis occurs in the Urosomoida pattern-that is, the fragmentation of kinety 3 is lacking. Three macronuclear nodules are generated before cytokinesis. Phylogenetic analyses consistently placed P. thompsoni within the stylonychines. New data on the morphogenesis of the dorsal ciliature justifies the transference of Sterkiella thompsoni to a new genus Parasterkiella. Copyright © 2011 Elsevier GmbH. All rights reserved.

Conceptual Design of Liquid Sodium Charging and Draining System of STELLA-2

Energy Technology Data Exchange (ETDEWEB)

Cho, Chungho; Nam, Ho-Yun; Kim, Jong-Man; Ko, Yung Joo; Kim, Byeongyeon; Cho, Youngil; Eoh, Jeahyuk; Yoon, Jung; Kim, Hyungmo; Lee, Hyeong-Yeon; Lee, Yong Bum; Jeong, Ji-Young; Kim, Jong-Bum [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

STELLA program consist of two phases. In the first phase of the program, separated effects tests for demonstrating the thermal-hydraulic performances of major components such as a decay heat exchanger (DHX), Natural-draft sodium-to-air heat exchanger (AHX) of the decay heat removal system, and mechanical sodium pump of the primary heat transport system (PHTS) had been successfully performed using STELLA-1 in 2015. Now is the time for us to proceed to the second phase of STELLA program. In the second phase, to demonstrate thermal-hydraulic performances and safety features and to produce base data for the specific design approval for the PGSFR (Prototype Generation IV Sodium-cooled Fast Reactor) which will be constructed by 2028 in Korea, integral effects tests will be carried out using the STELLA-2 test facility which is underway with detailed design and will be constructed in 2018. To establish the maintenance easiness of test facility and to prevent a de-functionalization of elementary sodium component located under the main experimental sodium loops, arrangement area was separated the sodium charging and draining piping area from main system experimental piping area. The operation margin of test facility and the best use of electro-magnetic pumps were established according to employ connecting line between RV charging piping and main experimental system charging piping. To prevent liquid sodium inflow into the piping of gas supply system, the overflow line was employed in sodium expansion tanks of PHDRS and ADHRS, RV, and reservoirs of IHTS.

Conceptual Design of Liquid Sodium Charging and Draining System of STELLA-2

International Nuclear Information System (INIS)

Cho, Chungho; Nam, Ho-Yun; Kim, Jong-Man; Ko, Yung Joo; Kim, Byeongyeon; Cho, Youngil; Eoh, Jeahyuk; Yoon, Jung; Kim, Hyungmo; Lee, Hyeong-Yeon; Lee, Yong Bum; Jeong, Ji-Young; Kim, Jong-Bum

2016-01-01

STELLA program consist of two phases. In the first phase of the program, separated effects tests for demonstrating the thermal-hydraulic performances of major components such as a decay heat exchanger (DHX), Natural-draft sodium-to-air heat exchanger (AHX) of the decay heat removal system, and mechanical sodium pump of the primary heat transport system (PHTS) had been successfully performed using STELLA-1 in 2015. Now is the time for us to proceed to the second phase of STELLA program. In the second phase, to demonstrate thermal-hydraulic performances and safety features and to produce base data for the specific design approval for the PGSFR (Prototype Generation IV Sodium-cooled Fast Reactor) which will be constructed by 2028 in Korea, integral effects tests will be carried out using the STELLA-2 test facility which is underway with detailed design and will be constructed in 2018. To establish the maintenance easiness of test facility and to prevent a de-functionalization of elementary sodium component located under the main experimental sodium loops, arrangement area was separated the sodium charging and draining piping area from main system experimental piping area. The operation margin of test facility and the best use of electro-magnetic pumps were established according to employ connecting line between RV charging piping and main experimental system charging piping. To prevent liquid sodium inflow into the piping of gas supply system, the overflow line was employed in sodium expansion tanks of PHDRS and ADHRS, RV, and reservoirs of IHTS

Changes in central sodium and not osmolarity or lactate induce panic-like responses in a model of panic disorder.

Science.gov (United States)

Molosh, Andre I; Johnson, Philip L; Fitz, Stephanie D; Dimicco, Joseph A; Herman, James P; Shekhar, Anantha

2010-05-01

Panic disorder is a severe anxiety disorder characterized by recurrent panic attacks that can be consistently provoked with intravenous (i.v.) infusions of hypertonic (0.5 M) sodium lactate (NaLac), yet the mechanism/CNS site by which this stimulus triggers panic attacks is unclear. Chronic inhibition of GABAergic synthesis in the dorsomedial hypothalamus/perifornical region (DMH/PeF) of rats induces a vulnerability to panic-like responses after i.v. infusion of 0.5 M NaLac, providing an animal model of panic disorder. Using this panic model, we previously showed that inhibiting the anterior third ventricle region (A3Vr; containing the organum vasculosum lamina terminalis, the median preoptic nucleus, and anteroventral periventricular nucleus) attenuates cardiorespiratory and behavioral responses elicited by i.v. infusions of NaLac. In this study, we show that i.v. infusions of 0.5 M NaLac or sodium chloride, but not iso-osmolar D-mannitol, increased 'anxiety' (decreased social interaction) behaviors, heart rate, and blood pressure responses. Using whole-cell patch-clamp preparations, we also show that bath applications of NaLac (positive control), but not lactic acid (lactate stimulus) or D-mannitol (osmolar stimulus), increases the firing rates of neurons in the A3Vr, which are retrogradely labeled from the DMH/PeF and which are most likely glutamatergic based on a separate study using retrograde tracing from the DMH/PeF in combination with in situ hybridization for vesicular glutamate transporter 2. These data show that hypertonic sodium, but not hyper-osmolarity or changes in lactate, is the key stimulus that provokes panic attacks in panic disorder, and is consistent with human studies.

Thermodynamic data for predicting concentrations of Th(IV), U(IV), Np(IV), and Pu(IV) in geologic environments

Energy Technology Data Exchange (ETDEWEB)

Rai, Dhanpat; Roa, Linfeng; Weger, H.T.; Felmy, A.R. [Battelle, Pacific Northwest National Laboratory (PNNL) (United States); Choppin, G.R. [Florida State University (United States); Yui, Mikazu [Waste Isolation Research Division, Tokai Works, Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

1999-01-01

This report provides thermodynamic data for predicting concentrations of Th(IV), U(IV), Np(IV), and Pu(IV) in geologic environments, and contributes to an integration of the JNC chemical thermodynamic database, JNC-TDB (previously PNC-TDB), for the performance analysis of geological isolation system for high-level radioactive wastes. Thermodynamic data for the formation of complexes or compounds with hydroxide, chloride, fluoride, carbonate, nitrate, sulfate and phosphate are discussed in this report. Where data for specific actinide(IV) species was lacking, the data were selected based on chemical analogy to other tetravalent actinides. In this study, the Pitzer ion-interaction model is used to extrapolate thermodynamic constants to zero ionic strength at 25degC. (author)

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.

Effectiveness of Chlorinated Water, Sodium Hypochlorite, Sodium ...

African Journals Online (AJOL)

This study evaluated the efficacy of chlorinated water, sodium hypochlorite solution, sodium chloride solution and sterile distilled water in eliminating pathogenic bacteria on the surfaces of raw vegetables. Lettuce vegetables were dipped in different concentrations of chlorinated water, sodium hypochlorite solution, sodium ...

The Chemical Chaperone, PBA, Reduces ER Stress and Autophagy and Increases Collagen IV α5 Expression in Cultured Fibroblasts From Men With X-Linked Alport Syndrome and Missense Mutations

Directory of Open Access Journals (Sweden)

Dongmao Wang

2017-07-01

Discussion: Sodium 4-phenylbutyrate increases collagen IV α5 mRNA levels, reduces ER stress and autophagy, and possibly facilitates collagen IV α5 extracellular transport. Whether these actions delay end-stage renal failure in men with X-linked Alport syndrome and missense mutations will only be determined with clinical trials.

About the structure and stability of complex carbonates of thorium (IV), cerium (IV), zirconium (IV), hafnium (IV)

International Nuclear Information System (INIS)

Dervin, Jacqueline

1972-01-01

This research thesis addressed the study of complex carbonates of cations of metals belonging to the IV A column, i.e. thorium (IV), zirconium (IV), hafnium (IV), and also cerium (IV) and uranium (VI), and more particularly focused on ionic compounds formed in solution, and also on the influence of concentration and nature of cations on stability and nature of the formed solid. The author first presents methods used in this study, discusses their precision and scope of validity. She reports the study of the formation of different complex ions which have been highlighted in solution, and the determination of their formation constants. She reports the preparation and study of the stability domain of solid complexes. The next part reports the use of thermogravimetric analysis, IR spectrometry, and crystallography for the structural study of these compounds

Assessment of Proliferation Resistance of Closed Nuclear Fuel Cycle System with Sodium Cooled Fast Reactors Using INPRO Evaluation Methodology

International Nuclear Information System (INIS)

Kim, Young In; Hahn, Do Hee; Won, Byung Chool; Lee, Dong Uk

2007-11-01

Using the INPRO methodology, the proliferation resistance of an innovative nuclear energy system(INS) defined as a closed nuclear fuel cycle system consisting of KALIMER and pyroprocessing, has been assessed. Considering a very early development stage of the INS concept, the PR assessment is carried out based on intrinsic features, if required information and data are not available. The PR assessment of KALIMER and JSFR using the INPRO methodology affirmed that an adequate proliferation resistance has been achieved in both INSs CNFC-SFR, considering the assessor's progress and maturity of design development. KALIMER and JSFR are developed or being developed conforming to the targets and criteria defined for developing Gen IV nuclear reactor system. Based on these assessment results, proliferation resistance and physical protection(PR and PP) of KALIMER and JSFR are evaluated from the viewpoint of requirements for future nuclear fuel cycle system. The envisioned INSs CNFC-SFR rely on active plutonium management based on a closed fuel cycle, in which a fissile material is recycled in an integrated fuel cycle facility within proper safeguards. There is no isolated plutonium in the closed fuel cycle. The material remains continuously in a sequence of highly radioactive matrices within inaccessible facilities. The proliferation resistance assessment should be an ongoing analysis that keeps up with the progress and maturity of the design of Gen IV SFR

Assessment of Proliferation Resistance of Closed Nuclear Fuel Cycle System with Sodium Cooled Fast Reactors Using INPRO Evaluation Methodology

Energy Technology Data Exchange (ETDEWEB)

Kim, Young In; Hahn, Do Hee; Won, Byung Chool; Lee, Dong Uk

2007-11-15

Using the INPRO methodology, the proliferation resistance of an innovative nuclear energy system(INS) defined as a closed nuclear fuel cycle system consisting of KALIMER and pyroprocessing, has been assessed. Considering a very early development stage of the INS concept, the PR assessment is carried out based on intrinsic features, if required information and data are not available. The PR assessment of KALIMER and JSFR using the INPRO methodology affirmed that an adequate proliferation resistance has been achieved in both INSs CNFC-SFR, considering the assessor's progress and maturity of design development. KALIMER and JSFR are developed or being developed conforming to the targets and criteria defined for developing Gen IV nuclear reactor system. Based on these assessment results, proliferation resistance and physical protection(PR and PP) of KALIMER and JSFR are evaluated from the viewpoint of requirements for future nuclear fuel cycle system. The envisioned INSs CNFC-SFR rely on active plutonium management based on a closed fuel cycle, in which a fissile material is recycled in an integrated fuel cycle facility within proper safeguards. There is no isolated plutonium in the closed fuel cycle. The material remains continuously in a sequence of highly radioactive matrices within inaccessible facilities. The proliferation resistance assessment should be an ongoing analysis that keeps up with the progress and maturity of the design of Gen IV SFR.

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.

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 ...

Weld Joint Design for SFR Metallic Fuel Element Closures

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Won; Kim, Soo Sung; Woo, Yoon Myeng; Kim, Hyung Tae; Kim, Ki Hwan; Yoon, Kyung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

The sodium-cooled fast reactor (SFR) system is among the six systems selected for Gen-IV promising systems and expected to become available for commercial introduction around 2030. In Korea, the R and D on SFR has been begun since 1997, as one of the national long-term nuclear R and D programs. The international collaborative research is under way on fuel developments within Advanced Fuel Project for Gen-IV SFR with the closed fuel cycle of full actinide recycling, while TRU bearing metallic fuel, U-TRU-Zr alloy fuel, was selected and is being developed. For the fabrication of SFR metallic fuel elements, the endplug welding is a crucial process. The sealing of endplug to cladding tube should be hermetically perfect to prevent a leakage of fission gases and to maintain a good reactor performance. In this study, the joint designs for endplug welding were investigated. For the irradiation test of SFR metallic fuel element, the TIG welding technique was adopted and the welding joint design was developed based on the welding conditions and parameters established. In order to make SFR metallic fuel elements, the weld joint design was developed based on the TIG welding technique.

Caracterización del gen mecA de Staphylococcus aureus resistentes a meticilina aislados de tres grupos poblacionales de la ciudad de Medellín

Directory of Open Access Journals (Sweden)

Marcela Sanchez

Full Text Available Introducción: Staphylococcus aureus resistente a la meticilina (SARM es responsable de infecciones intrahospitalarias, las que constituyen una importante causa de morbilidad y mortalidad en nuestro medio, por lo cual la rápida identificación y tipificación molecular de la resistencia como el complejo SSCmec es esencial para entender la epidemiología de la infección. Objetivo: Caracterizar fenotípicamente la resistencia a meticilina y genotípicamente el casete cromosomal SSCmec en cepas de S. aureus aislados de individuos de la ciudad de Medellín mediante PCR múltiple. Materiales y métodos: A 41 aislamientos (hospitalarios y de la comunidad de S. aureus se les estableció la resistencia a cefoxitin mediante la técnica de Kirby-Bauer y la concentración inhibitoria mínima para oxacilina. Mediante PCR convencional se les confirmó la presencia del gen mecA. Para la tipificación del complejo SSCmec se utilizó PCR múltiple para amplificar 6 loci diferentes de este gen. Resultados: A todos los aislamientos se les confirmó resistencia a meticilina y la presencia del gen mecA, de los cuales 17 fueron clasificados como SSC mec I, 1 como SSC mec II, 21 como SSC mecIV; dos aislamientos no fue posible clasificarlos. Conclusiones: Con el uso de esta técnica clasificamos el 95% de los aislamientos del estudio, encontrando una mayor prevalencia de los SSCmec I y IV. La implementación de esta técnica permite una fácil caracterización de los aislamientos SARM y un apropiado manejo de la información de los integrantes de los comités de infecciones hospitalarios, lo cual podría impactar positivamente en el tratamiento a los pacientes y el control de enfermedades infecciosas intrahospitalarias.

Attenuation of acute plasma cortisol response in calves following intravenous sodium salicylate administration prior to castration.

Science.gov (United States)

Coetzee, J F; Gehring, R; Bettenhausen, A C; Lubbers, B V; Toerber, S E; Thomson, D U; Kukanich, B; Apley, M D

2007-08-01

Pain associated with castration in cattle is an animal welfare concern in beef production. This study examined the effect of oral aspirin and intravenous (i.v.) sodium salicylate on acute plasma cortisol response following surgical castration. Twenty bulls, randomly assigned to the following groups, (i) uncastrated, untreated controls, (ii) castrated, untreated controls, (iii) 50 mg/kg sodium salicylate i.v. precastration and (iv) 50 mg/kg aspirin (acetylsalicylic acid) per os precastration, were blood sampled at 3, 10, 20, 30, 40, 50 min and 1, 1.5, 2, 4, 6, 8, 10 and 12 h postcastration. Samples were analyzed by competitive chemiluminescent immunoassay and fluorescence polarization immunoassay for cortisol and salicylate, respectively. Data were analyzed using noncompartmental analysis, a simple cosine model, anova and t-tests. Intravenous salicylate V(d(ss)) was 0.18 L/kg, Cl(B) was 3.36 mL/min/kg and t(1/2 lambda) was 0.63 h. Plasma salicylate concentrations above 25 microg/mL coincided with significant attenuation in peak cortisol concentrations (P = 0.029). Peak salicylate concentrations following oral aspirin administration was castrated groups was significantly higher than uncastrated controls (P = 0.018). These findings have implications for designing drug regimens to provide analgesia during routine animal husbandry procedures.

A gene-based analysis of variants in the serum/glucocorticoid regulated kinase (SGK genes with blood pressure responses to sodium intake: the GenSalt Study.

Directory of Open Access Journals (Sweden)

Changwei Li

Full Text Available Serum and glucocorticoid regulated kinase (SGK plays a critical role in the regulation of renal sodium transport. We examined the association between SGK genes and salt sensitivity of blood pressure (BP using single-marker and gene-based association analysis.A 7-day low-sodium (51.3 mmol sodium/day followed by a 7-day high-sodium intervention (307.8 mmol sodium/day was conducted among 1,906 Chinese participants. BP measurements were obtained at baseline and each intervention using a random-zero sphygmomanometer. Additive associations between each SNP and salt-sensitivity phenotypes were assessed using a mixed linear regression model to account for family dependencies. Gene-based analyses were conducted using the truncated p-value method. The Bonferroni-method was used to adjust for multiple testing in all analyses.In single-marker association analyses, SGK1 marker rs2758151 was significantly associated with diastolic BP (DBP response to high-sodium intervention (P = 0.0010. DBP responses (95% confidence interval to high-sodium intervention for genotypes C/C, C/T, and T/T were 2.04 (1.57 to 2.52, 1.79 (1.42 to 2.16, and 0.85 (0.30 to 1.41 mmHg, respectively. Similar trends were observed for SBP and MAP responses although not significant (P = 0.15 and 0.0026, respectively. In addition, gene-based analyses demonstrated significant associations between SGK1 and SBP, DBP and MAP responses to high sodium intervention (P = 0.0002, 0.0076, and 0.00001, respectively. Neither SGK2 nor SGK3 were associated with the salt-sensitivity phenotypes in single-maker or gene-based analyses.The current study identified association of the SGK1 gene and BP salt-sensitivity in the Han Chinese population. Further studies are warranted to identify causal SGK1 gene variants.

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.

UV-visible spectroscopic estimation of photodegradation of rhodamine-B dye using tin(IV) oxide nanoparticles.

Science.gov (United States)

Sangami, G; Dharmaraj, N

2012-11-01

Nanocrystalline, tin(IV) oxide (SnO(2)) particles has been prepared by thermal decomposition of tin oxalate precursor obtained from the reactions of tin(IV) chloride and sodium oxalate using eggshell membrane (ESM). The as-prepared SnO(2) nanoparticles were characterized by thermal studies, transmission electron microscopy (TEM), powder X-ray diffraction (XRD), Raman, FT-IR and UV-visible studies and used as a photocatalyst for the degradation of rhodamine-B (Rh-B) dye. The size of the prepared nanoparticles was in the range of 5-12nm as identified from the TEM images. Powder XRD data revealed the presence of a tetragonal, rutile crystalline phase of the tin(IV) oxide nanoparticles. Thermal analysis showed that the decomposition of tin oxalate precursor to yield the titled tin(IV) oxide nanoparticles was completed below 500°C. The extent of degradation of Rh-B in the presence of SnO(2) monitored by absorption spectral measurements demonstrated that 94.48% of the selected dye was degraded upon irradiation with UV light for 60 min. Copyright © 2012 Elsevier B.V. All rights reserved.

Applying the PR and PP Methodology for a qualitative assessment of a misuse scenario in a notional Generation IV Example Sodium Fast Reactor. Assessing design variations

Energy Technology Data Exchange (ETDEWEB)

Cojazzi, G.G.M.; Renda, G. [European Commission, Joint Research Centre, Institute for the Protection and Security of the Citizen, TP 210, Via E. Fermi 2749, I-21027, Ispra - Va (Italy); Hassberger, J. [Lawrence Livermore National Laboratory (United States)

2009-06-15

The Generation IV International Forum (GIF) Proliferation Resistance and Physical Protection (PR and PP) Working Group has developed a methodology for the PR and PP evaluation of advanced nuclear energy systems. The methodology is organised as a progressive approach applying alternative methods at different levels of thoroughness as more design information becomes available and research improves the depth of technical knowledge. The GIF Proliferation Resistance and Physical Protection (PR and PP) Working Group developed a notional sodium cooled fast neutron nuclear reactor, named the Example Sodium Fast Reactor (ESFR), for use in developing and testing the methodology. The ESFR is a hypothetical nuclear energy system consisting of four sodium-cooled fast reactors of medium size, co-located with an on-site dry fuel storage facility and a Fuel Cycle Facility with pyrochemical processing of the spent fuel and re-fabrication of new ESFR fuel elements. The baseline design is an actinide burner, with LWR spent fuel elements as feed material processed on the site. In the years 2007 and 2008 the GIF PR and PP Working Group performed a case study designed to both test the methodology and demonstrate how it can provide useful feedback to designers even during pre-conceptual design. The Study analysed the response of the entire ESFR system to different proliferation and theft strategies. Three proliferation threats were considered: Concealed diversion, Concealed Misuse and Abrogation. An overt theft threat was also studied. One of the objectives of the case study is to confirm the capability of the methodology to capture PR and PP differences among varied design configurations. To this aim Design Variations (DV) have been also defined corresponding respectively to a) a small variation of the baseline design (DV0), b) a deep burner configuration (DV1), c) a self sufficient core (DV2), and c) a breeder configuration (DV3). This paper builds on the approach followed for the

Trends and Developments for Fast Neutron Reactors and Related Fuel Cycles

International Nuclear Information System (INIS)

Carré, Frank

2013-01-01

• FR13 – A unique and dedicated framework to share updates on national programs of Fast Reactor developments, projects of new builds and plans for the future: - Near term projects of sodium and lead-alloy Fast Reactors; - Gen-IV visions of sodium-cooled and alternative types of Fast Neutron Reactors (GFR, LFR…). • FR13 – A special emphasis put on Fast Reactor Safety, Sustainability of nuclear fuel cycle and Young Generation perspective. • FR13 – A catalyst for further collaborations and alliances: - To share visions of goals and advisable options for future Fast Reactors and Nuclear Fuel Cycle; - To share cost of R&D and large demonstrations (safety, security, recycling); - To progress towards harmonized international standards; - To integrate national projects into a consistent international roadmap

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...

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.

Development of Preliminary PIRTs of Thermal-Hydraulic Phenomena for KALIMER-600

International Nuclear Information System (INIS)

Kwon, Young Min; Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo

2009-01-01

Sodium Cooled Fast Reactors (SFRs) are the most technologically developed of the GEN IV systems. The primary mission of the SFRs is the management of high-level wastes, in particular management of plutonium and other actinides. The SFR system is the nearest-term actinide management system among the GEN-IV system candidates. The mission of the SFR can be extended to electricity production if design innovations that reduce capital cost. KAERI has been performing design studies of KALIMER-600 at the conceptual level. To bring KALIMER-600 to deployment, several technology gaps in fuel cycle and reactor system must be closed. Research on both sides of the fuel cycle and the reactor system is necessary to bring KALIMER-600 to deployment. For the reactor system, technology gaps exist in assurance or verification of passive safety, and completion of the metallic fuel database including irradiation performance data. R and D programs for the KALIMER-600 safety are necessary to support the SFR deployment. The safety R and D challenges for the KALIMER-600 in the context of the GEN IV systems are: (a) to verify the predictability and effectiveness of the inherent passive benign responses to design basis events and accommodated beyond design basis events (b) to provide assurance that accommodated beyond design basis events considered in licensing can be sustained without loss of coolability of fuel and structural integrity. The Phenomena Identification and Ranking Table (PIRT) is an effective tool for providing an expert assessment of safety-related phenomena and for assessing R and D needs for KALIMER-600 licensing. The nine-step PIRT process has been established as a methodology for providing expert assessments of safety-relevant phenomena

Assessment of the Dry Processed Oxide Fuel in Liquid Metal Fast Reactors

Energy Technology Data Exchange (ETDEWEB)

Roh, Gyu Hong; Choi, Hang Bok

2005-09-15

The neutronic feasibility of the dry process oxide fuel was assessed for the sodium-cooled and lead-cooled fast reactors (SFR and LFR, respectively), which were recommended as Generation-IV (Gen-IV) reactor systems by the Gen-IV international forum. The reactor analysis was performed for the equilibrium fuel cycle of two core configurations: Hybrid BN-600 benchmark core with an enlarged lattice pitch and a modified BN-600 core. The dry process technology assumed in this study is the molten-salt process, which was developed by Russian scientists for recycling oxide fuels. The core calculation was performed by the REBUS-3 code and the reactor characteristics such as the transuranic (TRU) enrichment, breeding ratio, peak linear power, burnup reactivity swing, etc. were calculated for the equilibrium core under a fixed fuel management scheme. The results showed that a fissile self-sustainable breakeven core was achievable without blanket fuels when the fuel volume fraction was {approx}50% and most of the fission products were removed. If the design criteria used in this study is proved to be acceptable through a detailed physics design and thermal hydraulic analysis in the future, it is practically possible to construct an equilibrium fuel cycle of the SFR and LFR systems based on the oxide fuel by utilizing the dry process technology.

Assessment of the Dry Processed Oxide Fuel in Liquid Metal Fast Reactors

International Nuclear Information System (INIS)

Roh, Gyu Hong; Choi, Hang Bok

2005-09-01

The neutronic feasibility of the dry process oxide fuel was assessed for the sodium-cooled and lead-cooled fast reactors (SFR and LFR, respectively), which were recommended as Generation-IV (Gen-IV) reactor systems by the Gen-IV international forum. The reactor analysis was performed for the equilibrium fuel cycle of two core configurations: Hybrid BN-600 benchmark core with an enlarged lattice pitch and a modified BN-600 core. The dry process technology assumed in this study is the molten-salt process, which was developed by Russian scientists for recycling oxide fuels. The core calculation was performed by the REBUS-3 code and the reactor characteristics such as the transuranic (TRU) enrichment, breeding ratio, peak linear power, burnup reactivity swing, etc. were calculated for the equilibrium core under a fixed fuel management scheme. The results showed that a fissile self-sustainable breakeven core was achievable without blanket fuels when the fuel volume fraction was ∼50% and most of the fission products were removed. If the design criteria used in this study is proved to be acceptable through a detailed physics design and thermal hydraulic analysis in the future, it is practically possible to construct an equilibrium fuel cycle of the SFR and LFR systems based on the oxide fuel by utilizing the dry process technology

Potential application of Rankine and He-Brayton cycles to sodium fast reactors

International Nuclear Information System (INIS)

Perez-Pichel, G.D.; Linares, J.I.; Herranz, L.E.; Moratilla, B.Y.

2011-01-01

Highlights: → This paper has been focused on thermal efficiency of several Rankine and Brayton cycles for SFR. → A sub-critical Rankine configuration could reach a thermal efficiency higher than 43%. → It could be increased to almost 45% using super-critical configurations. → Brayton cycles thermal performance can be enhanced by adding a super-critical organic fluid Rankine cycle. → The moderate coolant temperature at the reactor makes Brayton configurations have poorer. - Abstract: Traditionally all the demos and/or prototypes of the sodium fast reactor (SFR) technology with power output, have used a steam sub-critical Rankine cycle. Sustainability requirement of Gen. IV reactors recommends exploring alternate power cycle configurations capable of reaching high thermal efficiency. By adopting the anticipated working parameters of next SFRs, this paper investigates the potential of some Rankine and He-Brayton layouts to reach thermal efficiencies as high as feasible, so that they could become alternates for SFR reactor balance of plant. The assessment has encompassed from sub-critical to super-critical Rankine cycles and combined cycles based on He-Brayton gas cycles of different complexity coupled to Organic Rankine Cycles. The sub-critical Rankine configuration reached at thermal efficiency higher than 43%, which has been shown to be a superior performance than any of the He-Brayton configurations analyzed. By adopting a super-critical Rankine arrangement, thermal efficiency would increase less than 1.5%. In short, according to the present study a sub-critical layout seems to be the most promising configuration for all those upcoming prototypes to be operated in the short term (10-15 years). The potential of super-critical CO 2 -Brayton cycles should be explored for future SFRs to be deployed in a longer run.

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

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...

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.

Sodium

Science.gov (United States)

Table salt is a combination of two minerals - sodium and chloride Your body needs some sodium to work properly. It helps with the function ... in your body. Your kidneys control how much sodium is in your body. If you have too ...

Sodium and T1rho MRI for molecular and diagnostic imaging of articular cartilage.

Science.gov (United States)

Borthakur, Arijitt; Mellon, Eric; Niyogi, Sampreet; Witschey, Walter; Kneeland, J Bruce; Reddy, Ravinder

2006-11-01

In this article, both sodium magnetic resonance (MR) and T1rho relaxation mapping aimed at measuring molecular changes in cartilage for the diagnostic imaging of osteoarthritis are reviewed. First, an introduction to structure of cartilage, its degeneration in osteoarthritis (OA) and an outline of diagnostic imaging methods in quantifying molecular changes and early diagnostic aspects of cartilage degeneration are described. The sodium MRI section begins with a brief overview of the theory of sodium NMR of biological tissues and is followed by a section on multiple quantum filters that can be used to quantify both bi-exponential relaxation and residual quadrupolar interaction. Specifically, (i) the rationale behind the use of sodium MRI in quantifying proteoglycan (PG) changes, (ii) validation studies using biochemical assays, (iii) studies on human OA specimens, (iv) results on animal models and (v) clinical imaging protocols are reviewed. Results demonstrating the feasibility of quantifying PG in OA patients and comparison with that in healthy subjects are also presented. The section concludes with the discussion of advantages and potential issues with sodium MRI and the impact of new technological advancements (e.g. ultra-high field scanners and parallel imaging methods). In the theory section on T1rho, a brief description of (i) principles of measuring T1rho relaxation, (ii) pulse sequences for computing T1rho relaxation maps, (iii) issues regarding radio frequency power deposition, (iv) mechanisms that contribute to T1rho in biological tissues and (v) effects of exchange and dipolar interaction on T1rho dispersion are discussed. Correlation of T1rho relaxation rate with macromolecular content and biomechanical properties in cartilage specimens subjected to trypsin and cytokine-induced glycosaminoglycan depletion and validation against biochemical assay and histopathology are presented. Experimental T1rho data from osteoarthritic specimens, animal models

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...

Study of the permeability of the various parts of the tubules to sodium and potassium ions

International Nuclear Information System (INIS)

Morel, F.; Falbriard, A.

1959-01-01

The method of stop flow analysis has been used in rabbits together with radioactive sodium and potassium injected in the middle of a six minutes period of arrest of urine flow during an osmotic diuresis. Urine was subsequently collected in 60 ta 80 mg samples. The specific activities of sodium and potassium suggest that both ions pass directly from the renal interstitial tissue into the urine at different and distinct areas in the tubules. The whole distal segment, including the area of active reabsorption of this ion, is impermeable to sodium in the direction interstitial tissue to lumen. The adjacent, more proximal tubule is, however, extremely permeable. The distal tubular impermeability to potassium is more limited. The specific activity already having reached a maximum at the level of active sodium reabsorption. Reprint of a paper published in 'Revue Francaise d'Etudes Cliniques et Biologiques', n. 5, vol IV, p. 471-474 [fr

77 FR 59375 - Sodium Hexametaphosphate From the People's Republic of China: Final Results of Antidumping Duty...

Science.gov (United States)

2012-09-27

... supplier distances; \\5\\ \\5\\ See I&D Memo at Comment IV.A. Valued truck freight and brokerage and handling.... The product covered by this review includes sodium hexametaphosphate in all grades, whether food grade.... United States, 117 F. 3d 1401 (Fed. Cir. 1997) (``Sigma''). B. Surrogate Value for Truck Freight C...

Mild hydrothermal crystal growth of new uranium(IV) fluorides, Na3.13Mg1.43U6F30 and Na2.50Mn1.75U6F30: Structures, optical and magnetic properties

Science.gov (United States)

Yeon, Jeongho; Smith, Mark D.; Tapp, Joshua; Möller, Angela; zur Loye, Hans-Conrad

2016-04-01

Two new uranium(IV) fluorides, Na3.13Mg1.43U6F30 (1) and Na2.50Mn1.75U6F30 (2), were synthesized through an in situ mild hydrothermal route, and were structurally characterized by single crystal X-ray diffraction. The compounds exhibit complex crystal structures composed of corner- or edge-shared UF9 and MF6 (M=Mg, Mn) polyhedra, forming hexagonal channels in the three-dimensional framework, in which ordered or disordered divalent metal and sodium atoms reside. The large hexagonal voids contain the nearly regular M(II)F6 octahedra and sodium ions, whereas the small hexagonal cavities include M(II) and sodium ions on a mixed-occupied site. Magnetic susceptibility measurements yielded effective magnetic moments of 8.36 and 11.6 μB for 1 and 2, respectively, confirming the presence and oxidation states of U(IV) and Mn(II). The large negative Weiss constants indicate the spin gap between a triplet and a singlet state in the U(IV). Magnetization data as a function of applied fields revealed that 2 exhibits paramagnetic behavior due to the nonmagnetic singlet ground state of U(IV) at low temperature. UV-vis diffuse reflectance and X-ray photoelectron spectroscopy data were also analyzed.

A Radical Sodium Reduction Policy is not Supported by Randomized Controlled Trials or Observational Studies

DEFF Research Database (Denmark)

Graudal, Niels

2016-01-01

Several health institutions recommend sodium intake be reduced to below 2,300 mg, which means that 6-7 billion individuals should alter their diet to accommodate. Such a radical recommendation should be based on solid evidence. However, this review reveals that (i) there are no randomized...... controlled trials (RCTs) allocating individuals to below 2,300 mg and measuring health outcomes; (ii) RCTs allocating risk groups such as obese prehypertensive individuals and hypertensive individuals down to (but not below) 2,300 mg show no effect of sodium reduction on all-cause mortality; (iii) RCTs...... allocating individuals to below 2,300 mg show a minimal effect on blood pressure in the healthy population (less than 1mm Hg) and significant increases in renin, aldosterone, noradrenalin cholesterol, and triglyceride; and (iv) observational studies show that sodium intakes below 2,645 and above 4,945 mg...

Development of Digital Materials Database for Design and Construction of New Power Plants

International Nuclear Information System (INIS)

Ren, Weiju

2008-01-01

To facilitate materials selection, structural design, and future maintenance of the Generation IV nuclear reactor systems, an interactive, internet accessible materials property database, dubbed Gen IV Materials Handbook, has been under development with the support of the United States Department of Energy. The Handbook will provide an authoritative source of information on structural materials needed for the development of various Gen IV nuclear reactor systems along with powerful data analysis and management tools. In this paper, the background, history, framework, major features, contents, and development strategy of the Gen IV Materials Handbook are discussed. Current development status and future plans are also elucidated.

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

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.

Study of the moderating effect of salts on the sodium-water reaction on the cleaning of irradiated fuel assemblies from fast neutron reactors, using fluid sodium heat transfer

International Nuclear Information System (INIS)

Lacroix, Marie

2014-01-01

Within the framework of the development of generation IV reactors one of the research tracks is related to the development of fast neutron reactors using fluid sodium heat transfer. The CEA (French Alternative Energies and Atomic Energy Commission) plans to build a prototype of reactor of this type called 'ASTRID'. To address development requirements for this prototype, research is in progress on the reactor's availability and in particular on the reduction of the washing duration for residual sodium fuel assemblies during their discharge. In fact, because sodium is very reactive with water (presently the only available process), the washing is done, for example, by very gradual addition. A solution currently being studied at the CEA and which is the subject of this thesis report consists of the addition of an aqueous salts solutions to the washing water in order to slow down the kinetic reaction. This doctoral dissertation describes the various salts, which have been evaluated and aims to explain their action mode. (author) [fr

Safeguards Considerations for the Design of a Future Fast Neutron Sodium Cooled Reactor

International Nuclear Information System (INIS)

Cazalet, J.; Raymond, P.; Masson, M.; Saturnin, A.

2015-01-01

Incorporating safeguards at an early stage of a reactor design is a way to increase the effectiveness and efficiency of safeguards measures minimizing the possibilities of misuse of the plant or nuclear material diversion. It also reduces the impact on the construction and operation cost. At the preliminary phase, the design will integrate: confinement, containment, surveillance features and non-destructive assay equipment. Taking into account these requirements will help the operator in the approval of the plant at the design phase by national and international authorities in charge of Nuclear Material accounting and safeguards. A large amount of work has been made by the GEN IV International Forum to assess the proliferation resistance of nuclear systems. The IAEA has developed guidelines on ''Safeguards by design'' describing reference requirements for future nuclear facilities. Based on these studies, this communication details implementation of safeguards in the design of a sodium cooled fast neutron reactor (SFR) currently studied in France. Specificities are the use of MOX fuel with high concentration of plutonium and the potential capacity of breeding. A great attention should be paid to avoid diversion of nuclear material contained in fresh or irradiated fuel. Scenarios of reactor misuse are analyzed. The identification of diversion pathways and requirements for nuclear material accountancy, leads to an approach of safeguards, specific to SFR: Material Balance Areas (MBA) and some key measurement points (KMP) are characterized. Specific instrumentation assay helping in the identification and/or characterization of fuel elements and the inventory of nuclear material is described. As concerns the fuel cycle, the safeguards of the reprocessing unit will be progressively increased through the development of materials monitoring and the implementation of these measures at strategic locations of buildings, thus providing real-time information

Cerebral and brainstem electrophysiologic activity during euthanasia with pentobarbital sodium in horses.

Science.gov (United States)

Aleman, M; Williams, D C; Guedes, A; Madigan, J E

2015-01-01

An overdose of pentobarbital sodium administered i.v. is the most commonly used method of euthanasia in veterinary medicine. Determining death after the infusion relies on the observation of physical variables. However, it is unknown when cortical electrical activity and brainstem function are lost in a sequence of events before death. To examine changes in the electrical activity of the cerebral cortex and brainstem during an overdose of pentobarbital sodium solution for euthanasia. Our testing hypothesis is that isoelectric pattern of the brain in support of brain death occurs before absence of electrocardiogram (ECG) activity. Fifteen horses requiring euthanasia. Prospective observational study. Horses with neurologic, orthopedic, and cardiac illnesses were selected and instrumented for recording of electroencephalogram, electrooculogram, brainstem auditory evoked response (BAER), and ECG. Physical and neurologic (brainstem reflexes) variables were monitored. Loss of cortical electrical activity occurred during or within 52 seconds after the infusion of euthanasia solution. Cessation of brainstem function as evidenced by a lack of brainstem reflexes and disappearance of the BAER happened subsequently. Despite undetectable heart sounds, palpable arterial pulse, and mean arterial pressure, recordable ECG was the last variable to be lost after the infusion (5.5-16 minutes after end of the infusion). Overdose of pentobarbital sodium solution administered i.v. is an effective, fast, and humane method of euthanasia. Brain death occurs within 73-261 seconds of the infusion. Although absence of ECG activity takes longer to occur, brain death has already occurred. Copyright © 2015 The Authors. Journal of Veterinary Internal Medicine published by Wiley Periodicals, Inc. on behalf of the American College of Veterinary Internal Medicine.

Sodium fire tests for investigating the sodium leak in Monju

International Nuclear Information System (INIS)

Seino, Hiroshi; Miyahara, Shinya; Miyake, Osamu; Tanabe, Hiromi

1996-01-01

As a part of the work for investigating the sodium leak accident which occurred in Monju on December 8, 1995, three tests, (1) sodium leak test, (2) sodium fire test-I, and (3) sodium fire test-II, were carried out at OEC/PNC. Main objectives of these tests are to confirm leak and burning behavior of sodium from the damaged thermometer, and effects of the sodium fire on integrity of the surrounding structure, etc. The main conclusions obtained from the tests are shown as below. 1) Average sodium leak rate obtained from the sodium leak test was about 50 g/sec. This was equivalent to the value estimated from level change in the sodium overflow tank in the Monju accident. 2) Observation from video cameras in the sodium fire tests revealed that in early stages of sodium leak, sodium dropped down out of the flexible tube of thermometer in drips. This dripping and burning were expanded in range as sodium splashed on the duct. 3) Though, in the sodium fire test-I, there was a decrease of about 1 mm at a thickness of the burning pan in the vicinity in just under in the leak point, there were completely no crack and failure. In the meantime, in the sodium fire test-II the six open holes were found in the floor liner. By this liner failure, the reaction between sodium and concrete might take place. At present, while the detailed evaluation on the sodium fire test-II has been mainly carried out, the investigation for clarifying the cause of the liner failure has been also carried out. (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

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.

Sodium technology handbook

International Nuclear Information System (INIS)

2005-09-01

This document was published as a textbook for the education and training of personnel working for operations and maintenances of sodium facilities including FBR plants and those engaged in R and D activities related to sodium technology. This handbook covers the following technical areas. Properties of sodium. Compatibilities of sodium with materials. Thermalhydraulics and structural integrity. Sodium systems and components. Sodium instrumentations. Sodium handling technology. Sodium related accident evaluation and countermeasures for FBRs. Operation, maintenance and repair technology of sodium facilities. Safety measures related to sodium. Laws, regulations and internal rules related to sodium. The plannings and discussions of the handbook were made in the Sodium Technology Education Committee organized in O-arai Engineering Center consisting of the representatives of the related departments including Tsuruga headquarters. Experts in various departments participated in writing individual technical subjects. (author)

Toltrazuril sulfone sodium salt: synthesis, analytical detection, and pharmacokinetics in the horse.

Science.gov (United States)

Dirikolu, L; Karpiesiuk, W; Lehner, A F; Tobin, T

2012-06-01

Toltrazuril sulfone (ponazuril) is a triazine-based antiprotozoal agent with clinical application in the treatment of equine protozoal myeloencephalomyelitis (EPM). In this study, we synthesized and determined the bioavailability of a sodium salt formulation of toltrazuril sulfone that can be used for the treatment and prophylaxis of EPM in horses. Toltrazuril sulfone sodium salt was rapidly absorbed, with a mean peak plasma concentration of 2400 ± 169 (SEM) ng/mL occurring at 8 h after oral-mucosal dosing and was about 56% bioavailable compared with the i.v. administration of toltrazuril sulfone in dimethylsulfoxide (DMSO). The relative bioavailability of toltrazuril sulfone suspended in water compared with toltrazuril sulfone sodium salt was 46%, indicating approximately 54% less oral bioavailability of this compound suspended in water. In this study, we also investigated whether this salt formulation of toltrazuril sulfone can be used as a feed additive formulation without significant reduction in oral bioavailability. Our results indicated that toltrazuril sulfone sodium salt is relatively well absorbed when administered with feed with a mean oral bioavailability of 52%. Based on these data, repeated oral administration of toltrazuril sulfone sodium salt with or without feed will yield effective plasma and cerebrospinal fluid (CSF) concentrations of toltrazuril sulfone for the treatment and prophylaxis of EPM and other protozoal diseases of horses and other species. As such, toltrazuril sulfone sodium salt has the potential to be used as feed additive formulations for both the treatment and prophylaxis of EPM and various other apicomplexan diseases. © 2011 Blackwell Publishing Ltd.

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

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...

Thermodynamic properties of actinide complexes. Part 5: Uranyl(VI)-thioglycolate system; thorium(IV)-glycolate and -thioglycolate systems

Energy Technology Data Exchange (ETDEWEB)

di Bernardo, P; Roncari, E; Mazzi, U; Bettella, F [Padua Univ. (Italy). Istituto di Chimica Generale ed Inorganica; Consiglio Nazionale delle Ricerche, Padua (Italy). Lab. di Chimica e Tecnologia dei Radioelementi); Magon, L [Ferrara Univ. (Italy). Istituto Chimico

1978-04-01

The changes in free energy, enthalpy and entropy for the formation of uranyl(VI)-thioglycolate, thorium(IV)-glycolate and -thioglycolate complexes have been determined. The changes in free energy were calculated from the stability constants obtained from a potentiometric determination of the concentration of free hydrogen ion, using a glass or quinhydrone electrode. The enthalpy values were measured calorimetrically. The measurements were performed at 25.0/sup 0/C in an aqueous sodium perchlorate medium with the total sodium concentration equal to 100 M. A comparison of the magnitude of the enthalpy and entropy changes for the various systems gives additional support of the view that the thioglycolate acts as a monodentate ligand while the glycolate forms chelate rings.

[Antidotal effects of sulfhydryl compounds on acute poisonings by sodium ammonium dimethyl-2-(propane-1,3-dithiosulfate) monohydrate, nereistoxin and cartap].

Science.gov (United States)

Cao, B J; Chen, Z K; Chi, Z Q

1990-03-01

Sodium dimercaptopropanesulphonate (DMPS) and sodium dimercaptosuccinate (DMS) were discovered to be effective antidotes for acute poisoning of insecticides SCD [sodium ammonium dimethyl-2-(propane-1,3-dithiosulfate) monohydrate], nereistoxin (4-N,N-dimethylamino-1,2-dithiolane) and cartap (dihydronereistoxin dicarbamate). In mice, DMPS (250 mg/kg) or DMS (1000 mg/kg) ip 20 min before SCD increased LD50 of ig SCD from 97 to 374 or 251 mg/kg, respectively. The prophylactic effect of DMPS was better than that of DMS. Administration of DMPS prior to cartap increased LD50 of ig cartap from 130 to 375 mg/kg. The therapeutic effect of DMPS was also demonstrated in SCD-poisoned conscious rabbits. DMPS 62.5 mg/kg or DMS 500 mg/kg iv completely antagonized the neuromuscular blockade and respiratory depression caused by SCD, nereistoxin and cartap in anesthetized rabbits. The antagonism of SCD-induced neuromuscular blockade by cysteine (400 mg/kg, iv) was less effective and of shorter duration than that by DMPS and DMS. Dimercaprol 50 mg/kg im showed little effect on SCD-induced paralysis. The antagonistic actions of sulfhydryl compounds on neuromuscular blockade induced by these insecticides probably belong to chemical antagonism.

Inhibitin: a specific inhibitor of sodium/sodium exchange in erythrocytes.

OpenAIRE

Morgan, K; Brown, R C; Spurlock, G; Southgate, K; Mir, M A

1986-01-01

An inhibitor of ouabain-insensitive sodium/sodium exchange in erythrocytes has been isolated from leukemic promyelocytes. To explore the specific effects of this inhibitor, named inhibitin, sodium transport experiments were carried out in human erythrocytes. Inhibitin reduced ouabain-insensitive bidirectional sodium transport. It did not change net sodium fluxes, had no significant effect on rubidium influx, and did not inhibit sodium-potassium-ATPase activity. The inhibitory effect of inhibi...

Development of digital materials database for design and construction of new power plants

International Nuclear Information System (INIS)

Ren, W.

2008-01-01

To facilitate materials selection, structural design, and future maintenance of the Generation IV nuclear reactor systems, an interactive, internet accessible materials property database, dubbed Gen IV Materials Handbook, has been under development with the support of the United States Department of Energy. The Handbook will provide an authoritative source of information on structural materials needed for the development of various Gen IV nuclear reactor systems along with powerful data analysis and management tools. In this paper the background, history, framework, major features, contents, and development strategy of the Gen IV Materials Handbook are discussed. Current development status and future plans are also elucidated. (authors)

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.

Suicide Attempts with Sodium Hipochlorid Injection: Case Report

Directory of Open Access Journals (Sweden)

Cemil Kavalci

2013-08-01

Full Text Available A suicide attempt is a health problem affecting all age groups. Suicides are usually by medicine overdose, gun-shot injury and hanging. 35 year old male patient was brought to our emergency department by 112 EMS due to suicidal attempt. Approximately two hours before the story of both arms, by iv injection of sodium hipochlorid was learned that he wants to commit suicide. On physical examination, his right arm 3,5 cm in diameter and his left arm 3 cm diameter red color ecchymosis and edema was present. There was no evidence of sistemical pathological finding. The patient was discharged after 24 hours of observation.

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

An optioneering and concept design study for the Astrid sodium-gas heat exchanger matrix

International Nuclear Information System (INIS)

Hattrell, T.; Lopez-Ramirez, S.; Pilatis, N.

2014-01-01

The ASTRID generation IV sodium cooled fast reactor design being developed by the CEA requires a component to transfer heat from the core to the power cycle. One of the ASTRID configurations currently being developed by the CEA uses a sodium to gas heat exchanger (SGHE) to fulfil this function. The design of the SGHE is challenging because of the high temperature of the sodium coolant and the significant pressure differential between the sodium and gas sides of the heat exchanger. This paper presents a study of the options examined for the ASTRID SGHE. A compact, superplastic formed diffusion bonded (SPF-DB) heat exchanger matrix (e.g. SGHE core) is proposed, based on the aerospace technology used by Rolls-Royce to manufacture light and strong wide chord fan blades for gas turbines. The in-house code CHESS is used to examine a number of feasible configurations for the matrix of the heat exchanger component and an optimisation study to maximise the thermal and mechanical performance of the most promising configurations is reported. The optimal matrix geometry identified by the study has a power density for the heat transfer region 157%1 greater than the baseline geometry (authors)

Basic Design of Experimental Facility for Measuring Pressure Drop of IHX in a SFR

Energy Technology Data Exchange (ETDEWEB)

Ko, Yung-Joo; Eoh, Jae-Hyuk; Kim, Hyungmo; Lee, Dong-Won; Jeong, Ji-Young; Lee, Hyeong-Yeon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dong Eok [Kyungpook National Univ., Daegu (Korea, Republic of)

2015-05-15

The conceptual design of the Prototype gen-IV SFR (PGSFR) with a 150 MWe capacity was commenced in 2012 through the national long-term R and D program by KAERI. Then, PGSFR is now being designed with the defense in depth concept with active, passive and inherent safety features to acquire design approval for PGSFR from the Korean regulatory authority by 2020. PGSFR is a sodium-cooled pool-type fast reactor with all primary components including the primary heat transport system (PHTS) pumps and IHXs are located inside a sodium pool. The heat produced due to fission in the core is transported by primary sodium to secondary sodium in a sodium to sodium intermediate heat exchanger (IHX), which in turn is transferred to water in a steam generator (SG). Basic design of the IHX flow characteristic test facility, WEIPA was conducted based on the three-level scaling methodology in order to preserve the flow characteristics of the IHX in PGSFR. This test facility is intended to measure a high precision pressure drop at the shell-side of the IHX. This paper describes the aspects of the current design features of the IHX in PGSFR, scaling and basic design features of the facility.

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

Adiabatic flame temperature of sodium combustion and sodium-water reaction

International Nuclear Information System (INIS)

Okano, Y.; Yamaguchi, A.

2001-01-01

In this paper, background information of sodium fire and sodium-water reaction accidents of LMFBR (liquid metal fast breeder reactor) is mentioned at first. Next, numerical analysis method of GENESYS is described in detail. Next, adiabatic flame temperature and composition of sodium combustion are analyzed, and affect of reactant composition, such oxygen and moisture, is discussed. Finally, adiabatic reaction zone temperature and composition of sodium-water reaction are calculated, and affects of reactant composition, sodium vaporization, and pressure are stated. Chemical equilibrium calculation program for generic chemical system (GENESYS) is developed in this study for the research on adiabatic flame temperature of sodium combustion and adiabatic reaction zone temperature of sodium-water reaction. The maximum flame temperature of the sodium combustion is 1,950 K at the standard atmospheric condition, and is not affected by the existence of moisture. The main reaction product is Na 2 O (l) , and in combustion in moist air, with NaOH (g) . The maximum reaction zone temperature of the sodium-water reaction is 1,600 K, and increases with the system pressure. The main products are NaOH (g) , NaOH (l) and H2 (g) . Sodium evaporation should be considered in the cases of sodium-rich and high pressure above 10 bar

Sodium in diet

Science.gov (United States)

Diet - sodium (salt); Hyponatremia - sodium in diet; Hypernatremia - sodium in diet; Heart failure - sodium in diet ... Too much sodium in the diet may lead to: High blood pressure in some people A serious buildup of fluid in people with heart failure , cirrhosis of ...

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.

Determination of disulfide bridges of two spider toxins: hainantoxin-III and hainantoxin-IV

Directory of Open Access Journals (Sweden)

W Wang

2009-01-01

Full Text Available Peptide toxins are usually highly bridged proteins with multipairs of intrachain disulfide bonds. Analysis of disulfide connectivity is an important facet of protein structure determination. In this paper, we successfully assigned the disulfide linkage of two novel peptide toxins, called HNTX-III and HNTX-IV, isolated from the venom of Ornithoctonus hainana spider. Both peptides are useful inhibitors of TTX-sensitive voltage-gated sodium channels and are composed of six cysteine residues that form three disulfide bonds, respectively. Firstly, the peptides were partially reduced by tris(2-carboxyethyl-phosphine (TCEP in 0.1 M citrate buffer containing 6 M guanidine-HCl at 40° C for ten minutes. Subsequently, the partially reduced intermediates containing free thiols were separated by reversed-phase high-performance liquid chromatography (RP-HPLC and alkylated by rapid carboxamidomethylation. Then, the disulfide bonds of the intermediates were analyzed by Edman degradation. By using the strategy above, disulfide linkages of HNTX-III and HNTX-IV were determined as I-IV, II-V and III-VI pattern. In addition, this study also showed that this method may have a great potential for determining the disulfide bonds of spider peptide toxins.

Development of generation IV nuclear energy systems

International Nuclear Information System (INIS)

Matsui, Kazuaki; Oka, Yoshiaki; Ogawa, Masuro; Ichimiya, Masakazu; Noda, Hiroshi

2003-01-01

The fifth 'Generation IV International Forum (GIF), Policy Group Meetings' was held at the Zen-Nikku Hotel in Tokyo, on September 19-20, 2002, under participations of Abraham, Secretary of DOE in U.S.A., Columbani, Secretary of CEA in France, Fujiie, Chairman of CAE in Japan, Kano, Parliamental Minister of MIS in Japan, and so on. Ten nations entering GIF (Argentina, Brazil, Canada, France, Japan, Korea, South Africa, Switzerland, U.K., and U.S.A.) selected six next generation nuclear energy concepts for objects of international cooperative research and development aiming at its practice by 2030. These concepts applicable to not only power generation, but also hydrogen production, sea water purification, and so on, are sodium liquid metal cooled reactor (Japan), high temperature gas cooled reactor (France), Super-critical pressure water cooled reactor (SCWR: Canada), Lead metal cooled reactor (Switzerland), Gas cooled fast reactor (U.S.A.), and molten salts reactor. On the generation IV nuclear reactor systems aiming to further upgrade their sustainability, safety, economical efficiency, and nuclear non proliferation, the 'Plans on Technical Development' (Road-map) to decide priority of their R and Ds has been cooperatively discussed under frameworks of international research cooperation by the GIF members nations. Here were shared descriptions on nuclear fuel cycle as a remise of technical evaluation and adopted concepts by Japanese participants contributing to making up the Road-map. (G.K.)

PR and PP evaluation. ESFR full system case study final report (Tentative translation)

International Nuclear Information System (INIS)

Sagara, Hiroshi; Kawakubo, Yoko; Inoue, Naoko

2014-01-01

The Generation IV (GEN IV) International Forum (GIF) Proliferation Resistance and Physical Protection Working Group (PRPP WG) was established in December, 2002, as one of the crosscut groups under GIF, in order to develop a methodology for evaluating PR and PP of potential GEN IV options. The group currently consists of the experts from the U.S. national laboratories and universities, from Canada, France, Republic of Korea (ROK), Japan, the International Atomic Energy Agency (IAEA), and European Union(EU). The present report, published in Oct. 2009, was used as a supporting study for development of the evaluation methodology for proliferation resistance and physical protection of GEN IV nuclear energy systems. The present report is summarizing the case study of the PR and PP evaluation of Example Sodium Fast Reactor (ESFR), a hypothetical nuclear energy system consisting of nine main system elements, and it provides for designers the practical experience of applying the PR and PP evaluation methodology to a nuclear energy system. The development of the future nuclear fuel cycle system with sufficient PR and PP features is a crucial task in Japan, and the demonstration and explanation about its effectiveness to the domestic and international society will be required. With the usefulness the present report for such purposes, it was translated and published here as a Japanese-language edition with the concurrence of the OECD-NEA. The original report in English language can be downloaded at the OECD-NEA website. The translation was performed as closely as possible to the original, and special attention was paid to the technical term translation for consistency. Terms difficult to be translated appropriately into Japanese was written with the original English wording. Safeguards terms were translated with reference to “IAEA Safeguards Glossary 2001 Edition” (Japanese), published by the Nuclear Material Control Center Japan (NMCC). The authors are grateful to the GIF

In situ Microscopic Observation of Sodium Deposition/Dissolution on Sodium Electrode

OpenAIRE

Yuhki Yui; Masahiko Hayashi; Jiro Nakamura

2016-01-01

Electrochemical sodium deposition/dissolution behaviors in propylene carbonate-based electrolyte solution were observed by means of in situ light microscopy. First, granular sodium was deposited at pits in a sodium electrode in the cathodic process. Then, the sodium particles grew linearly from the electrode surface, becoming needle-like in shape. In the subsequent anodic process, the sodium dissolved near the base of the needles on the sodium electrode and the so-called ?dead sodium? broke a...

4. generation sodium-cooled fast reactors. The ASTRID technological demonstrator

International Nuclear Information System (INIS)

2012-12-01

The sodium-cooled fast reactor (SFR) concept is one of the four fast neutron concepts selected by the Generation IV International Forum (GIF). SFRs have favourable technical characteristics and they are the sole type of reactor for which significant industrial experience feedback is available. After a discussion of the past experience gained on fast breeder reactors in the world (benefits, difficulties and problematics), the authors discuss the main improvement domains and the associated R and D advances (reactor safety, prevention and mitigation of severe accidents, the sodium-water risk, detection of sodium leaks, increased availability, instrumentation and inspection, control and repairability, assembly handling and washing). Then, they describe the technical requirements and safety objectives of the ASTRID experimental project, notably with its reactivity management, cooling management, and radiological containment management functions. They describe and discuss requirements to be met and choices made for Astrid, and the design options for its various components (core and fuels, nuclear heater, energy conversion system, fuel assembly handling, instrumentation and in-service inspection, control and command). They present the installations which are associated with the ASTRID cycle, evoke the development and use of simulations and codes, describe the industrial organization and the international collaboration about the ASTRID project, present the planning and cost definition

Development of the Level 1 PSA Model for PGSFR Regulatory

International Nuclear Information System (INIS)

Na, Hyun Ju; Lee, Yong Suk; Shin, Andong; Suh, Nam Duk

2014-01-01

SFR (sodium-cooled fast reactor) is Gen-IV nuclear energy system, which is designed for stability, sustainability and proliferation resistance. KALIMER-600 and PGSFR (Prototype Gen-IV SFR) are under development in Korea with enhanced passive safety concepts, e.g. passive reactor shutdown, passive residual heat removal, and etc. Risk analysis from a regulatory perspective is necessary for regulatory body to support the safety and licensing review of SFR. Safety issues should be identified in the early design phase in order to prevent the unexpected cost increase and the delay of PGSFR licensing schedule. In this respect, the preliminary PSA Model of KALIMER-600 had been developed for regulatory. In this study, the development of PSA Level 1 Model is presented. The important impact factors in the risk analysis for the PGSFR, such as Core Damage Frequency (CDF), have been identified and the related safety insights have been derived. The PSA level 1 model for PGSFR regulatory is developed and the risk analysis is conducted. Regarding CDF, LOISF frequency, uncertainty parameter for passive system CCF, loss of 125V DC control center bus and damper CCF are identified as the important factors. Sensitivity analyses show that the CDF would be differentiated (lowered) according to their values

Status of the Gen-IV Proliferation Resistance and Physical Protection (PRPP) Evaluation Methodology

International Nuclear Information System (INIS)

Whitlock, J.; Bari, R.; Peterson, P.; Padoani, F.; Cojazzi, G.G.M.; Renda, G.; ); Cazalet, J.; Haas, E.; Hori, K.; Kawakubo, Y.; Chang, S.; Kim, H.; Kwon, E.-H.; Yoo, H.; Chebeskov, A.; Pshakin, G.; Pilat, J.F.; Therios, I.; Bertel, E.

2015-01-01

Methodologies have been developed within the Generation IV International Forum (GIF) to support the assessment and improvement of system performance in the areas safeguards, security, economics and safety. Of these four areas, safeguards and security are the subjects of the GIF working group on Proliferation Resistance and Physical Protection (PRPP). Since the PRPP methodology (now at Revision 6) represents a mature, generic, and comprehensive evaluation approach, and is freely available on the GIF public website, several non-GIF technical groups have chosen to utilize the PRPP methodology for their own goals. Indeed, the results of the evaluations performed with the methodology are intended for three types of generic users: system designers, programme policy makers, and external stakeholders. The PRPP Working Group developed the methodology through a series of demonstration and case studies. In addition, over the past few years various national and international groups have applied the methodology to inform nuclear energy system designs, as well as to support the development of approaches to advanced safeguards. A number of international workshops have also been held which have introduced the methodology to design groups and other stakeholders. In this paper we summarize the technical progress and accomplishments of the PRPP evaluation methodology, including applications outside GIF, and we outline the PRPP methodology's relationship with the IAEA's INPRO methodology. Current challenges with the efficient implementation of the methodology are outlined, along with our path forward for increasing its accessibility to a broader stakeholder audience - including supporting the next generation of skilled professionals in the nuclear non-proliferation field. (author)

Optimized FFTF Acceptance Test Program covering Phases III, IV, and V

International Nuclear Information System (INIS)

Wykoff, W.R.; Jones, D.H.

1977-03-01

A detailed review of Phases III, IV, and V of the FFTF Acceptance Test Program has been completed. The purpose of this review was to formulate that test sequence which not only meets requirements for safe, reliable and useful operation of the plant, but also results in the earliest prudent demonstration of full-power performance. A test sequence based on the underlying assumption that sodium flows into the secondary sodium storage tank (T-44) no later than August 31, 1978, is described in detail. A time-scale which allows extra time to put systems and equipment into operation the first time, debugging, and learning how to operate most effectively has been superimposed on the test sequence. Time is not included for major equipment malfunctions. This test plan provides the basis for coordinating the many and varied activities and interfaces necessary for successful and timely execution of the FFTF Acceptance Test Program. In this report, the need dates have been identified for presently scheduled test articles and standard core components

The sodium coolant

International Nuclear Information System (INIS)

Rodriguez, G.

2004-01-01

The sodium is the best appropriate coolant for the fast neutrons reactors technology. Thus the fast neutrons reactors development is intimately bound to the sodium technology. This document presents the sodium as a coolant point of view: atomic structure and characteristics, sodium impacts on the fast neutron reactors technology, chemical properties of the sodium and the consequences, quality control in a nuclear reactor, sodium treatment. (A.L.B.)

Development of a Neutron Flux Monitoring System for Sodium-cooled Fast Reactors

OpenAIRE

Verma, Vasudha

2017-01-01

Safety and reliability are one of the key objectives for future Generation IV nuclear energy systems. The neutron flux monitoring system forms an integral part of the safety design of a nuclear reactor and must be able to detect any irregularities during all states of reactor operation. The work in this thesis mainly concerns the detection of in-core perturbations arising from unwanted movements of control rods with in-vessel neutron detectors in a sodium-cooled fast reactor. Feasibility stud...

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...

Sodium pool fire analysis of sodium-cooled fast reactor by calculation

International Nuclear Information System (INIS)

Yu Hong; Xu Mi; Jin Degui

2002-01-01

Theoretical models were established according to the characteristic of sodium pool fire, and the SPOOL code was created independently. Some transient processes in sodium pool fire were modeled, including chemical reaction of sodium and oxygen; sodium combustion heat transfer modes in several kids of media; production, deposition and discharge of sodium aerosol; mass and energy exchange between different media in different ventilating conditions. The important characteristic parameters were calculated, such as pressure and temperature of gas, temperature of building materials, mass concentration of sodium aerosol, and so on. The SPOOL code, which provided available safety analysis tool for sodium pool fire accidents in sodium-cooled fast reactor, was well demonstrated with experimental data

Comparative Evaluation of U.S. Brand and Generic Intravenous Sodium Ferric Gluconate Complex in Sucrose Injection: In Vitro Cellular Uptake

Directory of Open Access Journals (Sweden)

Min Wu

2017-12-01

Full Text Available Iron deficiency anemia is a common clinical consequence for people who suffer from chronic kidney disease, especially those requiring dialysis. Intravenous (IV iron therapy is a widely accepted safe and efficacious treatment for iron deficiency anemia. Numerous IV iron drugs have been approved by U.S. Food and Drug Administration (FDA, including a single generic product, sodium ferric gluconate complex in sucrose. In this study, we compared the cellular iron uptake profiles of the brand (Ferrlecit® and generic sodium ferric gluconate (SFG products. We used a colorimetric assay to examine the amount of iron uptake by three human macrophage cell lines. This is the first published study to provide a parallel evaluation of the cellular uptake of a brand and a generic IV iron drug in a mononuclear phagocyte system. The results showed no difference in iron uptake across all cell lines, tested doses, and time points. The matching iron uptake profiles of Ferrlecit® and its generic product support the FDA’s present position detailed in the draft guidance on development of SFG complex products that bioequivalence can be based on qualitative (Q1 and quantitative (Q2 formulation sameness, similar physiochemical characterization, and pharmacokinetic bioequivalence studies.

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....

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.

Sodium metabisulphite, a preservative agent, decreases the heart capillary volume and length, and curcumin, the main component of Curcuma longa, cannot protect it.

Science.gov (United States)

Noorafshan, A; Asadi-Golshan, R; Monjezi, S; Karbalay-Doust, S

2014-01-01

Sodium metabisulphite is used as an antioxidant agent in many pharmaceutical formulations. It is extensively used as a food preservative and disinfectant. It has been demonstrated that sulphite exposure can affect some organs. Curcumin, the main element of Curcuma longa, has been identified to have multiple protective properties. The present study extends the earlier works to quantitative evaluation of the effects of sulphite and curcumin on the heart structure using stereological methods. In this study, 28 rats were randomly divided into four experimental groups. The rats in groups I to IV received distilled water (group I), sodium metabisulphite (25 mg/ kg/day) (group II), curcumin (100 mg/kg/day) (group III), and sodium metabisulphite+curcumin (group IV), respectively, for 8 weeks. The left ventricle was subjected to stereological methods to estimate the quantitative parameters of the myocardium. A 20 % decrease was observed in the total volume of ventricular tissue in the sulphite-treated animals compared to the distilled water treatment (P curcumin did not protect the animals against the structural changes of the ventricle. Sulphite, as a preservative food agent, reduced the length and volume of the ventricular capillaries and curcumin could not protect them.

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"

Test Review: Advanced Clinical Solutions for WAIS-IV and WMS-IV

Science.gov (United States)

Chu, Yiting; Lai, Mark H. C.; Xu, Yining; Zhou, Yuanyuan

2012-01-01

The authors review the "Advanced Clinical Solutions for WAIS-IV and WMS-IV". The "Advanced Clinical Solutions (ACS) for the Wechsler Adult Intelligence Scale-Fourth Edition" (WAIS-IV; Wechsler, 2008) and the "Wechsler Memory Scale-Fourth Edition" (WMS-IV; Wechsler, 2009) was published by Pearson in 2009. It is a…

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.

Investigation of a Novel NDE Method for Monitoring Thermomechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems

Energy Technology Data Exchange (ETDEWEB)

Nagy, Peter

2013-09-30

The main goal of the proposed project is the development of validated nondestructive evaluation (NDE) techniques for in situ monitoring of ferritic-martensitic steels like Grade 91 9Cr-1Mo, which are candidate materials for Generation IV nuclear energy structural components operating at temperatures up to ~650{degree}C and for steam-generator tubing for sodium-cooled fast reactors. Full assessment of thermomechanical damage requires a clear separation between thermally activated microstructural evolution and creep damage caused by simultaneous mechanical stress. Creep damage can be classified as "negligible" creep without significant plastic strain and "ordinary" creep of the primary, secondary, and tertiary kind that is accompanied by significant plastic deformation and/or cavity nucleation and growth. Under negligible creep conditions of interest in this project, minimal or no plastic strain occurs, and the accumulation of creep damage does not significantly reduce the fatigue life of a structural component so that low-temperature design rules, such as the ASME Section III, Subsection NB, can be applied with confidence. The proposed research project will utilize a multifaceted approach in which the feasibility of electrical conductivity and thermo-electric monitoring methods is researched and coupled with detailed post-thermal/creep exposure characterization of microstructural changes and damage processes using state-of-the-art electron microscopy techniques, with the aim of establishing the most effective nondestructive materials evaluation technique for particular degradation modes in high-temperature alloys that are candidates for use in the Next Generation Nuclear Plant (NGNP) as well as providing the necessary mechanism-based underpinnings for relating the two. Only techniques suitable for practical application in situ will be considered. As the project evolves and results accumulate, we will also study the use of this technique for monitoring other GEN IV

Polimorfismos del gen BoLA-DRB3.2* en ganado criollo colombiano

Directory of Open Access Journals (Sweden)

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.

Direct complexonometric determination of thorium (IV), uranium (IV), neptunium (IV), plutonium (IV) by titration of diethylenetriaminepentaacetic acid with xylenol orange as indicator

International Nuclear Information System (INIS)

Rykov, A.G.; Piskunov, E.M.; Timofeev, G.A.

1975-01-01

The purpose of the present work was to develop a method of determining Th(IV), U(IV), Np(N) and Pu(IV) in acid solutions by titration with diethylenetriamine pentacetic acid, the indicator being xylenol orange. It has been established that Th, U, Np and Pu can be determined to within 0.5-1.5%. Th and U in quantities of tens of milligrams can be determined with greater accuracy, attaining hundredths of one per cent. During titration the determination is not hindered by singly- and doubly-charged metal ions, trivalent lanthanides and actinides, except plutonium. The proposed method can be used to determine U(IV) in the presence of considerable quantities of U(VI) and Np(IV) in the presence of Np(V). Total concentrations of uranium or neptunium are determined by reducing uranium (VI) or neptunium (V) by a standard method (for example, using metallic lead, cadmium or zinc amalgam) to the tetravalent state and applying the method described in the paper. (E.P.)

Low sodium diet (image)

Science.gov (United States)

... for you. Look for these words on labels: low-sodium, sodium-free, no salt added, sodium-reduced, ... for you. Look for these words on labels: low-sodium, sodium-free, no salt added, sodium-reduced, ...

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

Scientific Opinion on the safety evaluation of the active substances, sodium carbonate peroxyhydrate coated with sodium carbonate and sodium silicate, bentonite, sodium chloride, sodium carbonate for use in active food contact materials

OpenAIRE

EFSA Panel on Food Contact Materials, Enzymes, Flavourings and Processing Aids (CEF)

2013-01-01

This scientific opinion of the Panel on Food Contact Materials, Enzymes, Flavourings and Processing Aids deals with the safety evaluation of the powder mixture of the active substances sodium carbonate peroxyhydrate coated with sodium carbonate and sodium silicate (FCM substance No 1009), bentonite (CAS No 1302-78-9, FCM No 393), sodium chloride (CAS No 7647-14-5, FCM No 985), sodium carbonate (CAS No 497-19-8, FCM No 1008) which are intended to be used as combined oxygen generator and carbon...

Development of sodium disposal technology. Experiment of sodium compound solidification process

International Nuclear Information System (INIS)

Matsumoto, Toshiyuki; Ohura, Masato; Yatoh, Yasuo

2007-07-01

A large amount of sodium containing radioactive waste will come up at the time of final shutdown/decommission of FBR plant. The radioactive waste is managed as solid state material in a closed can in Japan. As for the sodium, there is no established method to convert the radioactive sodium to solid waste. Further, the sodium is highly reactive. Thus, it is recommended to convert the sodium to a stable substance before the solidification process. One of the stabilizing methods is conversion of sodium into sodium hydroxide solution. These stabilization and solidification processes should be safe, economical, and efficient. In order to develop such sodium disposal technology, nonradioactive sodium was used and a basic experiment was performed. Waste-fluid Slag Solidification method was employed as the solidification process of sodium hydroxide solution. Experimental parameters were mixing ratio of the sodium hydroxide and the slag solidification material, temperature and concentration of the sodium hydroxide. The best parameters were obtained to achieve the maximum filling ratio of the sodium hydroxide under a condition of enough high compressive strength of the solidified waste. In a beaker level test, the solidified waste was kept in a long term and it was shown that there was no change of appearance, density, and also the compressive strength was kept at a target value. In a real scale test, homogeneous profiles of the density and the compressive strength were obtained. The compressive strength was higher than the target value. It was shown that the Waste-fluid Slag Solidification method can be applied to the solidification process of the sodium hydroxide solution, which was produced by the stabilization process. (author)

Neutronic/Thermalhydraulic Coupling Technigues for Sodium Cooled Fast Reactor Simulations

Energy Technology Data Exchange (ETDEWEB)

Jean Ragusa; Andrew Siegel; Jean-Michel Ruggieri

2010-09-28

The objective of this project was to test new coupling algorithms and enable efficient and scalable multi-physics simulations of advanced nuclear reactors, with considerations regarding the implementation of such algorithms in massively parallel environments. Numerical tests were carried out to verify the proposed approach and the examples included some reactor transients. The project was directly related to the Sodium Fast Reactor program element of the Generation IV Nuclear Energy Systems Initiative and the Advanced Fuel cycle Initiative, and, supported the requirement of high-fidelity simulation as a mean of achieving the goals of the presidential Global Nuclear Energy Partnership (GNEP) vision.

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.

C-Scan Performance Test of Under-Sodium ultrasonic Waveguide Sensor in Sodium

International Nuclear Information System (INIS)

Joo, Young Sang; Bae, Jin Ho; Kim, Jong Bum

2011-01-01

Reactor core and in-vessel structures of a sodium-cooled fast (SFR) are submerged in opaque liquid sodium in the reactor vessel. The ultrasonic inspection techniques should be applied for observing the in-vessel structures under hot liquid sodium. Ultrasonic sensors such as immersion sensors and rod-type waveguide sensors have developed in order to apply under-sodium viewing of the in-vessel structures of SFR. Recently the novel plate-type ultrasonic waveguide sensor has been developed for the versatile application of under-sodium viewing in SFR. In previous studies, the ultrasonic waveguide sensor module was designed and manufactured, and the feasibility study of the ultrasonic waveguide sensor was performed. To improve the performance of the ultrasonic waveguide sensor in the under-sodium application, a new concept of ultrasonic waveguide sensors with a Be coated SS304 plate is suggested for the effective generation of a leaky wave in liquid sodium and the non-dispersive propagation of A 0 -mode Lamb wave in an ultrasonic waveguide sensor. In this study, the C-scan performance of the under-sodium ultrasonic waveguide sensor in sodium has been investigated by the experimental test in sodium. The under-sodium ultrasonic waveguide sensor and the sodium test facility with a glove box system and a sodium tank are designed and manufactured to carry out the performance test of under-sodium ultrasonic waveguide sensor in sodium environment condition

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

Sodium safety manual

International Nuclear Information System (INIS)

Hayes, D.J.; Gardiner, R.L.

1980-09-01

The sodium safety manual is based upon more than a decade of experience with liquid sodium at Berkeley Nuclear Laboratories (BNL). It draws particularly from the expertise and experience developed in the course of research work into sodium fires and sodium water reactions. It draws also on information obtained from the UKAEA and other sodium users. Many of the broad principles will apply to other Establishments but much of the detail is specific to BNL and as a consequence its application at other sites may well be limited. Accidents with sodium are at best unpleasant and at worst lethal in an extremely painful way. The object of this manual is to help prevent sodium accidents. It is not intended to give detailed advice on specific precautions for particular situations, but rather to set out the overall strategy which will ensure that sodium activities will be pursued safely. More detail is generally conveyed to staff by the use of local instructions known as Sodium Working Procedures (SWP's) which are not reproduced in this manual although a list of current SWP's is included. Much attention is properly given to the safe design and operation of larger facilities; nevertheless evidence suggests that sodium accidents most frequently occur in small-scale work particularly in operations associated with sodium cleaning and special care is needed in all such cases. (U.K.)

Diphenhydramine Overdose with Intraventricular Conduction Delay Treated with Hypertonic Sodium Bicarbonate and IV Lipid Emulsion

Directory of Open Access Journals (Sweden)

Amin Abdi

2014-11-01

Full Text Available Diphenhydramine toxicity commonly manifests with antimuscarinic features, including dry mucous membranes, tachycardia, urinary retention, mydriasis, tachycardia, and encephalopathy. Severe toxicity can include seizures and intraventricular conduction delay. We present here a case of a 23-year-old male presenting with recurrent seizures, hypotension and wide complex tachycardia who had worsening toxicity despite treatment with sodium bicarbonate. The patient was ultimately treated with intravenous lipid emulsion therapy that was temporally associated with improvement in the QRS duration. We also review the current literature that supports lipid use in refractory diphenhydramine toxicity. [West J Emerg Med. 2014;15(7:–0.

Synthesis and characterization of tin(IV) antimonate and study of its ion-exchange equilibria

International Nuclear Information System (INIS)

Burham, N.; Abdel-Halim, S.H.; El-Shahat, M.F.

1995-01-01

Tin(IV) antimonate with different Sb/Sn molar ratios has been prepared. The characterization of the product materials was carried out using X-ray diffraction pattern, thermal analysis and infrared spectra. The saturation capacities of sodium and cesium were found to increase with Sb/Sn molar ratios. The K d values on thermal treatment of tin(IV) antimonate, as a cation exchanger, have been measured for some heavy metal ions in the temperature range of 50-400 deg C. The maximum adsorption of 10 -4 M of the metal ions studied was obtained at 400 deg C. The selectivity sequence was Eu 3+ > Co 2+ > Sr 2+ > Cs + for the sample heated up to 400 deg C. No adsorption was observed on the sample heated at 700 deg C because of the formation of SnO 2 and Sb 6 O 13 . (author) 9 refs.; 7 figs.; 5 tabs

Preliminary Stress Analysis of an IHX Tube Support Plate in Prototype SFR

International Nuclear Information System (INIS)

Kim, Sung Kyun; Koo, Gyeong Hoi

2013-01-01

In this paper, the structural integrity about the conceptual design of IHX tube support plate was reviewed and the design should be changed because of its high stress concentration at the outer rim area. For reducing its maximum stress, two alternatives were proposed and reviewed for the structural integrity point of view. In both proposing support designs, the maximum stress decreases up to the stress design limit. Tube support plates (TSPs) of the intermediate heat exchanger (IHX) in Prototype GenIV Sodium Cooled Fast Reactor (PGSFR) act to horizontally support IHX tubes against hydraulic loadings and they have numerous flow holes where a primary sodium flows downward and secondary sodium flows upward. Due to its many penetrations, its geometric shape is quite complex and structurally its integrity is quite weaker than other parts. In this study, we investigated the structural integrity of the conceptually designed IHX tube support plate. In addition, TSP's supporting concepts were proposed to increase its structural integrity, and confirmed its integrity by using a finite element analysis

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

Urinary Sodium and Potassium Excretion and Dietary Sources of Sodium in Maputo, Mozambique

Directory of Open Access Journals (Sweden)

Ana Queiroz

2017-08-01

Full Text Available This study aimed to evaluate the urinary excretion of sodium and potassium, and to estimate the main food sources of sodium in Maputo dwellers. A cross-sectional evaluation of a sample of 100 hospital workers was conducted between October 2012 and May 2013. Sodium and potassium urinary excretion was assessed in a 24-h urine sample; creatinine excretion was used to exclude unlikely urine values. Food intake in the same period of urine collection was assessed using a 24-h dietary recall. The Food Processor Plus® was used to estimate sodium intake corresponding to naturally occurring sodium and sodium added to processed foods (non-discretionary sodium. Salt added during culinary preparations (discretionary sodium was computed as the difference between urinary sodium excretion and non-discretionary sodium. The mean (standard deviation urinary sodium excretion was 4220 (1830 mg/day, and 92% of the participants were above the World Health Organization (WHO recommendations. Discretionary sodium contributed 60.1% of total dietary sodium intake, followed by sodium from processed foods (29.0% and naturally occurring sodium (10.9%. The mean (standard deviation urinary potassium excretion was 1909 (778 mg/day, and 96% of the participants were below the WHO potassium intake recommendation. The mean (standard deviation sodium to potassium molar ratio was 4.2 (2.4. Interventions to decrease sodium and increase potassium intake are needed in Mozambique.

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.

Advanced Corrosion-Resistant Zr Alloys for High Burnup and Generation IV Application

International Nuclear Information System (INIS)

Jeong, Y. H.; Park, S. Y.; Lee, M. H.; Choi, B. K.; Baek, J. H.; Park, J. Y.; Kim, J. H.; Kim, H. G.; Jung, Y. H.; Bang, B. G.

2006-08-01

The systematic study was performed to develop the advanced corrosion-resistant Zr alloys for high burnup and Gen IV application. The corrosion behavior was significantly changed with the alloy composition and the corrosion environment. In general, the model alloys with a higher alloying elements showed a higher corrosion resistance. Among the model alloys tested in this study, Zr-10Cr-0.2Fe showed the best corrosion resistance regardless of the corrosion condition. The oxide on the higher corrosion-resistant alloy such as Zr-1.0Cr-0.2Fe consisted of mainly columnar grains, and it have a higher tetragonal phase stability. In comparison with other alloys being considered for the SCWR, the Zr alloys showed a lower corrosion rate than ferritic-martensitic steels. The results of this study imply that, at least from a corrosion standpoint, Zr alloys deserve consideration as potential cladding or structural materials in supercritical water cooled reactors

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 .

Assessment of flow induced vibration in a sodium-sodium heat exchanger

Energy Technology Data Exchange (ETDEWEB)

Prakash, V. [Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu (India)], E-mail: prakash@igcar.gov.in; Thirumalai, M.; Prabhakar, R.; Vaidyanathan, G. [Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu (India)

2009-01-15

The 500 MWe Prototype Fast Breeder Reactor (PFBR) is under construction at Kalpakkam. It is a liquid metal sodium cooled pool type fast reactor with all primary components located inside a sodium pool. The heat produced due to fission in the core is transported by primary sodium to the secondary sodium in a sodium to sodium Intermediate Heat Exchanger (IHX), which in turn is transferred to water in the steam generator. PFBR IHX is a shell and tube type heat exchanger with primary sodium on shell side and secondary sodium in the tube side. Since IHX is one of the critical components placed inside the radioactive primary sodium, trouble-free operation of the IHX is very much essential for power plant availability. To validate the design and the adequacy of the support system provided for the IHX, flow induced vibration (FIV) experiments were carried out in a water test loop on a 60 deg. sector model. This paper discusses the flow induced vibration measurements carried out in 60 deg. sector model of IHX, the modeling criteria, the results and conclusion.

Surfactant-impregnated activated carbon for enhanced adsorptive removal of Ce(IV) radionuclides from aqueous solutions

International Nuclear Information System (INIS)

Mahmoud, Mamdoh R.; Sharaf El-deen, Gehan E.; Soliman, Mohamed A.

2014-01-01

Highlights: • Activated carbon (AC) was impregnated in this work with CTAB and NaLS surfactants. • The materials were evaluated as a sorbent for adsorption of Ce(IV) radionuclides. • Adsorption capacity of AC–NaLS for Ce(IV) is two-times the capacity of AC. • The kinetic and equilibrium data are fitted to pseudo-second-order and D–R models. • The results suggest the applicability of surface modified AC for waste treatment. - Abstract: The surfactants cetyltrimethylammonium bromide (CTAB) and sodium lauryl sulfate (NaLS) were utilized for modifying the activated carbon’s surface. The materials were characterized using BET–N 2 , scanning electron microscope, and Fourier transform infrared (FT-IR) spectroscopy. Adsorption of Ce(IV) radionuclides from aqueous solutions by activated carbon (AC) and surfactant-impregnated AC was studied. The obtained data showed that adsorption of Ce(IV) is strongly dependent on the solution pH and AC–NaLS exhibits the widest pH-range of maximum removal. The experimental adsorption capacity of AC–NaLS (0.069 mmol/g) for Ce(IV) is found to be nearly twice greater than that of AC (0.036 mmol/g). The adsorption kinetics of Ce(IV) onto AC and AC–NaLS were analyzed by linear and non-linear fittings to the pseudo-first-order, pseudo-second-order and Elovich kinetic models. Of these models, the pseudo-second-order is the best kinetic expression for describing the experimental data. The diffusion studies indicated that adsorption of Ce(IV) radionuclides on AC and AC–NaLS is controlled by film diffusion. Linear and non-linear fittings of the adsorption equilibrium data for Ce(IV) onto AC and AC–NaLS revealed that the Dubinin–Radushkevich (D–R) isotherm model fits the experimental data better than Freundlich and Langmuir models. The values of adsorption free energy, E, calculated from both linear and non-linear methods suggested that Ce(IV) radionuclides are physically adsorbed onto AC and AC–NaLS

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

PVC Based Membrane of Ti(IV Iodovanadate for Pb(II Determination

Directory of Open Access Journals (Sweden)

Mu. Naushad

2008-08-01

Full Text Available Ti(IV iodovanadate has been synthesized by mixing a mixture of aqueous solutions of 0.1 M sodium vanadate and 0.1 M potassium iodate with 0.1 M solution of Ti(IV chloride at pH 1.0. Distribution coefficients (Kd of various metal ions were determined on the column of Ti(IV iodovanadate which showed the selectivity of Pb(II ions by this cation exchange material. So Ti(IV iodovanadate has been used as an electoactive material for the construction of Pb(II selective electrode. The main purpose of this study is to develop an inexpensive, simple and reliable ion-selective electrode for Pb(II determination. The sensor exhibit Nernstian response for Pb(II ions over a wide concentration range of 1 x 10-7 M to 1 x 10-1 M with a slope of 30±0.4 mV per decade of activity. The electrode is suitable for use in aqueous solution in a pH range of 2-7.2 with a response time of 10 second. The membrane electrode can be used at least for 4 months without any divergence in potential. The selectivity coefficients were determined by the mixed solution method and revealed that the electrode was selective for Pb(II ions in the presence of interfering cations. The sensor could be used as an indicator electrode in the potentiometric titration of Pb(II ions with EDTA. The practical applicability of the proposed sensor has been reported for Pb(II determination in a standard rock sample and water sample. The results are found to be in good agreement with those obtained by using conventional methods.

Congenital bilateral neuroblastoma (stage IV-S): case report

International Nuclear Information System (INIS)

Lee, Jeong Hee; Lee, Hee Jung; Woo, Seong Ku; Lee, Sang Rak; Kim, Heung Sik

2002-01-01

Congenital neonatal neuroblastoma is not uncommon but bilateral adrenal neuroblastoma is rare, accounting for about ten percent of neuroblastomas in children. We report the US the MR findings of a stage IV-S congenital bilateral neuroblastoma occurring in a one-day-old neonate

Sodium vapor deposition onto a horizontal flat plate above liquid sodium surface, (3)

International Nuclear Information System (INIS)

Kudo, Kazuhiko; Hirata, Masaru.

1978-01-01

Sodium vapour and sodium mist in the cover gas of a sodium system of a fast breeder reactor cause various problems. In this report, with the results of measurements of sodium mist concentration, the distribution of sodium mist diameter in cover gas was analytically obtained. The analysis was made by using the different nucleus model B. The measurement of the concentration of sodium mist was carried out with a sodium mist pot designed by the author. The experiment was done at the sodium temperature of 400 and 500 degree centigrade. The relations among sodium temperature, upper wall temperature, and the sodium mist concentration in cover gas were obtained. Evaluation of effective condensed nuclear radius in the cover gas was made by the comparison of analysis and experimental results. The results of this evaluation shows the following conclusions. It is impossible to express the distribution of sodium mist diameter by normal distribution or logarithmic normal distribution. Drop of sodium temperature results in the decrease of weight mean radius of generated sodium mist. Drop of upper wall temperature causes the decrease of weight mean radius, and increases sodium mist concentration. (Kato, T.)

An investigation of sodium iodide solubility in sodium-stainless steel systems

International Nuclear Information System (INIS)

Sagawa, Norihiko; Tashiro, Suguru

1996-01-01

Sodium iodide and major constituents of stainless steel in sodium are determined by using the steel capsules to obtain a better understanding on contribution of the constituents to the apparent iodide solubility in sodium. The capsule loaded with 20 g sodium and 0.1 - 0.3 g powder of sodium iodide is heated at its upper part in a furnace and cooled at its bottom on brass plates to establish a large temperature gradient along the capsule tube. After a given period of equilibration, the iodide and constituents are fixed in solidified sodium by quick quenching of the capsules. Sodium samples are taken from the sectioned capsule tube and submitted to sodium dissolution by vaporized water for determination of the iodine and to vacuum distillation for determination of the metal elements. Iron and nickel concentrations are observed to be lower in the samples at higher iodine concentrations. Chromium and manganese concentrations are seen to be insensitive to the iodine concentrations. The observations can be interpreted by a model that sodium oxide combines with metal iodide in sodium to form a complex compound and with consideration that the compound will fall and deposit onto the bottom of the capsule by thermal diffusion. (author)

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

49 CFR 173.189 - Batteries containing sodium or cells containing sodium.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Batteries containing sodium or cells containing sodium. 173.189 Section 173.189 Transportation Other Regulations Relating to Transportation PIPELINE AND... Than Class 1 and Class 7 § 173.189 Batteries containing sodium or cells containing sodium. (a...

Thermal hydraulic core simulation of the MYRRHA Reactor in steady state operation

International Nuclear Information System (INIS)

Ferandes, Gustavo H.N.; Ramos, Mário C.; Carvalho, Athos M.S.S.; Cabrera, Carlos E.V.; Costa, Antonella L.; Pereira, Claubia

2017-01-01

MYRRHA (Multi-purpose Hybrid Research Reactor for High-tech Applications) is a prototype nuclear subcritical reactor driven by a particle accelerator. As a special property, the reactor maintains the nuclear fission chain reaction by means of an external neutron source provided by a particle accelerator. The main aim of this work is to study two types of coolants, LBE (Lead-Bismuth Eutectic) and Na (Sodium) that are two strong candidates to be used in ADS systems as well as in Generation IV (GEN-IV) reactors. Firstly, it was developed a thermal hydraulic model of the MYRRHA core using the RELAP5-3D, considering LBE as coolant (original project). After this, the LBE was substituted by Na coolant to investigate the reactor behavior in such case. Results have demonstrated the high heat transfer capacity of the LBE coolant in this type of system. (author)

Thermal hydraulic core simulation of the MYRRHA Reactor in steady state operation

Energy Technology Data Exchange (ETDEWEB)

Ferandes, Gustavo H.N.; Ramos, Mário C.; Carvalho, Athos M.S.S.; Cabrera, Carlos E.V.; Costa, Antonella L.; Pereira, Claubia, E-mail: ghnfernandes@gmail.com, E-mail: marc5663@gmail.com, E-mail: athos1495@yahoo.com.br, E-mail: carlosvelcab@hotmail.com, E-mail: antonella@nuclear.ufmg.br, E-mail: claubia@nuclear.ufmg.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Instituto Nacional de Ciência e Tecnologia de Reatores Nucleares Inovadores/CNPq (Brazil)

2017-07-01

MYRRHA (Multi-purpose Hybrid Research Reactor for High-tech Applications) is a prototype nuclear subcritical reactor driven by a particle accelerator. As a special property, the reactor maintains the nuclear fission chain reaction by means of an external neutron source provided by a particle accelerator. The main aim of this work is to study two types of coolants, LBE (Lead-Bismuth Eutectic) and Na (Sodium) that are two strong candidates to be used in ADS systems as well as in Generation IV (GEN-IV) reactors. Firstly, it was developed a thermal hydraulic model of the MYRRHA core using the RELAP5-3D, considering LBE as coolant (original project). After this, the LBE was substituted by Na coolant to investigate the reactor behavior in such case. Results have demonstrated the high heat transfer capacity of the LBE coolant in this type of system. (author)

Measurement and Estimation of Effective Thermal Conductivity for Sodium based Nanofluid using 3-Omega Method

Energy Technology Data Exchange (ETDEWEB)

Oh, Sun Ryung; Park, Hyun Sun [POSTECH, Pohang (Korea, Republic of); Kim, Moo Hwan [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The sodium-cooled fast reactor (SFR) is one of generation IV type reactors and has been extensively researched since 1950s. A strong advantage of the SFR is its liquid sodium coolant which is well-known for its superior thermal properties. However, in terms of possible pipe leakage or rupture, a liquid sodium coolant possesses a critical issue due to its high chemical reactivity which leads to fire or explosion. Due to its safety concerns, dispersion of nanoparticles in liquid sodium has been proposed to reduce the chemical reactivity of sodium. In case of sodium based titanium nanofluid (NaTiNF), the chemical reactivity suppression effect when interacting with water has been proved both experimentally and theoretically [1,2]. Suppression of chemical reactivity is critical without much loss of high heat transfer characteristic of sodium. As there is no research conducted for applying 3-omega sensor in liquid metal as well as high temperature liquid, the sensor development is performed for using in NaTiNF as well as effective thermal conductivity model validation. Based on the acquired effective thermal conductivity of NaTiNF, existing effective thermal conductivity models are evaluated. Thermal conductivity measurement is performed for liquid sodium based titanium nanofluid (NaTiNF) through 3-Omega method. The experiment is conducted at three temperature points of 120, 150, and 180 .deg. C for both pure liquid sodium and NaTiNF. By using 3- omega sensor, thermal conductivity measurement of liquid metal can be more conveniently conducted in labscale. Also, its possibility to measure the thermal conductivity of high temperature liquid metal with metallic nanoparticles being dispersed is shown. Unlike other water or oil-based nanofluids, NaTiNF exhibits reduction of thermal conductivity compare with liquid sodium. Various nanofluid models are plotted, and it is concluded that the MSBM which considers interfacial resistance and Brownian motion can be used in predicting

Measurement and Estimation of Effective Thermal Conductivity for Sodium based Nanofluid using 3-Omega Method

International Nuclear Information System (INIS)

Oh, Sun Ryung; Park, Hyun Sun; Kim, Moo Hwan

2016-01-01

The sodium-cooled fast reactor (SFR) is one of generation IV type reactors and has been extensively researched since 1950s. A strong advantage of the SFR is its liquid sodium coolant which is well-known for its superior thermal properties. However, in terms of possible pipe leakage or rupture, a liquid sodium coolant possesses a critical issue due to its high chemical reactivity which leads to fire or explosion. Due to its safety concerns, dispersion of nanoparticles in liquid sodium has been proposed to reduce the chemical reactivity of sodium. In case of sodium based titanium nanofluid (NaTiNF), the chemical reactivity suppression effect when interacting with water has been proved both experimentally and theoretically [1,2]. Suppression of chemical reactivity is critical without much loss of high heat transfer characteristic of sodium. As there is no research conducted for applying 3-omega sensor in liquid metal as well as high temperature liquid, the sensor development is performed for using in NaTiNF as well as effective thermal conductivity model validation. Based on the acquired effective thermal conductivity of NaTiNF, existing effective thermal conductivity models are evaluated. Thermal conductivity measurement is performed for liquid sodium based titanium nanofluid (NaTiNF) through 3-Omega method. The experiment is conducted at three temperature points of 120, 150, and 180 .deg. C for both pure liquid sodium and NaTiNF. By using 3- omega sensor, thermal conductivity measurement of liquid metal can be more conveniently conducted in labscale. Also, its possibility to measure the thermal conductivity of high temperature liquid metal with metallic nanoparticles being dispersed is shown. Unlike other water or oil-based nanofluids, NaTiNF exhibits reduction of thermal conductivity compare with liquid sodium. Various nanofluid models are plotted, and it is concluded that the MSBM which considers interfacial resistance and Brownian motion can be used in predicting

Construcción de un vector de expresión derivado de virus adenoasociados para corregir in vitro el defecto genético de la enfermedad de Morquio A

Directory of Open Access Journals (Sweden)

Luis Alejandro Barrera

2008-09-01

Full Text Available Introducción. La mucopolisacaridosis IV A (Morquio A es una enfermedad de depósito lisosómico causada por la deficiencia en la actividad de la enzima N-acetil-galactosamina- 6-sulfato-sulfatasa que produce la acumulación intralisosómica de queratán y condroitín-6-sulfato. Hasta el momento, su manejo es paliativo, por lo que las investigaciones se han enfocado en establecer una terapia que pueda aplicarse tempranamente y garantice la expresión estable de la enzima. En este sentido, la terapia génica se presenta como una de las potenciales alternativas terapéuticas para corregir el defecto genético en la mucopolisacaridosis IV A. Objetivo. Construir vectores de expresión derivados de virus adenoasociados para corregir in vitro la deficiencia enzimática en la mucopolisacaridosis IV A. Materiales y métodos. Se produjeron vectores derivados de virus adenoasociados que portaban el gen humano de la enzima N-acetil-galactosamina-6-sulfato-sulfatasa dirigido por el promotor temprano del citomegalovirus humano, empleando un sistema libre de adenovirus. Se transfectaron células HEK293 y fibroblastos humanos Morquio A con los virus recombinantes, y se determinó la actividad enzimática en el lisado celular a las 24 y 48 horas después de la transfección. Resultados. Se obtuvieron virus adenoasociados recombinantes, libres de adenovirus, con títulos hasta de 2,08 x 1010 cápsides/ml. Tanto en células HEK293 como en fibroblastos Morquio A transfectados, se obtuvieron actividades enzimáticas hasta de 3,05 nmoles/mg por hora, 48 horas después de la transfección. Conclusión. Los virus recombinantes producidos expresaron in vitro la enzima GALNS en las células transfectadas. Estos resultados constituyen el paso inicial para el desarrollo de una terapia génica para la enfermedad de Morquio A empleando vectores derivados de virus adenoasociados.

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...

Cavitation erosion in sodium flow, sodium cavitation tunnel testing

International Nuclear Information System (INIS)

Courbiere, Pierre.

1981-04-01

The high-volume sodium flows present in fast neutron reactors are liable to induce cavitation phenomena in various portion of the sodium lines and pumps. The absence of sufficient data in this area led the C.E.A. to undertake an erosion research program in cavitating sodium flow. This paper discusses the considerations leading to the definition and execution of sodium cavitation erosion tests, and reviews the tests run with 400 0 C sodium on various steel grades: 316, 316 L, 316 Ti (Z8CNDT17-12), Poral (Z3CND18-12), 304 L and LN2 - clad 316 L (Ni coating-clad 316 L). Acoustic detection and signal processing methods were used with an instrument package designed and implemented at the Cadarache Nuclear Research Center

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.

Elaboration and characterization of solid electrolytes for electrochemical oxygen sensors in liquid sodium

International Nuclear Information System (INIS)

Gabard, M.

2013-01-01

This PhD thesis was prepared within the framework of the research program on 'Generation IV' nuclear reactors with sodium as coolant. One of the main technological problem concerns the control of the corrosion processes of the materials (structural materials, fuel claddings, etc.) by liquid sodium. A key parameter is the dissolved oxygen content in the coolant. This thesis focuses on the development and characterization of ceramic materials based on ThO 2 doped with Y 2 O 3 for making potentiometric oxygen sensor used in liquid sodium. Work has been carried out and probes were tested in the past, however, the probes had at the time, a lack of reliability. The objective of this thesis is to develop and characterize electrolytes based on thorium oxide doped with yttrium oxide using specific synthesis techniques to control purity, grain size, compactness, etc. To develop experimental protocols a ceramic model has been chosen, i.e., yttria-doped ceria. Transport processes were studied using the impedance spectroscopy technique. An interpretation of the blocking phenomena of the ionic conduction in both ceramics as a function of the oxygen partial pressure has been given. (author) [fr

Removal of sodium from the component of the sodium purification loop

International Nuclear Information System (INIS)

Kim, Byung Ho; Jeong, Kyung Chai; Jeong, Ji Young; Kim, Jong Man; Choi, Byung Hae; Nam, Ho Yun

2005-01-01

The purpose of a cleaning process is to remove the residual sodium adhering to the component walls once it has been properly drained. It is necessary to clean and decontaminate a component, especially the large components of the primary coolant system; such as the intermediate heat exchangers and the primary pump. Improper and inadequate cleaning has in a number of cases resulted in problems in the storage, handling, and reuse of components. Several types of failures due to improper cleaning procedures have been defined in the past. Inadequate and incomplete removal of sodium results in residues which may contain metallic sodium and alkaline compounds such as sodium hydroxide, sodium oxide, sodium carbonate, and various types of alcoholates. Reinsertion of components containing these compounds into a high-temperature sodium system can result in either the intergranular penetration characteristic of a high-oxygen sodium or an accelerated corrosion due to oxygen. The methods used for cleaning sodium equipment depend on the condition and types of equipment to be cleaned and whether the equipment is to be reused. Cleaning methods are needed that will avoid a deleterious local overheating, material surface degradation or deposits, chemical, physical, or mechanical damage, and external effects. This paper discusses a steam-nitrogen gas cleaning method for the routine applications that permits the reuse of the cold trap in sodium

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

Apparatus for removing impurities in the sodium of sodium cooled reactors

Energy Technology Data Exchange (ETDEWEB)

Yamauchi, A

1970-11-11

An apparatus is provided for removing oxygen from liquid sodium flowing in a sodium cooled reactor. The removal of oxygen is complete with high efficiency. The liquid sodium to be purified is disposed outside a cylindrical wall and negatively charged, whereas sodium as a reducing material is disposed inside the same wall. The cylindrical wall is made of zirconia-calcia (ZrO/sub 2/)sub(0.87)(CaO)sub(0.13) solid electrolyte, the cylinder having a thickness of 2.5mm, a diameter of 3cm and a depth of 20cm under the sodium level. Electric resistance of the solid electrolyte is 2.3 ohm at 500/sup 0/C. A current of 1A by the application of 25 volts treats 0.3g of oxygen. Consequently, 1 liter or 1kg of liquid sodium containing 1,000ppm of oxygen can be purified for about 3 hours at an electrical consumption of 7.5 watt-hour. In one embodiment, a cylindrical electrolytic solid made of zirconia-calcia or zirconia-yttria was disposed in a container. Liquid sodium containing oxygen flowed outside of the cylinder. Liquid sodium as a reducing material was present inside the cylinder and the container and the cylinder were electrically insulated. An electrode was inserted at the center of the cylinder and a baffle plate at the upper portion of the electrode to shield heat and rising sodium vapor was provided. The space above the container was filled with an inert gas. The oxygen in the liquid sodium to be purified transferred through the wall of the cylinder into the interior of the cylinder so as to oxydize the reducing sodium material. The supersaturated sodium oxide inside the cylinder was deposited.

Thermodynamics of the complex formation between thorium(IV) and some polydentate ligands in aqueous solution

International Nuclear Information System (INIS)

Di Bernado, P.; Cassol, A.; Tomat, G.; Bismondo, A.; Magon, L.

1983-01-01

The changes in free energy, enthalpy, and entropy for the formation of thorium(IV)-oxydiacetate, -iminodiacetate, -thiodiacetate, and -succinate complexes have been determined by potentiometric and calorimetric titrations at 25 deg C in aqueous 1 mol dm - 3 sodium perchlorate. All the ligands form 1:1 chelate complexes with the thorium(IV) ion the stability of which is dependent on both the chelate ring dimensions and the nature of the donor group in the chain. The order of the relative stabilities (iminodiacetate > oxydiacetate > thiodiacetate > succinate) is mainly dependent on the reaction enthalpies, since the δS values are close to each other. In the thorium(IV)-oxydiacetate system the maximum number of three ligands for every metal ion was reached. Because of precipitation of solid compounds in the other systems, it was only possible to define complexes with a lower number of co-ordinated ligands: two for succinate and thiodiacetate, and one for iminodiacetate. Owing to the lower stability of the chelate ring of thiodiacetate and succinate complexes and the high basicity of the amino-group of iminodiacetate, these ligands form also unchelated protonated complexes. (author)

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.

Neutronic/Thermal-hydraulic Coupling Technigues for Sodium Cooled Fast Reactor Simulations

International Nuclear Information System (INIS)

Ragusa, Jean; Siegel, Andrew; Ruggieri, Jean-Michel

2010-01-01

The objective of this project was to test new coupling algorithms and enable efficient and scalable multi-physics simulations of advanced nuclear reactors, with considerations regarding the implementation of such algorithms in massively parallel environments. Numerical tests were carried out to verify the proposed approach and the examples included some reactor transients. The project was directly related to the Sodium Fast Reactor program element of the Generation IV Nuclear Energy Systems Initiative and the Advanced Fuel cycle Initiative, and, supported the requirement of high-fidelity simulation as a mean of achieving the goals of the presidential Global Nuclear Energy Partnership (GNEP) vision.

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.

Effect of sodium lactate /sodium diacetate in combination with sodium nitrite on physiochemical, microbial properties and sensory evaluation of cow sausage

Directory of Open Access Journals (Sweden)

Habib Sedghi

2014-11-01

Full Text Available Sodium nitrite has been always considered as one of the common additives due to its antibacterial effects on Clostridium botulinum and meat products' color, however it produces cancer creating nitrosamine. Recently, organic acids and their salts such as lactates have been employed as antimicrobial compounds. Lactates also improve organileptic properties including color, texture and taste and antioxidant properties. Sodium lactate causes to more reduction of anaerobic spore former bacteria than nitrite, inhibits botulin produced by Clostridium botulinum. Sodium lactate produces a permanent reddish pink color through reduction of deoxymygloboline and producing deoxymyoglobuline. In this study, the decrease of sodium nitrite amount from 120ppm to 15ppm by adding sodium lactate / sodium diacetate led to achieve an acceptable product. The best results revealed through adding 3.0625% of sodium lactate / sodium diacetate in combination with 30ppm sodium nitrite. Results also exhibited more reduction of pathogens' growth than nitrite, enhanced flavor slightly, but unable to produce reddish pink color as produced by nitrite. Results also exhibited that sodium lactate / diacetate cause to retard in microbial growth, reducing chemical change, enhance sensory properties, partially improvement in taste and texture. Although inappropriate color demonstrated sodium lactate / diacetate's inability in red pink color production in 4th sample (contains 15 ppm nitrite, its synergy effect in combination with sodium nitrite on nitroso myoglobuline production has been proven, led to sodium nitrite reduction in sausages.

Electrolytic process to produce sodium hypochlorite using sodium ion conductive ceramic membranes

Science.gov (United States)

Balagopal, Shekar; Malhotra, Vinod; Pendleton, Justin; Reid, Kathy Jo

2012-09-18

An electrochemical process for the production of sodium hypochlorite is disclosed. The process may potentially be used to produce sodium hypochlorite from seawater or low purity un-softened or NaCl-based salt solutions. The process utilizes a sodium ion conductive ceramic membrane, such as membranes based on NASICON-type materials, in an electrolytic cell. In the process, water is reduced at a cathode to form hydroxyl ions and hydrogen gas. Chloride ions from a sodium chloride solution are oxidized in the anolyte compartment to produce chlorine gas which reacts with water to produce hypochlorous and hydrochloric acid. Sodium ions are transported from the anolyte compartment to the catholyte compartment across the sodium ion conductive ceramic membrane. Sodium hydroxide is transported from the catholyte compartment to the anolyte compartment to produce sodium hypochlorite within the anolyte compartment.

Multidrug resistance in epilepsy and polymorphisms in the voltage-gated sodium channel genes SCN1A, SCN2A, and SCN3A: correlation among phenotype, genotype, and mRNA expression.