WorldWideScience

Sample records for gen iv materials

  1. Gen IV Materials Handbook Implementation Plan

    International Nuclear Information System (INIS)

    Rittenhouse, P.; Ren, W.

    2005-01-01

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

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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

  11. Millimeter-Wave Thermal Analysis Development and Application to GEN IV Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Wosko, Paul; Sundram, S. K.

    2012-10-16

    New millimeter-wave thermal analysis instrumentation has been developed and studied for characterization of materials required for diverse fuel and structural needs in high temperature reactor environments such as the Next Generation Nuclear Plant (NGNP). A two-receiver 137 GHz system with orthogonal polarizations for anisotropic resolution of material properties has been implemented at MIT. The system was tested with graphite and silicon carbide specimens at temperatures up to 1300 ºC inside an electric furnace. The analytic and hardware basis for active millimeter-wave radiometry of reactor materials at high temperature has been established. Real-time, non contact measurement sensitivity to anisotropic surface emissivity and submillimeter surface displacement was demonstrated. The 137 GHz emissivity of reactor grade graphite (NBG17) from SGL Group was found to be low, ~ 5 %, in the 500 – 1200 °C range and increases by a factor of 2 to 4 with small linear grooves simulating fracturing. The low graphite emissivity would make millimeter-wave active radiometry a sensitive diagnostic of graphite changes due to environmentally induced stress fracturing, swelling, or corrosion. The silicon carbide tested from Ortek, Inc. was found to have a much higher emissivity at 137 GHz of ~90% Thin coatings of silicon carbide on reactor grade graphite supplied by SGL Group were found to be mostly transparent to millimeter-waves, increasing the 137 GHz emissivity of the coated reactor grade graphite to about ~14% at 1250 ºC.

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-04-23

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

  14. 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.

  15. The web-enabled database of JRC-EC, a useful tool for managing European Gen IV materials data

    International Nuclear Information System (INIS)

    Over, H.H.; Dietz, W.

    2008-01-01

    Materials and document databases are important tools to conserve knowledge and experimental materials data of European R and D projects. A web-enabled application guarantees a fast access to these data. In combination with analysis tools the experimental data are used for e.g. mechanical design, construction and lifetime predictions of complex components. The effective and efficient handling of large amounts of generic and detailed materials data with regard to properties related to e.g. fabrication processes, joining techniques, irradiation or aging is one of the basic elements of data management within ongoing nuclear safety and design related European research projects and networks. The paper describes the structure and functionality of Mat-DB and gives examples how these tools can be used for the management and evaluation of materials data of European (national or multi-national) R and D activities or future reactor types such as the EURATOM FP7 Generation IV reactor types or the heavy liquid metals cooled reactor

  16. Market share scenarios for Gen-DIII and gen-IV reactors in Europe

    International Nuclear Information System (INIS)

    Roelofs, F.; Heek, A. V.; Durpel, L. V. D.

    2008-01-01

    Nuclear energy is back on the agenda worldwide in order to meet growing energy demand and especially the growth in electricity demand. Many objectives direct to an increased use of nuclear energy, i.e. minimising energy costs, reducing climate change effects and others. In the light of the potential renewed growth of nuclear energy, the public demands a clear view on what nuclear energy may contribute towards meeting these objectives and especially how nuclear energy may address some socio-political obstructions with respect to economics, radioactive waste, safety and proliferation of fissile materials. To address these questions, the future nuclear reactor park mix in Europe has been analysed applying an integrated dynamic process modelling technique. Various market share scenarios for nuclear energy are derived including sub-variants with regard to the intra-nuclear options. In the analyses, it is assumed that different types of new reactors may be built, taking into account the introduction date of considered Gen-Ill (i.e. EPR) and Gen-IV (i.e. SCWR, HTR, FR) reactors, and the economic evaluation of the complete fuel cycle. The assessment was undertaken using the DANESS code (Dynamic Analysis of Nuclear Energy System Strategies). The analyses show that given the considered realistic nuclear energy demand and given a limited number of available Gen-III and Gen-IV reactor types, the future European nuclear park will exist of combinations of Gen-III and Gen-IV reactors. This mix will always consist of a set of reactor types each having its specific strengths. The analyses also highlight the triggers influencing the choice between different nuclear energy deployment scenarios. (authors)

  17. 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)

  18. 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)

  19. Improvement of Steam Generator Reliability for GEN-IV SFR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seong O; Kim Se Yun; Kim, Seok Hoon; Eoh, Jae Hyuk; Lee, Hyeong Yeon; Choi, Byung Seon

    2005-11-15

    The R and D items performed in this study were selected from the R and D task of ' Reliability improvement of Steam Generator' of GEN-IV SFR Component Design and BOP. Since this project deals with one of the most important issues for a GEN-IV SFR system, it needs to enhance the domestic technical backgrounds associated with the corresponding R and D items even for a very short period by 2005. This study provides the R and D results for i) Development of assessment methodology for dissimilar metal weld and ii) Development of multi-dimensional simulation methodology for a SWR event in a SFR steam generator.

  20. Improvement of Steam Generator Reliability for GEN-IV SFR

    International Nuclear Information System (INIS)

    Kim, Seong O; Kim Se Yun; Kim, Seok Hoon; Eoh, Jae Hyuk; Lee, Hyeong Yeon; Choi, Byung Seon

    2005-11-01

    The R and D items performed in this study were selected from the R and D task of ' Reliability improvement of Steam Generator' of GEN-IV SFR Component Design and BOP. Since this project deals with one of the most important issues for a GEN-IV SFR system, it needs to enhance the domestic technical backgrounds associated with the corresponding R and D items even for a very short period by 2005. This study provides the R and D results for i) Development of assessment methodology for dissimilar metal weld and ii) Development of multi-dimensional simulation methodology for a SWR event in a SFR steam generator

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

    International Nuclear Information System (INIS)

    Belot, Clotilde

    2013-01-01

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

  2. 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)

  3. 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

  4. 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.

  5. 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

  6. 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)

  7. 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

  8. 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

  9. Direct Bandgap Group IV Materials

    Science.gov (United States)

    2016-01-21

    AFRL-AFOSR-JP-TR-2017-0049 Direct Bandgap group IV Materials Hung Hsiang Cheng NATIONAL TAIWAN UNIVERSITY Final Report 01/21/2016 DISTRIBUTION A...NAME(S) AND ADDRESS(ES) NATIONAL TAIWAN UNIVERSITY 1 ROOSEVELT RD. SEC. 4 TAIPEI CITY, 10617 TW 8. PERFORMING ORGANIZATION REPORT NUMBER 9. SPONSORING...14. ABSTRACT Direct bandgap group IV materials have been long sought for in both academia and industry for the implementation of photonic devices

  10. 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

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

    International Nuclear Information System (INIS)

    Nakai, Ryodai

    2013-01-01

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

  12. 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

  13. 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)

  14. 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)

  15. 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)

  16. 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)

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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).

  3. 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).

  4. GEN IV: Carbide Fuel Elaboration for the 'Futurix Concepts' experiment

    International Nuclear Information System (INIS)

    Vaudez, Stephane; Riglet-Martial, Chantal; Paret, Laurent; Abonneau, Eric

    2008-01-01

    In order to collect information on the behaviour of the future GFR (Gas Fast Reactor) fuel under fast neutron irradiation, an experimental irradiation program, called 'Futurix-concepts' has been launched at the CEA. The considered concept is a composite material made of a fissile fuel embedded in an inert ceramic matrix. Fissile fuel pellets are made of UPuN or UPuC while ceramics are SiC for the carbide fuel and TiN for the nitride fuel. This paper focuses on the description of the carbide composite fabrication. The UPuC pellets are manufactured using a metallurgical powder process. Fabrication and handling of the fuels are carried out in glove boxes under a nitrogen atmosphere. Carbide fuel is synthesized by carbo-thermic reduction under vacuum of a mixture of actinide oxide and graphitic carbon up to 1550 deg. C. After ball milling, the UPuC powder is pressed to create hexagonal or spherical compacts. They are then sintered up to 1750 deg. C in order to obtain a density of 85 % of the theoretical one. The sintered pellets are inserted into an inert and tight capsule of SiC. In order to control the gap between the fuel and the matrix precisely, the pellets are abraded. The inert matrix is then filled with the pellets and the whole system is sealed by a BRASiC R process at high temperature under a helium atmosphere. Fabrication of the sample to be irradiated was done in 2006 and the irradiation began in May 2007 in the Phenix reactor. This presentation will detail and discuss the results obtained during this fabrication phase. (authors)

  5. 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

  6. 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)

  7. 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)

  8. 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)

  9. 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)

  10. 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

  11. 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.

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Jaewoon Yoo

    2016-10-01

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

  14. 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

  15. A preliminary safety analysis for the prototype Gen IV Sodium-Cooled Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-15

    Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR). To assess the effectiveness of the inherent safety features of the PGSFR, the system transients during design basis accidents and design extended conditions are analyzed with MARS-LMR and the subchannel blockage events are analyzed with MATRA-LMR-FB. In addition, the in-vessel source term is calculated based on the super-safe, small, and simple reactor methodology. The results show that the PGSFR meets safety acceptance criteria with a sufficient margin during the events and keeps accidents from deteriorating into more severe accidents.

  16. Progress reports for Gen IV sodium fast reactor activities FY 2007

    International Nuclear Information System (INIS)

    Cahalan, J. E.; Tentner, A. M.

    2007-01-01

    for prevention of progression into severe accident conditions (prevention of core melting) or for mitigation of severe accident consequences (mitigation of the impact of core melting to protect public health and safety). Because design measures for severe accident prevention and mitigation are beyond the normal design basis, established regulatory guidelines and codes do not provide explicit identification of the design performance requirements for severe accident accommodation. The treatment of severe accidents is one of the key issues of R and D plans for the Gen IV systems in general, and for the Sodium Fast Reactor (SFR) in particular. Despite the lack of an unambiguous definition of safety approach applicable for severe accidents, there is an emerging consensus on the need for their consideration for the design. The US SFR program and Argonne National Laboratory (ANL) in particular have actively studied the potential scenarios and consequences of Hypothetical Core Disruptive Accidents (HCDA) for SFRs with oxide fuel during the Fast Flux Test Facility (FFTF) and Clinch River Breeder Reactor Plant (CRBRP) programs in the 70s and 80s. Later, the focus of the US SFR safety R and D activities shifted to the prevention of all HCDAs through passive safety features of the SFRs with metal fuel in the Integral Fast Reactor (IFR) program, and the study of severe accident consequences was de-emphasized. The goal of this paper is to provide an overview of the current SFR safety approach and the role of severe accidents in Japan and France, in preparation for an expected and more active collaboration in this area between the US, Japan, and France

  17. Mechanical Design Concept of Fuel Assembly for Prototype GEN-IV Sodium-cooled Fast Reactor

    International Nuclear Information System (INIS)

    Yoon, K. H.; Lee, C. B.

    2014-01-01

    The prototype GEN-IV sodium-cooled fast reactor (PGSFR) is an advanced fast reactor plant design that utilizes compact modular pool-type reactors sized to enable factory fabrication and an affordable prototype test for design certification at minimum cost and risk. The design concepts of the fuel assembly (FA) were introduced for a PGSFR. Unlike that for the pressurized water reactor, there is a neutron shielding concept in the FA and recycling metal fuel. The PGSFR core is a heterogeneous, uranium-10% zirconium (U-10Zr) metal alloy fuel design with 112 assemblies: 52 inner core fuel assemblies, 60 outer core fuel assemblies, 6 primary control assemblies, 3 secondary control assemblies, 90 reflector assemblies and 102 B4C shield assemblies. This configuration is shown in Fig. 1. The core is designed to produce 150 MWe with an average temperature rise of 155 .deg. C. The inlet temperature is 390 .deg. C and the bulk outlet temperature is 545 .deg. C. The core height is 900 mm and the gas plenum length is 1,250 mm. A mechanical design of a fuel assembly for a PGSFR was established. The mechanical design concepts are well realized in the design. In addition to this, the analytical and experimental works will be carries out for verifying the design soundness

  18. Mechanical Design Concept of Fuel Assembly for Prototype GEN-IV Sodium-cooled Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, K. H.; Lee, C. B. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The prototype GEN-IV sodium-cooled fast reactor (PGSFR) is an advanced fast reactor plant design that utilizes compact modular pool-type reactors sized to enable factory fabrication and an affordable prototype test for design certification at minimum cost and risk. The design concepts of the fuel assembly (FA) were introduced for a PGSFR. Unlike that for the pressurized water reactor, there is a neutron shielding concept in the FA and recycling metal fuel. The PGSFR core is a heterogeneous, uranium-10% zirconium (U-10Zr) metal alloy fuel design with 112 assemblies: 52 inner core fuel assemblies, 60 outer core fuel assemblies, 6 primary control assemblies, 3 secondary control assemblies, 90 reflector assemblies and 102 B4C shield assemblies. This configuration is shown in Fig. 1. The core is designed to produce 150 MWe with an average temperature rise of 155 .deg. C. The inlet temperature is 390 .deg. C and the bulk outlet temperature is 545 .deg. C. The core height is 900 mm and the gas plenum length is 1,250 mm. A mechanical design of a fuel assembly for a PGSFR was established. The mechanical design concepts are well realized in the design. In addition to this, the analytical and experimental works will be carries out for verifying the design soundness.

  19. Level II Probabilistic Safety Analysis Methodology for the Application to GEN-IV Sodium-cooled Fast Reactor

    International Nuclear Information System (INIS)

    Park, S. Y.; Kim, T. W.; Han, S. H.; Jeong, H. Y.

    2010-03-01

    The Korea Atomic Energy Research Institute (KAERI) has been developing liquid metal reactor (LMR) design technologies under a National Nuclear R and D Program. Nevertheless, there is no experience of the probabilistic safety assessment (PSA) domestically for a fast reactor with the metal fuel. Therefore, the objective of this study is to establish the methodologies of risk assessment for the reference design of GEN-IV sodium fast reactor (SFR). An applicability of the PSA methodology of U. S. NRC and PRISM plant to the domestic GEN-IV SFR has been studied. The study contains a plant damage state analysis, a containment event tree analysis, and a source-term release category binning process

  20. 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

  1. Uranium enrichment reduction in the Prototype Gen-IV sodium-cooled fast reactor (PGSFR) with PBO reflector

    Energy Technology Data Exchange (ETDEWEB)

    Hartanto, Donny; Kim, Chi Hyung; Kim, Yong Hee [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST), Daejeon (Korea, Republic of)

    2016-04-15

    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.

  2. 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

  3. 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.

  4. 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

  5. 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)

  6. 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

  7. 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)

  8. 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)

  9. 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

  10. 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.

  11. 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)

  12. 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)

  13. A Stochastic Proof of the Resonant Scattering Kernel and its Applications for Gen IV Reactors Type

    International Nuclear Information System (INIS)

    Becker, B.; Dagan, R.; Broeders, C.H.M.; Lohnert, G.

    2008-01-01

    Monte Carlo codes such as MCNP are widely accepted as almost-reference for reactor analysis. The Monte Carlo Code should therefore use as few as possible approximations in order to produce 'experimental-level' calculations. In this study we deal with one of the most problematic approximations done in MCNP in which the resonances are ignored for the secondary neutron energy distribution, namely the change of the energy and angular direction of the neutron after interaction with a heavy isotope with pronounced resonances. The endeavour of exploiting the influence of the resonances on the scattering kernel goes back to 1944 where E. Wigner and J. Wilkins developed the first temperature dependent scattering kernel. However only in 1998, the full analytical solution for the double differential resonant dependent scattering kernel was suggested by W. Rothenstein and R. Dagan. An independent stochastic approach is presented for the first time to confirm the above analytical kernel with a complete different methodology. Moreover, by manipulating in a subtle manner the scattering subroutine COLIDN of MCNP, it is proven that this very subroutine is, to some extent, inappropriate as well as the relevant explanation in the MCNP manual. The impact of this improved resonance dependent scattering kernel on diverse types of reactors, in particular for the Generation IV innovative core design HTR, is shown to be significant. (authors)

  14. 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.

  15. 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)

  16. 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

  17. A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems

    International Nuclear Information System (INIS)

    Ren, Weiju; Swindeman, Robert W.

    2010-01-01

    Alloy 800H is currently under consideration for applications in the Next Generation Nuclear Plant at operational temperatures above 750 C. To provide supporting information in this paper at the attempt to facilitate the consideration, service requirements of the nuclear system for structural materials is first described; and then an extensive review of Alloy 800H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application; an finally further research and development activities to support the materials qualification are suggested.

  18. Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors

    Directory of Open Access Journals (Sweden)

    Walter Borreani

    2017-12-01

    Full Text Available Although Lead-cooled Fast Reactor (LFR is not a new concept, it continues to be an example of innovation in the nuclear field. Recently, there has been strong interest in liquid lead (Pb or liquid lead–bismuth eutectic (LBE both critical and subcritical systems in a relevant number of Countries, including studies performed in the frame of GENERATION-IV initiative. In this paper, the theoretical and computational findings for three different designs of Primary Circulation Pump (PCP evolving liquid lead (namely the jet pump, the Archimedean pump and the blade pump are presented with reference to the ALFRED (Advanced Lead Fast Reactor European Demonstrator design. The pumps are first analyzed from the theoretical point of view and then modeled with a 3D CFD code. Required design performance of the pumps are approximatively around an effective head of 2 bar with a mass flow rate of 5000 kg/s. Taking into account the geometrical constraints of the reactor and the fluid dynamics characteristics of the molten lead, the maximum design velocity for molten lead fluid flow of 2 m/s may be exceeded giving rise to unacceptable erosion phenomena of the blade or rotating component of the primary pumping system. For this reason a deep investigation of non-conventional axial pumps has been performed. The results presented shows that the design of the jet pump looks like beyond the current technological feasibility while, once the mechanical challenges of the Archimedean (screw pump and the fluid-dynamic issues of the blade pump will be addressed, both could represent viable solutions as PCP for ALFRED. Particularly, the blade pump shows the best performance in terms of pressure head generated in normal operation conditions as well as pressure drop in locked rotor conditions. Further optimizations (mainly for what the geometrical configuration is concerned are still necessary.

  19. 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)

  20. Electromagnet Response Time Tests on Primary CRDM of a Prototype Gen-IV SFR

    International Nuclear Information System (INIS)

    Lee, Jae-Han; Koo, Gyeong-Hoi

    2015-01-01

    This paper identifies the electromagnetic response characteristics of the electromagnet of a primary control rod drive mechanism (CRDM) used for the reactor scram function. The test measures the electromagnet response time required to release an armature from a stator controlled by a loss of an electromagnetic force on an armature after shorting a power supply to an electromagnet coil. These tests are carried out while changing the electromagnet core material, an assist spring, and an armature holding current. The main factors influencing the test parameters on the response are found to be the armature holding current for holding the armature loads, and the material type of the electromagnet cores. The minimum response time is 0.13 seconds in the case of using SS410 material as an armature, while the S10C material as an armature has a response time of 0.21 seconds. Electromagnet response time characteristics from the test results will be evaluated by comparing the precise moving data of an electromagnet armature through the use of a high-speed camera and a potentiometer in the future

  1. Special Issue: NextGen Materials for 3D Printing

    Directory of Open Access Journals (Sweden)

    Chee Kai Chua

    2018-04-01

    Full Text Available Only a handful of materials are well-established in three-dimensional (3D printing and well-accepted in industrial manufacturing applications. However, recent advances in 3D printable materials have shown potential for enabling numerous novel applications in the future. This special issue, consisting of 2 reviews and 10 research articles, intends to explore the possible materials that could define next-generation 3D printing.

  2. Training Courses in Support of GEN-IV Development – The Case of SVBR Technology

    International Nuclear Information System (INIS)

    Kondaurov, A.; Zaitseva, N.; Yunikova, A.; Artisiuk, V.

    2014-01-01

    Conclusions: For prototype nuclear power reactor the development of training materials requires high level expertise from the R&D side. The First International Course focusing the SVBR technology was developed and piloted in ROSATOM Central Institute for Continuing Education&Training to support HRD for Open Joint-Stock Company «AKME-engineering» - owner and operator of SVBR-100. The Course is available for international participants

  3. 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.

  4. Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Fanglin Frank [Univ. of South Carolina, Columbia, SC (United States); Adams, Thad M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Brinkman, Kyle [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Reifsnider, Kenneth [Univ. of South Carolina, Columbia, SC (United States)

    2011-09-30

    Several types of high-temperature proton conductors based on SrCeO3 and BaCeO3 have been systematically investigated in this project for tritium separation in NGNP applications. One obstacle for the field application is the chemical stability issues in the presence of steam and CO2 for these proton conductors. Several strategies to overcome such issues have been evaluated, including A site doping and B site co-doping method for perovskite-structured proton conductors. Novel zirconium-free proton conductors have also been developed with improved electrical conductivity and enhanced chemical stability. Novel catalytic materials for the proton-conducting separation membranes have been investigated. A tubular geometry proton-conducting membrane has been developed for the proton separation membranes. Total dose rate estimated from tritium decay (beta emission) under realistic membrane operating conditions, combined with electron irradiation experiments, indicates that proton ceramic materials possess the appropriate radiation stability for this application.

  5. 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)

  6. 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)

  7. GEN IV: Carbide Fuel Elaboration for the 'Futurix Concepts' experiment

    Energy Technology Data Exchange (ETDEWEB)

    Vaudez, Stephane; Riglet-Martial, Chantal; Paret, Laurent; Abonneau, Eric [Commissariat a l' Energie Atomique (C.E.A.), Direction de l' Energie Nucleaire, Centre d' Etudes de Cadarache, 13108 Saint Paul lez Durance Cedex (France)

    2008-07-01

    In order to collect information on the behaviour of the future GFR (Gas Fast Reactor) fuel under fast neutron irradiation, an experimental irradiation program, called 'Futurix-concepts' has been launched at the CEA. The considered concept is a composite material made of a fissile fuel embedded in an inert ceramic matrix. Fissile fuel pellets are made of UPuN or UPuC while ceramics are SiC for the carbide fuel and TiN for the nitride fuel. This paper focuses on the description of the carbide composite fabrication. The UPuC pellets are manufactured using a metallurgical powder process. Fabrication and handling of the fuels are carried out in glove boxes under a nitrogen atmosphere. Carbide fuel is synthesized by carbo-thermic reduction under vacuum of a mixture of actinide oxide and graphitic carbon up to 1550 deg. C. After ball milling, the UPuC powder is pressed to create hexagonal or spherical compacts. They are then sintered up to 1750 deg. C in order to obtain a density of 85 % of the theoretical one. The sintered pellets are inserted into an inert and tight capsule of SiC. In order to control the gap between the fuel and the matrix precisely, the pellets are abraded. The inert matrix is then filled with the pellets and the whole system is sealed by a BRASiC{sup R} process at high temperature under a helium atmosphere. Fabrication of the sample to be irradiated was done in 2006 and the irradiation began in May 2007 in the Phenix reactor. This presentation will detail and discuss the results obtained during this fabrication phase. (authors)

  8. 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.

  9. 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

  10. Abdominal 64-MDCT for suspected appendicitis: the use of oral and IV contrast material versus IV contrast material only.

    Science.gov (United States)

    Anderson, Stephan W; Soto, Jorge A; Lucey, Brian C; Ozonoff, Al; Jordan, Jacqueline D; Ratevosian, Jirair; Ulrich, Andrew S; Rathlev, Niels K; Mitchell, Patricia M; Rebholz, Casey; Feldman, James A; Rhea, James T

    2009-11-01

    The objective of our study was to compare the diagnostic accuracy of IV contrast-enhanced 64-MDCT with and without the use of oral contrast material in diagnosing appendicitis in patients with abdominal pain. We conducted a randomized trial of a convenience sample of adult patients presenting to an urban academic emergency department with acute nontraumatic abdominal pain and clinical suspicion of appendicitis, diverticulitis, or small-bowel obstruction. Patients were enrolled between 8 am and 11 pm when research assistants were present. Consenting subjects were randomized into one of two groups: Group 1 subjects underwent 64-MDCT performed with oral and IV contrast media and group 2 subjects underwent 64-MDCT performed solely with IV contrast material. Three expert radiologists independently reviewed the CT examinations, evaluating for the presence of appendicitis. Each radiologist interpreted 202 examinations, ensuring that each examination was interpreted by two radiologists. Individual reader performance and a combined interpretation performance of the two readers assigned to each case were calculated. In cases of disagreement, the third reader was asked to deliver a tiebreaker interpretation to be used to calculate the combined reader performance. Final outcome was based on operative, clinical, and follow-up data. We compared radiologic diagnoses with clinical outcomes to calculate the diagnostic accuracy of CT in both groups. Of the 303 patients enrolled, 151 patients (50%) were randomized to group 1 and the remaining 152 (50%) were randomized to group 2. The combined reader performance for the diagnosis of appendicitis in group 1 was a sensitivity of 100% (95% CI, 76.8-100%) and specificity of 97.1% (95% CI, 92.7-99.2%). The performance in group 2 was a sensitivity of 100% (73.5-100%) and specificity of 97.1% (92.9-99.2%). Patients presenting with nontraumatic abdominal pain imaged using 64-MDCT with isotropic reformations had similar characteristics for the

  11. 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

  12. 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.

  13. 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)

  14. 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

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

    International Nuclear Information System (INIS)

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

    2010-02-01

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

  16. On the safety and performance demonstration tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and validation and verification of computational codes

    International Nuclear Information System (INIS)

    Kim, Jong Bum; Jeong, Ji Young; Lee, Tae Ho; Kim, Sung Kyun; Euh, Dong Jin; Joo, Hyung Kook

    2016-01-01

    The design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the validation and verification (V and V) activities to demonstrate the system performance and safety are in progress. In this paper, the current status of test activities is described briefly and significant results are discussed. The large-scale sodium thermal-hydraulic test program, Sodium Test Loop for Safety Simulation and Assessment-1 (STELLA-1), produced satisfactory results, which were used for the computer codes V and V, and the performance test results of the model pump in sodium showed good agreement with those in water. The second phase of the STELLA program with the integral effect tests facility, STELLA-2, is in the detailed design stage of the design process. The sodium thermal-hydraulic experiment loop for finned-tube sodium-to-air heat exchanger performance test, the intermediate heat exchanger test facility, and the test facility for the reactor flow distribution are underway. Flow characteristics test in subchannels of a wire-wrapped rod bundle has been carried out for safety analysis in the core and the dynamic characteristic test of upper internal structure has been performed for the seismic analysis model for the PGSFR. The performance tests for control rod assemblies (CRAs) have been conducted for control rod drive mechanism driving parts and drop tests of the CRA under scram condition were performed. Finally, three types of inspection sensors under development for the safe operation of the PGSFR were explained with significant results

  17. On the safety and performance demonstration tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and validation and verification of computational codes

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Bum; Jeong, Ji Young; Lee, Tae Ho; Kim, Sung Kyun; Euh, Dong Jin; Joo, Hyung Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the validation and verification (V and V) activities to demonstrate the system performance and safety are in progress. In this paper, the current status of test activities is described briefly and significant results are discussed. The large-scale sodium thermal-hydraulic test program, Sodium Test Loop for Safety Simulation and Assessment-1 (STELLA-1), produced satisfactory results, which were used for the computer codes V and V, and the performance test results of the model pump in sodium showed good agreement with those in water. The second phase of the STELLA program with the integral effect tests facility, STELLA-2, is in the detailed design stage of the design process. The sodium thermal-hydraulic experiment loop for finned-tube sodium-to-air heat exchanger performance test, the intermediate heat exchanger test facility, and the test facility for the reactor flow distribution are underway. Flow characteristics test in subchannels of a wire-wrapped rod bundle has been carried out for safety analysis in the core and the dynamic characteristic test of upper internal structure has been performed for the seismic analysis model for the PGSFR. The performance tests for control rod assemblies (CRAs) have been conducted for control rod drive mechanism driving parts and drop tests of the CRA under scram condition were performed. Finally, three types of inspection sensors under development for the safe operation of the PGSFR were explained with significant results.

  18. 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.

  19. 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)

  20. On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes

    Directory of Open Access Journals (Sweden)

    Jong-Bum Kim

    2016-10-01

    Full Text Available The design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR has been developed and the validation and verification (V&V activities to demonstrate the system performance and safety are in progress. In this paper, the current status of test activities is described briefly and significant results are discussed. The large-scale sodium thermal-hydraulic test program, Sodium Test Loop for Safety Simulation and Assessment-1 (STELLA-1, produced satisfactory results, which were used for the computer codes V&V, and the performance test results of the model pump in sodium showed good agreement with those in water. The second phase of the STELLA program with the integral effect tests facility, STELLA-2, is in the detailed design stage of the design process. The sodium thermal-hydraulic experiment loop for finned-tube sodium-to-air heat exchanger performance test, the intermediate heat exchanger test facility, and the test facility for the reactor flow distribution are underway. Flow characteristics test in subchannels of a wire-wrapped rod bundle has been carried out for safety analysis in the core and the dynamic characteristic test of upper internal structure has been performed for the seismic analysis model for the PGSFR. The performance tests for control rod assemblies (CRAs have been conducted for control rod drive mechanism driving parts and drop tests of the CRA under scram condition were performed. Finally, three types of inspection sensors under development for the safe operation of the PGSFR were explained with significant results.

  1. 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)

  2. 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.

  3. 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)

  4. Transferable tight-binding model for strained group IV and III-V materials and heterostructures

    Science.gov (United States)

    Tan, Yaohua; Povolotskyi, Michael; Kubis, Tillmann; Boykin, Timothy B.; Klimeck, Gerhard

    2016-07-01

    It is critical to capture the effect due to strain and material interface for device level transistor modeling. We introduce a transferable s p3d5s* tight-binding model with nearest-neighbor interactions for arbitrarily strained group IV and III-V materials. The tight-binding model is parametrized with respect to hybrid functional (HSE06) calculations for varieties of strained systems. The tight-binding calculations of ultrasmall superlattices formed by group IV and group III-V materials show good agreement with the corresponding HSE06 calculations. The application of the tight-binding model to superlattices demonstrates that the transferable tight-binding model with nearest-neighbor interactions can be obtained for group IV and III-V materials.

  5. 3D continuum phonon model for group-IV 2D materials

    DEFF Research Database (Denmark)

    Willatzen, Morten; Lew Yan Voon, Lok C.; Gandi, Appala Naidu

    2017-01-01

    . In this paper, we use the model to not only compare the phonon spectra among the group-IV materials but also to study whether these phonons differ from those of a compound material such as molybdenum disulfide. The origin of quadratic modes is clarified. Mode coupling for both graphene and silicene is obtained......, contrary to previous works. Our model allows us to predict the existence of confined optical phonon modes for the group-IV materials but not for molybdenum disulfide. A comparison of the long-wavelength modes to density-functional results is included....

  6. Hydrogen-bond Specific Materials Modification in Group IV Semiconductors

    Energy Technology Data Exchange (ETDEWEB)

    Tolk, Norman H. [Vanderbilt Univ., Nashville, TN (United States); Feldman, L. C. [Vanderbilt Univ., Nashville, TN (United States); Luepke, G. [College of William and Mary, Williamsburg, VA (United States)

    2015-09-14

    Executive summary Semiconductor dielectric crystals consist of two fundamental components: lattice atoms and electrons. The former component provides a crystalline structure that can be disrupted by various defects or the presence of an interface, or by transient oscillations known as phonons. The latter component produces an energetic structure that is responsible for the optical and electronic properties of the material, and can be perturbed by lattice defects or by photo-excitation. Over the period of this project, August 15, 1999 to March 31, 2015, a persistent theme has been the elucidation of the fundamental role of defects arising from the presence of radiation damage, impurities (in particular, hydrogen), localized strain or some combination of all three. As our research effort developed and evolved, we have experienced a few title changes, which reflected this evolution. Throughout the project, ultrafast lasers usually in a pump-probe configuration provided the ideal means to perturb and study semiconductor crystals by both forms of excitation, vibrational (phonon) and electronic (photon). Moreover, we have found in the course of this research that there are many interesting and relevant scientific questions that may be explored when phonon and photon excitations are controlled separately. Our early goals were to explore the dynamics of bond-selective vibrational excitation of hydrogen from point defects and impurities in crystalline and amorphous solids, initiating an investigation into the behavior of hydrogen isotopes utilizing a variety of ultrafast characterization techniques, principally transient bleaching spectroscopy to experimentally obtain vibrational lifetimes. The initiative could be divided into three related areas: (a) investigation of the change in electronic structure of solids due to the presence of hydrogen defect centers, (b) dynamical studies of hydrogen in materials and (c) characterization and stability of metastable hydrogen

  7. 3D continuum phonon model for group-IV 2D materials

    KAUST Repository

    Willatzen, Morten

    2017-06-30

    A general three-dimensional continuum model of phonons in two-dimensional materials is developed. Our first-principles derivation includes full consideration of the lattice anisotropy and flexural modes perpendicular to the layers and can thus be applied to any two-dimensional material. In this paper, we use the model to not only compare the phonon spectra among the group-IV materials but also to study whether these phonons differ from those of a compound material such as molybdenum disulfide. The origin of quadratic modes is clarified. Mode coupling for both graphene and silicene is obtained, contrary to previous works. Our model allows us to predict the existence of confined optical phonon modes for the group-IV materials but not for molybdenum disulfide. A comparison of the long-wavelength modes to density-functional results is included.

  8. 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

  9. 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

  10. The web-enabled database of JRC-EC: a useful tool for managing european gen 4 materials data

    International Nuclear Information System (INIS)

    Over, H.H.; Dietz, W.

    2008-01-01

    Materials and document databases are important tools to conserve knowledge and experimental materials data of European R and D projects. A web-enabled application guarantees a fast access to these data. In combination with analysis tools the experimental data are used for e.g. mechanical design, construction and lifetime predictions of complex components. The effective and efficient handling of large amounts of generic and detailed materials data with regard to properties related to e.g. fabrication processes, joining techniques, irradiation or aging is one of the basic elements of data management within ongoing nuclear safety and design related European research projects and networks. The paper describes the structure and functionality of Mat-DB and gives examples how these tools can be used for the management and evaluation of materials data for EURATOM FP7 Generation IV reactor types. (authors)

  11. Microscopy investigation on the corrosion of Canadian generation IV SCWR materials

    Energy Technology Data Exchange (ETDEWEB)

    Li, J. [CanmetMATERIALS, Hamilton, ON (Canada); Huang, X. [Carleton Univ., Ottawa, ON (Canada); Zeng, Y.; Zheng, W. [CanmetMATERIALS, Hamilton, ON (Canada); Woo, O.T.; Guzonas, D. [Atomic Energy Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Selection of fuel cladding materials for the Canadian Generation-IV Supercritical Water-cooled Reactor (SCWR) concept faces major challenges due to the severe operating conditions (650 {sup o}C and 25 MPa). High temperature microstructure stability and excellent resistance to general corrosion and stress corrosion cracking are key criteria. While corrosion resistance are generally assessed using weight change measurements and surface oxide examinations by optical and Scanning Electron Microscope (SEM) techniques, for materials exposed to SCW conditions, advanced analytical techniques that involve the use of Focused Ion Beam (FIB) and Transmission Electron Microscopy (TEM) techniques are required. This paper provides examples of such work conducted at CanmetMATERIALS and AECL to provide an in-depth understanding of the corrosion mechanisms of alloys exposed under SCW conditions. (author)

  12. Generation IV and transmutation materials (GETMAT) project: First assessment of selected results

    International Nuclear Information System (INIS)

    Fazio, Concetta; Serrano, Marta; Gessi, Alessandro; Henry, Jean; Malerba, Lorenzo

    2015-01-01

    The Generation IV and Transmutation Material (GETMAT) project has been initiated within the 7. EURATOM framework programme with the objective to support the development of innovative reactor designs. Emphasis has been put on the investigation, both in the theoretical and experimental domains, of selected material properties that are cross-cutting among the various Generation IV and Transmutation systems. The selection of the properties to be investigated has been performed by identifying relevant conditions of key components as cores and primary systems. Moreover, taking into account the envisaged conditions of these components it turned out that innovative materials might be a better choice with respect to conventional nuclear grade steels. Therefore, ODS alloys and 9-12 Cr Ferritic/Martensitic (F/M) steels have been selected as reference for the GETMAT project. The R and D activities have been focused on basic characterisation of ODS alloys produced ad hoc for the project and on an extensive PIE programme of F/M steels irradiated in previous programmes. Finally, first principle modelling studies to explain irradiation hardening and embrittlement of F/M alloys were an additional important task. The objective of this manuscript is to make a first assessment of the results obtained within GETMAT. (authors)

  13. Structure and properties of phosphorene-like IV-VI 2D materials.

    Science.gov (United States)

    Ma, Zhinan; Wang, Bo; Ou, Liangkai; Zhang, Yan; Zhang, Xu; Zhou, Zhen

    2016-10-14

    Because of the excellent physical and chemical properties of phosphorene, phosphorene and phosphorene-like materials have attracted extensive attention. Since phosphorus belongs to group V, some group IV-VI compounds could also form phosphorene-like configurations. In this work, GeO, SnO, GeS, and SnS monolayers were constructed to investigate the structural and electronic properties by employing first-principles computations. Phonon spectra suggest that these monolayers are dynamically stable and could be realized in experiments. These monolayers are all semiconductors with the band gaps of 2.26 ∼ 4.13 eV. Based on the monolayers, GeO, SnO, GeS, and SnS bilayers were also constructed. The band gaps of these bilayers are smaller than those of the corresponding monolayers. Moreover, the optical properties of these monolayers and bilayers were calculated, and the results indicate that the SnO, GeS and SnS bilayers exhibit obvious optical absorption in the visible spectrum. All the results suggest that phosphorene-like IV-VI materials are promising candidates for electronic and optical devices.

  14. Naturally occurring radioactive materials (NORM IV). Proceedings of an international conference

    International Nuclear Information System (INIS)

    2005-10-01

    Radionuclides of natural origin are ubiquitous in both working and public environments, although their activity concentrations vary considerably. Exposures to natural sources are in most cases not a matter for regulatory concern. However, there are situations where exposures to natural sources may warrant consideration as to whether controls should be applied. One such situation is where the conditions are conducive to the buildup of elevated concentrations of radon in air. Another situation is the mining and/or processing of material where the activity concentrations of radionuclides of natural origin in the material itself, or in any material arising from the process, are significantly elevated - such material has come to be referred to as Naturally Occurring Radioactive Material (NORM). In the past, regulatory attention has been focused mostly on exposures arising from the mining and processing of uranium ores because such activities are part of the nuclear fuel cycle. More recently, attention has been broadened to include exposures from other industrial activities involving NORM, in recognition of the potential for such activities to also give rise to significant exposures of workers and members of the public if not adequately controlled. More and more countries are now including provisions in their national legislation and regulations for the control of exposures to natural sources, and the body of radiological data on such exposures is growing rapidly. This international conference, NORM IV, follows three previous conferences dealing with radon and NORM. The first was held in Amsterdam in 1997, the second in Krefeld, Germany in 1998 (NORM II), and the third in Brussels in 2001 (NORM III). In addition, an International Symposium on Technologically Enhanced Natural Radiation was held in Rio de Janeiro in 1999 - the IAEA was involved in the organization of that symposium, and published the proceedings as IAEA-TECDOC-1271. The main topic addressed at NORM IV was

  15. Structure and magnetism in novel group IV element-based magnetic materials

    Energy Technology Data Exchange (ETDEWEB)

    Tsui, Frank [Univ. of North Carolina, Chapel Hill, NC (United States)

    2013-08-14

    The project is to investigate structure, magnetism and spin dependent states of novel group IV element-based magnetic thin films and heterostructures as a function of composition and epitaxial constraints. The materials systems of interest are Si-compatible epitaxial films and heterostructures of Si/Ge-based magnetic ternary alloys grown by non-equilibrium molecular beam epitaxy (MBE) techniques, specifically doped magnetic semiconductors (DMS) and half-metallic Heusler alloys. Systematic structural, chemical, magnetic, and electrical measurements are carried out, using x-ray microbeam techniques, magnetotunneling spectroscopy and microscopy, and magnetotransport. The work is aimed at elucidating the nature and interplay between structure, chemical order, magnetism, and spin-dependent states in these novel materials, at developing materials and techniques to realize and control fully spin polarized states, and at exploring fundamental processes that stabilize the epitaxial magnetic nanostructures and control the electronic and magnetic states in these complex materials. Combinatorial approach provides the means for the systematic studies, and the complex nature of the work necessitates this approach.

  16. Effect of HNO3-cerium(IV) decontamination on stainless steel canister materials

    International Nuclear Information System (INIS)

    Westerman, R.E.; Mackey, D.B.

    1991-01-01

    Stainless steel canisters will be filled with vitrified radioactive waste at the West Valley Demonstration Project (WVDP), West Valley, NY. After they are filled, the sealed canisters will be decontaminated by immersion in a HNO 3 -Ce(IV) solution, which will remove the oxide film and a small amount of metal from the surface of the canisters. Studies were undertaken in support of waste form qualification activities to determine the effect of this decontamination treatment on the legibility of the weld-bead canister identification label, and to determine whether this decontamination treatment could induce stress-corrosion cracking (SCC) in the AISI 304L stainless steel (SS) canister material. Neither the label legibility nor the canister integrity with regard to SCC were found to be prejudiced by the simulated decontamination treatment

  17. Studies of the effects of organic materials on the sorption of uranium(IV) and thorium(IV) on London clay and Caithness flagstones

    International Nuclear Information System (INIS)

    Baston, G.M.N.; Berry, J.A.; Bond, K.A.; Brownsword, M.; Linklater, C.M.

    1991-08-01

    The effects of the presence of cellulosic degradation products on the sorption of uranium (IV) and thorium(IV) on London clay and Caithness flagstones have been studied using the batch sorption method. Experimental conditions were chosen to simulate both those expected close to a cementitious repository (pH ∼11) and at the edge of the zone of migration of the alkaline plume (pH ∼ 8). Work was carried out (i) under baseline conditions, in the absence of organic materials; (ii) with 2 x 10 -3 M gluconate, acting as a well-characterised degradation product simulant; (iii) with authentic degradation products. The results show that the presence of authentic degradation products has a small effect on sorption and the presence of gluconate at a high concentration has a marked impact. (author)

  18. Studies of the effects of organic materials on the sorption of uranium(IV) and thorium(IV) on London clay and Caithness flagstones

    Energy Technology Data Exchange (ETDEWEB)

    Baston, G.M.N.; Berry, J.A.; Bond, K.A.; Brownsword, M.; Linklater, C.M.

    1991-08-01

    The effects of the presence of cellulosic degradation products on the sorption of uranium (IV) and thorium(IV) on London clay and Caithness flagstones have been studied using the batch sorption method. Experimental conditions were chosen to simulate both those expected close to a cementitious repository (pH {approx}11) and at the edge of the zone of migration of the alkaline plume (pH {approx} 8). Work was carried out (i) under baseline conditions, in the absence of organic materials; (ii) with 2 x 10{sup -3}M gluconate, acting as a well-characterised degradation product simulant; (iii) with authentic degradation products. The results show that the presence of authentic degradation products has a small effect on sorption and the presence of gluconate at a high concentration has a marked impact. (author).

  19. Condensation and homogenization of cross sections for the deterministic transport codes with Monte Carlo method: Application to the GEN IV fast neutron reactors

    International Nuclear Information System (INIS)

    Cai, Li

    2014-01-01

    In the framework of the Generation IV reactors neutronic research, new core calculation tools are implemented in the code system APOLLO3 for the deterministic part. These calculation methods are based on the discretization concept of nuclear energy data (named multi-group and are generally produced by deterministic codes) and should be validated and qualified with respect to some Monte-Carlo reference calculations. This thesis aims to develop an alternative technique of producing multi-group nuclear properties by a Monte-Carlo code (TRIPOLI-4). At first, after having tested the existing homogenization and condensation functionalities with better precision obtained nowadays, some inconsistencies are revealed. Several new multi-group parameters estimators are developed and validated for TRIPOLI-4 code with the aid of itself, since it has the possibility to use the multi-group constants in a core calculation. Secondly, the scattering anisotropy effect which is necessary for handling neutron leakage case is studied. A correction technique concerning the diagonal line of the first order moment of the scattering matrix is proposed. This is named the IGSC technique and is based on the usage of an approximate current which is introduced by Todorova. An improvement of this IGSC technique is then presented for the geometries which hold an important heterogeneity property. This improvement uses a more accurate current quantity which is the projection on the abscissa X. The later current can represent the real situation better but is limited to 1D geometries. Finally, a B1 leakage model is implemented in the TRIPOLI-4 code for generating multi-group cross sections with a fundamental mode based critical spectrum. This leakage model is analyzed and validated rigorously by the comparison with other codes: Serpent and ECCO, as well as an analytical case.The whole development work introduced in TRIPOLI-4 code allows producing multi-group constants which can then be used in the core

  20. Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR and GEN IV

    International Nuclear Information System (INIS)

    O'Donnell, William J.; Griffin, Donald S.

    2007-01-01

    The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.

  1. Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR & GEN IV

    Energy Technology Data Exchange (ETDEWEB)

    William J. O’Donnell; Donald S. Griffin

    2007-05-07

    The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.

  2. PENGEMBANGAN RPP DAN LKPD BERBASIS REALISTIC MATHEMATICS EDUCATION DENGAN MEMERHATIKAN BEBAN KOGNITIF SISWA MATERI BANGUN RUANG SEDERHANA KELAS IV SD

    Directory of Open Access Journals (Sweden)

    Eko Waluyo

    2016-12-01

    Dalam suatu pembelajaran, dengan melibatkan siswa dalam menemukan suatu konsep materi matematika, siswa akan lebih mudah untuk memahami materi. Materi matematika dalam dipelajari dengan melibatkan obyek dunia nyata siswa sekolah dasar dengan memerhatikan beban kognitif siswa. Melalui bimbingan guru, siswa akan lebih mudah dalam menemukan konsep. Dalam tulisan ini dibahas pengembangan RPP dan LKPD berbasis Realistic Mathematics Education dengan memerhatikan beban kognitif siswa materi bangun ruang sederhana kelas IV SD. Model pengembangan yang digunakan model Plomp dengan lima fase. Hasil pengembangan RPP dan LKPD ini valid, praktis, dan efektif.

  3. First principles calculation of material properties of group IV elements and III-V compounds

    Science.gov (United States)

    Malone, Brad Dean

    This thesis presents first principles calculations on the properties of group IV elements and group III-V compounds. It includes investigations into what structure a material is likely to form in, and given that structure, what are its electronic, optical, and lattice dynamical properties as well as what are the properties of defects that might be introduced into the sample. The thesis is divided as follows: • Chapter 1 contains some of the conceptual foundations used in the present work. These involve the major approximations which allow us to approach the problem of systems with huge numbers of interacting electrons and atomic cores. • Then, in Chapter 2, we discuss one of the major limitations to the DFT formalism introduced in Chapter 1, namely its inability to predict the quasiparticle spectra of materials and in particular the band gap of a semiconductor. We introduce a Green's function approach to the electron self-energy Sigma known as the GW approximation and use it to compute the quasiparticle band structures of a number of group IV and III-V semiconductors. • In Chapter 3 we present a first-principles study of a number of high-pressure metastable phases of Si with tetrahedral bonding. The phases studied include all experimentally determined phases that result from decompression from the metallic beta-Sn phase, specifically the BC8 (Si-III), hexagonal diamond (Si-IV), and R8 (Si-XII). In addition to these, we also study the hypothetical ST12 structure found upon decompression from beta-Sn in germanium. • Our attention is then turned to the first principles calculations of optical properties in Chapter 4. The Bethe-Salpeter equation is then solved to obtain the optical spectrum of this material including electron-hole interactions. The calculated optical spectrum is compared with experimental data for other forms of silicon commonly used in photovoltaic devices, namely the cubic, polycrystalline, and amorphous forms. • In Chapter 5 we present

  4. Building competencies for New Gen IV Reactors

    International Nuclear Information System (INIS)

    Pavel, G.L.; Ghitescu, P.

    2015-01-01

    The Advanced Lead Fast Reactor European Demonstrator - ALFRED is designed and sustained by several European countries. It is a 300 MWt (125 MWe) reactor, intended to be built in Romania, near the Pitesti site. Pure lead is used as primary coolant and it is foreseen to have a 40% thermal efficiency. Secondary cycle contains superheated water steam at around 450 Celsius degrees. Through ARCADIA cooperation, 26 partners from all over Europe joined their forces to provide the necessary research support for ALFRED. In Romania, several entities are providing nuclear courses but only the University Politechnica of Bucharest is offering a complete training program for nuclear industry but targeted courses for LFR technology need to be developed and implemented. Issues like physics of breeding, coolant analysis and behavior, targeted computer codes, core design and dynamics, safety still needs to be tackled

  5. Group IV all-semiconductor spintronics. Materials aspects and optical spin selection rules

    Energy Technology Data Exchange (ETDEWEB)

    Sircar, Narayan

    2012-04-03

    In the scope of the present thesis various aspects for the realization of spintronic applications based on group IV semiconductors are discussed. This work comprises a refined material characterization of the magnetic semiconductor GeMn. We furthermore present efforts to utilize this material as spin injector for a Si-based optical spintronic device. Applying transmission electron microscopy and atom probe tomography, we are able to resolve a vertical anisotropy in the self-assembly, leading to the stacking of well-defined clusters in the growth direction. Three-dimensional atom distribution maps confirm that clusters are built from a nonstoichiometric GeMn alloy and exhibit a high-Mn-concentration core with a decreasing Mn concentration toward a shell. An amorphous nature of the cluster cores as well as the crystallinity of the shells, coherent with the surrounding Ge lattice, are revealed in scanning transmission electron microscopy. We localize a strain field surrounding each GeMn cluster by scanning transmission electron microscopy. The importance of strain to the stacking phenomenon of the clusters becomes clear in studies of Ge/GeMn superlattice structures, where a vertical spatial correlation of clusters over 30 nm-thick Ge spacer layers is observed. We present evidence that electrical transport properties of the p-type GeMn thin films fabricated on high-resistivity Ge substrates are severely influenced by parallel conduction through the substrate. It is shown that substrate conduction persists also for wellconducting degenerate p-type reference thin films, giving rise to an effective two-layer conduction scheme. GeMn thin films fabricated on these substrates exhibit only a negligible magnetoresistance effect. Before integrating GeMn in an optical spintronic device, some key aspects important for an understanding of the optical injection and detection of carrier spins in Si and Si-based heterostructures are clarified in the second part of this thesis. In

  6. Decontamination of stainless steel using cerium(IV): Material recycle and reuse

    International Nuclear Information System (INIS)

    Kurath, D.E.; Bray, L.A.; Jarrett, J.H.

    1997-01-01

    It has been demonstrated that the Cerium(IV) process can effectively remove radioactive contamination from stainless steel. Ce(IV) is a powerful oxidizing agent that is applied in an inorganic acid solution or as an atomized spray by injection into steam directed at the contaminated surface. Ce(IV) attacks the oxide layer and underlying metal surface to remove a 0.5-μm to 3-μm layer. This process has been implemented in a number of actual operations. In one application, a Ce(IV) steam decontamination process was instrumental in renovating hot cells at the High-Level Radiochemistry Facility (325-A building) at the Hanford site. The initial dose rate of approximately 100,000 mR/h was reduced to <50 mR/h and allowed manned entry during hot cell renovation activities. These valuable facilities have been returned to full operation. In an application at the West Valley Nuclear Services Co., Inc., the surfaces of stainless steel canisters that had been filled with vitrified high-level waste have been decontaminated. In some cases the free release levels for surface contamination have been achieved. In another application, five plutonium contaminated stainless steel vessels were decontaminated during decommissioning of the Critical Mass Facility at Hanford

  7. PENGEMBANGAN PERANGKAT PEMBELAJARAN MATERI PECAHAN BERBASIS TEORI BRUNER DI KELAS IV SD LABSCHOOL UNESA

    Directory of Open Access Journals (Sweden)

    Lina Wijayanti

    2015-07-01

    Full Text Available Penelitian ini bertujuan untuk menghasilkan perangkat pembelajaran pada materi pecahan tema 3 berbasis teori Bruner ditinjau dari kualitas produk secara umum (kevalidan, kepraktisan, dan keefektifan dan dalam peningkatan kemampuan pemecahan masalah dan prestasi belajar peserta didik di kelas IV SD Labschool Unesa. Penelitian ini termasuk penelitian dan pengembangan yang menggunakan model yang dikembangkan oleh Borg & Gall. Subjek penelitian dalam uji coba terbatas berjumlah 4 siswa, sedangkan dalam uji coba lapangan berjumlah 8 siswa. Subjek uji coba produk operasional pada kelas eksperimen sebanyak 17 siswa dan kelas kontrol sebanyak 18 siswa. Pengumpulan data dalam penelitian ini menggunakan lembar penilaian produk perangkat pembelajaran, lembar observasi guru, lembar observasi peserta didik, tes hasil belajar, angket respon guru, dan agket respon peserta didik. Analisis data menggunakan independent sample t-test dengan taraf signifikansi 0,05. Hasil penelitian menunjukkan bahwa perangkat pembelajaran hasil pengembangan dinyatakan valid dengan kategori sebagai berikut: silabus berkategori baik, RPP berkategori sangat baik, tes hasil belajar berkategori baik, dan media berkategori sangat baik, sehingga rerata hasil semua perangkat pembelajaran adalah berkategori baik. Penerapan perangkat pembelajaran secara umum dapat terlaksana dengan baik. Berdasarkan hasil uji coba kelas eksperimen dan kelas kontrol, terdapat perbedaan yang signifikan pada ketercapaian hasil belajar sehingga perangkat pembelajaran dikatakan efektif, sedangkan untuk kemampuan pemecahan masalah dan prestasi belajar siswa yang mengikuti pembelajaran menggunakan perangkat pembelajaran berbasis teori Bruner hasil pengembangan mengalami peningkatan. Kata Kunci: perangkat pembelajaran, teori Bruner, kemampuan pemecahan masalah, prestasi belajar DEVELOPING TEACHING KIT BASED ON THE THEORY OF BRUNER IN GRADE FOUR STUDENTS OF SD LABSCHOOL UNESA Abstract This study aims to develop a

  8. 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)

  9. 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...

  10. In-Pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-12-01

    For many years, the increase in efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase in fuel burnup and fuel residence time leads to a reduction in the volume of fresh fuel loaded and spent fuel discharged, respectively. More demanding nuclear fuel cycle parameters are combined with a need to operate nuclear power plants with maximal availability and load factors, in load-follow mode and with longer fuel cycles. In meeting these requirements, fuel has to operate in a demanding environment of high radiation fields, high temperatures, high mechanical stresses and high coolant flow. Requirements of increased fuel reliability and minimal fuel failures also remain in force. Under such circumstances, continuous development of more radiation resistant fuel materials, especially advanced cladding, careful and incremental examinations, and improved understanding and modelling of high burnup fuel behaviour are required. Following a recommendation of the IAEA Technical Working Group on Fuel Performance and Technology, the Technical Meeting on In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials was held in Halden, Norway, on 21-24 August 2012. The purpose of the meeting was to review the current status and the progress in methods and technologies used for the in-pile testing of nuclear fuel achieved since the previous IAEA meeting on In-core Instrumentation and Reactor Core Assessment, also held in Halden in 2007. Emphasis was placed on advanced techniques applied for the understanding of high burnup fuel behaviour of water cooled power reactors that represent the vast majority of the current nuclear reactor fleet. However, the meeting also included papers and discussion on testing techniques applied or developed specifically for new fuel and structural materials considered for Generation-IV systems. The meeting was attended by 43

  11. 3D continuum phonon model for group-IV 2D materials

    KAUST Repository

    Willatzen, Morten; Lew Yan Voon, Lok C; Gandi, Appala; Schwingenschlö gl, Udo

    2017-01-01

    A general three-dimensional continuum model of phonons in two-dimensional materials is developed. Our first-principles derivation includes full consideration of the lattice anisotropy and flexural modes perpendicular to the layers and can thus

  12. Development of metal fuel and study of construction materials (I-IV), Part II

    International Nuclear Information System (INIS)

    Mihajlovic, A.

    1965-11-01

    The studies were devoted to problems related to application of metal uranium as fuel in heavy water reactors. Influence of thermal treatment on material texture and recrystallization of cast uranium was investigated. Structural changes of uranium alloys with molybdenum and niobium were tested during different heat treatments. A review of the possibilities for using metal uranium fuel in heavy water reactors is included

  13. Development of methods for measuring materials nuclear characteristics, Phases, I, II, II and IV

    International Nuclear Information System (INIS)

    Maglic, R.

    1963-04-01

    This report contains the following phases of the project 'measurement of nuclear characteristics of reactor materials': nuclear performances of the neutron chopper; method for measuring total effective cross sections by transmission method on the chopper; review of methods for measuring activation cross sections; measurement of neutron spectra of the RA reactor and measurement of total effective cross section of gold by using the chopper

  14. Experiments on container materials for Swiss high-level waste disposal projects. Part IV

    International Nuclear Information System (INIS)

    Simpson, J.P.

    1989-12-01

    One concept for final disposal of high-level waste in switzerland consists of a repository at a depth of 1000 to 1500 m in the crystalline bedrock of Northern Switzerland. The waste will be placed in a container which will be required to function as a high integrity barrier for at least 100 years. This report is the fourth and last in the current series dealing with the evaluation of potential materials for such containers. Four materials were identified for further evaluation in the first of these reports: cast steel, nodular cast iron, copper and Ti-Code 12. This report deals with the problem of demonstrating that cast steel containers will not fail by stress corrosion cracking and with the problem of hydrogen produced by the reduction of water. The experimental results on pre-cracked specimens revealed no susceptibility of cast steel to stress corrosion cracking under model repository conditions. No crack growth was detected on compact DCB specimens exposed in aerobic and anaerobic groundwaters at 80 and 140 o C for 16-24 months. Cast steel remains a candidate material for high-level waste containers. As expected from thermodynamic considerations no hydrogen could be detected from copper immersed in model groundwaters at 50 o C. Hydrogen is evolved from corroding steel under anaerobic conditions. Hydrogen evolution due to corrosion of iron or steel in waste repositories has to be considered in any safety analysis; the amounts produced can be significant. Evidence todate suggests that both cast steel and copper are suitable container materials. Because the corrosion behaviour of both materials is sensitive to service conditions, in particular length of the aerobic phase, groundwater chemistry and temperature, further testing should be undertaken when a specific site has been identified. (author) 9 tabs., 11 figs., 25 refs

  15. NATO Advanced Study Institute on Materials Issues for Generation IV Systems : Status, Open Questions and Challenges

    CERN Document Server

    Gorse, Dominique; Mazière, Dominique; Pontikis, Vassilis

    2008-01-01

    Global warming, shortage of low-cost oil resources and the increasing demand for energy are currently controlling the world's economic expansion while often opposing desires for sustainable and peaceful development. In this context, atomic energy satisfactorily fulfills the criteria of low carbon gas production and high overall yield. However, in the absence of industrial fast-breeders the use of nuclear fuel is not optimal, and the production of high activity waste materials is at a maximum. These are the principal reasons for the development of a new, fourth generation of nuclear reactors, minimizing the undesirable side-effects of current nuclear energy production technology while increasing yields by increasing operation temperatures and opening the way for the industrial production of hydrogen through the decomposition of water. The construction and use of such reactors is hindered by several factors, including performance limitations of known structural materials, particularly if the life of the project...

  16. Current means for plasma diagnostics and their application for materials and environment control. Materials of IV Russian seminar

    International Nuclear Information System (INIS)

    2003-01-01

    The collection contains reports made at the Fourth Russian seminar Current means of plasma diagnostics and their application for materials and environment control. The seminar took place in Moscow, November 12-14, 2003. The content of the collection covers both questions of plasma diagnostics in thermonuclear reactors and problems of diagnostics of pulsed and stationary gas discharges in research and technological installations. The reports on plasma diagnostics applied for some tasks of medicine and environment control are presented [ru

  17. 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

  18. 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...

  19. Thermocatalytic Behavior of Manganese (IV Oxide as Nanoporous Material on the Dissociation of a Gas Mixture Containing Hydrogen Peroxide

    Directory of Open Access Journals (Sweden)

    Zaid B. Jildeh

    2018-04-01

    Full Text Available In this article, we present an overview on the thermocatalytic reaction of hydrogen peroxide (H 2 O 2 gas on a manganese (IV oxide (MnO 2 catalytic structure. The principle of operation and manufacturing techniques are introduced for a calorimetric H 2 O 2 gas sensor based on porous MnO 2 . Results from surface analyses by X-ray photoelectron spectroscopy (XPS and scanning electron microscopy (SEM of the catalytic material provide indication of the H 2 O 2 dissociation reaction schemes. The correlation between theory and the experiments is documented in numerical models of the catalytic reaction. The aim of the numerical models is to provide further information on the reaction kinetics and performance enhancement of the porous MnO 2 catalyst.

  20. Thermocatalytic Behavior of Manganese (IV) Oxide as Nanoporous Material on the Dissociation of a Gas Mixture Containing Hydrogen Peroxide.

    Science.gov (United States)

    Jildeh, Zaid B; Oberländer, Jan; Kirchner, Patrick; Wagner, Patrick H; Schöning, Michael J

    2018-04-21

    In this article, we present an overview on the thermocatalytic reaction of hydrogen peroxide (H 2 O 2 ) gas on a manganese (IV) oxide (MnO 2 ) catalytic structure. The principle of operation and manufacturing techniques are introduced for a calorimetric H 2 O 2 gas sensor based on porous MnO 2 . Results from surface analyses by X-ray photoelectron spectroscopy (XPS) and scanning electron microscopy (SEM) of the catalytic material provide indication of the H 2 O 2 dissociation reaction schemes. The correlation between theory and the experiments is documented in numerical models of the catalytic reaction. The aim of the numerical models is to provide further information on the reaction kinetics and performance enhancement of the porous MnO 2 catalyst.

  1. Introduction to vacuum technology: supplementary study material developed for IVS sponsored vacuum courses

    International Nuclear Information System (INIS)

    Bhusan, K.G.

    2008-01-01

    Vacuum technology has advanced to a large extent mainly from the demands of experimental research scientists who have more than ever understood the need for clean very low pressure environments. This need only seems to increase as the lowest pressures achievable in a laboratory setup are dropping down by the decade. What is not usually said is that conventional techniques of producing ultrahigh vacuum have also undergone a metamorphosis in order to cater to the multitude of restrictions in modern day scientific research. This book aims to give that practical approach to vacuum technology. The basics are given in the first chapter with more of a definition oriented approach - which is practically useful. The second chapter deals with the production of vacuum and ultrahigh vacuum with an emphasis on the working principles of several pumps and their working pressure ranges. Measurement of low pressures, both total and partial is presented in the third chapter with a note on leak detection and mass spectrometric techniques. Chapter 4 gives an overview of the materials that are vacuum compatible and their material properties. Chapter 5 gives the necessary methods to be followed for cleaning of vacuum components especially critical if ultrahigh vacuum environment is required. The practical use of a ultrahigh vacuum environment is demonstrated in Chapter 6 for production of high quality thin films through vapour deposition

  2. 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.

  3. Study of diluting and absorber materials to control the reactivity during a postulated core meltdown accident in generation IV reactors

    International Nuclear Information System (INIS)

    Plevacova, Kamila

    2010-01-01

    In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium Fast Reactors, absorber materials in or near the core, such as boron carbide B 4 C, and diluting materials in the core catcher will be used to prevent recriticality within the mixture of molten oxide fuel and molten structures called corium. The aim of the PhD thesis was to select materials of both types and to understand their behaviour during their interaction with corium, from chemical and thermodynamic points of view. Concerning B 4 C, thermodynamic calculations and experiments agree with the formation of two immiscible phases at high temperature in the B 4 C - UO 2 system: one oxide and one boride. This separation of phases can reduce the efficiency of the neutrons absorption inside the molten fuel contained in the oxide phase. Moreover, volatilization of a part of the boron element can occur. According to these results, the necessary quantity of B 4 C to be introduced should be reconsidered for postulated severe accident sequence. Other solution could be the use of Eu 2 O 3 or HfO 2 as absorber material. These oxides form a solid solution with the oxide fuel. Concerning the diluting materials, mixed oxides Al 2 O 3 - HfO 2 and Al 2 O 3 - Eu 2 O 3 were preselected. These systems being completely unknown to date at high temperature in association with UO 2 , first points on the corresponding ternary phase diagrams were researched. Contrary to Al 2 O 3 - Eu 2 O 3 - UO 2 system, the Al 2 O 3 - HfO 2 - UO 2 mixture presents only one eutectic and thus only one solidification path which makes easier forecasting the behaviour of corium in the core catcher. (author)

  4. Study of diluting and absorber materials to control reactivity during a postulated core melt down accident in Generation IV reactors

    International Nuclear Information System (INIS)

    Plevacova, K.

    2010-01-01

    In order to limit the consequences of a hypothetical core meltdown accident in Generation IV Sodium Fast Reactors, absorber materials in or near the core, such as boron carbide B 4 C, and diluting materials in the core catcher will be used to prevent recriticality within the mixture of molten oxide fuel and molten structures called corium. The aim of the PhD thesis was to select materials of both types and to understand their behaviour during their interaction with corium, from chemical and thermodynamic point of view. Concerning B 4 C, thermodynamic calculations and experiments agree with the formation of two immiscible phases at high temperature in the B 4 C - UO 2 system: one oxide and one boride. This separation of phases can reduce the efficiency of the neutrons absorption inside the molten fuel contained in the oxide phase. Moreover, a volatilization of a part of the boron element can occur. According to these results, the necessary quantity of B 4 C to be introduced should be reconsidered for postulated severe accident sequence. Other solution could be the use of Eu 2 O 3 or HfO 2 as absorber material. These oxides form a solid solution with the oxide fuel. Concerning the diluting materials, mixed oxides Al 2 O 3 - HfO 2 and Al 2 O 3 - Eu 2 O 3 were preselected. These systems being completely unknown to date at high temperature in association with UO 2 , first points on the corresponding ternary phase diagrams were researched. Contrary to Al 2 O 3 - Eu 2 O 3 - UO 2 system, the Al 2 O 3 - HfO 2 - UO 2 mixture presents only one eutectic and thus only one solidification path which makes easier forecasting the behaviour of corium in the core catcher. (author) [fr

  5. Developing and Evaluating Candidate Materials for Generation IV Supercritical Water Reactors

    International Nuclear Information System (INIS)

    Jang, Jin Sung; Kim, Sung Ho; Hwang Sung Sik and others

    2006-03-01

    High temperature mechanical behavior High temperature behavior of two F-M steels were investigated, considering the transient temperature range of the SCWR (above 800 .deg. C). T91 and T122 specimens were five times cyclically heat treated to the temperature 810 .deg. C and 845 .deg. C respectively. And the heat treatments were found to have little effect on the creep rupture behavior at 550, 600, or 650 .deg. C. However, the microstructural change was detected by the rapid hardness change after the holding the specimens at 840 .deg. C even for 10 sec. (by INL, previously ANL-W) A 20Cr Fe-base ODS alloy (MA956) was isothermally heat treated at 475 .deg. C for various times and then impact tested. The material was found to become very brittle after the heat treatment even for 100 hrs by the drastic decrease of the impact absorption energy (from 300 J to about the nil) and by the typically brittle fracture surface. (by KAIST) Corrosion and SCC Behavior in SCW (1) The corrosion behaviors of the F-M steels (T91, T92, and T122) and high Ni alloys (alloy 625, Alloy 690, and alloy 800H) and an ODS alloy (MA 956) were studied in the aerated SCW (8 ppm of D.O; dissolved oxygen) under 25 MPa from 300 to 600 .deg. C with an interval of 50 .deg. C. The test durations were 100, 200, and 500 hrs respectively. In general high Ni alloys were definitely more resistant to corrosion in SCW than F-M steels. As the Cr content increases the resistance of F-M steels to corrosion becomes better. The resistance of F-M steels to corrosion at 350 .deg. C, a subcritical temperature, was revealed to be comparatively similar to those at 550 .deg. C, a 200 .deg. C higher temperature. (2) The SCC resistance of F-M steels, T91 and T92, was evaluated by CERT (constant extension rate test) method. T91 specimens were tested at 500, 550 and 600 .deg. C in a fully deaerated SCW (below 10 ppb D.O), and SCC did not happen in the T91 specimens. T92 specimens were tested at 500 .deg. C in SCW of different

  6. Developing and Evaluating Candidate Materials for Generation IV Supercritical Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Jin Sung; Kim, Sung Ho; Hwang Sung Sik and others

    2006-03-15

    High temperature mechanical behavior High temperature behavior of two F-M steels were investigated, considering the transient temperature range of the SCWR (above 800 .deg. C). T91 and T122 specimens were five times cyclically heat treated to the temperature 810 .deg. C and 845 .deg. C respectively. And the heat treatments were found to have little effect on the creep rupture behavior at 550, 600, or 650 .deg. C. However, the microstructural change was detected by the rapid hardness change after the holding the specimens at 840 .deg. C even for 10 sec. (by INL, previously ANL-W) A 20Cr Fe-base ODS alloy (MA956) was isothermally heat treated at 475 .deg. C for various times and then impact tested. The material was found to become very brittle after the heat treatment even for 100 hrs by the drastic decrease of the impact absorption energy (from 300 J to about the nil) and by the typically brittle fracture surface. (by KAIST) Corrosion and SCC Behavior in SCW (1) The corrosion behaviors of the F-M steels (T91, T92, and T122) and high Ni alloys (alloy 625, Alloy 690, and alloy 800H) and an ODS alloy (MA 956) were studied in the aerated SCW (8 ppm of D.O; dissolved oxygen) under 25 MPa from 300 to 600 .deg. C with an interval of 50 .deg. C. The test durations were 100, 200, and 500 hrs respectively. In general high Ni alloys were definitely more resistant to corrosion in SCW than F-M steels. As the Cr content increases the resistance of F-M steels to corrosion becomes better. The resistance of F-M steels to corrosion at 350 .deg. C, a subcritical temperature, was revealed to be comparatively similar to those at 550 .deg. C, a 200 .deg. C higher temperature. (2) The SCC resistance of F-M steels, T91 and T92, was evaluated by CERT (constant extension rate test) method. T91 specimens were tested at 500, 550 and 600 .deg. C in a fully deaerated SCW (below 10 ppb D.O), and SCC did not happen in the T91 specimens. T92 specimens were tested at 500 .deg. C in SCW of different

  7. RETRACTED: Nuclear Materials IV

    International Nuclear Information System (INIS)

    Degueldre, C.

    2011-01-01

    This article has been retracted: please see Elsevier Policy on Article Withdrawal ( (http://www.elsevier.com/locate/withdrawalpolicy)). This article has been retracted at the request of the Publisher. This document was mistakenly published instead of the editorial of this special issue. The correct editorial is published in J. Nucl. Mater., 419 (2011) 398, (http://dx.doi.org/10.1016/j.jnucmat.2011.11.033). Apologies are offered to the guest editors and to readers of the Journal that this error was not detected during the production process.

  8. Zirconium(IV) oxide: New coating material for nanoresonators for shell-isolated nanoparticle-enhanced Raman spectroscopy

    Science.gov (United States)

    Krajczewski, Jan; Abdulrahman, Heman Burhanalden; Kołątaj, Karol; Kudelski, Andrzej

    2018-03-01

    One tool that can be used for determining the structure and composition of surfaces of various materials (even in in situ conditions) is shell-isolated nanoparticle-enhanced Raman spectroscopy (SHINERS). In SHINERS measurements, the surface under investigation is covered with a layer of surface-protected plasmonic nanoparticles, and then the Raman spectrum of the surface analysed is recorded. The plasmonic cores of the used core-shell structures act as electromagnetic nanoresonators, significantly locally enhancing the intensity of the electric field of the incident radiation, leading to a large increase in the efficiency of the generation of the Raman signal from molecules in the close proximity to the deposited SHINERS nanoresonators. A protective layer (from transparent dielectrics such as SiO2, Al2O3 or TiO2) prevents direct interaction between the plasmonic metal and the analysed surface (such interactions may lead to changes in the structure of the surface) and, in the case of plasmonic cores other than gold cores, the dielectric layer increases the chemical stability of the metal core. In this contribution, we show for the first time that core-shell nanoparticles having a silver core (both a solid and hollow one) and a shell of zirconium(IV) oxide are very efficient SHINERS nanoresonators that are significantly more stable in acidic and alkaline media than the silver-silica core-shell structures typically used for SHINERS experiments.

  9. 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...

  10. 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...

  11. 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...

  12. 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

  13. 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

  14. 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 ...

  15. Potentiometric Sensor for Gadolinium(III Ion Based on Zirconium(IV Tungstophosphate as an Electroactive Material

    Directory of Open Access Journals (Sweden)

    Harish K. Sharma

    2009-01-01

    Full Text Available A new inorganic ion exchanger has been synthesized namely Zirconium(IV tungstophosphate [ZrWP]. The synthesized exchanger was characterized using ion exchange capacity and distribution coefficient (Kd. For further studies, exchanger with 0.35 meq/g ion-exchange capacity was selected. Electrochemical studies were carried out on the ion exchange membranes using epoxy resin as a binder. In case of ZrWP, the membrane having the composition; Zirconium(IV tugstophosphate (40% and epoxy resin (60% exhibits best performance. The membrane works well over a wide range of concentration from 1×10-5 to 1×10-1 M of Gd(III ion with an over- Nernstian slope of 30 mv/ decade. The response time of the sensor is 15 seconds. For this membrane, effect of internal solution has been studied and the electrode was successfully used in partially non-aqueous media too. Fixed interference method and matched potential method has been used for determining selectivity coefficient with respect to alkali, alkaline earth, some transition and rare earth metal ions that are normally present along with Gd(III in its ores. The electrode can be used in the pH range 4.0-10.0 for 10-1 M and 3.0-7.0 for 10-2 M concentration of target ion. These sensors have been used as indicator electrodes in the potentiometric titration of Gd(III ion against EDTA and oxalic acid.

  16. Group IV Materials for High Performance Methane Sensing in Novel Slot Optical Waveguides at 2.883 μm and 3.39 μm

    Directory of Open Access Journals (Sweden)

    Vittorio M. N. PASSARO

    2012-03-01

    Full Text Available In this paper a detailed investigation of novel photonic sensors based on slot waveguides has been carried out. Appropriate alloys of group IV materials, such as germanium (Ge, silicon (Si, carbon (C and tin (Sn, are applied in silicon-on-insulator (SOI technology for homogeneous optical sensing at 2.883 µm and 3.39 μm. Electronic and optical properties of group IV alloys have been investigated. In addition, we have designed novel group IV vertical slot waveguides in order to achieve ultra-high sensitivities, as well as good fabrication tolerances. All these features have been compared with well-known SOI slot waveguides for optical label-free homogeneous sensing at 1.55 µm. In conclusion, theoretical investigation of ring resonators based on these novel slot waveguides has revealed very good results in terms of ultra high sensing performance of methane gas, i.e., limit of detection ~ 3.6×10-5 RIU and wavelength sensitivity > 2×103 nm/RIU.

  17. Derivation of residual radioactive material guidelines for 13 radionuclides present in Operable Unit IV at Brookhaven National Laboratory, Upton, New York

    International Nuclear Information System (INIS)

    Faillace, E.; Nimmagadda, M.; Yu, C.

    1994-12-01

    Residual radioactive material guidelines for 13 radionuclides (americium-241; cobalt-60; cesium-137; europium-152, -154, and -155; plutonium-238, -239, and -240; strontium-90; and uranium-234, -235, and -238) were derived for Operable Unit (OU) IV at Brookhaven National Laboratory. This site has been identified for remedial action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986. Single-nuclide guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of OU IV should not exceed a dose constraint of 30 mrem/yr following remedial action for the current use and plausible future use scenarios or a dose limit of 100 mrem/yr for plausible but less likely future use scenarios. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for determining residual radioactive material guidelines. Four potential scenarios were considered; each assumed that, for a period of 1,000 years following remedial action, the site would be used without radiological restrictions. The four scenarios varied with regard to the type of site use, time spent at the site, and sources of food consumed

  18. 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

  19. Asteroids IV

    Science.gov (United States)

    Michel, Patrick; DeMeo, Francesca E.; Bottke, William F.

    Asteroids are fascinating worlds. Considered the building blocks of our planets, many of the authors of this book have devoted their scientific careers to exploring them with the tools of our trade: ground- and spacebased observations, in situ space missions, and studies that run the gamut from theoretical modeling efforts to laboratory work. Like fossils for paleontologists, or DNA for geneticists, they allow us to construct a veritable time machine and provide us with tantalizing glimpses of the earliest nature of our solar system. By investigating them, we can probe what our home system was like before life or even the planets existed. The origin and evolution of life on our planet is also intertwined with asteroids in a different way. It is believed that impacts on the primordial Earth may have delivered the basic components for life, with biology favoring attributes that could more easily survive the aftermath of such energetic events. In this fashion, asteroids may have banished many probable avenues for life to relative obscurity. Similarly, they may have also prevented our biosphere from becoming more complex until more recent eras. The full tale of asteroid impacts on the history of our world, and how human life managed to emerge from myriad possibilities, has yet to be fully told. The hazard posed by asteroid impacts to our civilization is low but singular. The design of efficient mitigation strategies strongly relies on asteroid detection by our ground- and spacebased surveys as well as knowledge of their physical properties. A more positive motivation for asteroid discovery is that the proximity of some asteroids to Earth may allow future astronauts to harvest their water and rare mineral resources for use in exploration. A key goal of asteroid science is therefore to learn how humans and robotic probes can interact with asteroids (and extract their materials) in an efficient way. We expect that these adventures may be commonplace in the future

  20. 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.

  1. 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.

  2. Advanced Non-Destructive Assessment Technology to Determine the Aging of Silicon Containing Materials for Generation IV Nuclear Reactors

    Science.gov (United States)

    Koenig, T. W.; Olson, D. L.; Mishra, B.; King, J. C.; Fletcher, J.; Gerstenberger, L.; Lawrence, S.; Martin, A.; Mejia, C.; Meyer, M. K.; Kennedy, R.; Hu, L.; Kohse, G.; Terry, J.

    2011-06-01

    To create an in-situ, real-time method of monitoring neutron damage within a nuclear reactor core, irradiated silicon carbide samples are examined to correlate measurable variations in the material properties with neutron fluence levels experienced by the silicon carbide (SiC) during the irradiation process. The reaction by which phosphorus doping via thermal neutrons occurs in the silicon carbide samples is known to increase electron carrier density. A number of techniques are used to probe the properties of the SiC, including ultrasonic and Hall coefficient measurements, as well as high frequency impedance analysis. Gamma spectroscopy is also used to examine residual radioactivity resulting from irradiation activation of elements in the samples. Hall coefficient measurements produce the expected trend of increasing carrier concentration with higher fluence levels, while high frequency impedance analysis shows an increase in sample impedance with increasing fluence.

  3. CHEMISORPtION OF SULFUR (IV OXIDeBY PoLYETHYLENEPOLYAMINE IMPREGNATED FIBROUS MATERIALS. 1. HYDROPHILIC POLYETHYLENEPOLYAMINE IMPREGNATED FIBROUS MATERIALS

    Directory of Open Access Journals (Sweden)

    A. A. Ennan

    2015-03-01

    Full Text Available The hydrophilicity of artificial and synthetic fibers and polyethylenepolyamine (PEPA impregnated fibrous materials based on them was investigated under static conditions using a vacuum sorption installation. Water vapor sorption isotherms were analyzed and monolayer capacitance values  and a water molecules adsorption in the first layer heats were determined in the framework of polymolecular adsorption Brunauer – Emmett – Teller. It has been found that the hydrophilicity of the fibers studied to change in the following sequence: viscose > VION AN-3 > VION KN-1 > nylon-polyester > nitrone > polyester > polypropylene; PEPA modified hydrophilic fibrous material does not depend essentially on the chemical nature of the carrier.

  4. IVS Organization

    Science.gov (United States)

    2004-01-01

    International VLBI Service (IVS) is an international collaboration of organizations which operate or support Very Long Baseline Interferometry (VLBI) components. The goals are: To provide a service to support geodetic, geophysical and astrometric research and operational activities. To promote research and development activities in all aspects of the geodetic and astrometric VLBI technique. To interact with the community of users of VLBI products and to integrate VLBI into a global Earth observing system.

  5. 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

  6. 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.

  7. 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.

  8. 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

  9. 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)

  10. 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)

  11. Graphenated tantalum(IV) oxide and poly(4-styrene sulphonic acid)-doped polyaniline nanocomposite as cathode material in an electrochemical capacitor

    International Nuclear Information System (INIS)

    Njomo, Njagi; Waryo, Tesfaye; Masikini, Milua; Ikpo, Chinwe O.; Mailu, Stephen; Tovide, Oluwakemi; Ross, Natasha; Williams, Avril; Matinise, Nolubabalo; Sunday, Christopher E.; Mayedwa, Noluthando; Baker, Priscilla G.L.; Ozoemena, Kenneth I.; Iwuoha, Emmanuel I.

    2014-01-01

    Nanostructured poly(4-styrene sulphonic acid) and tantalum (IV) oxide-doped polyaniline nanocomposite were synthesised and their electro-conductive properties were determined. The oxide was synthesized using a modified sol-gel method and then dispersed in acidic media through sonication and entrapped in-situ into the polymeric matrix during the oxidative chemical polymerization of aniline doped with poly(4-styrene sulphonic acid). The oxides and novel polymeric nanocomposite were characterised with TEM, SEM, EDX, XRD, FTIR, UV-visible to ascertain elemental and phase composition, successful polymerization, doping, morphology and entrapment of the metal oxide nanoparticles. The electro-conductivity of the nanomaterial was interrogated using scanning electrochemical microscopy (SECM) and cyclic voltammetry (CV). The material was then anchored on activated graphitic carbon and used in the design of an asymmetric supercapacitor cell using 6 M KOH aqueous electrolyte. Characteristically high specific capacitance values of 318.4 F/g with a corresponding energy and power densities of 1.57 kWh/kg and 0.435 kW/kg, respectively, were demonstrated. The cell also showed high coulombic efficiency of 94.9% with a long cycle life and good cycle stability making the nanomaterial suitable for constructing supercapacitor cell electrodes

  12. 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...

  13. 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.

  14. 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

  15. 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.

  16. 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].

  17. Description of Sharon gen. nov. for the Chilean species Asaphes amoenus Philippi, 1861 (Coleoptera: Elateridae

    Directory of Open Access Journals (Sweden)

    Elizabeth T. Arias-Bohart

    2015-10-01

    Full Text Available Sharon gen. nov. is here described to include Asaphes? amoenus Philippi, 1861 comb. nov. from Chile. A redescription of the species is based on the female holotype and material from different geographic locations. Candèze (1891 placed Asaphes amoenus and Parasaphes elegans in the suprageneric group Asaphites. We discuss differences between Sharon gen. nov. and Hemicrepidius Germar, 1839, where Asaphes amoenus was later placed by Blackwelder (1944. Based on morphological characters, Sharon gen. nov. appears to be related to Parasaphes Candèze, 1881, Wynarka Calder, 1986, and Tasmanelater Calder, 1996, all from Australia, suggesting Gondwanan relationships.

  18. 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.

  19. 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)

  20. The Kubo-Greenwood spin-dependent electrical conductivity of 2D transition-metal dichalcogenides and group-IV materials: A Green's function study

    Science.gov (United States)

    Hoi, Bui Dinh; Yarmohammadi, Mohsen

    2018-04-01

    The spin-dependent electrical conductivity of counterparts of graphene, transition-metal dichalcogenides (TMDs) and group-IV nanosheets, have investigated by a magnetic exchange field (MEF)-induction to gain the electronic transport properties of charge carriers. We have implemented a k.p Hamiltonian model through the Kubo-Greenwood formalism in order to address the dynamical behavior of correlated Dirac fermions. Tuning the MEF enables one to control the effective mass of carriers in group-IV and TMDs, differently. We have found the Dirac-like points in a new quantum anomalous Hall (QAH) state at strong MEFs for both structures. For both cases, a broad peak in electrical conductivity originated from the scattering rate and entropy is observed. Spin degeneracy at some critical MEFs is another remarkable point. We have found that in the limit of zero or uniform MEFs with respect to the spin-orbit interaction, the large resulting electrical conductivity depends on the spin sub-bands in group-IV and MLDs. Featuring spin-dependent electronic transport properties, one can provide a new scenario for future possible applications.

  1. 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.

  2. Estabilidade dimensional dos moldes de poliéter e polissulfeto obtidos com a técnica do casquete de acrílico, vazados em gesso pedra especial tipo IV e V = Dimensional stability of polyether and polysulfide impression materials obtained with acrylic coping techniques pouring in stone type IV and V

    Directory of Open Access Journals (Sweden)

    Alves, Maria Cechinel

    2005-01-01

    Full Text Available O propósito deste estudo foi verificar o comportamento de moldes de polissulfeto (Permlastic e poliéter (Impregum Soft obtidos por meio da técnica do casquete de resina acrílica. Avaliou-se a estabilidade dimensional dos moldes confeccionados de uma matriz metálica contendo dois preparos protéticos, com diâmetros e alturas diferentes. Os moldes de cada material foram vazados com gessos pedra IV (Vel-mix e gesso pedra V (Exadur, perfazendo um total de quatro combinações experimentais: (polissulfeto/gesso-pedra IV, polissulfeto/gesso-pedra V, poliéter/gesso-pedra IV e poliéter/gesso-pedra V. Os troquéis de gesso foram mensurados com um paquímetro digital, 24 horas após sua obtenção. Os resultados obtidos foram submetidos a ANOVA a 5%. Pode-se concluir que os moldes de poliéter vazados com gesso pedra tipo V apresentaram melhor estabilidade dimensional em relação às outras condições experimentais

  3. Description of Sharon gen. nov. for the Chilean species Asaphes amoenus Philippi, 1861 (Coleoptera: Elateridae)

    OpenAIRE

    Elizabeth T. Arias-Bohart; Mario Elgueta

    2015-01-01

    Sharon gen. nov. is here described to include Asaphes? amoenus Philippi, 1861 comb. nov. from Chile. A redescription of the species is based on the female holotype and material from different geographic locations. Candèze (1891) placed Asaphes amoenus and Parasaphes elegans in the suprageneric group Asaphites. We discuss differences between Sharon gen. nov. and Hemicrepidius Germar, 1839, where Asaphes amoenus was later placed by Blackwelder (1944). Based on morphological characters, Sharon g...

  4. 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

  5. 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.

  6. 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.

  7. Synthesis and characterization of poly-o-anisidine Sn(IV tungstate: A new and novel ‘organic–inorganic’ nano-composite material and its electro-analytical applications as Hg(II ion-selective membrane electrode

    Directory of Open Access Journals (Sweden)

    Asif A. Khan

    2012-07-01

    Full Text Available An organic–inorganic nano-composite poly-o-anisidine Sn(IV tungstate was chemically synthesized by sol–gel mixing of the incorporation of organic polymer o-anisidine into the matrices of inorganic ppt of Sn(IV tungstate in different mixing volume ratios. This composite material has been characterized using various analytical techniques like XRD (X-ray diffraction, FTIR (Fourier transform infrared, SEM (Scanning electron microscopy, TEM (Transmission electron microscopy and simultaneous TGA (Thermogravimetric analysis studies. On the basis of distribution studies, the material was found to be highly selective for Hg(II. Using this nano-composite cation exchanger as electro-active material, a new heterogeneous precipitate based on ion-sensitive membrane electrode was developed for the determination of Hg(II ions in solutions. The membrane electrode was mechanically stable, with a quick response time, and can be operated within a wide pH range. The electrode was also found to be satisfactory in electrometric titrations.

  8. 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

  9. IV treatment at home

    Science.gov (United States)

    ... Other IV treatments you may receive after you leave the hospital include: Treatment for hormone deficiencies Medicines for severe nausea that cancer chemotherapy or pregnancy may cause Patient-controlled analgesia (PCA) for pain (this is IV ...

  10. Fundamental Technology Development for Radiation Damage in Nuclear Materials

    International Nuclear Information System (INIS)

    Kwon, Sang Chul; Kwon, J. H.; Kim, E. S. and others

    2005-04-01

    This project was performed to achieve technologies for the evaluation of radiation effects at materials irradiated at HANARO and nuclear power plants, to establish measurement equipment and software for the analysis of radiation defects and to set up facilities for the measurements of radiation damage with non-destructive methods. Major targets were 1) establishment of hot laboratories and remote handling facilities/ technologies for the radioactive material tests, 2) irradiation test for the simulation of nuclear power plant environment and measurement/calculation of physical radiation damage, 3) evaluation and analysis of nano-scale radiation damage, 4) evaluation of radiation embrittlement with ultrasonic resonance spectrum measurement and electromagnetic measurement and 5) basic research of radiation embrittlement and radiation damage mechanism. Through the performance of 3 years, preliminary basics were established for the application research to evaluation of irradiated materials of present nuclear power plants and GEN-IV systems. Particularly the results of SANS, PAS and TEM analyses were the first output in Korea. And computer simulations of radiation damage were tried for the first time in Korea. The technologies will be developed for the design of GEN-IV material

  11. Genève Reconnaissante

    CERN Multimedia

    2001-01-01

    Robert Cailliau (centre), with Geneva's Mayor Alain Vaissade (left) and Jean Erhardt, Secretary General of the Administrative Council of Geneva (right). Geneva recognised the contribution of two CERN people to the reputation of the city last Tuesday when Mayor Alain Vaissade presented the Genève Reconaissante Medal to Tim Berners-Lee and Robert Cailliau. Berners-Lee, who was not able to be present in person, invented the World Wide Web at CERN just over a decade ago, while Cailliau was his first collaborator. Quoting Cailliau, Vaissade said that whilst there is no doubt that something like the Web would have appeared sooner or later, the fact that it happened at CERN, in Geneva, was no accident. Both the Laboratory and the city are places where people from around the world meet and work in harmony.

  12. Crusticorallina gen. nov., a nongeniculate genus in the subfamily Corallinoideae (Corallinales, Rhodophyta).

    Science.gov (United States)

    Hind, Katharine R; Gabrielson, Paul W; P Jensen, Cassandra; Martone, Patrick T

    2016-12-01

    Molecular phylogenetic analyses of 18S rDNA (SSU) gene sequences confirm the placement of Crusticorallina gen. nov. in Corallinoideae, the first nongeniculate genus in an otherwise geniculate subfamily. Crusticorallina is distinguished from all other coralline genera by the following suite of morpho-anatomical characters: (i) sunken, uniporate gametangial and bi/tetrasporangial conceptacles, (ii) cells linked by cell fusions, not secondary pit connections, (iii) an epithallus of 1 or 2 cell layers, (iv) a hypothallus that occupies 50% or more of the total thallus thickness, (v) elongate meristematic cells, and (vi) trichocytes absent. Four species are recognized based on rbcL, psbA and COI-5P sequences, C. painei sp. nov., the generitype, C. adhaerens sp. nov., C. nootkana sp. nov. and C. muricata comb. nov., previously known as Pseudolithophyllum muricatum. Type material of Lithophyllum muricatum, basionym of C. muricata, in TRH comprises at least two taxa, and therefore we accept the previously designated lectotype specimen in UC that we sequenced to confirm its identity. Crusticorallina species are very difficult to distinguish using morpho-anatomical and/or habitat characters, although at specific sites, some species may be distinguished by a combination of morpho-anatomy, habitat and biogeography. The Northeast Pacific now boasts six coralline endemic genera, far more than any other region of the world. © 2016 Phycological Society of America.

  13. Forensic engineering of advanced polymeric materials Part IV: Case study of oxo-biodegradable polyethylene commercial bag - Aging in biotic and abiotic environment.

    Science.gov (United States)

    Musioł, Marta; Rydz, Joanna; Janeczek, Henryk; Radecka, Iza; Jiang, Guozhan; Kowalczuk, Marek

    2017-06-01

    The public awareness of the quality of environment stimulates the endeavor to safe polymeric materials and their degradation products. The aim of the forensic engineering case study presented in this paper is to evaluate the aging process of commercial oxo-degradable polyethylene bag under real industrial composting conditions and in distilled water at 70°C, for comparison. Partial degradation of the investigated material was monitored by changes in molecular weight, thermal properties and Keto Carbonyl Bond Index and Vinyl Bond Index, which were calculated from the FTIR spectra. The results indicate that such an oxo-degradable product offered in markets degrades slowly under industrial composting conditions. Even fragmentation is slow, and it is dubious that biological mineralization of this material would occur within a year under industrial composting conditions. The slow degradation and fragmentation is most likely due to partially crosslinking after long time of degradation, which results in the limitation of low molecular weight residues for assimilation. The work suggests that these materials should not be labeled as biodegradable, and should be further analyzed in order to avoid the spread of persistent artificial materials in nature. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Structural materials issues for the next generation fission reactors

    Science.gov (United States)

    Chant, I.; Murty, K. L.

    2010-09-01

    Generation-IV reactor design concepts envisioned thus far cater to 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-W 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 environments, 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 article addresses the material requirements for these advanced fission reactor types, specifically addressing structural materials issues depending on the specific application areas.

  15. 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.

  16. Development of methods for measuring materials nuclear characteristics, Phases, I, II, II and IV; Razvijanje metoda merenja nuklearnih karakteristika materijala, I, II, II i VI faza

    Energy Technology Data Exchange (ETDEWEB)

    Maglic, R [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1963-04-15

    This report contains the following phases of the project 'measurement of nuclear characteristics of reactor materials': nuclear performances of the neutron chopper; method for measuring total effective cross sections by transmission method on the chopper; review of methods for measuring activation cross sections; measurement of neutron spectra of the RA reactor and measurement of total effective cross section of gold by using the chopper.

  17. Development of metal fuel and study of construction materials (I-IV), Part II; Razvoj metalnog goriva i ispitivanje konstrukcionih materijala (I-VI deo); II deo

    Energy Technology Data Exchange (ETDEWEB)

    Mihajlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    The studies were devoted to problems related to application of metal uranium as fuel in heavy water reactors. Influence of thermal treatment on material texture and recrystallization of cast uranium was investigated. Structural changes of uranium alloys with molybdenum and niobium were tested during different heat treatments. A review of the possibilities for using metal uranium fuel in heavy water reactors is included.

  18. Emissivity of Candidate Materials for VHTR Applicationbs: Role of Oxidation and Surface Modification Treatments

    International Nuclear Information System (INIS)

    Sridharan, Kumar; Allen, Todd; Anderson, Mark; Cao, Guoping; Kulcinski, Gerald

    2011-01-01

    The Generation IV (GEN IV) Nuclear Energy Systems Initiative was instituted by the Department of Energy (DOE) with the goal of researching and developing technologies and materials necessary for various types of future reactors. These GEN IV reactors will employ advanced fuel cycles, passive safety systems, and other innovative systems, leading to significant differences between these future reactors and current water-cooled reactors. The leading candidate for the Next Generation Nuclear Plant (NGNP) to be built at Idaho National Lab (INL) in the United States is the Very High Temperature Reactor (VHTR). Due to the high operating temperatures of the VHTR, the Reactor Pressure Vessel (RPV) will partially rely on heat transfer by radiation for cooling. Heat expulsion by radiation will become all the more important during high temperature excursions during off-normal accident scenarios. Radiant power is dictated by emissivity, a material property. The NGNP Materials Research and Development Program Plan (1) has identified emissivity and the effects of high temperature oxide formation on emissivity as an area of research towards the development of the VHTR.

  19. 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

  20. Determinação seletiva de tributilestanho na presença de Sn(IV em amostras ambientais usando HG-ICP OES e Saccharomyces cerevisiae como material sorvente Selective determination of tributyltin in the presence of Sn(IV in environmental samples using HG-ICP OES and Saccharomyces cerevisiae as sorbing material

    Directory of Open Access Journals (Sweden)

    Monizze Vannuci e Silva

    2010-01-01

    Full Text Available A method for selective determination of tributyltin in the presence of Sn(IV by combining hydride generation inductively coupled plasma optical emission spectrometry (HG-ICP OES and solid phase extraction (SPE using baker's yeast is proposed. The procedure is based on selective retention of TBT by the yeast at pH = 6. Detection limit of 1.9 µg L-1 and quantification limit of 6.3 µg L-1 were obtained. TBT and San(IV were determined in the range of 0-25 µg L-1 and the proposed approach was applied to analyze river water, sea water and biological extracts, with recoveries of 114, 101 and 86%, respectively.

  1. Generation IV national program

    International Nuclear Information System (INIS)

    Preville, M.; Sadhankar, R.; Brady, D.

    2007-01-01

    This paper outlines the Generation IV National Program. This program involves evolutionary and innovative design with significantly higher efficiencies (∼50% compared to present ∼30%) - sustainable, economical, safe, reliable and proliferation resistant - for future energy security. The Generation IV Forum (GIF) effectively leverages the resources of the participants to meet these goals. Ten countries signed the GIF Charter in 2001

  2. Optimisation of the mechanical alloying process for odsferritic steels for generation IV reactors application

    International Nuclear Information System (INIS)

    Stanciulescu, M.; Carlan, P.; Mihalache, M.; Abrudeanu, M.

    2016-01-01

    ODS ferritic steels appear as promising materials for fusion and Gen IV fission reactors, offering high temperature performance, corrosion and irradiation resistance and meeting low activation criteria. Mechanical alloying (MA) is a powder metallurgy technique efficient for fabricating advanced materials, and has been used for strengthening structural materials including Fe-Cr alloys. In this paper a high-energy ball mill is used to study the microstructural evolution of 14YW alloy during the mechanical alloying process. The elemental powders are milled at a rotation speed of 250rot/min in cycles of 10min milling and 5min pause, with a ball-to-powder ration of 10:1 and in argon protective atmosphere. After 72 hours milling, the morphology and element distribution of the MA powders is investigated by scanning electron microscopy (SEM) and energy dispersive X-ray (EDX) analysis, respectively. It is observed that the particles size increases in the first milling stages and then decreases with the milling time. Changes in the material composition are analysed by X-ray diffraction (DRX). It seems that after milling part of the W remains non-dissolved in the Fe-Cr matrix retarding the solid solution formation. (authors)

  3. 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!

  4. Fuel, structural material and coolant for an advanced fast micro-reactor

    International Nuclear Information System (INIS)

    Nascimento, Jamil A. do; Guimaraes, Lamartine N.F.; Ono, Shizuca

    2011-01-01

    The use of nuclear reactors in space, seabed or other Earth hostile environment in the future is a vision that some Brazilian nuclear researchers share. Currently, the USA, a leader in space exploration, has as long-term objectives the establishment of a permanent Moon base and to launch a manned mission to Mars. A nuclear micro-reactor is the power source chosen to provide energy for life support, electricity for systems, in these missions. A strategy to develop an advanced micro-reactor technologies may consider the current fast reactor technologies as back-up and the development of advanced fuel, structural and coolant materials. The next generation reactors (GEN-IV) for terrestrial applications will operate with high output temperature to allow advanced conversion cycle, such as Brayton, and hydrogen production, among others. The development of an advanced fast micro-reactor may create a synergy between the GEN-IV and space reactor technologies. Considering a set of basic requirements and materials properties this paper discusses the choice of advanced fuel, structural and coolant materials for a fast micro-reactor. The chosen candidate materials are: nitride, oxide as back-up, for fuel, lead, tin and gallium for coolant, ferritic MA-ODS and Mo alloys for core structures. The next step will be the neutronic and burnup evaluation of core concepts with this set of materials. (author)

  5. Neptunium (IV) oxalate solubility

    International Nuclear Information System (INIS)

    Luerkens, D.W.

    1983-07-01

    The equilibrium solubility of neptunium (IV) oxalate in nitric/oxalic acid solutions was determined at 22 0 C, 45 0 C, and 60 0 C. The concentrations of nitric/oxalic acid solutions represented a wide range of free oxalate ion concentration. A mathematical solubility model was developed which is based on the formation of the known complexes of neptunium (IV) oxalate. the solubility model uses a simplified concentration parameter which is proportional to the free oxalate ion concentration. The solubility model can be used to estimate the equilibrium solubility of neptunium (IV) oxalate over a wide range of oxalic and nitric acid concentrations at each temperature

  6. NNDSS - Table IV. Tuberculosis

    Data.gov (United States)

    U.S. Department of Health & Human Services — NNDSS - Table IV. Tuberculosis - 2016.This Table includes total number of cases reported in the United States, by region and by states, in accordance with the...

  7. NNDSS - Table IV. Tuberculosis

    Data.gov (United States)

    U.S. Department of Health & Human Services — NNDSS - Table IV. Tuberculosis - 2014.This Table includes total number of cases reported in the United States, by region and by states, in accordance with the...

  8. NNDSS - Table IV. Tuberculosis

    Data.gov (United States)

    U.S. Department of Health & Human Services — NNDSS - Table IV. Tuberculosis - 2015.This Table includes total number of cases reported in the United States, by region and by states, in accordance with the...

  9. SAGE IV Pathfinder

    Data.gov (United States)

    National Aeronautics and Space Administration — Utilizing a unique, new occultation technique involving imaging, the SAGE IV concept will meet or exceed the quality of previous SAGE measurements at a small...

  10. 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.

  11. 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...

  12. Tools for Designing, Evaluating, and Certifying NextGen Technologies and Procedures: Automation Roles and Responsibilities

    Science.gov (United States)

    Kanki, Barbara G.

    2011-01-01

    Barbara Kanki from NASA Ames Research Center will discuss research that focuses on the collaborations between pilots, air traffic controllers and dispatchers that will change in NextGen systems as automation increases and roles and responsibilities change. The approach taken by this NASA Ames team is to build a collaborative systems assessment template (CSAT) based on detailed task descriptions within each system to establish a baseline of the current operations. The collaborative content and context are delineated through the review of regulatory and advisory materials, policies, procedures and documented practices as augmented by field observations and interviews. The CSAT is developed to aid the assessment of key human factors and performance tradeoffs that result from considering different collaborative arrangements under NextGen system changes. In theory, the CSAT product may be applied to any NextGen application (such as Trajectory Based Operations) with specified ground and aircraft capabilities.

  13. Efeito da desinfecção por aerossóis sobre a capacidade de umedecimento de moldes de poliéter por gesso tipo IV Wettability of a polyether impression material - adverse effects of spray disinfection

    Directory of Open Access Journals (Sweden)

    Maria Cristina Rosifini ALVES-REZENDE

    1999-12-01

    Full Text Available A desinfecção de todo e qualquer molde obtido é medida de biossegurança obrigatória na atividade clínica. Tão importante quanto a desinfecção é a seleção do método e da solução desinfetante a ser utilizada para cada material de moldagem. É imperativo que a capacidade de reprodução de detalhes, a estabilidade dimensional e o grau de umedecimento (ou "molhabilidade" não sejam criticamente afetados. O propósito deste trabalho foi avaliar o grau de umedecimento de uma marca comercial de poliéter (Impregum F por três diferentes marcas comerciais de gesso tipo IV (Herostone, Durone e Polirock, após sua desinfecção por aerossóis de hipoclorito de sódio 1% (líquido de Milton ou glutaraldeído 2% (Glutalabor II. Foram confeccionados 45 moldes de poliéter, os quais, em grupos de 15, receberam aerossóis de água (Grupo Controle, Líquido de Milton ou Glutalabor II. Em seguida, sobre a superfície dos moldes foram confeccionados modelos de gesso tipo IV, em número de 5 para cada marca de gesso. Após seu seccionamento mediano e preparo da superfície de corte, os modelos foram levados ao microscópio Carl Zeiss para leitura do ângulo de contato. Os resultados obtidos permitiram concluir que: a a capacidade de umedecimento do poliéter por diferentes marcas comerciais de gesso tipo IV variou para os gessos estudados; b o gesso Durone adaptou-se melhor aos moldes de poliéter do que os gessos Herostone e Polirock; c a desinfecção dos moldes com aerossóis de hipoclorito de sódio 1% (líquido de Milton ou glutaraldeído 2% (Glutalabor não afetou a adaptação entre os gessos e o poliéter.Impressions carried out in the dental office are potential contamination pathways. The aim of this paper was to evaluate the effects of spray disinfection on the wetting of polyether material (Impregum F by stones. Three kinds of stones (Herostone, Durone and Polirock and two disinfectant solutions (2% glutaraldehyde and 1% hypochlorite

  14. 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...

  15. 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

  16. 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.

  17. International Conference on NextGen Electronic Technologies

    CERN Document Server

    Thalmann, Nadia; Bhaaskaran, V

    2017-01-01

    This book is a collection of keynote lectures from international experts presented at International Conference on NextGen Electronic Technologies (ICNETS2-2016). ICNETS2 encompasses six symposia covering all aspects of electronics and communications domains, including relevant nano/micro materials and devices . This volume comprises of recent research in areas like computational signal processing analysis, intelligent embedded systems, nanoelectronic materials and devices, optical and microwave technologies, VLSI design: circuits systems and application, and wireless communication networks, and the internet of things. The contents of this book will be useful to researchers, professionals, and students working in the core areas of electronics and their applications, especially to signal processing, embedded systems, and networking.

  18. 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

  19. 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.

  20. 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)

  1. IV access in dental practice.

    LENUS (Irish Health Repository)

    Fitzpatrick, J J

    2009-04-01

    Intravenous (IV) access is a valuable skill for dental practitioners in emergency situations and in IV sedation. However, many people feel some apprehension about performing this procedure. This article explains the basic principles behind IV access, and the relevant anatomy and physiology, as well as giving a step-by-step guide to placing an IV cannula.

  2. 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

  3. 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.

  4. 1L Mark-IV Target Design Review

    Energy Technology Data Exchange (ETDEWEB)

    Koehler, Paul E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-11-16

    This presentation includes General Design Considerations; Current (Mark-III) Lower Tier; Mark-III Upper Tier; Performance Metrics; General Improvements for Material Science; General Improvements for Nuclear Science; Improving FOM for Nuclear Science; General Design Considerations Summary; Design Optimization Studies; Expected Mark-IV Performance: Material Science; Expected Mark-IV Performance: Nuclear Science (Disk); Mark IV Enables Much Wider Range of Nuclear-Science FOM Gains than Mark III; Mark-IV Performance Summary; Rod or Disk? Center or Real FOV?; and Project Cost and Schedule.

  5. Internet Economics IV

    Science.gov (United States)

    2004-08-01

    edts.): Internet Economics IV Technical Report No. 2004-04, August 2004 Information Systems Laboratory IIS, Departement of Computer Science University of...level agreements (SLA), Information technology (IT), Internet address, Internet service provider 16. PRICE CODE 17. SECURITY CLASSIFICATION 18... technology and its economic impacts in the Internet world today. The second talk addresses the area of AAA protocol, summarizing authentication

  6. Uranium (IV) carboxylates - I

    Energy Technology Data Exchange (ETDEWEB)

    Satpathy, K C; Patnaik, A K [Sambalpur Univ. (India). Dept. of Chemistry

    1975-11-01

    A few uranium(IV) carboxylates with monochloro and trichloro acetic acid, glycine, malic, citric, adipic, o-toluic, anthranilic and salicylic acids have been prepared by photolytic methods. The I.R. spectra of these compounds are recorded and basing on the spectral data, structure of the compounds have been suggested.

  7. PLATO IV Accountancy Index.

    Science.gov (United States)

    Pondy, Dorothy, Comp.

    The catalog was compiled to assist instructors in planning community college and university curricula using the 48 computer-assisted accountancy lessons available on PLATO IV (Programmed Logic for Automatic Teaching Operation) for first semester accounting courses. It contains information on lesson access, lists of acceptable abbreviations for…

  8. Materialism.

    Science.gov (United States)

    Melnyk, Andrew

    2012-05-01

    Materialism is nearly universally assumed by cognitive scientists. Intuitively, materialism says that a person's mental states are nothing over and above his or her material states, while dualism denies this. Philosophers have introduced concepts (e.g., realization and supervenience) to assist in formulating the theses of materialism and dualism with more precision, and distinguished among importantly different versions of each view (e.g., eliminative materialism, substance dualism, and emergentism). They have also clarified the logic of arguments that use empirical findings to support materialism. Finally, they have devised various objections to materialism, objections that therefore serve also as arguments for dualism. These objections typically center around two features of mental states that materialism has had trouble in accommodating. The first feature is intentionality, the property of representing, or being about, objects, properties, and states of affairs external to the mental states. The second feature is phenomenal consciousness, the property possessed by many mental states of there being something it is like for the subject of the mental state to be in that mental state. WIREs Cogn Sci 2012, 3:281-292. doi: 10.1002/wcs.1174 For further resources related to this article, please visit the WIREs website. Copyright © 2012 John Wiley & Sons, Ltd.

  9. 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

  10. 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

  11. LIFE Materials: Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    Turchi, P A; Kaufman, L; Fluss, M

    2008-12-19

    The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical, and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an entire report (Volume 8 - Molten-salt Fuels) is dedicated to it. Then, in a second part, with the specific LIFE specifications in mind, the various fuel options with their most critical issues are revisited with a path forward for each of them in terms of research, both experimental and theoretical. Since LIFE is applicable to very high burn-up of various fuels, distinctions will be made depending on the mission, i.e., energy production or incineration. Finally a few conclusions are drawn in terms of the specific needs for integrated materials modeling and the in depth knowledge on time-evolution thermo-chemistry that controls and drastically affects the performance of the nuclear materials and their immediate environment. Although LIFE demands materials that very likely have not yet been fully optimized, the challenges are not insurmountable, and a well concerted experimental-modeling effort should lead to dramatic advances that should well serve other fission programs such as Gen-IV, GNEP, AFCI as well as the international fusion program, ITER.

  12. 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...

  13. 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

  14. Database of thermophysical properties of liquid metal coolants for GEN-IV

    International Nuclear Information System (INIS)

    Sobolev, V.

    2011-01-01

    The report presents an Fe-Cr interatomic potential to model high-Cr ferritic alloys. The potential is fitted to thermodynamic and point-defect properties obtained from density functional theory (DFT) calculations and experiments. The developed potential is also benchmarked against other potentials available in literature. It shows particularly good agreement with the DFT obtained mixing enthalpy of the random alloy, the formation energy of intermetallics and experimental excess vibrational entropy and phase diagram. In addition, DFT calculated point-defect properties, both interstitial and substitutional, are well reproduced, as is the screw dislocation core structure. As a first validation of the potential, we study the precipitation hardening of Fe-Cr alloys via static simulations of the interaction between Cr precipitates and screw dislocations. It is concluded that the description of the dislocation core modification near a precipitate might have a significant influence on the interaction mechanisms observed in dynamic simulations.

  15. 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.

  16. Control Rod Withdrawal Events Analyses for the Prototype Gen-IV SFR

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chiwoong; Ha, Kwiseo; Jeong, Taekyeong; Jeong, Jaeho; Chang, Wonpyo; Lee, Seungwon; An, Sangjun; Lee, Kwilim [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    To confirm the limiting condition, based on the maximum allowable reactivity insertion of 0.3 $, three cases from the end of cycle (EOC) are selected. In addition, assuming the failure of CRSS by earthquake, additional cases is defined at beginning of cycle (BOC). When the CRW occurs, the reactor can be protected by plant protection system (PPS). In this study, PPS mechanism is sequentially studied for all initiating events. For design basis accidents (DBA), the reactor can be scrammed by reactor protection system (RPS). The first and seconds RPS signals are checked during transients. When RPS is failed, so called as anticipated transient without scram (ATWS), the reactor will be protected by diverse protection system (DPS). In this study, in order to analyze various initiating events related control rod withdrawal, four kinds of operating condition is defined. TOP events are analyzed using MARS-LMR. The influence of various plant protection system such as RPS and DPS are investigated.

  17. Studies on woloszynskioid dinoflagellates IV: the genus Biecheleria gen. nov

    DEFF Research Database (Denmark)

    Moestrup, Øjvind; Lindberg, Karin; Daugbjerg, Niels

    2009-01-01

    in the dinoflagellates. Biecheleria also comprises the brackish water species Biecheleria baltica sp. nov. (presently identified as Woloszynskia halophila) and the marine species Biecheleria natalensis (syn. Gymnodinium natalense). Gymnodinium halophilum described in 1952 by B. Biecheler but apparently not subsequently...... refound, is transferred to Biecheleria. The Suessiaceae further includes the marine species Protodinium simplex, described by Lohmann in 1908 but shortly afterwards (1921) transferred to Gymnodinium by Kofoid and Swezy and subsequently known as Gymnodinium simplex. It only distantly related to Gymnodinium...

  18. Analyses of Design Extended Condition Events for the Prototype Gen-IV SFR

    International Nuclear Information System (INIS)

    Choi, Chiwoong; Jeong, Taekyung; Lee, Kwilim; Jeong, Jaeho; Ha, Kwiseok

    2015-01-01

    In this study, the sensitivity tests are conducted. In the case of the UTOP event, a sensitivity test for the reactivity insertion amount and rate were conducted. This analysis can give a requirement for margin of control rod stop system (CRSS). For example, the CRSS in the PRISM designed based on the 0.4 $ reactivity insertion, which is analyzed with safety analysis of UTOP event. Moreover, the sensitivity tests for weighting factor in the core radial expansion reactivity feedback model were also carried out for all ATWS events. Currently, the reactivity feedback model for the PGSFR is not validated yet. However, the reactivity feedback models in the MARS-LMR are validating with various plant-based data including EBR-II SHRT. The ATWS events for the PGSFR classified in the design extended condition including UTOP, ULOF, and ULOHS are analyzed with MARS-LMR. In this study, the sensitivity tests for reactivity insertion amount and rate in the UTOP event are conducted. The reactivity insertion amount is obviously an influential parameter. The reactivity insertion amount can give a requirement for design of the CRSS, therefore, this sensitivity result is very important to the CRSS. In addition, sensitivity tests for the weighting factor in the radial expansion reactivity model are carried out. The weighting factor for a grid plate, W GP , which means contribution of feedback in the grid plate is changed for all unprotected events. The grid plate expansion is governed by a core inlet temperature. As the W GP is increased, the power in the UTOP and the ULOF is increased, however, the power in the ULOHS is decreased. The higher power during transient means lower reactivity feedback and smaller expansion. Thus, the core outlet temperature rise is dominant in the UTOP and ULOF events, however, the core inlet temperature rise is dominant in the ULOHS. Therefore, the grid plate expansion in the ULOHS is predominant

  19. 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

  20. Optimized, Competitive Supercritical-CO2 Cycle GFR for Gen IV Service

    International Nuclear Information System (INIS)

    M.J. Driscoll; P. Hejzlar; G. Apostolakis

    2008-01-01

    An overall plant design was developed for a gas-cooled fast reactor employing a direct supercritical Brayton power conversion system. The most important findings were that (1) the concept could be capital-cost competitive, but startup fuel cycle costs are penalized by the low core power density, specified in large part to satisfy the goal of significant post-accident passive natural convection cooling; (2) active decay heat removal is preferable as the first line of defense, with passive performance in a backup role; (3) an innovative tube-in-duct fuel assembly, vented to the primary coolant, appears to be practicable; and (4) use of the S-Co2 GFR to support hydrogen production is a synergistic application, since sufficient energy can be recuperated from the product H2 and 02 to allow the electrolysis cell to run 250 C hotter than the reactor coolant, and the water boilers can be used for reactor decay heat removal. Increasing core power density is identified as the top priority for future work on GFRs of this type

  1. Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps

    International Nuclear Information System (INIS)

    Chen, Franglin Frank; Adams, Thad M.; Brinkman, Kyle; Reifsnider, Kenneth

    2011-01-01

    Several perovskite structured proton conductors based on SrCeO 3 and BaCeO 3 have been investigated in the project. The solid solutions for SrCeO 3 and BaCeO 3 were first investigated. The morphological and electrical properties of Ba 1-x Sr x Ce 0.8 Y 0.2 O 3-δ with x varying from 0 to 1 prepared by a modified Pechini method were investigated as potential high temperature proton conductors. Dense microstructures were achieved for all the samples upon sintering at 1500ees)C for 5 h. The phase structure analysis indicated that perovskite phase was formed for 0≤x≤0.2, while for x larger than 0.5, impurity phases of Sr 2 CeO 4 and Y 2 O 3 appeared. The stability tests indicated that the resistance to boiling water for Ba 1-x Sr x Ce 0.8 Y 0.2 O 3-δ was between that of BaCe 0.8 Y 0.2 O 3-δ and SrCe 0.8 Y 0.2 O 3-δ Due to the tendency of the reaction with CO 2 for both BaCe 0.8 Y 0.2 O 3-δ and SrCe 0.8 Y 0.2 O 3-δ , it was not surprising that Ba 1-x Sr x Ce 0.8 Y 0.2 O 3-δ was also not stable in CO 2 containing atmospheres. The conductivity tests indicated that Ba 1-x Sr x Ce 0.8 Y 0.2 O 3-δ possessed the electrical conductivity between BaCe 0.8 Y 0.2 O 3-δ and SrCe 0.8 Y 0.2 O 3-δ . The conductivity decreased and the activation energy increased with the increase in Sr content in Ba 1-x Sr x Ce 0.8 Y 0.2 O 3-δ .

  2. Preliminary Comparative Evaluation Study on Reference Design of GEN-IV SFR

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Yoon Sub; Kim, Yeong Il; Hong, Ser Gi (and others)

    2005-11-15

    A fast reactor has a good transmutation capability and it enables breeding of fuel and use of a closed fuel cycle. By these characteristics of a fast reactor, the limited uranium resources of the world can be much more effectively utilized and the nuclear wastes of a high level of radioactivity and toxicity from the current nuclear power reactors of LWRs and HWRs can be drastically reduced in its volume and the management of the wastes can be easily treated. Also electricity can be generated more effectively since a fast reactor has the feature of high operation temperature. These features of a fast reactor makes it inevitable on a long term basis to construct fast reactors in Korea. The domestic fast reactor technology level, however, is at the level of coming out of a beginning stage and needs utilization of international expertise. Recently an international cooperation program called GIF has been formulated and our KALIMER was selected as one of the two reference designs for the international joint R and D works with JSFR of Japan. In the current frame of the GIF program, the two selected reference designs are supposed to be evaluated against each other in future and one design is to be finally selected. To make the international cooperation program directed more useful to our fast reactor technology development, it is required to strengthen the competitiveness of KALIMER so that it can be selected. To meet the necessity, a study was made in this research for pre-evaluation of the GIF reference designs and setting up plans for development of designs and technology that will enhance the competitiveness of KALIMER.

  3. Sensitivity Tests for the Unprotected Events of the Prototype Gen-IV SFR

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chiwoong; Lee, Kwilim; Jeong, Jaeho; Yu, Jin; An, Sangjun; Lee, Seung Won; Chang, Wonpyo; Ha, Kwiseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Unprotected Transient Over Power, (UTOP), Unprotected Loss Of Flow (ULOF), and Unprotected Loss Of Heat Sink (ULOHS) are selected as ATWS events. Among these accidents, the ULOF event shows the lowest clad temperature. However, the ULOHS event showed the highest peak clad temperature, due to the positive CRDL/RV expansion reactivity feedback and insufficient DHRS capacity. In this study, the sensitivity tests are conducted. In the case of the UTOP event, a sensitivity test for the reactivity insertion amount and rate were conducted. This analysis can give a requirement for margin of control rod stop system (CRSS). Currently, the reactivity feedback model for the PGSFR is not validated yet. However, the reactivity feedback models in the MARS-LMR are validating with various plant-based data including EBR-II SHRT. The ATWS events for the PGSFR classified in the design extended condition including UTOP, ULOF, and ULOHS are analyzed with MARS-LMR. In this study, the sensitivity tests for reactivity insertion amount and rate in the UTOP event are conducted. The reactivity insertion amount is obviously an influential parameter. The reactivity insertion amount can give a requirement for design of the CRSS, therefore, this sensitivity result is very important to the CRSS. In addition, sensitivity tests for the weighting factor in the radial expansion reactivity model are carried out. The weighting factor for a grid plate, W{sub GP}, which means contribution of feedback in the grid plate is changed for all unprotected events. The grid plate expansion is governed by a core inlet temperature. As the W{sub GP} is increased, the power in the UTOP and the ULOF is increased, however, the power in the ULOHS is decreased. The higher power during transient means lower reactivity feedback and smaller expansion. Thus, the core outlet temperature rise is dominant in the UTOP and ULOF events, however, the core inlet temperature rise is dominant in the ULOHS. Therefore, the grid plate expansion in the ULOHS is predominant. These analysis results will give better understanding for the unprotected events and provide feedback to design for the PGSFR. In addition, the safety analyses for unprotected events: UTOP, ULOF, and ULOHS will be recalculated with CDF, which is a safety criteria in the near future.

  4. Enhanced Design Alternative IV

    International Nuclear Information System (INIS)

    Kramer, N.E.

    1999-01-01

    This report evaluates Enhanced Design Alternative (EDA) IV as part of the second phase of the License Application Design Selection (LADS) effort. The EDA IV concept was compared to the VA reference design using criteria from the Design Input Request for LADS Phase II EDA Evaluations (CRWMS M and O 1999b) and (CRWMS M and O 1999f). Briefly, the EDA IV concept arranges the waste packages close together in an emplacement configuration known as line load. Continuous pre-closure ventilation keeps the waste packages from exceeding their 350 C cladding and 200 C (4.3.6) drift wall temperature limits. This EDA concept keeps relatively high, uniform emplacement drift temperatures (post-closure) to drive water away from the repository and thus dry out the pillars between emplacement drifts. The waste package is shielded to permit human access to emplacement drifts and includes an integral filler inside the package to reduce the amount of water that can contact the waste form. Closure of the repository is desired 50 years after first waste is emplaced. Both backfill and drip shields will be emplaced at closure to improve post-closure performance. The EDA IV concept includes more defense-in-depth layers than the VA reference design because of its backfill, drip shield, waste package shielding, and integral filler features. These features contribute to the low dose-rate to the public achieved during the first 10,000 years of repository life as shown in Figure 3. Investigation of the EDA IV concept has led to the following general conclusions: (1) The total life cycle cost for EDA IV is about $21.7 billion which equates to a $11.3 billion net present value (both figures rounded up). (2) The incidence of design basis events for EDA IV is similar to the VA reference design. (3) The emplacement of the waste packages in drifts will be similar to the VA reference design. However, heavier equipment may be required because the shielded waste package will be heavier. (4) The heavier

  5. 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.

  6. 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

  7. Targeted NextGen Capabilities for 2025

    Science.gov (United States)

    2011-11-01

    increased arrival capacity to single runways by reducing longitudinal wake separation standards for Instrument Flight Rules ( IFR ) operations under certain...b. ABSTRACT unclassified c. THIS PAGE unclassified Standard Form 298 (Rev. 8-98) Prescribed by ANSI Std Z39-18 Targeted NextGen Capabilities...The examples cited are not intended to cover every aircraft and every flight. In some instances, the available capabilities for 2025 will not be

  8. InGen Inconsistencies: The "Dinosaurs" Of Jurassic Park May Not Be What The Corporation Claims

    Science.gov (United States)

    Haupt, R. J.; Traer, M. M.

    2017-12-01

    biotech companies have been able to do at present. These inconsistencies suggest that the actual technological assets developed by InGen might be slightly, or even significantly, different than what their promotional materials claim, and that paleontologists should be wary of using these animals as study organisms to test paleontological hypotheses.

  9. Review Paper: Review of Instrumentation for Irradiation Testing of Nuclear Fuels and Materials

    International Nuclear Information System (INIS)

    Kim, Bong Goo; Rempe, Joy L.; Villard, Jean-Francois; Solstadd, Steinar

    2011-01-01

    Over 50 years of nuclear fuels and materials irradiation testing has led to many countries developing significant improvements in instrumentation to monitor physical parameters and to control the test conditions in material test reactors (MTRs). Recently, there is increased interest to irradiate new materials and reactor fuels for advanced pressurized water reactors and Gen-IV reactor systems, such as sodium-cooled fast reactors, very high temperature reactors, supercritical water-cooled reactors, and gas-cooled fast reactors. This review paper documents the current state of instrumentation technologies in MTRs in the world and summarizes ongoing research efforts to deploy new sensors. As described in this paper, a wide range of sensors is available to measure key parameters of interest during fuels and materials irradiations in MTRs. Ongoing development efforts focus on providing MTR users a wider range of parameter measurements with smaller, higher accuracy sensors.

  10. Materials

    CSIR Research Space (South Africa)

    Van Wyk, Llewellyn V

    2009-02-01

    Full Text Available . It is generally included as part of a structurally insulated panel (SIP) where the foam is sandwiched between external skins of steel, wood or cement. Cement composites Cement bonded composites are an important class of building materials. These products... for their stone buildings, including the Egyptians, Aztecs and Inca’s. As stone is a very dense material it requires intensive heating to become warm. Rocks were generally stacked dry but mud, and later cement, can be used as a mortar to hold the rocks...

  11. A sputnik IV saga

    Science.gov (United States)

    Lundquist, Charles A.

    2009-12-01

    The Sputnik IV launch occurred on May 15, 1960. On May 19, an attempt to deorbit a 'space cabin' failed and the cabin went into a higher orbit. The orbit of the cabin was monitored and Moonwatch volunteer satellite tracking teams were alerted to watch for the vehicle demise. On September 5, 1962, several team members from Milwaukee, Wisconsin made observations starting at 4:49 a.m. of a fireball following the predicted orbit of Sputnik IV. Requests went out to report any objects found under the fireball path. An early morning police patrol in Manitowoc had noticed a metal object on a street and had moved it to the curb. Later the officers recovered the object and had it dropped off at the Milwaukee Journal. The Moonwarch team got the object and reported the situation to Moonwatch Headquarters at the Smithsonian Astrophysical Observatory. A team member flew to Cambridge with the object. It was a solid, 9.49 kg piece of steel with a slag-like layer attached to it. Subsequent analyses showed that it contained radioactive nuclei produced by cosmic ray exposure in space. The scientists at the Observatory quickly recognized that measurements of its induced radioactivity could serve as a calibration for similar measurements of recently fallen nickel-iron meteorites. Concurrently, the Observatory directorate informed government agencies that a fragment from Sputnik IV had been recovered. Coincidently, a debate in the UN Committee on Peaceful Uses of Outer Space involved the issue of liability for damage caused by falling satellite fragments. On September 12, the Observatory delivered the bulk of the fragment to the US Delegation to the UN. Two days later, the fragment was used by US Ambassador Francis Plimpton as an exhibit that the time had come to agree on liability for damage from satellite debris. He offered the Sputnik IV fragment to USSR Ambassador P.D. Morozov, who refused the offer. On October 23, Drs. Alla Massevitch and E.K. Federov of the USSR visited the

  12. 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

  13. 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...

  14. 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

  15. TidGen Power System Commercialization Project

    Energy Technology Data Exchange (ETDEWEB)

    Sauer, Christopher R. [President & CEO; McEntee, Jarlath [VP Engineering & CTO

    2013-12-30

    ORPC Maine, LLC, a wholly-owned subsidiary of Ocean Renewable Power Company, LLC (collectively ORPC), submits this Final Technical Report for the TidGen® Power System Commercialization Project (Project), partially funded by the U.S. Department of Energy (DE-EE0003647). The Project was built and operated in compliance with the Federal Energy Regulatory Commission (FERC) pilot project license (P-12711) and other permits and approvals needed for the Project. This report documents the methodologies, activities and results of the various phases of the Project, including design, engineering, procurement, assembly, installation, operation, licensing, environmental monitoring, retrieval, maintenance and repair. The Project represents a significant achievement for the renewable energy portfolio of the U.S. in general, and for the U.S. marine hydrokinetic (MHK) industry in particular. The stated Project goal was to advance, demonstrate and accelerate deployment and commercialization of ORPC’s tidal-current based hydrokinetic power generation system, including the energy extraction and conversion technology, associated power electronics, and interconnection equipment capable of reliably delivering electricity to the domestic power grid. ORPC achieved this goal by designing, building and operating the TidGen® Power System in 2012 and becoming the first federally licensed hydrokinetic tidal energy project to deliver electricity to a power grid under a power purchase agreement in North America. Located in Cobscook Bay between Eastport and Lubec, Maine, the TidGen® Power System was connected to the Bangor Hydro Electric utility grid at an on-shore station in North Lubec on September 13, 2012. ORPC obtained a FERC pilot project license for the Project on February 12, 2012 and the first Maine Department of Environmental Protection General Permit issued for a tidal energy project on January 31, 2012. In addition, ORPC entered into a 20-year agreement with Bangor Hydro Electric

  16. 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

  17. Basic research in support of innovative fuels design for the Generation IV systems (F-BRIDGE project)

    International Nuclear Information System (INIS)

    Valot, Carole; Bertolus, Marjorie; Konings, Rudy; Somers, Joe; Groot, Sander de

    2010-01-01

    F-BRIDGE (Basic Research in support of Innovative Fuels Design for the GEN IV systems) is a 4-year project which started in 2008. It seeks to bridge the gap between basic research and technological applications for generation IV nuclear reactor systems. One of the challenges for the next generation of reactors is to significantly increase the efficiency in designing innovative fuels. The object of the F-BRIDGE project is to complement the empirical approach by a physically-based description of fuel and cladding materials to enable a rationalization of the design process and a better selection of promising fuel systems. Advanced modelling and separate effects experiments are carried out in order to obtain more exact physical descriptions of ceramic fuels and cladding, at relevant scales from the atomic to the macroscopic scale. Research is also focused on assessing and improving 'sphere-pac' fuel, a composite-ceramics concept which has shown promise. The project activities can be broken down into four main areas: (i) Basic research investigations using a multi-scale approach in both experimentation and modelling to enable the generation of missing basic data, the identification of relevant mechanisms and the development of appropriate models; (ii) Transfer between technological issues and basic research by bringing together within the same project materials scientists, engineers and end-users; (iii) Assessment of the drawbacks and benefits of the sphere-pac fuel application to various Generation IV systems; (iv) Education and training to promote research in the field of fuel materials, to ensure the exchange of results and ideas among the participants and to link the project with other related European or international initiatives. The project relies on the complementary expertise of 19 partners: nuclear and non nuclear research organisations, universities, a nuclear engineering company, as well as technology and project management consultancy small and medium

  18. 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.)

  19. Diaquatetrabromidotin(IV trihydrate

    Directory of Open Access Journals (Sweden)

    Fei Ye

    2012-09-01

    Full Text Available The title compound, [SnBr4(H2O2]·3H2O, forms large colourless crystals in originally sealed samples of tin tetrabromide. It constitutes the first structurally characterized hydrate of SnBr4 and is isostructural with the corresponding hydrate of SnCl4. It is composed of SnIV atoms octahedrally coordinated by four Br atoms and two cis-related water molecules. The octahedra exhibit site symmetry 2. They are arranged into columns along [001] via medium–strong O—H...O hydrogen bonds involving the two lattice water molecules (one situated on a twofold rotation axis while the chains are interconnected via longer O—H...Br hydrogen bonds, forming a three-dimensional network.

  20. Cyclopentadienyluranium(IV) acetylacetonates

    International Nuclear Information System (INIS)

    Bagnall, K.W.; Edwards, J.; Rickard, C.E.F.; Tempest, A.C.

    1979-01-01

    Cyclopentadienyluranium(IV) acetylacetonate complexes, (eta 5 C 5 H 5 )UClsub(3-x)(acac)sub(x), where x = 1 or 2, and the corresponding bis triphenylphosphine oxide (tppo) complexes have been prepared. The bis cyclopentadienyl complexes, (eta 5 C 5 H 5 ) 2 U(acac) 2 and (eta 5 C 5 H 5 ) 2 UCl(acac)(tppo) 2 have also been prepared and are stable with respect to disproportionation, whereas (eta 5 C 5 H 5 ) 2 UCl(acac) is not. The IR and UV/visible spectra of the complexes are reported, together with some additional information on the UCl 2 (acac) 2 thf and -tppo systems. (author)

  1. 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…

  2. Caracterización clínico genética del síndrome Prader Willi

    OpenAIRE

    Travieso Tellez, Anitery; Menéndez García, Reinaldo; Licourt Otero, Deysi

    2014-01-01

    Introducción: el síndrome Prader Willi es un desorden genético causado por la pérdida de genes contenidos en la región 15q11-q13 del cromosoma paterno. Objetivo: describir las características clínicas y genéticas de los pacientes con síndrome Prader Willi. Material y método: se realizó un estudio descriptivo, de corte transversal, con el universo de 15 pacientes con sospecha de síndrome Prader Willi remitidos a consulta provincial de Genética Clínica durante el año 2013. Se consideraron como ...

  3. 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

  4. 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.

  5. 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…

  6. Tadaridanema delicatus (Schwartz, 1927) n. gen., n. comb. (Trichostrongylina: Molineidae) parasite of Molossidae bats.

    Science.gov (United States)

    Falcón-Ordaz, Jorge; Guzmán-Cornejo, Carmen; García-Prieto, Luis; Gardner, Scott Lyell

    2006-10-01

    On the basis of the revision of the type material of Anoplostrongylus delicatus Schwartz, 1927, and new specimens collected from Tadarida brasiliensis mexicana (Saussure, 1860) in 4 arid localities from Mexico, we describe a new genus (Tadaridanema n. gen.), to which A. delicatus is transferred (as Tadaridanema delicatus (Schwartz, 1927) n. gen., n. comb.). This new genus differs from all other genera included in Anoplostrongylinae by having ray 2 larger than ray 3. In addition, T. delicatus can be differentiated from the type species of Anoplostrongylus (Anoplostrongylus paradoxus (Travassos, 1918)) because it possess vestibular branches equal in length, cephalic inflation divided into 2 regions, and synlophe with many small ridges at the midbody level, whereas in T. delicatus, vestibular branches are equal in size, cephalic inflation is simple in structure, and the synlophe has only 2 well-developed dorsal cuticular ridges.

  7. Heat and power from MicroGen

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1999-10-01

    This paper reports on the design of a domestic gas-fired cogeneration system developed to replace the central heating boiler. Technical details of the MicroGen demonstration unit are given, and the use of a Linear Free Piston Stirling Engine as the prime mover, and the results of modelling studies of energy demand indicating cost savings compared to conventional boilers are discussed. The enhancement of the benefits of micro-cogeneration through use of thermal and power storage and energy demand management, and the impact of micro-cogeneration on energy use in the home are considered. The UK and European Commission's targets for increased cogeneration capacity are noted.

  8. NextGen Future Safety Assessment Game

    Science.gov (United States)

    Ancel, Ersin; Gheorghe, Adrian; Jones, Sharon Monica

    2011-01-01

    The successful implementation of the next generation infrastructure systems requires solid understanding of their technical, social, political and economic aspects along with their interactions. The lack of historical data that relate to the long-term planning of complex systems introduces unique challenges for decision makers and involved stakeholders which in turn result in unsustainable systems. Also, the need to understand the infrastructure at the societal level and capture the interaction between multiple stakeholders becomes important. This paper proposes a methodology in order to develop a holistic approach aiming to provide an alternative subject-matter expert (SME) elicitation and data collection method for future sociotechnical systems. The methodology is adapted to Next Generation Air Transportation System (NextGen) decision making environment in order to demonstrate the benefits of this holistic approach.

  9. 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

  10. The GenDev Curriculum Development Workshop.

    Science.gov (United States)

    D'cunha, J

    1997-01-01

    This article describes the second Curriculum Development Workshop held in May 1997 at the Asian Institute of Technology (AIT) in Bangkok, Thailand. The workshop aimed to review critically and restructure the Gender and Development Studies (GenDev) curriculum and to assess AIT's role in training gender experts for the region. Participants included 22 people from 16 countries in Asia, Europe, and the US who were teaching graduate students about gender issues and who were activists with nongovernmental organizations working on gender issues. It was determined that the following were required courses: Culture, Knowledge and Gender Relations; Gender, Technology, and Development; Principles of Gender Research and Methodology in Science and Technology; and Gender Analysis and Field Methods. Other suggested core courses included: Gender and Natural Resource Management; Enterprise Management, Technology, and Gender; Gender and Agrarian Reform; Urbanization: A Gender Perspective; Gender-Responsive Development Planning; and Gender and Economic Change: Past and Present Concerns. Participants distinguished between GenDev courses offered to anyone attending AIT and training courses designed to produce gender experts in the region. The aim of training courses for AIT graduate students was to sensitize potential managers, technologists, and others on gender issues and to create awareness of the importance of including gender perspectives within decision-making, policy formation, and implementation. Training courses to produce gender experts should be directed to those with a prior background in gender studies and include gender analysis in field methods. Participants agreed that there should be an independent and autonomous field of gender and development studies. Participants made six recommendations for such a field of study.

  11. 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.)

  12. Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward

    International Nuclear Information System (INIS)

    Turchi, P.E.; Kaufman, L.; Fluss, M.J.

    2008-01-01

    The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an entire report is dedicated to it. Then, in a second part, with the specific LIFE specifications in mind, the various fuel options with their most critical issues are revisited with a path forward for each of them in terms of research, both experimental and theoretical. Since LIFE is applicable to very high burn-up of various fuels, distinctions will be made depending on the mission, i.e., energy production or incineration. Finally a few conclusions are drawn in terms of the specific needs for integrated materials modeling and the in depth knowledge on time-evolution thermochemistry that controls and drastically affects the performance of the nuclear materials and their immediate environment. Although LIFE demands materials that very likely have not yet been fully optimized, the challenge are not insurmountable and a well concerted experimental-modeling effort should lead to dramatic advances that should well serve other fission programs such as Gen-IV, GNEP, AFCI as well as the international fusion program, ITER

  13. Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    Turchi, P E; Kaufman, L; Fluss, M J

    2008-11-10

    The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an entire report is dedicated to it. Then, in a second part, with the specific LIFE specifications in mind, the various fuel options with their most critical issues are revisited with a path forward for each of them in terms of research, both experimental and theoretical. Since LIFE is applicable to very high burn-up of various fuels, distinctions will be made depending on the mission, i.e., energy production or incineration. Finally a few conclusions are drawn in terms of the specific needs for integrated materials modeling and the in depth knowledge on time-evolution thermochemistry that controls and drastically affects the performance of the nuclear materials and their immediate environment. Although LIFE demands materials that very likely have not yet been fully optimized, the challenge are not insurmountable and a well concerted experimental-modeling effort should lead to dramatic advances that should well serve other fission programs such as Gen-IV, GNEP, AFCI as well as the international fusion program, ITER.

  14. 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

  15. Glycogen Storage Disease Type IV

    DEFF Research Database (Denmark)

    Bendroth-Asmussen, Lisa; Aksglaede, Lise; Gernow, Anne B

    2016-01-01

    molecular genetic analyses confirmed glycogen storage disease Type IV with the finding of compound heterozygosity for 2 mutations (c.691+2T>C and c.1570C>T, p.R524X) in the GBE1 gene. We conclude that glycogen storage disease Type IV can cause early miscarriage and that diagnosis can initially be made...

  16. 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 ...

  17. 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 ...

  18. 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

  19. 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

  20. 3D flow simulation of liquid lead in the erosion test facility for ADS materials

    International Nuclear Information System (INIS)

    Muscher, Heinrich; Kieser, Martin; Weisenburger, Alfons; Mueller, Georg

    2009-01-01

    Future nuclear reactor concepts, such as GEN IV or ADS use liquid lead for neutron multiplication and coolant purposes. The design concepts assumes that the structural material is in contact with the liquid metal at temperatures up to 600 C and a flow rate of 20 m/s. Therefore a significant effect of liquid metal corrosion/erosion is expected. The paper describes the fluid dynamical simulation of the ADS erosion test facility. Earlier studies on the laminar flow modeling were completed by introduction of transient behavior and extended to 3D-models. The results for liquid lead should be transferable to LBE (lead bismuth eutectic). Further work has to include a mass transport model for modeling of the global isothermal erosion rate of the structural material dependent on time (for liquid lead and LBE).

  1. Diffusion, Thermal Properties and Chemical Compatibilities of Select MAX Phases with Materials For Advanced Nuclear Systems

    Energy Technology Data Exchange (ETDEWEB)

    Barsoum, Michel [Drexel Univ., Philadelphia, PA (United States); Bentzel, Grady [Drexel Univ., Philadelphia, PA (United States); Tallman, Darin J. [Drexel Univ., Philadelphia, PA (United States); Sindelar, Robert [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Garcia-Diaz, Brenda [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hoffman, Elizabeth [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-04-04

    The demands of Gen IV nuclear power plants for long service life under neutron irradiation at high temperature are severe. Advanced materials that would withstand high temperatures (up to 1000+ ºC) to high doses in a neutron field would be ideal for reactor internal structures and would add to the long service life and reliability of the reactors. The objective of this work is to investigate the chemical compatibility of select MAX with potential materials that are important for nuclear energy, as well as to measure the thermal transport properties as a function of neutron irradiation. The chemical counterparts chosen for this work are: pyrolytic carbon, SiC, U, Pd, FLiBe, Pb-Bi and Na, the latter 3 in the molten state. The thermal conductivities and heat capacities of non-irradiated MAX phases will be measured.

  2. 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

  3. Sorption of radionuclides on mesoporous Sn(IV) silicate: a new sorbent

    Energy Technology Data Exchange (ETDEWEB)

    Sepehrian, H. [Jaber Ibn Hayan Research Labs., Nuclear Science and Technology Research Inst., AEOI, Tehran (Iran); Dept. of Applied Chemistry, Univ. of Tarbiat Moallem, Tehran (Iran); Yavari, R.; Ghannadi Maragheh, M. [Jaber Ibn Hayan Research Labs., Nuclear Science and Technology Research Inst., AEOI, Tehran (Iran); Husain, S.W. [Dept. of Applied Chemistry, Univ. of Tarbiat Moallem, Tehran (Iran)

    2008-07-01

    Four different samples of mesoporous Sn(IV) silicate with varying mole ratio of Si/Sn have been used to study the sorption behavior of 18 radionuclides on these materials. Ion-exchange capacity, SEM, distribution coefficient and chemical stability have been studied and discussed. Separation of Tl(I) from Th(IV), Cs(I) from Th(IV) and Cs(I) from Zr(IV) have been developed on columns of this sorbent. (orig.)

  4. Sorption of radionuclides on mesoporous Sn(IV) silicate: a new sorbent

    International Nuclear Information System (INIS)

    Sepehrian, H.; Yavari, R.; Ghannadi Maragheh, M.; Husain, S.W.

    2008-01-01

    Four different samples of mesoporous Sn(IV) silicate with varying mole ratio of Si/Sn have been used to study the sorption behavior of 18 radionuclides on these materials. Ion-exchange capacity, SEM, distribution coefficient and chemical stability have been studied and discussed. Separation of Tl(I) from Th(IV), Cs(I) from Th(IV) and Cs(I) from Zr(IV) have been developed on columns of this sorbent. (orig.)

  5. O papel de marcadores moleculares na genética forense

    Directory of Open Access Journals (Sweden)

    Daniele Decanine

    2016-07-01

    Full Text Available O objetivo desse trabalho foi apresentar uma revisão bibliográfica sobre as tecnologias utilizadas na Genética Forense, enfatizando o uso de marcadores moleculares para a identificação humana. Apresento aqui alguns exemplos do potencial da Biologia Molecular para auxiliar na investigação criminal, bem como na definição de parentesco (maternidade e paternidade. A utilização desses marcadores é atualmente a peça fundamental para os testes de DNA forense. Estes sistemas são, na sua maioria, baseados na análise de painéis de sequências microssatélites específicas (STRs. Foi possível discorrer sobre o uso forense do DNA, sobre a presença de regiões hipervariáveis no material genético, o papel de marcadores moleculares, bem como abordar técnicas de análise de DNA e suas aplicações. A busca por novas metodologias se faz importante para reduzir os custos e impulsionar uma nova cultura genética na Ciência Forense, as quais terão impacto no futuro do DNA forense com a expansão da Biologia Molecular.

  6. Status of the Polyhedral Mesh Generator using SALOME PLATFORM and TetGen

    International Nuclear Information System (INIS)

    Lee, Sang Yong; Park, Chan Eok; Kim, Shin Whan

    2014-01-01

    Recently developed porous body approach codes such as SPACE and CUPID require a CAD system to estimate the porosity. Since they 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 described for the efforts to combine TetGen with it. In section 2, brief introduction will be made on the CAD and mesh generation capability of SALOME and Tetgen. SALOME and TetGen codes are being integrated to construct robust polyhedral mesh generator. Procedures to merge boundary faces and to cut concave cells are developed to remove concave cells to get final convex polyhedral mesh. Treating the internal boundary face, i.e. non-manifold face will be the next task in the future investigation

  7. TrayGen: Arranging objects for exhibition and packaging

    KAUST Repository

    Yang, Yongliang; Huang, Qixing

    2013-01-01

    We present a framework, called TrayGen, to generate tray designs for the exhibition and packaging of a collection of objects. Based on principles from shape perception and visual merchandising, we abstract a number of design guidelines on how

  8. 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.

  9. 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...

  10. Parapedobacter koreensis gen. nov., sp. nov.

    Science.gov (United States)

    Kim, Myung Kyum; Na, Ju-Ryun; Cho, Dong Ha; Soung, Nak-Kyun; Yang, Deok-Chun

    2007-06-01

    Strain Jip14(T), a Gram-negative, non-spore-forming, rod-shaped, non-motile bacterium, was isolated from dried rice straw and characterized in order to determine its taxonomic position. 16S rRNA gene sequence analysis revealed that strain Jip14(T) belongs to the family Sphingobacteriaceae, and the highest degree of sequence similarity was determined to be to Pedobacter saltans DSM 12145(T) (88.5 %), Pedobacter africanus DSM 12126(T) (87.6 %), Pedobacter heparinus DSM 2366(T) (87.1 %) and Pedobacter caeni LMG 22862(T) (86.9 %). Chemotaxonomic data revealed that strain Jip14(T) possesses menaquinone MK-7 and the predominant fatty acids C(15 : 0) iso, C(16 : 0), C(16 : 0) 10-methyl, C(17 : 0) iso 3-OH and summed feature 3 (C(15 : 0) iso 2-OH/C(16 : 1)omega7c). The results of physiological and biochemical tests clearly demonstrated that strain Jip14(T) represents a distinct species. Based on these data, Jip14(T) should be classified within a novel genus and species, for which the name Parapedobacter koreensis gen. nov., sp. nov. is proposed. The type strain of Parapedobacter koreensis is Jip14(T) (=KCTC 12643(T)=LMG 23493(T)).

  11. Banque Cantonale de Genève

    CERN Multimedia

    Banque Cantonale de Genève

    2011-01-01

    7e Salon Immobilier BCGE le samedi 3 septembre 2011, de 8 h 30 à 13 h 00, au Centre de formation de Conches À cette occasion, les meilleurs spécialistes professionnels genevois de l’immobilier seront réunis en un seul et même lieu. Si vous le souhaitez, un conseiller spécialisé dans les financements hypothécaires évaluera vos possibilités d’investissement immobilier adaptées à votre situation personnelle. En parallèle, les plus importantes régies immobilières de Genève seront à votre disposition pour vous présenter leurs offres actuelles, ainsi que les projets immobiliers futurs et discuter avec vous de la meilleure stratégie à adopter pour trouver l’objet de vos rêves. De plus, vous aurez la possibilité...

  12. Book of abstracts Chemical Engineering: IV All-Russian Conference on chemical engineering, All-Russian Youth Conference on chemical engineering, All-Russian school on chemical engineering for young scientists and specialists. Engineering of polymers and composite materials. Catalysis in chemical engineering

    International Nuclear Information System (INIS)

    Zakhodyaeva, Yu.A.; Belova, V.V.

    2012-01-01

    In the given volume of abstracts of the IV All-Russian Conference on chemical engineering, All-Russian Youth Conference on chemical engineering, All-Russian school on chemical engineering for young scientists and specialists (Moscow, March 18-23, 2012) there are the abstracts of the reports concerning polymer and composite materials technology as well as catalysis in chemical engineering. The abstracts deal with state-of-the-art and future development of theoretical and experimental investigations as well as with experience in practical realization of development works in the field of chemical engineering and relative areas [ru

  13. Book of abstracts Chemical Engineering: IV All-Russian Conference on chemical engineering, All-Russian Youth Conference on chemical engineering, All-Russian school on chemical engineering for young scientists and specialists. Plenary reports. Engineering of inorganic substances and materials

    International Nuclear Information System (INIS)

    Zakhodyaeva, Yu.A.; Belova, V.V.

    2012-01-01

    In the given volume of abstracts of the IV All-Russian Conference on chemical engineering, All-Russian Youth Conference on chemical engineering, All-Russian school on chemical engineering for young scientists and specialists (Moscow, March 18-23, 2012) there are the abstracts of the reports concerning chemical engineering of inorganic substances and materials. The abstracts deal with state-of-the-art and future development of theoretical and experimental investigations as well as with experience in practical realization of development works in the field of chemical engineering and relative areas [ru

  14. Book of abstracts Chemical Engineering: IV All-Russian Conference on chemical engineering, All-Russian Youth Conference on chemical engineering, All-Russian school on chemical engineering for young scientists and specialists. Materials of All-Russian Symposium on chemistry and extraction engineering. Chemical-metallurgical processes of ore and secondary raw material processing. Analytical control of chemical industries, man-made and natural objects

    International Nuclear Information System (INIS)

    Zakhodyaeva, Yu.A.; Belova, V.V.

    2012-01-01

    In the given volume of abstracts of the IV All-Russian Conference on chemical engineering, All-Russian Youth Conference on chemical engineering, All-Russian school on chemical engineering for young scientists and specialists (Moscow, March 18-23, 2012) there are the abstracts of the reports concerning polymer and composite materials technology as well as catalysis in chemical engineering. The abstracts deal with state-of-the-art and future development of theoretical and experimental investigations as well as with experience in practical realization of development works in the field of chemical engineering and relative areas [ru

  15. Optimización topológica mediante algoritmos genéticos, estrategias evolutivas y el método de Baluja

    OpenAIRE

    Estupiñan, J.; Oñate, E.; Suárez, B.

    1998-01-01

    El trabajo presenta la aplicación de varios mdtodos evolutivos al campo de la optimización topológica de estructuras. El trabajo desarrollado se basa en la búsqueda de una distribución de material dentro de un dominio específico y bajo unas condiciones de contorno concretas. Los algoritmos evolutivos obedecen a las leyes de superviviencia del mejor dotado de Darwiri y a su base genético molecular: mutación y recombinación del material genético. Los métodos evolutivos (ME) que se presentan ...

  16. Genetic diversity of the VP1/VP2 gene of canine parvovirus type 2b amplified from clinical specimens in Brazil Diversidade genética no gene VP1/VP2 do parvovirus canino tipo 2b amplificado de material clínico no Brasil

    Directory of Open Access Journals (Sweden)

    Cesar A. D. Pereira

    2000-10-01

    Full Text Available We evaluated the genetic diversity in the VP1/VP2 gene of CPV type 2b isolates from symptomatic dogs in Brazil. A total of 21 isolates collected from 1990 through 1995 previously typed as CPV2b by PCR assay were studied. Overall we found a high degree of similarity among sequences from different CPV clinical isolates collected. Genetic analysis of this selected region gave no indication of a specific Brazilian parvovirus lineage.Neste estudo foi avaliada a diversidade genética no gene VP1/VP2 do parvovírus canino tipo 2b a partir de amostras isoladas de cães sintomáticos no Brasil. Foram estudadas 21 amostras coletadas no período de 1990 à 1995, previamente caracterizadas como CPV 2b pela técnica de PCR. Observou-se alto grau de similaridade entre as seqüências estudadas e a análise genética da região selecionada não indicou a presença de uma linhagem brasileira específica.

  17. Aircraft engines. IV

    Energy Technology Data Exchange (ETDEWEB)

    Ruffles, P C

    1989-01-01

    Configurational design and thermodynamic performance gain trends are projected into the next 50 years, in view of the growing interest of aircraft manufacturers in both larger and more efficient high-bypass turbofan engines for subsonic flight and variable cycle engines for supersonic flight. Ceramic- and metal-matrix composites are envisioned as the key to achievement of turbine inlet temperatures 300 C higher than the 1400 C which is characteristic of the state-of-the-art, with the requisite high stiffness, strength, and low density. Such fiber-reinforced materials can be readily tailored to furnish greatest strength in a specific direction of loading. Large, low-density engines are critical elements of future 1000-seat aircraft.

  18. 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.

  19. ARIES-IV Nested Shell Blanket Design

    International Nuclear Information System (INIS)

    Wong, C.P.C.; Redler, K.; Reis, E.E.; Will, R.; Cheng, E.; Hasan, C.M.; Sharafat, S.

    1993-11-01

    The ARIES-IV Nested Shell Blanket (NSB) Design is an alternate blanket concept of the ARIES-IV low activation helium-cooled reactor design. The reference design has the coolant routed in the poloidal direction and the inlet and outlet plena are located at the top and bottom of the torus. The NSB design has the high velocity coolant routed in the toroidal direction and the plena are located behind the blanket. This is of significance since the selected structural material is SiC-composite. The NSB is designed to have key high performance components with characteristic dimensions of no larger than 2 m. These components can be brazed to form the blanket module. For the diverter design, we eliminated the use of W as the divertor coating material by relying on the successful development of the gaseous divertor concept. The neutronics and thermal-hydraulic performance of both blanket concepts are similar. The selected blanket and divertor configurations can also meet all the projected structural, neutronics and thermal-hydraulics design limits and requirements. With the selected blanket and divertor materials, the design has a level of safety assurance rate of I (LSA-1), which indicates an inherently safe design

  20. Inicio de replicación y estabilidad genómica en Saccharomyces cerevisiae

    OpenAIRE

    Ayuda Durán, Pilar

    2014-01-01

    [ES]La levadura de gemación Saccharomyces cerevisiae constituye un buen sistema modelo para el estudio de los mecanismos que dirigen la replicación del material genético y controlan su estabilidad en organismos eucariotas. Utilizando este modelo se ha estudiado el efecto de la desregulación de actividad CDK durante la fase G1 del ciclo celular de esta levadura, a causa de la carencia de sus reguladores específicos (las proteínas Cdh1, Sic1 y el dominio N-terminal de la proteína Cdc6). L...

  1. Selection and challenges for LFR reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    Weisenburger, A.; Jianu, A.; Del Giacco, M.; Fetzer, R.; Heinzel, A.; Mueller, G. [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany). Inst. for Pulsed Power and Microwave Technology

    2013-07-01

    Nuclear energy using Fast GenIV reactors can fulfil future demands concerning CO2 free, base load capability and sustainability. One of the most promising coolants especially due to its high thermal inertia is liquid lead (Pb). Since several years researches all over the world investigate this coolant and its impact on the reactor design and by that on the materials to be selected. The LEADER project, a follow up of ELSY, aims to design a prototypical demonstrator ALFRED and to continue with several design related aspects of the ELFR reactor. For a demonstrator the criteria of material selection are somewhat different to a commercial type like the ELFR. Material selection for ELFR of course considers all the aspects relevant for ALFRED plus the targeted burn up and the expected total dpa related damage especially of the fuel pins. In the past compatibility of structural material (steels like 316L, T91 and 15-15Ti (1.4970)) that can be employed for Pb cooled fast nuclear reactors were investigated in several EU projects like EUROTRANS and worldwide. Solubility of steel alloying elements like Ni, Fe, Cr is the driving force for the reduced corrosion resistance in contact with Pb. In-situ oxidation is the acknowledged measure to protect steels in Pb up to certain temperatures that are material dependent. Based on experiments and the derived temperature limits the average core outlet temperatures of ALFRED and the ELFR are set to 480 C. The most challenging conditions with respect to temperature are at the fuel assembly and the heat exchangers. For both, thin stable oxide scales with negligible reduction in heat transfer are the requested protection method. This presentation will give an overview on the selected materials for ALFRED and ELFR considering, beside pure compatibility, the influence of mechanical interaction like creep and fretting. (orig.)

  2. Heterogeneidad clínica y genética en pacientes con retinosis pigmentaria en Pinar del Río. Importancia del asesoramiento genético

    Directory of Open Access Journals (Sweden)

    Nercy Rodríguez Garcia

    2013-12-01

    Full Text Available Introducción: la retinosis pigmentaria (RP es una degeneración progresiva, crónica y de carácter hereditario de la retina, que conduce a discapacidad visual o ceguera sin un tratamiento adecuado. Objetivo: determinar la variabilidad de la expresión clínica en la presentación de la retinosis pigmentaria, así como el tipo de herencia con que se transmite en los enfermos y familias de los individuos ingresados en el servicio provincial de la enfermedad en Pinar del Río, lo que permitirá aplicar una estrategia para el asesoramiento genético individual y familiar. Material y Método: se realizó una investigación descriptiva, retrospectiva y transversal, teniendo como universo y muestra a los 259 pacientes con diagnóstico del padecimiento, registrados en el servicio provincial, de enero a septiembre del año 2012. Resultados: predominó el sexo masculino con 154 pacientes y el grupo de edades entre 40 y 59 años de edad con un 46,71 %. De acuerdo a la clasificación cubana, prevalece el debut precoz, el estadio I, la herencia autosómica recesiva y la forma típica de presentación. Resaltan el síndrome de Usher como entidad asociada y en 99 familias se determinó que la enfermedad sigue un patrón de herencia autosómico recesivo, en 38 de las cuales existe consanguinidad. Las limitaciones de estos enfermos obligan a suministrarles una información adecuada y precisa mediante los servicios de asesoramiento genético. Conclusiones: la gran heterogeneidad clínica y genética de la enfermedad ha generado que la estrategia de asesoramiento genético incluya la personalización del proceso de acuerdo a cada paciente y familia y se le brinde mayor importancia a los grupos de apoyo mutuo.

  3. 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

  4. 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

  5. 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.

  6. ANALISIS GEN HAEMAGGLUTININ PADA VIRUS CAMPAK LIAR

    Directory of Open Access Journals (Sweden)

    Subangkit Subangkit

    2015-05-01

    Full Text Available AbstrakPenyakit Campak disebabkan oleh virus campak yang termasuk genus Morbilivirus dan Family Paramyxoviridae. Penyakit campak masih menjadi masalah kesehatan karena masih ditemukan Kejadian Luar Biasa (KLB di Indonesia. Salah satu penyebab terjadinya KLB tersebut diduga sebagaiakibat perbedaan antigenesitas antara strain vaksin yang digunakan dengan strain virus campak liar yang beredar di Indonesia. Penelitian ini bertujuan mendapatkan gambaran tentang karakteristik genetik gen Haemagglutinin virus campak liar yang ada di Indonesia. Spesimen yang digunakan sebanyak 27 isolat virus penyebab KLB dari 17 propinsi selama periode tahun 2003-2010. Isolat virus dilakukan pemeriksaan secara RT-PCR dan sekuensing dengan metode Sanger. Hasil sekuensing dianalisis dengan menggunakan perangkat lunak Bioedit 7.0 dan MEGA 4.0. Hasil penelitian didapatkan perbedaan 10 asam amino antara virus campak strain vaksin CAM-70 dan virus campak liar pada posisi D416N; K424T; V451M; N455T; V466I; I473T; F476L; Y481S atau Y481N; H495N; G505D. Kesimpulan penelitian ini adalah terdapat perbedaan karakteristik genetik antara virus campak liar di Indonesia berbeda dengan strain virus vaksin CAM-70.Kata kunci : Campak, Analisis Molekuler, Hemagglutinin, CD46AbstractMeasles is caused by virus belonging to the genus Morbilivirus and Family Paramyxoviridae. Measles is still a public health problem because outbreak of measles still found in Indonesia. Outbreak is suspected as a result of differences in antigenicity between vaccine strains used with wild-type measles virus strains circulating in Indonesia. This study aims to get genetic characteristics of wild-type measles virus haemagglutinin gene in Indonesia. The specimens were used 27 viral isolates from 17 provinces period 2003-2010. Viral isolates examined by RT-PCR and sequencing with Sanger method. Sequencing analysis were conducted using Bioedit 7.0 and MEGA 4.0 software. The results showed 10 amino acid differences

  7. Free-format RPG IV

    CERN Document Server

    Martin, Jim

    2013-01-01

    This how-to guide offers a concise and thorough introduction to the increased productivity, better readability, and easier program maintenance that comes with the free-format style of programming in RPG IV. Although free-format information is available in IBM manuals, it is not separated from everything else, thereby requiring hours of tedious research to track down the information needed. This book provides everything one needs to know to write RPG IV in the free-format style, and author Jim Martin not only teaches rules and syntax but also explains how this new style of coding has the pot

  8. Biotecnologia aplicada ao melhoramento genético do cafeeiro Biotechnology applied to the genetic improvement of coffee plant

    Directory of Open Access Journals (Sweden)

    Tâmara Prado de Morais

    2011-05-01

    Full Text Available O melhoramento genético do cafeeiro mediante técnicas convencionais é trabalhoso e demorado. A biotecnologia oferece estratégias alternativas para auxiliar na multiplicação e no desenvolvimento de novas variedades com resistência a estresses bióticos e abióticos, melhor qualidade de bebida e maturação mais uniforme dos frutos. As técnicas de cultura de tecidos têm possibilitado a obtenção de grande número de plantas e a garantia da uniformidade genética do material. O emprego de marcadores moleculares, principalmente através da seleção assistida, facilitou o rápido progresso do melhoramento genético da cultura, assim como a transformação genética, via cultura e fusão de protoplastos, biobalística ou mediada por Agrobacterium sp. Esta revisão objetiva sumarizar o histórico, situação atual e perspectivas da biotecnologia no melhoramento genético do cafeeiro.Genetic improvement of coffee through classical breeding is laborious and time consuming. Biotechnology offers alternative strategies to assist multiplication and development of new and improved coffee varieties, including those resistant to biotic and abiotic stresses, with better cup quality, and with uniform fruit maturation. Tissue culture techniques have enabled the production of a large number of plants with genetic uniformity. The use of molecular markers, especially through assisted selection, led to rapid progress of coffee plant breeding, as well as the use of genetic transformation by protoplasts culture and fusion, biobalistics, or Agrobacterium-mediated. This review provides a summary of biotechnology history, current situation and directions applied to the genetic improvement of coffee plant.

  9. Variabilidade genética de Genipa americana L. pertencente ao baixo curso do rio São Francisco

    Directory of Open Access Journals (Sweden)

    Allívia Rouse Carregosa Rabbani

    2012-06-01

    Full Text Available A utilização de marcadores genéticos em estudos de caracterização de ecossistemas florestais permite avanços no entendimento genético das populações naturais, bem como auxilia na definição de estratégias de recuperação ou restauração florestal. Este trabalho foi realizado com o objetivo de avaliar a diversidade genética entre 18 indivíduos de Jenipapo (Genipa americana L. procedentes da região do Baixo São Francisco sergipano por meio de marcadores RAPD. Para a amplificação do material genético foram utilizados 12 oligonucleotídeos para análise da diversidade. Pelo índice de Jaccard, a similaridade genética média (Sgm entre os indivíduos foi de 60,4% sendo que, a maior obtida foi identificada entre os indivíduos G11 e G12 (83,6%±0,03 e a menor entre os indivíduos G4 e G18 (36,5%, ±0,02. Com base na Sgm (78,4%, sete pares indivíduos foram considerados geneticamente semelhantes. A partir destas análises, os indivíduos podem ser utilizados como matrizes fornecedoras de sementes em combinação com outros indivíduos em programas de restauração de áreas degradadas, porém devem compor áreas distantes.

  10. Aplicación de la biotecnología en los recursos genéticos forestales

    Directory of Open Access Journals (Sweden)

    R. Martínez

    2003-01-01

    Full Text Available A medida que aumenta la población y sus demandas de productos forestales, las tierras disponibles para la producción disminuyen, por lo que se necesitan esfuerzos coordinados para conseguir la sostenibilidad de la producción forestal. Aunque los sistemas tradicionales de silvicultura y mejoramiento genético continúan siendo importantes en las actividades forestales actuales, los programas convencionales de mejoramiento genético se ven limitados por el largo ciclo de desarrollo de los árboles forestales y la dificultad para distinguir siempre entre la expresión genotípica y los efectos ambientales. La biotecnología ofrece nuevas técnicas que complementan a las metodologías tradicionales del mejoramiento genético forestal. Los avances importantes de la técnica de cultivo de tejidos vegetales y la biología molecular que han tenido lugar en las dos últimas décadas se encuentran en la base del desarrollo de campos como la crioconservación y la regeneración masiva de plantas (expresión de la totipotencia celular, los marcadores de ADN, la genómica de árboles y la transformación genética. En el ámbito de los recursos genéticos, los marcadores de ADN permiten caracterizar la naturaleza, amplitud y distribución de la variabilidad genética de especies vegetales, y por tanto, facilitan la toma de decisiones sobre qué y cómo preservar. La crioconservación y la regeneración de plantas in vitro se están utilizando para conservar y micropropagar material vegetal específico, a fin de llevar a cabo la conservación ex situ y permitir el desarrollo de la silvicultura clonal. En este trabajo se realiza una revisión de las aplicaciones de estos campos a las especies forestales. En este contexto se aporta información sobre la actividad de la biotecnología forestal en las diferentes áreas de investigación.

  11. A spallation-based irradiation test facility for fusion and future fission materials

    International Nuclear Information System (INIS)

    Samec, K.; Fusco, Y.; Kadi, Y.; Luis, R.; Romanets, Y.; Behzad, M.; Aleksan, R.; Bousson, S.

    2014-01-01

    The EU's FP7 TIARA program for developing accelerator-based facilities has recently demonstrated the unique capabilities of a compact and powerful spallation source for irradiating advanced nuclear materials. The spectrum and intensity of the neutron flux produced in the proposed facility fulfils the requirements of the proposed DEMO fusion reactor, ADS reactors and also Gen III / IV reactors. Test conditions can be modulated, covering temperature from 400 to 550 deg. C, liquid metal corrosion, cyclical or static stress up to 500 MPa and neutron/proton irradiation damage of up to 25 DPA per annum over a volume occupying one litre. The entire 'TMIF' facility fits inside a cube 2 metres on a side, and is dimensioned for an accelerator beam power of 100 kW, thus reducing costs and offering great versatility and flexibility. (authors)

  12. Impact of material thicknesses on fission observables obtained with the FALSTAFF experimental setup

    Directory of Open Access Journals (Sweden)

    Thulliez L.

    2017-01-01

    Full Text Available In the past years, the fission studies have been mainly focused on thermal fission because most of the current nuclear reactors work in this energy domain. With the development of GEN-IV reactor concepts, mainly working in the fast energy domain, new nuclear data are needed. The FALSTAFF spectrometer under development at CEA-Saclay, France, is a two-arm spectrometer which will provide mass yields before (2V method and after (EV method neutron evaporation and consequently will have access to the neutron multiplicity as a function of mass. The axial ionization chamber, in addition to the kinetic energy value, will measure the energy loss profile of the fragment along its track. This energy loss profile will give information about the fragment nuclear charge. This paper will focus on recent developments on the FALSTAFF design. A special attention will be paid to the impact of the detector material thickness on the uncertainty of different observables.

  13. A spallation-based irradiation test facility for fusion and future fission materials

    CERN Document Server

    Samec, K; Kadi, Y; Luis, R; Romanets, Y; Behzad, M; Aleksan, R; Bousson, S

    2014-01-01

    The EU’s FP7 TIARA program for developing accelerator-based facilities has recently demonstrated the unique capabilities of a compact and powerful spallation source for irradiating advanced nuclear materials. The spectrum and intensity of the neutron flux produced in the proposed facility fulfils the requirements of the DEMO fusion reactor for ITER, ADS reactors and also Gen III / IV reactors. Test conditions can be modulated, covering temperature from 400 to 550°C, liquid metal corrosion, cyclical or static stress up to 500 MPa and neutron/proton irradiation damage of up to 25 DPA per annum. The entire “TMIF” facility fits inside a cube 2 metres on a side, and is dimensioned for an accelerator beam power of 100 kW, thus reducing costs and offering great versatility and flexibility.

  14. Ultrathin magnetic structures IV applications of nanomagnetism

    CERN Document Server

    Heinrich, Bretislav

    2004-01-01

    The ability to understand and control the unique properties of interfaces has created an entirely new field of magnetism which already has a profound impact in technology and is providing the basis for a revolution in electronics. The last decade has seen dramatic progress in the development of magnetic devices for information technology but also in the basic understanding of the physics of magnetic nanostructures. Volume III describes thin film magnetic properties and methods for characterising thin film structure topics that underpin the present 'spintronics' revolution in which devices are based on combined magnetic materials and semiconductors. The present volume (IV) deals with the fundamentals of spintronics: magnetoelectronic materials, spin injection and detection, micromagnetics and the development of magnetic random access memory based on GMR and tunnel junction devices. Together these books provide readers with a comprehensive account of an exciting and rapidly developing field. The treatment is de...

  15. 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.

  16. Estudios sobre plantas andinas,- IV

    Directory of Open Access Journals (Sweden)

    Cuatrecasas José

    1943-04-01

    Full Text Available Caracteres genéricos:-Capitulo radiado, con flores dimorfas, las externas apenas más largas que las interiores. Invólucro cónico, de brácteas pluriseriadas pero poco numerosas, flojas, lineal-lanceoladas, agudas, de consistencia herbácea incluso en la fructificación, más largas que el resto del capitulo. Receptáculo alveolado ,con el margen de las fositas ,escamoso-lacerado. Corolas exteriores femeninas, liguladas, con tubo muy corto y casi rectas, ,con 4 líneas longitudinales y 3 dientes gruesos y callosos, en 2-3 filas, con frecuencia provistas de un apéndice lineal en la garganta, rudimento de labio superior.

  17. Clinical and radiographic evaluation of Bio-Gen with biocollagen compared with Bio-Gen with connective tissue in the treatment of class II furcation defects: a randomized clinical trial

    Science.gov (United States)

    JENABIAN, Niloofar; HAGHANIFAR, Sina; MABOUDI, Avideh; BIJANI, Ali

    2013-01-01

    Objective Treatment of furcation defects are thought to be challenging. The purpose of this study was to evaluate the clinical and radiographic parameters of Bio-Gen with Biocollagen compared with Bio-Gen with connective tissue in the treatment of Class II furcation defects. Material and Methods In this clinical trial, 24 patients with Class II furcation defect on a buccal or lingual mandibular molar were recruited. After oral hygiene instruction, scaling and root planing and achievement of acceptable plaque control, the patients were randomly chosen to receive either connective tissue and Bio-Gen (case group) or Biocollagen and Bio-Gen (control group). The following parameters were recorded before the first and re-entry surgery (six months later): vertical clinical attachment level (VCAL), gingival index (GI), plaque index (PI), horizontal probing depth (HPD), vertical probing depth (VPD), gingival recession (GR), furcation vertical component (FVC), furcation to alveolar crest (FAC), fornix to base of defect (FBD), and furcation horizontal component (FHC) were calculated at the time of first surgery and during re-entry. A digital periapical radiograph was taken in parallel before first surgery and re-entry. The radiographs were then analyzed by digital subtraction. The differences with p value <0.05 were considered significant. Results Only the mean changes of FAC, FHC, mean of FHC, FBD in re-entry revealed statistically significant differences between the two groups. HPD, VPD, FBD, FAC, and FHC showed statistically significant differences after 6 months in the case group. However, in the control group, statistically significant differences were found in GR and HPD. We did not observe any significant difference in radiographic changes among the two groups. Conclusion The results of this trial indicate that better clinical outcomes can be obtained with connective tissue grafts in combination with bone material compared with a resorbable barrier with bone material

  18. Clinical and radiographic evaluation of Bio-Gen with biocollagen compared with Bio-Gen with connective tissue in the treatment of class II furcation defects: a randomized clinical trial

    Directory of Open Access Journals (Sweden)

    Niloofar Jenabian

    2013-09-01

    Full Text Available OBJECTIVE: Treatment of furcation defects are thought to be challenging. The purpose of this study was to evaluate the clinical and radiographic parameters of Bio-Gen with Biocollagen compared with Bio-Gen with connective tissue in the treatment of Class II furcation defects. MATERIAL AND METHODS: In this clinical trial, 24 patients with Class II furcation defect on a buccal or lingual mandibular molar were recruited. After oral hygiene instruction, scaling and root planing and achievement of acceptable plaque control, the patients were randomly chosen to receive either connective tissue and Bio-Gen (case group or Biocollagen and Bio-Gen (control group. The following parameters were recorded before the first and re-entry surgery (six months later: vertical clinical attachment level (VCAL, gingival index (GI, plaque index (PI, horizontal probing depth (HPD, vertical probing depth (VPD, gingival recession (GR, furcation vertical component (FVC, furcation to alveolar crest (FAC, fornix to base of defect (FBD, and furcation horizontal component (FHC were calculated at the time of first surgery and during re-entry. A digital periapical radiograph was taken in parallel before first surgery and re-entry. The radiographs were then analyzed by digital subtraction. The differences with p value <0.05 were considered significant. RESULTS: Only the mean changes of FAC, FHC, mean of FHC, FBD in re-entry revealed statistically significant differences between the two groups. HPD, VPD, FBD, FAC, and FHC showed statistically significant differences after 6 months in the case group. However, in the control group, statistically significant differences were found in GR and HPD. We did not observe any significant difference in radiographic changes among the two groups. CONCLUSION: The results of this trial indicate that better clinical outcomes can be obtained with connective tissue grafts in combination with bone material compared with a resorbable barrier with bone

  19. 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.

  20. 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.

  1. 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...

  2. 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.

  3. 11. IV avati Draakoni galeriis...

    Index Scriptorium Estoniae

    2005-01-01

    Tanel Saare (sünd. 1979) näitus "Gott und huhn episode IV: seed shower". Eksponeeritakse väljavõtteid aktsioonidest aastatel 2000-2004 Turus, Nürnbergis, Berliinis, Lohusalus ja Soulis. Osa aktsioone toimus koos rühmitusega Non Grata

  4. 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.

  5. Materials for innovative lead alloy cooled nuclear systems: Overview

    International Nuclear Information System (INIS)

    Mueller, Georg; Weisenburger, Alfons; Fetzer, Renate; Heinzel, Annette; Jianu, Adrian

    2015-01-01

    One of the most challenging issues for all future innovative nuclear systems including Gen IV reactors are materials. The selection of the structural materials determines the design which has to consider the properties and the availability of the materials. Beside general requirements for material properties that are common for all fast reactor types specific issues arise from coolant compatibility. The high solubility of steel alloying elements in liquid Pb-alloys at reactor relevant temperatures is clearly detrimental. Therefore, all steels that are considered as structural materials have to be protected by dissolution barriers. The most common barriers for steels under consideration are oxide scales that form in situ during operation. However, increasing the temperature above 500 deg. C will result either in dissolution attack or in enhanced oxidation. For higher temperatures additional barriers like alumina forming surface alloys are discussed and investigated. Mechanical loads like creep stress and fretting will act on the steels. These mechanical loads will interact with the coolant and can increase the negative effects. For a LFR (Lead Fast Reactor) Demonstrator and MYHRRA (ADS) austenitic steels (316L) are selected for most in core components. The 15-15Ti is the choice for the fuel cladding of MYHRRA and a Pb cooled demonstrator. For an industrial LFR (Lead Fast Reactor) the ferritic martensitic steel T91 was selected as fuel clad material due to its improved irradiation resistance. T91 is in both designs the material to be used for the heat exchanger. Surface alloying with alumina forming alloys is considered to assure material functionality at higher temperatures and is therefore selected for fuel cladding of the ELFR and the heat exchanger tubes. This presentation will give an overview on the selected materials for innovative Pb alloy cooled nuclear systems considering, beside pure compatibility, the influence of mechanical interaction like creep and

  6. 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 ...

  7. 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

  8. Efecto sedante del midazolam genérico versus innovador en ratas Wistar

    Directory of Open Access Journals (Sweden)

    Radamés Alemón-Medina

    2015-11-01

    Full Text Available Antecedentes: ocho de cada diez pacientes en Terapia Intensiva del Instituto Nacional de Pediatría no obtienen el mismo efecto ansiolítico y sedante con midazolam genérico (PiSA®, que con el innovador (Dormicum, Roche® a pesar de que su biodisponibilidad es de 100%.  Objetivo: determinar diferencias significativas en el efecto sedante del midazolam genérico y del innovador administrados parenteralmente.  Material y métodos: estudio aleatorizado cruzado en 24 ratas Wistar macho distribuidas en 4 grupos (n=6. A cada individuo se le administró una dosis de 0.5 mg/kg de peso vía intraperitoneal. Se determinaron los grados de sedación mediante la escala de Salamone. Se midió la concentración del fármaco en las ampolletas de ambas marcas por cromatografía líquida de alta resolución. Resultados: el efecto sedante del midazolam apareció al mismo tiempo y tuvo la misma duración, ndependientemente de la marca. El efecto tiende a ser más duradero con el innovador pero sin ser estadísticamente significativo (ANOVA, p ≤ 0.05. Asimismo, la mayoría de los animales llegaron al nivel 3 de sedación con ambas marcas.   Conclusión: tanto el midazolam innovador como el genérico tienen el mismo efecto sedante: aparece al mismo tiempo y tiene la misma duración.

  9. Studies on the genus Atriplex L. (Amaranthaceae) in Italy. IV ...

    African Journals Online (AJOL)

    Studies on the genus Atriplex L. (Amaranthaceae) in Italy. IV. Atriplex bocconei Guss. – Atriplex bocconei Guss. is here typified on one herbarium specimen kept in NAP. The identity of the species is also clarified on the basis of literature analysis and examination of type material and other specimens that allowed to include it ...

  10. IV Bach conference on radiation chemistry. Abstracts of reports

    International Nuclear Information System (INIS)

    2005-01-01

    IV Bach conference on radiation chemistry was conducted in the framework of the conference Physico-chemical foundations of new technologies of XXI century. Problems of radiolysis of modern polymeric materials, post-irradiation examination of different organic and inorganic compounds treated with ionizing radiation, equipment used for these examinations, application of data obtained in these researches were represented in reports [ru

  11. 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....

  12. 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 ...

  13. 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

  14. GenBank blastn search result: AK064582 [KOME

    Lifescience Database Archive (English)

    Full Text Available AK064582 002-112-F03 AY007820.1 Daucus carota ATPase8 (ATP8) gene, ATP8-Sp1b allele, complete cds; chimeric... ATPase9 (ATP9) gene, ATP9-Sp3 allele, complete cds; and chimeric ATPase6 (ATP6) gen

  15. 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.

  16. 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.

  17. Justicia y genética: compensando las diferencias

    Directory of Open Access Journals (Sweden)

    Alejandra Zúñiga-Fajuri

    2013-01-01

    Full Text Available Se analizan los dilemas morales asociados a los avances científicos que en la actualidad nos exigen repensar el concepto de igualdad equitativa de oportunidades. Asimismo, se pasa revista a la discusión filosófica en torno al origen de las desventajas sociales y genéticas que permiten las desigualdades sociales.

  18. 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.

  19. Meet Mr. and Mrs. Gen X: A New Parent Generation

    Science.gov (United States)

    Howe, Neil

    2010-01-01

    Slowly but surely, Generation Xers have been taking over from Baby Boomers as the majority of parents in elementary and secondary education. In the early 1990s, Gen Xers began joining parent-teacher associations in the nation's elementary schools. Around 2005, they became the majority of middle school parents. By the fall of 2008, they took over…

  20. PowerGen plc report and accounts 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The annual report and accounts of PowerGen plc for the year 1994 are presented. Financial highlights are quoted, followed by the Chairman's statement, reviews by the Chief Executive and Financial Directors, reports by the Auditors and Directors, balance sheets and details of the consolidated profit and loss account and principal accounting policies. A four year summary and shareholder information are included. (UK)

  1. Measuring Gen-Y Customer Experience in the Banking Sector

    Directory of Open Access Journals (Sweden)

    Kyguolienė Asta

    2017-12-01

    Full Text Available The article analyses customer experience as the subject of marketing research and presents methods for assessing customer experience. The results of empirical research revealing the Gen-Y customer experience in using the Lithuanian commercial banks’ services are presented.

  2. A New Parent Generation: Meet Mr. and Mrs. Gen X

    Science.gov (United States)

    Howe, Neil

    2010-01-01

    Slowly but surely, Generation Xers have been taking over from Baby Boomers as the majority of parents in elementary and secondary education. Gen-X parents and Boomer parents belong to two neighboring generations, each possessing its own location in history and its own peer personality. They are similar in some respects, but clearly different in…

  3. GenSVM: a generalized multiclass support vector machine

    NARCIS (Netherlands)

    G.J.J. van den Burg (Gertjan); P.J.F. Groenen (Patrick)

    2016-01-01

    textabstractTraditional extensions of the binary support vector machine (SVM) to multiclass problems are either heuristics or require solving a large dual optimization problem. Here, a generalized multiclass SVM is proposed called GenSVM. In this method classification boundaries for a K-class

  4. Genetic variability of Passiflora spp. from commercial fields in the Federal District, Brazil Variabilidade genética de Passiflora spp. em plantios comerciais do Distrito Federal, Brasil

    Directory of Open Access Journals (Sweden)

    Ana Paula Gomes de Castro

    2011-06-01

    Full Text Available This study aimed to characterize the genetic variability in commercial accessions of passion fruit from the Federal District, Brazil, by RAPD markers. Genetic analyses were done with leaf samples of 30 accessions. DNA samples were amplified by RAPD technique, and respective markers converted into a binary matrix, from which the genetic distances between the accessions were estimated. Clustering analyis based on genetic distances allowed to detect a wide range of genetic variabillity among the accessions of sour passion fruit, and to separate them from the two sweet passion fruit. The graphical positioning of 'BRS Ouro Vermelho' confirms its potential to improve the genetic variability of commercial varieties of sour passion fruit. Dispersal of genetic distances among commercial accessions of sour passion fruit supports evidence for different genetic origins of the materials planted in the Federal District. The verified genetic variability indicates the potential success of future breeding programs for this region.Este estudo teve como objetivo caracterizar a variabilidade genética de acessos de maracujá comerciais no Distrito Federal por meio de marcadores RAPD. Análises genéticas foram feitas com amostras foliares de 30 acessos. As amostras de DNA foram amplificadas pela técnica de RAPD e os respectivos marcadores convertidos em uma matriz binária, a partir da qual as distâncias genéticas entre os acessos foram estimadas. Análises de agrupamento baseadas em distâncias genéticas permitiram detectar uma ampla gama de variabilidade genética entre os acessos de maracujazeiro-azedo, bem como para separá-los dos dois de maracujazeiro-doce. O posicionamento gráfico de 'BRS Ouro Vermelho' confirma a sua importante contribuição para aumentar a variabilidade genética das atuais variedades comerciais de maracujazeiro-azedo. A dispersão das distâncias genéticas entre os acessos comerciais de maracujazeiro-azedo suportam as evid

  5. Uruguay; 2011 Article IV Consultation

    OpenAIRE

    International Monetary Fund

    2011-01-01

    This 2011 Article IV Consultation highlights that the growth momentum in Uruguay has continued into 2011 but a slowdown is under way, led by weaker exports and slower public investment. Uruguay’s economic and financial vulnerabilities are modest, and the government has reduced debt vulnerabilities significantly and built important financial buffers. Executive Directors have commended authorities’ skillful macroeconomic management that has underpinned Uruguay’s excellent economic performance, ...

  6. Austria; 2013 Article IV Consultation

    OpenAIRE

    International Monetary Fund

    2013-01-01

    This paper presents details of Austria’s 2013 Article IV Consultation. Austria has been growing economically but is facing challenges in the financial sector. Full implementation of medium-term fiscal adjustment plans require specifying several measures and plans that need gradual strengthening to take expected further bank restructuring cost into account. It suggests that strong early bank intervention and resolution tools, a better designed deposit insurance system, and a bank-financed reso...

  7. Pemotongan dan Menyambung DNA dalam Kloning Gen, Studi pada Kloning Gen Prolidase dari Bakteri Asam Laktat

    Directory of Open Access Journals (Sweden)

    Ketut Suriasih

    2015-03-01

    Full Text Available Gene cloning in lactic acid bacteria (LAB is crucial in term to increase their ability to hydrolyze milk protein such as proline. This proline could be hydrolyzed when the LAB undergone cloning on their genome coding the enzyme. The cloning process need technology to separate/isolate the gene capable of proline hydrolyze. Isolation of DNA containing prolidase gene, need DNA genome cutting. After isolation of DNA gene coding prolidase, it is then recombined with other bacterial DNA to obtained recombinant gene. The process need ligase. In gene cloning, knowledge of cutting and joining the DNA should be understood. The enzyme take the role in cutting and joining the DNA were restriction endonuclease and ligase. The restriction enzyme function (1 in inserting a gen into plasmid contained in a vector during gene cloning, and gene expression experiment, and (2 to identify the gene. It is important that the researcher already have standardized  sequenced gene as control. The DNA contained target gene was cut using some restriction enzyme, then the gene was arrayed in electrophoresis gel using southern blot technique. DNA sequence was elucidated by addition of ethydium bromide. To identify/characterize the isolated gene, this DNA sequence was encountered the control DNA.

  8. ASTRID, the SFR Gen IV technology demonstrator project: where are we, where do we stand for? - 15439

    International Nuclear Information System (INIS)

    Rouault, J.; Abonneau, E.; Settimo, D.; Hamy, J.M.; Hayafune, H.; Gefflot, R.; Benard, R.P.; Mandement, O.; Chauveau, T.; Lambert, G.; Audouin, P.; Mochida, H.; Iitsuka, T.; Fukuie, M; Molyneux, J.; Mazel, J.L.

    2015-01-01

    The Preconceptual Design phase (AVP1) of the ASTRID Project ended late 2012, the main goal was to evaluate innovative options. It is now followed by the AVP2 phase planned until the end of 2015 whose objectives are both to focus the design in order to finalize a coherent reactor outline and to finalize by December 2015 the Safety Option Report. The CEA acts as the industrial architect of the project. In 2014, twelve industrial partners were involved in the project. Japan which participates now in the design studies and also in Research/Development in support of the ASTRID Project and VELAN of the French 'Pole Nucleaire de Bourgogne', are the latest partners to join the Project. The Option Selection Process (RCO) is continuing during the AVP2 phase although structuring decisions remain to be made (the choice of the Energy Conversion System between Rankine cycle and Gas Brayton cycle). Other important option selections, which could nevertheless be reconsidered before starting the core of the Basic Design phase are: the choice of an internal fuel storage and a gas fuel handling chain, a rectangular reactor building with a single wall containment, the steam generator size the vertical handling of components. In addition, BOP studies considering the Marcoule site as a possible one are going on. The next important milestone is at the end of 2015 with the release by the Project team of a convincing and coherent Conceptual Design file. (authors)

  9. New RELAP5-3D Lead and LBE Thermophysical Properties Implementation for Safety Analysis of Gen IV Reactors

    Directory of Open Access Journals (Sweden)

    P. Balestra

    2016-01-01

    Full Text Available The latest versions of RELAP5-3D© code allow the simulation of thermodynamic system, using different type of working fluids, that is, liquid metals, molten salt, diathermic oil, and so forth, thanks to the ATHENA code integration. The RELAP5-3D© water thermophysical properties are largely verified and validated; however there are not so many experiments to generate the liquid metals ones in particular for the Lead and the Lead Bismuth Eutectic. Recently, new and more accurate experimental data are available for liquid metals. The comparison between these state-of-the-art data and the RELAP5-3D© default thermophysical properties shows some discrepancy; therefore a tool for the generation of new properties binary files has been developed. All the available data came from experiments performed at atmospheric pressure. Therefore, to extend the pressure domain below and above this pressure, the tool fits a semiempirical model (soft sphere model with inverse-power-law potential, specific for the liquid metals. New binary files of thermophysical properties, with a detailed mesh grid of point to reduce the code mass error (especially for the Lead, were generated with this tool. Finally, calculations using a simple natural circulation loop were performed to understand the differences between the default and the new properties.

  10. 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.

  11. Titanium(IV), zirconium, hafnium and thorium

    International Nuclear Information System (INIS)

    Brown, Paul L.; Ekberg, Christian

    2016-01-01

    Titanium can exist in solution in a number of oxidation states. The titanium(IV) exists in acidic solutions as the oxo-cation, TiO 2+ , rather than Ti 4+ . Zirconium is used in the ceramics industry and in nuclear industry as a cladding material in reactors where its reactivity towards hydrolysis reactions and precipitation of oxides may result in degradation of the cladding. In nature, hafnium is found together with zirconium and as a consequence of the contraction in ionic radii that occurs due to the 4f -electron shell, the ionic radius of hafnium is almost identical to that of zirconium. All isotopes of thorium are radioactive and, as a consequence of it being fertile, thorium is important in the nuclear fuel cycle. The polymeric hydrolysis species that have been reported for thorium are somewhat different to those identified for zirconium and hafnium, although thorium does form the Th 4 (OH) 8 8+ species.

  12. 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.

  13. Optimized Gen-II FeCrAl cladding production in large quantity for campaign testing

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, Yukinori [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sun, Zhiqian [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pint, Bruce A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrani, Kurt A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-06-03

    There are two major objectives in this report; (1) to optimize microstructure control of ATF FeCrAl alloys during tube drawing processes, and (2) to provide an update on the progress of ATF FeCrAl tube production via commercial manufacturers. Experimental efforts have been made to optimize the process parameters balancing the tube fabricability, especially for tube drawing processes, and microstructure control of the final tube products. Lab-scale sheet materials of Gen II FeCrAl alloys (Mo-containing and Nb-containing FeCrAl alloys) were used in the study, combined with a stepwise warm-rolling process and intermediate annealing, aiming to simulate the tube drawing process in a commercial tube manufacturer. The intermediate annealing at 650ºC for 1h was suggested for the tube-drawing process of Mo-containing FeCrAl alloys because it successfully softened the material by recovering the work hardening introduced through the rolling step, without inducing grain coarsening due to recrystallization. The final tube product is expected to have stabilized deformed microstructure providing the improved tensile properties with sufficient ductility. Optimization efforts on Nb-containing FeCrAl alloys focused on the effect of alloying additions and annealing conditions on the stability of deformed microstructure. Relationships between the second-phase precipitates (Fe2Nb-Laves phase) and microstructure stability are discussed. FeCrAl tube production through commercial tube manufacturers is currently in progress. Three different manufacturers, Century Tubes, Inc. (CTI), Rhenium Alloys, Inc. (RAI), and Superior Tube Company, Inc. (STC), are providing capabilities for cold-drawing, warm-drawing, and HPTR cold-pilgering, respectively. The first two companies are currently working on large quantity tube production (expected 250 ft length) of Gen I model FeCrAl alloy (B136Y3, at CTI) and Gen II (C35M4, at RAI), with the process parameters obtained from the experimental

  14. Crystalline cerium(IV) phosphates

    International Nuclear Information System (INIS)

    Herman, R.G.; Clearfield, A.

    1976-01-01

    The ion exchange behaviour of seven crystalline cerium(IV) phosphates towards some of the alkali metal cations is described. Only two of the compounds (A and C) possess ion exchange properties in acidic solutions. Four others show some ion exchange characteristics in basic media with some of the alkali cations. Compound G does not behave as an ion exchanger in solutions of pH + , but show very little Na + uptake. Compound E undergoes ion exchange with Na + and Cs + , but not with Li+. Both Li + and Na + are sorbed by compounds A and C. The results are indicative of structures which show steric exclusion phenomena. (author)

  15. PREPARATION OF OXOPORPHINATOMANGANESE (IV) COMPLEX

    Energy Technology Data Exchange (ETDEWEB)

    Willner, I.; Otvos, J.; Calvin, M.

    1980-07-01

    Oxo-manganese-tetraphenylporphyrin (O=Mn{sup IV}-TPP) has been prepared by an oxygen-transfer reaction from iodosylbenzene to MnIITPP and characterized by its i.r. and field desorption mass spectra, which are identical to those of the product obtained by direct oxidation of Mn{sup III}(TPP) in an aqueous medium; it transfers oxygen to triphenylphosphine to produce triphenylphosphine oxide, and it is suggested that similar intermediates are important in oxygen activation by cytochrome P-450 as well as in the photosynthetic evolution of oxygen.

  16. Development of Electromagnetic Analysis Model for IV-CEAPI

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jinseok; Jang, Yongtae; Lee, Myounggoo; Cho, Yeonho; Kim, Hyunmin [KEPCO Engineering and Construction, Inc., Daejeon (Korea, Republic of); Hong, Hoonbin; Baek, Minho [Woojin Inc., Osan (Korea, Republic of)

    2016-05-15

    There are many different types of position indicators such as reed switch type, ultrasonic type, solenoid type, etc. Through an analysis of strengths and weakness of those types, solenoid type was selected for an IV-CEAPI. Although solenoid type CEAPIs have been used world-wide, the IV-CEAPI is to be very different from the conventional designs due to its harsh operating environment. The concept of the IV-CEAPI is simple as shown in Figure 1. The coil is made of mineral insulated wire to be able to operate inside reactor vessel. The CEA is connected to the shaft which is made of ferromagnetic material. As the CEA position varies, the inductance variation is detected by the inductance meter located outside the vessel. Unlike the conventional ones, the IV-CEAPI used only one coil to eliminate coil connection point and electric components inside vessel. A finite element model was developed to calculate inductance of the solenoid type IV-CEAPI. The model considers eddy current effect to calculate frequency dependent inductance value. Analyses were performed to produce an inductance curve to the shaft position.

  17. Development of Electromagnetic Analysis Model for IV-CEAPI

    International Nuclear Information System (INIS)

    Park, Jinseok; Jang, Yongtae; Lee, Myounggoo; Cho, Yeonho; Kim, Hyunmin; Hong, Hoonbin; Baek, Minho

    2016-01-01

    There are many different types of position indicators such as reed switch type, ultrasonic type, solenoid type, etc. Through an analysis of strengths and weakness of those types, solenoid type was selected for an IV-CEAPI. Although solenoid type CEAPIs have been used world-wide, the IV-CEAPI is to be very different from the conventional designs due to its harsh operating environment. The concept of the IV-CEAPI is simple as shown in Figure 1. The coil is made of mineral insulated wire to be able to operate inside reactor vessel. The CEA is connected to the shaft which is made of ferromagnetic material. As the CEA position varies, the inductance variation is detected by the inductance meter located outside the vessel. Unlike the conventional ones, the IV-CEAPI used only one coil to eliminate coil connection point and electric components inside vessel. A finite element model was developed to calculate inductance of the solenoid type IV-CEAPI. The model considers eddy current effect to calculate frequency dependent inductance value. Analyses were performed to produce an inductance curve to the shaft position

  18. Experimental facilities for Generation IV reactors research

    International Nuclear Information System (INIS)

    Krecanova, E.; Di Gabriele, F.; Berka, J.; Zychova, M.; Macak, J.; Vojacek, A.

    2013-06-01

    Centrum Vyzkumu Rez (CVR) is research and development Company situated in Czech Republic and member of the UJV group. One of its major fields is material research for Generation IV reactor concepts, especially supercritical water-cooled reactor (SCWR), very high temperature/gas-cooled fast reactor (VHTR/GFR) and lead-cooled fast reactor (LFR). The CVR is equipped by and is building unique experimental facilities which simulate the environment in the active zones of these reactor concepts and enable to pre-qualify and to select proper constructional materials for the most stressed components of the facility (cladding, vessel, piping). New infrastructure is founded within the Sustainable Energy project focused on implementation the Generation IV and fusion experimental facilities. The research of SCWR concept is divided to research and development of the constructional materials ensured by SuperCritical Water Loop (SCWL) and fuel components research on Fuel Qualification Test loop (SCWL-FQT). SCWL provides environment of the primary circuits of European SCWR, pressure 25 MPa, temperature 600 deg. C and its major purpose is to simulate behavior of the primary medium and candidate constructional materials. On-line monitoring system is included to collect the operational data relevant to experiment and its evaluation (pH, conductivity, chemical species concentration). SCWL-FQT is facility focused on the behavior of cladding material and fuel at the conditions of so-called preheater, the first pass of the medium through the fuel (in case of European SCWR concept). The conditions are 450 deg. C and 25 MPa. SCWL-FQT is unique facility enabling research of the shortened fuel rods. VHTR/GFR research covers material testing and also cleaning methods of the medium in primary circuit. The High Temperature Helium Loop (HTHL) enables exposure of materials and simulates the VHTR/GFR core environment to analyze the behavior of medium, especially in presence of organic compounds and

  19. 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...

  20. 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.

  1. 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.

  2. A COMPARATIVE CLINICAL STUDY BETWEEN IV ESMOLOL AND IV FENTANYL ON ATTENUATION OF HAEMODYNAMIC RESPONSES TO LARYNGOSCOPY AND INTUBATION

    Directory of Open Access Journals (Sweden)

    Abu Lais Mustaque

    2016-04-01

    Full Text Available INTRODUCTION Laryngoscopy and intubation is an integral part for providing general anaesthesia to patients undergoing various types of surgery. It also plays an important role in critical care units viz. for providing mechanical ventilation. It is a very essential tool in the hands of anaesthesiologist in maintaining airway. The present study is undertaken to determine and compare the efficacy of single bolus dose of IV esmolol 1 mg/kg and IV fentanyl 2 mcg/kg in attenuating the haemodynamic responses to laryngoscopy and tracheal intubation and to ascertain the effectiveness of esmolol hydrochloride and fentanyl citrate in suppressing sympathetic responses. MATERIAL & METHODS The study was conducted under the Department of Anaesthesiology and Critical Care, Assam Medical College and Hospital, Dibrugarh, during the period July 2013 to June 2014. For this purpose, 150 patients of either sex between 20-50 years of ASA I & II physical status were selected after obtaining informed and written consent and were divided into two groups namely, Group E receiving IV esmolol (1 mg/kg and Group F receiving IV fentanyl (2 mcg/kg. RESULTS Inj. fentanyl 2 mcg/kg IV administered 5 minutes before laryngoscopy and intubation was able to prevent adverse haemodynamic changes better than Inj. esmolol 1 mg/kg IV administered 3 minutes prior to laryngoscopy and intubation during elective surgeries under general anaesthesia. CONCLUSION Hence, from the findings of this study we can conclude that IV bolus dose of fentanyl 2 mcg/kg administered 5 minutes before laryngoscopy and intubation can attenuate the sympathetic response to laryngoscopy and intubation without any side effects of the drug in healthy patients undergoing elective surgeries under general anaesthesia.

  3. 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…

  4. NextGen Avionics Roadmap Version 2.0

    Science.gov (United States)

    2011-09-30

    Systems Analysis ( IPSA ) Division has defined multiple NextGen Operational (NGOps) Levels, projecting relative performance and risk based on differing...degrees of capability improvements, as shown in Figure 4. IPSA forecasts include the most likely performance NGOps level (i.e., NGOps 3-4), as well...in the near-term. Figures 5 through 9 de- pict the various programs and capabilities aligned with the various NGOps levels. Factors from the IPSA

  5. EVALUATION DE LA SENSIBILITE A Bemisia tabaci (GEN) DE 13 ...

    African Journals Online (AJOL)

    AISA

    champ, le comportement de 13 variétés de tomate contre la pression de Bemisia tabaci (Gen), une mouche vecteur du virus de la jaunisse en cuillère des ... en saison sèche il y a une vingtaine d'années atteignaient 100 % et les pertes de production ... semaines. Le semis s'est effectué sur une planche de 9 m2 (9 x 1 m2).

  6. Light water reactor fuel analysis code FEMAXI-IV(Ver.2). Detailed structure and user's manual

    International Nuclear Information System (INIS)

    Suzuki, Motoe; Saitou, Hiroaki.

    1997-11-01

    A light water reactor fuel behavior analysis code FEMAXI-IV(Ver.2) was developed as an improved version of FEMAXI-IV. Development of FEMAXI-IV has been already finished in 1992, though a detailed structure and input manual of the code have not been open to users yet. Here, the basic theories and structure, the models and numerical solutions applied to FEMAXI-IV(Ver.2), and the material properties adopted in the code are described in detail. In FEMAXI-IV(Ver.2), programming bugs in previous FEMAXI-IV were eliminated, renewal of the pellet thermal conductivity was performed, and a model of thermal-stress restraint on FP gas release was incorporated. For facilitation of effective and wide-ranging application of the code, methods of input/output of the code are also described in detail, and sample output is included. (author)

  7. Long-term risk of complications after mid-urethral sling IVS implantation

    Directory of Open Access Journals (Sweden)

    Grzegorz Surkont

    2015-02-01

    Full Text Available [b]Introduction[/b]. Results of short-term evaluation of multifilament microporous midurethral tape IVS differ a great deal. During the first year of implantation, erosions have been observed in 0%–26% of operated women. Long-term observations are rare. They suggest high risk of extrusion and infection even after years of implantation. [b]Objective[/b]. The purpose of the study was to evaluate long-term risk of complications after IVS implantation. Material and methods. Between 2001–2005, 72 women were operated on with the use of IVS mid-urethral tape. [b]Results[/b]. Two women had vaginal erosions during the first 3 months after the operation. Twelve women had vaginal erosions, purulent vaginal discharge, with IVS tape sticking out of the abdominal wall or vagina, and abdominal abscess. These complications were diagnosed between 9 months and 6 years after IVS implantation. The patients were operated on vaginally and open abdominally, 1–5 times because of complications after IVS implantation. [b]Conclusions[/b]. In the case of post-IVS complication, as much tape as possible should be excised. Long-term follow up on patients with IVS implantation should be recommended to the centres where IVS tape was used, even to patients after removal of the tape. Risk of erosion, extrusion and infection after midurethral multifilament microporous IVS tape implantation is too high – which is the reason it should no longer be used.

  8. Technical and management challenges associated with structural materials degradation in nuclear reactors in the future

    International Nuclear Information System (INIS)

    Ford, F.P.

    2007-01-01

    There are active plans worldwide to increase nuclear power production by significant amounts. In the near term (i.e. by 2020) this will be accomplished by, (a) increasing the power output of the existing reactors and extending their life, and by, (b) constructing new reactors that are very similar to the current water-cooled designs. Beyond 2025-2030, it is possible that new reactors (i.e. the 'GEN IV' designs) will be very different from those currently in service. A full discussion of the technical and management concerns associated with materials degradation that might arise over the next 40 years would need to address a wide range of topics. Quite apart from discussing the structural integrity issues for the materials of construction and the fuel cladding, the debate would also need to cover, for example, fuel resources and the associated issues of fuel cycle management and waste disposal, manufacturing capacity, inspection capabilities, human reliability, etc., since these all impact to one degree or another on the choice of material and the reactor operating conditions. For brevity, the scope of this article is confined to the integrity of the materials of construction for passive components in the current water-cooled reactors and the evolutionary designs (which will dominate the near term new constructions), and the very different GEN IV reactor designs. In all cases the operating environments will be more aggressive than currently encountered. For instance, the concerns for flow accelerated corrosion and flow-induced vibration will be increased under extended power uprate conditions for the current water-cooled reactors. Of greater concern, the design life will be at least 60 years for all of the new reactors and for those current reactors operating with extended licenses. This automatically presents challenges with regard to managing both irradiation damage in metallic and non-metallic materials of construction, and environmentally assisted cracking. This

  9. 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.

  10. 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

  11. Cycle for innovative nuclear Gen 4. systems=

    International Nuclear Information System (INIS)

    2004-01-01

    In the framework of the development of nuclear systems of the 4. generation, the preliminary and schematic reprocessing goals are a cleaning of fission products without a priori separation of the different actinides. The objective of the workshop is to exchange information about the potential efficiency of innovative fuel processing treatments in order to evaluate the impact of impurities on the design of the fuel during its re-fabrication and re-introduction inside the reactor, and on the materials and systems. This document gathers the slides of the 18 presentations given at this workshop: 1 - from the PWR fuel to the closed cycle fast spectrum concepts of generation 4 systems (P. Anzieu, F. Carre, Ph. Brossard, M. Delpech); 2 - the double strata scenarios: objectives and characteristics (S. David and F. Varaine); 3 - why a molten salts thorium file (D. Heuer); 4 - the common 'molten salts' research program of the CNRS (D. Heuer, S. Sanchez); 5 - the hydro-metallurgical reprocessing, the knowledge gained and the statuses of the 5. PCRD, synthesis of the OECD works (C. Madic); 6 - pyro-chemistry: Pyropep status (H. Boussier); 7 - technological bolts identified during the Most project of the 5. PCRD (C. Renault, Ch. Le Brun, M. Delpech and C. Garzenne); 8 - the molten salt reactor concept and its reprocessing options, expected efficiencies (L. Mathieu); 9 - methodology of evaluation of pyro-chemical fuel reprocessing schemes (H. Boussier); 10 - molten salt reactor, design-aided tools for the reactor and the reprocessing plant (O. Gastaldi, E. Walle, O. Koberl, D. Lecarpentier); 11 - status of CEA's prospective studies for the front-end of the fuel reprocessing process/dry ways (S. Bourg); 12 - results of activity coefficient measurements in liquid metals (J. Finne, E. Walle, G. Picard, S. Sanchez and O. Conocar); 13 - potentialities of electrolytic separation and liquid-liquid extraction processes (molten salts/molten metal) for the multi-recycling of actinides (J

  12. Irradiation-Accelerated Corrosion of Reactor Core Materials. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Jiao, Zhujie [Univ. of Michigan, Ann Arbor, MI (United States); Was, Gary [Univ. of Michigan, Ann Arbor, MI (United States); Bartels, David [Univ. of Notre Dame, IN (United States)

    2015-04-02

    This project aims to understand how radiation accelerates corrosion of reactor core materials. The combination of high temperature, chemically aggressive coolants, a high radiation flux and mechanical stress poses a major challenge for the life extension of current light water reactors, as well as the success of most all GenIV concepts. Of these four drivers, the combination of radiation and corrosion places the most severe demands on materials, for which an understanding of the fundamental science is simply absent. Only a few experiments have been conducted to understand how corrosion occurs under irradiation, yet the limited data indicates that the effect is large; irradiation causes order of magnitude increases in corrosion rates. Without a firm understanding of the mechanisms by which radiation and corrosion interact in film formation, growth, breakdown and repair, the extension of the current LWR fleet beyond 60 years and the success of advanced nuclear energy systems are questionable. The proposed work will address the process of irradiation-accelerated corrosion that is important to all current and advanced reactor designs, but remains very poorly understood. An improved understanding of the role of irradiation in the corrosion process will provide the community with the tools to develop predictive models for in-reactor corrosion, and to address specific, important forms of corrosion such as irradiation assisted stress corrosion cracking.

  13. Engineering design of the Aries-IV gaseous divertor

    International Nuclear Information System (INIS)

    Hasan, M.Z.; Najmabadi, F.; Sharafat, S.

    1994-01-01

    ARIES-IV is a conceptual, D-T burning, steady-state tokamak fusion reactor producing 1000 MWe net. It operates in the second plasma stability regime. The structural material is SiC composite and the primary coolant is helium at 10MPa base pressure. ARIES-IV uses double-null divertors for particle control. Total thermal power recovered from the divertors is 425MW, which is 16% of the total reactor thermal power. Among the desirable goals of divertor design were to avoid the use of tungsten and to use the same structural material and primary coolant as in the blanket design. In order to reduce peak heat flux, the innovative gaseous divertor has been used in ARIES-IV. A gaseous divertor reduces peak heat flux by increasing the surface area and by distributing particle and radiation energy more uniformly. Another benefit of gaseous divertor is the reduction of plasma temperature in the divertor chamber, so that material erosion due to sputtering, can be diminished. This makes the use of low-Z material possible in a gaseous divertor

  14. 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...

  15. "Rencontres de Genève - Histoire et Cité": building peace

    CERN Multimedia

    Laurianne Trimoulla

    2015-01-01

    How did people conceive, picture or imagine peace in former times? How did they contribute to it in concrete terms? Why and how were they sometimes obliged to fight to promote or enforce it? Which material, symbolic, financial, political and economic means were used to foster cohesion between societies, peoples and communities? The Rencontres de Genève - Histoire et Cité festival invites us to learn about the past to better understand the present.   Events taking place at Geneva University (Uni Dufour and Uni Bastions) and elsewhere in the city from Wednesday, 13 May to Saturday, 16 May. Organised by Geneva University’s Maison de l'histoire in collaboration with the Geneva Graduate Institute of International and Development Studies and the University of Applied Sciences and Arts of Western Switzerland (HES-SO), this first festival of history in Switzerland features a comprehensive programme of events taking place at various locations. The cit...

  16. Cyanomargarita gen. nov. (Nostocales, Cyanobacteria): convergent evolution resulting in a cryptic genus.

    Science.gov (United States)

    Shalygin, Sergei; Shalygina, Regina; Johansen, Jeffrey R; Pietrasiak, Nicole; Berrendero Gómez, Esther; Bohunická, Markéta; Mareš, Jan; Sheil, Christopher A

    2017-08-01

    Two populations of Rivularia-like cyanobacteria were isolated from ecologically distinct and biogeographically distant sites. One population was from an unpolluted stream in the Kola Peninsula of Russia, whereas the other was from a wet wall in the Grand Staircase-Escalante National Monument, a desert park-land in Utah. Though both were virtually indistinguishable from Rivularia in field and cultured material, they were both phylogenetically distant from Rivularia and the Rivulariaceae based on both 16S rRNA and rbcLX phylogenies. We here name the new cryptic genus Cyanomargarita gen. nov., with type species C. melechinii sp. nov., and additional species C. calcarea sp. nov. We also name a new family for these taxa, the Cyanomargaritaceae. © 2017 Phycological Society of America.

  17. Variabilidad genética en cepas de Sporothrix schenckii aisladas en Abancay, Perú

    Directory of Open Access Journals (Sweden)

    Susan Holechek

    2004-04-01

    Full Text Available Objetivo: Identificar los genotipos de S. schenckii que circulan en 2 distritos de la provincia de Abancay, Perú. Material y Métodos: Se evaluaron 17 cepas procedentes de pacientes con lesiones linfocutáneas y lesión cutánea fija mediante la técnica del ADN Polimorfo Amplificado Aleatorio - Reacción en Cadena de la Polimerasa (RAPD - PCR con el cebador GTG 5 (GTG GTG GTG GTG GTG. Resultados: Identificamos 6 genotipos, siendo el genotipo I el predominante en las áreas de estudio. No se logró asociar los genotipos obtenidos con caracteres clínicos y geográficos. Conclusiones: Nuestros resultados evidencian que existe biodiversidad genética entre las cepas de S. schenckii que circulan en ambas zonas.

  18. AstroGen: A Progress Report

    Science.gov (United States)

    Tenn, Joseph S.; AstroGen Team

    2018-01-01

    Since early 2014 a small group of volunteers has been compiling the world's astronomy-related doctoral dissertations. Working almost entirely with data available online, we have now listed more than 24,000 such theses, including nearly complete coverage of 21 countries: the United States (14,183), United Kingdom (3699), Spain (1091), Netherlands (982), Canada (872), Australia (738), Sweden (375), Greece (239), Argentina (182), Finland (165), Denmark (110), Ireland (103), South Africa (97), New Zealand (87), Norway (79), Chile (42), Iran (25), Mauritius (5), Iceland (3), Pakistan (2), and Ethiopia (1). These numbers are as of mid-September 2017 and subject to revision. For each country we go back to the beginning of the modern Ph.D. or equivalent. Fully half of the doctorates have been earned since 1999. For each thesis we try to include the author (with links to a website or obituary), awarding institution, year of degree, thesis title, link to the thesis if online (about 64% are), translation of title if necessary, advisor(s), and other mentors.Our goal is to emulate the Mathematics Genealogy Project (MGP: http://www.genealogy.ams.org/) with a website having a page for each person with links to that person's advisor(s) and students, if any. We will also have a page for each university. We have posted some introductory material on the website (https://astrogen.aas.org/), and are waiting for help from the AAS IT department to convert our data, currently in spreadsheets, to a database and then a website. We expect this to occur in early 2018.I will present some summaries of our results to date and conduct a discussion of how we can expand our database. We have people currently working on France, Russia, and India, but we need volunteers with linguistic ability and, preferably, familiarity with the academic cultures, to take on Germany, Italy, and nearly all the countries of Asia.

  19. Crescimento de genótipos de frangos tipo caipira

    Directory of Open Access Journals (Sweden)

    R. C. Veloso

    2015-10-01

    Full Text Available RESUMOObjetivou-se com este trabalho comparar o padrão de crescimento, mediante ajustes das respectivas curvas de crescimento por modelos não lineares, bem como estudar o desenvolvimento de cortes de carcaça em relação ao peso da carcaça em diferentes genótipos de frangos tipo caipira. Foram utilizados 840 pintos de um dia, machos, distribuídos em delineamento inteiramente ao acaso, dos seguintes genótipos da linhagem Redbro: Caboclo, Carijó, Colorpak, Gigante Negro, Pesadão Vermelho, Pescoço Pelado e Tricolor. As aves foram alojadas em 28 boxes, sendo 30 aves/boxe, em galpão de alvenaria com acesso a um piquete de 45m², com quatro repetições. O peso corporal individual dos frangos foi medido ao nascer, aos 14, 28, 42, 56, 70 e 84 dias de idade. Para a determinação das curvas de crescimento do peso corporal das aves, os dados coletados foram avaliados por meio dos modelos não lineares: Brody, Gompertz, Logístico, Richards e von Bertalanffy. Foi empregado o PROC NLIN do SAS, utilizando-se o método interativo de Gauss-Newton. Os critérios usados para escolha do modelo de melhor ajuste da curva de crescimento foram o coeficiente de determinação, o desvio padrão assintótico, o desvio médio absoluto dos resíduos e o índice assintótico. As análises para obtenção dos coeficientes alométricos foram realizadas por meio do PROC GLM do SAS para os genótipos Carijó, Colorpak, Pesadão Vermelho, Pescoço Pelado e Tricolor. Foram avaliados os pesos da carcaça, do peito, das coxas, das sobrecoxas, das pernas e das asas das aves abatidas aos 85 dias de idade. Apenas as equações propostas por Gompertz, von Bertalanffy e Logístico atingiram a convergência, e o modelo proposto por von Bertalanffy foi o mais adequado para descrever o crescimento dos genótipos de frangos caipiras. Todos os cortes avaliados apresentaram crescimento tardio em relação ao peso da carcaça em genótipos de frangos tipo caipira.

  20. Some oxozirconium(IV) compounds

    Energy Technology Data Exchange (ETDEWEB)

    Paul, R C; Gupta, S K; Parmar, S S; Vasisht, S K [Punjab Univ., Chandigarh (India). Dept. of Chemistry

    1976-01-01

    Some new oxozirconium(IV) complexes, ZrO(An)/sub 2/, ZrO(Gly)/sub 2/, ZrO(HSal)/sub 2/, ZrO(HPth)/sub 2/, ZrO(Pic)/sub 2/(HPic)/sub 2/, and ZrO(Quin)/sub 2/(HQuin)/sub 2/ have been isolated from the reactions of ZrO(CH/sub 3/COO)/sub 2/CH/sub 3/COOH with anthranilic acid (HAn), glycine (HGly), salicylic acid (H/sub 2/Sal), phthalic acid (H/sub 2/Pth), picolinic acid (HPic), and 8-quinolinol (HQuin) respectively. Their important infrared bands and wherever possible molar conductance and molecular weight have been reported.

  1. The dependence of C IV broad absorption line properties on accompanying Si IV and Al III absorption: relating quasar-wind ionization levels, kinematics, and column densities

    Energy Technology Data Exchange (ETDEWEB)

    Filiz Ak, N.; Brandt, W. N.; Schneider, D. P.; Trump, J. R. [Department of Astronomy and Astrophysics, Pennsylvania State University, University Park, PA 16802 (United States); Hall, P. B. [Department of Physics and Astronomy, York University, 4700 Keele Street, Toronto, Ontario M3J 1P3 (Canada); Anderson, S. F. [Astronomy Department, University of Washington, Seattle, WA 98195 (United States); Hamann, F. [Department of Astronomy, University of Florida, Gainesville, FL 32611-2055 (United States); Myers, Adam D. [Department of Physics and Astronomy, University of Wyoming, Laramie, WY 82071 (United States); Pâris, I. [Departamento de Astronomía, Universidad de Chile, Casilla 36-D, Santiago (Chile); Petitjean, P. [Institut d' Astrophysique de Paris, Universite Paris 6, F-75014 Paris (France); Ross, Nicholas P. [Lawrence Berkeley National Laboratory, 1 Cyclotron Road, Berkeley, CA 94720 (United States); Shen, Yue [Carnegie Observatories, 813 Santa Barbara Street, Pasadena, CA 91101 (United States); York, Don, E-mail: nfilizak@astro.psu.edu [Department of Astronomy and Astrophysics, The University of Chicago, Chicago, IL 60637 (United States)

    2014-08-20

    We consider how the profile and multi-year variability properties of a large sample of C IV Broad Absorption Line (BAL) troughs change when BALs from Si IV and/or Al III are present at corresponding velocities, indicating that the line of sight intercepts at least some lower ionization gas. We derive a number of observational results for C IV BALs separated according to the presence or absence of accompanying lower ionization transitions, including measurements of composite profile shapes, equivalent width (EW), characteristic velocities, composite variation profiles, and EW variability. We also measure the correlations between EW and fractional-EW variability for C IV, Si IV, and Al III. Our measurements reveal the basic correlated changes between ionization level, kinematics, and column density expected in accretion-disk wind models; e.g., lines of sight including lower ionization material generally show deeper and broader C IV troughs that have smaller minimum velocities and that are less variable. Many C IV BALs with no accompanying Si IV or Al III BALs may have only mild or no saturation.

  2. 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.

  3. Las bases genéticas de la longevidad y la hipótesis de las abuelas

    OpenAIRE

    Madrigal, Lorena

    2005-01-01

    La idea de que la longevidad inusual se transmita por vía materna se apoya en observaciones empíricas de que los centenarios tienen una frecuencia alta de ciertos alelos del mtADN en comparación a la población general. Estos estudios han comparado el material genético de centenarios con sujetos de la población general cuando los controles con los que se deberían de comparar los centenarios son los individuos que nacieron en la misma generación pero que no vivieron tantos años. La hipótesis qu...

  4. Genetics Home Reference: glycogen storage disease type IV

    Science.gov (United States)

    ... Home Health Conditions Glycogen storage disease type IV Glycogen storage disease type IV Printable PDF Open All ... Javascript to view the expand/collapse boxes. Description Glycogen storage disease type IV (GSD IV) is an ...

  5. A cerium(IV)-carbon multiple bond

    Energy Technology Data Exchange (ETDEWEB)

    Gregson, Matthew; Lu, Erli; McMaster, Jonathan; Lewis, William; Blake, Alexander J.; Liddle, Stephen T. [Nottingham Univ. (United Kingdom). School of Chemistry

    2013-12-02

    Straightforward access to a cerium(IV)-carbene complex was provided by one-electron oxidation of an anionic ''ate'' cerium(III)-carbene precursor, thereby avoiding decomposition reactions that plague oxidations of neutral cerium(III) compounds. The cerium(IV)-carbene complex is the first lanthanide(IV)-element multiple bond and involves a twofold bonding interaction of two electron pairs between cerium and carbon. [German] Auf direktem Wege zu einem Cer(IV)-Carbenkomplex gelangt man durch die Einelektronenoxidation einer anionischen Carben-Cerat(III)-Vorstufe. So werden Zersetzungsprozesse vermieden, die die Oxidation neutraler Cer(III)-Verbindungen erschweren. Der Cer(IV)-Carbenkomplex enthaelt die erste Lanthanoid(IV)-Element-Mehrfachbindung; dabei binden Cer und Kohlenstoff ueber zwei Elektronenpaare.

  6. iväkoti Riemula

    OpenAIRE

    Alanko, Reetta; Ihanamäki, Katja

    2012-01-01

    Opinnäytetyössä kuvataan yleisesti päivähoidon kehitystä Suomessa sekä päivähoitoa yrittäjän näkökulmasta, tuoden esille sen tämän päivän haasteet ja mahdollisuudet. Työssä on pohdittu yhteistyön merkitystä kunnan kanssa ja sitä, miten kunta voi osaltaan joko rajoittaa tai edesauttaa yksityisen päivähoitoyrityksen toimintaa. Opinnäytetyössä kerrotaan teoriassa Päiväkoti Riemula nimisen, erityispäivähoitopalveluita tarjoavan yrityksen perustamiseen liittyvistä suunnitelmista. Suunnitelluss...

  7. Genetic control of cowpea seed sizes Controle genético do tamanho das sementes de caupi

    Directory of Open Access Journals (Sweden)

    Francisco Cláudio da Conceição Lopes

    2003-01-01

    Full Text Available Cowpea [Vigna unguiculata (L. Walp.] is one of the most widely adapted grain legumes in hot regions of Africa, Asia and the Americas. In the semiarid Northeast of Brazil, it is the main subsistence crop, an excellent protein source of low cost, for the poor population. The objective of this work was to estimate genetic parameters to understand the inheritance of seed sizes in cowpea. The parents P1 and P2 and the generations, F1, F2, BC1 and BC2 of the cross TVx5058-09C X Manteiguinha formed the genetic material for this study. These six generates (P1, P2, F1, F2, BC1 and BC were evaluated in a completely randomized block-design with six replications, in Teresina - PI, Brazil, in 1998. The genetic parameters estimated were: phenotypic and total genetic variance, additive and dominance genetic components of variance and the variance attributed to the environment, heritability in the broad and narrow senses, average degree of dominance and the number of genes controlling the character. The additive - dominance model fitted the data for 100-seeds weight in as much as the midparental value and the additive effect were the more important genetic parameters for the determination of this character. The number of genes that control its expression is five. The occurrence of high values for narrow sense heritability indicates that the selection for seed size can be made in early generations.Caupi [Vigna unguiculata (L. Walp.] é uma das leguminosas mais adaptadas às regiões quentes da África, Ásia e das Américas. No semi-árido do nordeste do Brasil é a principal cultura de subsistência, por ser uma excelente fonte de proteína de baixo custo para a população mais carente. O objetivo deste trabalho foi estimar parâmetros genéticos que podem explicar a herança do tamanho das sementes de caupi. Os genótipos parentais P1 e P2 e as gerações F1, F2, RC1 e RC2 do cruzamento TVx5058-09C X Manteiguinha, constituíram o material genético utilizado

  8. Relationship between microstructure and mechanical properties in ODS materials for nuclear application

    International Nuclear Information System (INIS)

    De Carlan, Y.

    2013-01-01

    Oxide Dispersion Strengthened ferritic/martensitic alloys are developed as prospective cladding materials for future Sodium-Cooled-Fast-Reactors (GEN IV) [1]. These advanced alloys present a good resistance to irradiation and a high creep rupture strength due to a reinforcement by the homogeneous dispersion of hard nano-sized particles (such as Y 2 O 3 or YTiO). ODS alloys are elaborated by powder metallurgy, consolidated by hot extrusion and manufactured into cladding tube using the Pilger cold-rolling process [2, 3]. ODS alloys present usually low ductility and high hardness. The aim of this talk is to present the specificity of the metallurgy of ODS materials in relationship with the main mechanical properties (tensile and creep properties, toughness, transition temperature). Two types of alloys will be presented: Fe-9Cr martensitic ODS and Fe-14Cr ferritic ODS alloys. Mechanical properties of the materials depend on the metallurgical state (fine grains, recrystallized, martensitic) and very different behaviors are observed as a function of final microstructure. For example, for a Fe-9Cr ODS alloy, tempered martensite lets obtaining material with high strength whereas softened ferrite see figure 1 [4] tolerates high deformation levels. (authors)

  9. 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

  10. 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.

  11. Postsynthesis Modification of a Metallosalen-Containing Metal-Organic Framework for Selective Th(IV)/Ln(III) Separation.

    Science.gov (United States)

    Guo, Xiang-Guang; Qiu, Sen; Chen, Xiuting; Gong, Yu; Sun, Xiaoqi

    2017-10-16

    An uncoordinated salen-containing metal-organic framework (MOF) obtained through postsynthesis removal of Mn(III) ions from a metallosalen-containing MOF material has been used for selective separation of Th(IV) ion from Ln(III) ions in methanol solutions for the first time. This material exhibited an adsorption capacity of 46.345 mg of Th/g. The separation factors (β) of Th(IV)/La(III), Th(IV)/Eu(III), and Th(IV)/Lu(III) were 10.7, 16.4, and 10.3, respectively.

  12. BAHAN AJAR BERBASIS PENDIDIKAN KARAKTER UNTUK SISWA KELAS IV SEKOLAH DASAR

    Directory of Open Access Journals (Sweden)

    Pity Asriani

    2017-11-01

    Full Text Available This study aims to produce character education based teaching materials for grade IV elementary school. The writer used the 4D model (Thiagarajan, et al., 1974 for his research and development. The 4D model consists of four stages. They are defining, designing, developing, and disseminating. Types of data used are qualitative. Data were collected by validity testing, questionnaire, observation, and character assessment. This study produced a character education based teaching materials for grade IV elementary school. That is the student book and the teacher book. The results showed that character education based teaching materials for grade IV elementary school is compliant to use in learning since it has met the expected criteria according to the assessment of the material experts, linguists, media experts, teachers, and students. Penelitian ini bertujuan menghasilkan bahan ajar berbasis pendidikan karakter untuk kelas IV Sekolah Dasar. Model penelitian dan pengembangan yang digunakan adalah model pengembangan 4D (Thiagarajan, dkk., 1974. Model 4-D ini terdiri atas tahap pendefinisian (define, perancangan (design, pengembangan (develop, dan penyebaran (disseminate. Jenis data yang digunakan yaitu data kualitatif. Data dikumpulkan melalui uji validasi, angket, observasi, dan penilaian karakter. Penelitian ini menghasilkan bahan ajar berbasis pendidikan karakter untuk kelas IV Sekolah Dasar yang terdiri atas Buku Siswa dan Buku Guru. Hasil penelitian menunjukkan bahwa bahan ajar berbasis pendidikan karakter untuk kelas IV Sekolah Dasar ini telah memenuhi persyaratan untuk digunakan dalam pembelajaran karena telah memenuhi kriteria menurut penilaian ahli materi, ahli bahasa, ahli desain, guru, dan siswa.

  13. Extended analysis of Cu IV

    International Nuclear Information System (INIS)

    Meinders, E.; Uijlings, P.

    1980-01-01

    Wavelength data and classifications of 974 Cu IV lines in the region 750-1275 Angstroem are presented. Most of the lines have been classified as transitions from the previously unknown high even configurations 3d 7 5s and 3d 7 4d to 3d 7 4p. The configuration 3d 7 4d is seriously perturbed by 3d 6 4s 2 . The analysis resulted in the identification of 27 levels of 3d 7 5s and 113 levels of (3d 7 4d + 3d 6 4s 2 ) which are reported. The earlier published levels of 3d 7 4s and 3d 7 4p have to be shifted downward as a consequence of improved wavelength data. Radial paramter values, resulting from least-squares fits, are compared to Hartree-Fock values. The eigenvectors obtained in the parametric fitting are used to calculate transition probabilities in intermediate coupling. The relation between the observed intensities of the transitions 3d 7 4d-3d 7 4p and 3d 7 Ss-3d 7 4p is compared to the relation between theoretical values of the transition integrals obtained from Hartree-Fock calculations. A spectroscopic value for the ionization potentials is calculated from the 3d 7 ns configurations. (orig.)

  14. 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)

  15. Distancias genéticas en poblaciones del NOA

    Directory of Open Access Journals (Sweden)

    Acreche, Noemí

    1996-01-01

    Full Text Available La mayor parte de los trabajos realizados en nuestro país sobre polimorfismos hematológicos, abordan la necesaria descripción de las poblaciones. Se pone de relieve la importancia de encarar estudios, en base a la valiosa información publicada, que vinculen los grupos con técnicas que permitan realizar nuevas inferencias sobre sus relaciones. Conocidas en gran medida en cuanto a sus manifestaciones culturales, pueden aportar desde lo genético a la comprensión de los procesos microevolutivos ocurridos en una región. Para el NOA, se ha considerado la presencia de comunidades aborígenes incluídas en cuatro familias lingüísticas. Se tendrán en cuenta estos complejos como representativos de afinidades que se establecen a partir de estrechas relaciones entre las etnias, no sólo por la lengua, sino también por las características de sus sistemas productivos, religiosidad y organización. En base a las frecuencias génicas publicadas correspondientes a los siguientes alelos: I*A, I*B, I*O; M, N, S, s; Dia , Dib; P1, P2; C, c; D, d, E, e; Le, le; Fya, Fyb; Jka, Jkb; K y k se construyeron tablas de frecuencias. Se estimaron los coeficientes de distancias genéticas que fueron analizados y posteriormente incluídos en la construcción de un fenograma de los grupos de estudio, mediante agrupaciones (Sahn Cluster secuenciales, aglomerativas, jerárquicas y anidadas. De acuerdo a la información recopilada de las frecuencias de los 25 alelos estudiados en trece poblaciones de aborígenes del NOA y Paraguay, las distancias genéticas obtenidas reflejan los caracteres lingüístico-culturales.

  16. 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.

  17. La fiction de Madame de Genlis, espace d’interrogation

    Directory of Open Access Journals (Sweden)

    Isabelle Tremblay

    2013-09-01

    Full Text Available The novel constitutes an ideal genre in which to discuss a central question in the eighteenth century: virtue. As opposed to her contemporaries, Mme de Genlis depicts virtue as a state of mind attained through independence and self-confidence rather than through the atonement of one’s faults. How do her heroines realize their potential? Are they able to find a middle ground between their perception of their roles and identity and the expectations that weigh on them? What paths are available to them?

  18. Sistema genérico de replicación

    OpenAIRE

    Jiménez Ortiz, Raúl

    2014-01-01

    Este proyecto se desarrolla en una de las principales compañías eléctricas de España, y trata sobre la creación de un sistema genérico de replicación de datos. La idea surge de la necesidad de estandarizar la forma de traspasar información entre departamentos o sistemas, debido a que existen gran variedad de interfaces diferentes, y cada vez que surge la necesidad de crear una implica nuevos costes de desarrollo, mantenimiento y futuros evolutivos. Entre los diferentes departamentos de ...

  19. TrayGen: Arranging objects for exhibition and packaging

    KAUST Repository

    Yang, Yongliang

    2013-10-01

    We present a framework, called TrayGen, to generate tray designs for the exhibition and packaging of a collection of objects. Based on principles from shape perception and visual merchandising, we abstract a number of design guidelines on how to organize the objects on the tray for the exhibition of their individual features and mutual relationships. Our framework realizes these guidelines by analyzing geometric shapes of the objects and optimizing their arrangement. We demonstrate that the resultant tray designs not only save space, but also highlight the characteristic of each object and the inter-relations between objects. © 2013 The Eurographics Association and John Wiley & Sons Ltd.

  20. Justicia en salud y genética

    OpenAIRE

    Maria Graciela De Ortuzar

    2014-01-01

    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,...

  1. GenHyPEM: an EC-supported STREP program on high pressure PEM water electrolysis

    International Nuclear Information System (INIS)

    Millet, P.

    2006-01-01

    GenHyPEM (generateur d'hydrogene PEM) is an international research project related to the electrolytic production of hydrogen from water, using proton exchange membrane (PEM) - based electrochemical generators. The specificity of this project is that all basic research efforts are devoted to the optimization of already existing electrolysers of industrial size, in order to facilitate the introduction of this technology in the industry and to propose technological solutions for the industrial and domestic production of electrolytic hydrogen. GenHyPEM is a three years long research program financially supported by the European Commission, gathering partners from academic institutions and from the industry, in order to reach three main technological objectives aimed at improving the performances of current 1000 Nliter/hour H 2 industrial PEM water electrolysers: (i) Development of alternative low-cost membrane electrode assemblies and stack components with electrochemical performances similar to those of state-of-the-art systems. The objectives are the development of nano-scaled electrocatalytic structures for reducing the amount of noble metals; the synthesis and characterization of non-noble metal catalytic compounds provided by molecular chemistry and bio-mimetic approaches; the preparation of new composite membrane materials for high current density, high pressure and high temperature operation; the development and optimization of low-cost porous titanium sheets acting as current collectors in the electrolysis stack; (ii) Development of an optimized stack structure for high current density (1 A.cm-2) and high pressure (50 bars) operation for direct pressurized storage; (iii) Development of an automated and integrated electrolysis unit allowing gas production from intermittent renewable sources of energy such as photovoltaic-solar and wind. Current status of the project as well as perspectives are described in this paper. This project, coordinated by University of

  2. Irradiation Test in HANARO of the Parts of an X-Gen Nuclear Fuel Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Choo, K. N.; Kim, B. G.; Kang, Y. H. (and others)

    2008-08-15

    An instrumented capsule of 07M-13N was designed, fabricated and irradiated for an evaluation of the neutron irradiation properties of the parts of an X-Gen nuclear fuel assembly for PWR requested by KNF. Some specimens requested by Westinghouse Co. and Hanyang university were also inserted. 389 KNF specimens such as bucking and spring test specimens of 1x1 cell spacer grid, tensile, microstructure and tensile of welded parts, irradiation growth, spring test specimens made of HANA tube, Zirlo, Zircaloy-4, Inconel-718 were placed in the capsule. The capsule was composed of 5 stages having many kinds of specimens and an independent electric heater at each stage. During the irradiation test, the temperature of the specimens and the thermal/fast neutron fluences were measured by 14 thermocouples and 7 sets of Ni-Ti-Fe (2 sets contain additional Nb-Ag) neutron fluence monitors installed in the capsule. The capsule was irradiated for 59.19days (4 cycles) in the CT test hole of HANARO of a 30MW thermal output at 300 {approx} 420 .deg. C(for KNF specimens) up to a fast neutron fluence of 1.27x10{sup 21}(n/cm{sup 2}) (E>1MeV). After an irradiation test, the main body of the capsule was cut off at the bottom of the protection tube with a cutting system and it was transported to the IMEF (Irradiated Materials Examination Facility). The irradiated specimens were tested to evaluate the irradiation performance of the parts of an X-Gen fuel assembly in the IMEF hot cell.

  3. FRECUENCIAS ALELICAS Y GENOTIPICAS DEL GEN KAPPA CASEINA EN BOVINOS DE DOBLE PROPOSITO

    Directory of Open Access Journals (Sweden)

    Nohémi Gabriela Cortes López

    2012-01-01

    Full Text Available En este trabajo, las frecuencias alélicas (A y B del gen CAS se determinaron como criterio de selección en la calidad de la leche en el ganado bovino de doble propósito. Se tomaron muestras sanguíneas de 200 hembras bovinas y se colocaron en tubos que contenían EDTA. Se amplifico el marcador MB002 a partir de material genético extraído. Los RFLP se realizaron con la enzima de restricción Hinf I para el diagnóstico de los alelos A y B en CASκ. Las frecuencias genotípicas obtenidas correspondían a 0.34, 0.01 y 0.65 para los alelos AA, BB y AB, respectivamente. Las frecuencias alélicas fueron de 0.67 y 0.33 para los alelos A y B, respectivamente. Además, se registró una heterocigosidad promedio de 0.6481. La población es estudio no se encuentra en equilibrio Hardy Weinberg, el valor ji cuadrada fue de 2 = 14.8 con 2 grados de libertad (P < 0.005. Basado en la frecuencia alélica de CAS  B (0.34 observada en este estudio, el ganado de doble propósito puede ser una opción viable para aumentar la calidad de la leche si se utilizan sementales con el genotipo BB para el cruce. De esta manera, los alelos B asociados a la calidad de la leche pueden mejorarse en pocas generaciones.

  4. PREFACE: International Symposium on Vacuum Science & Technology and its Application for Accelerators (IVS 2012)

    Science.gov (United States)

    Pandit, V. S.; Pal, Gautam

    2012-11-01

    The Indian Vacuum Society (IVS) was established in 1970 to promote vacuum science and technology in academic, industrial and R&D institutions in India. IVS is a member society of the International Union for Vacuum Science, Technique and Applications (IUVSTA). It has organized International and national symposia, short term courses and workshops on different aspects of Vacuum Science and Technology at regular intervals. So far 27 National symposia, 4 International Symposia and 47 courses have been organized at various locations in India. There has been an active participation from R&D establishments, universities and Indian industries during all these events. In view of the current global situation and emerging trends in vacuum technology, the executive committee of the IVS suggested to us that we organize an International Symposium at the Variable Energy Cyclotron Centre, Kolkata from 15-17 February 2012. At the Variable Energy Cyclotron Centre we have a large number of high vacuum systems used in the K130 Cyclotron and K500 Superconducting Cyclotron. Also a large cryogenic system using LHe plant is in operation for cryopanels and a superconducting magnet for K-500 Cyclotron. The main areas covered at the symposium were the production and measurement of vacuums, leak detection, design and development of large vacuum systems, vacuum metallurgy, vacuum materials and the application of high vacuums in cyclotrons, LINACS and other accelerators. This symposium provided an opportunity for interaction between active researchers and technologists and allowed them to review the current situation, report recent experimental results, share the available expertise and consider the future R&D efforts needed in this area. Keeping the industrial significance of vacuum technology in mind, an exhibition of the vacuum related equipment, accessories, products etc by various suppliers and manufactures was organized alongside the symposium. Participation by a large number of exhibitors

  5. Parâmetros e tendência genética da produção de leite de cabra no Brasil

    Directory of Open Access Journals (Sweden)

    Gonçalves Heraldo Cesar

    2002-01-01

    Full Text Available A caprinocultura leiteira no Brasil, apesar de ser uma atividade rural consolidada há algumas décadas, tem se mostrado totalmente dependente de outros países no que se refere ao melhoramento genético. A maioria dos plantéis existentes atualmente tem como base animais importados, e a renovação do material genético é feita por meio da importação de sêmen. Inexistem informações sobre o valor genético dos animais e sua evolução no decorrer dos anos. No presente trabalho, foram estimadas a herdabilidade e a repetibilidade da produção de leite utilizando o REML. Os valores obtidos foram 0,21557 e 0,21564, respectivamente. Para a predição do valor gênico dos animais, foi usado o procedimento BLUP com modelo animal. A mudança na tendência genética anual estimada por um modelo quadrático foi -0,8109 kg/ano², indicando desaceleração no ganho genético. A correlação de Pearson entre os valores gênicos dos bodes estimados com base na média da capacidade provável de produção das filhas obtida pelo método de mínimos quadrados com as estimadas pelas equações do modelo misto foi de 0,5751. A correlação de SPEARMAN entre as classificações dos bodes obtidos pelos dois métodos foi de 0,5813.

  6. Zirconium (IV) complexes with some polymethylenediimines | Na ...

    African Journals Online (AJOL)

    The syntheses of zirconium (IV) complexes have been carried out by the reaction of oxozirconium (IV) chloride with the appropriate diimines (Schiff bases). The complexes were isolated as yellow solids which are stable to heat. The complexes were found to be insoluble in most solvents. The infrared spectra, elemental ...

  7. Astragaloside IV liposomes ameliorates adriamycin-induced ...

    African Journals Online (AJOL)

    Methods: The rats were given a single tail intravenous injection of adriamycin (6 mg/kg) within 1 week, and then divided into four groups including normal, model, benazepril and astragaloside IV liposomes group. They were all orally administered dosage of benazepril and astragaloside IV liposomes once daily for 8 weeks.

  8. Generation IV reactors: international projects

    International Nuclear Information System (INIS)

    Carre, F.; Fiorini, G.L.; Kupitz, J.; Depisch, F.; Hittner, D.

    2003-01-01

    Generation IV international forum (GIF) was initiated in 2000 by DOE (American department of energy) in order to promote nuclear energy in a long term view (2030). GIF has selected 6 concepts of reactors: 1) VHTR (very high temperature reactor system, 2) GHR (gas-cooled fast reactor system), 3) SFR (sodium-cooled fast reactor system, 4) SCWR (super-critical water-cooled reactor system), 5) LFR (lead-cooled fast reactor system), and 6) MFR (molten-salt reactor system). All these 6 reactor systems have been selected on criteria based on: - a better contribution to sustainable development (through their aptitude to produce hydrogen or other clean fuels, or to have a high energy conversion ratio...) - economic profitability, - safety and reliability, and - proliferation resistance. The 6 concepts of reactors are examined in the first article, the second article presents an overview of the results of the international project on innovative nuclear reactors and fuel cycles (INPRO) within IAEA. The project finished its first phase, called phase-IA. It has produced an outlook into the future role of nuclear energy and defined the need for innovation. The third article is dedicated to 2 international cooperations: MICANET and HTR-TN. The purpose of MICANET is to propose to the European Commission a research and development strategy in order to develop the assets of nuclear energy for the future. Future reactors are expected to be more multiple-purposes, more adaptable, safer than today, all these developments require funded and coordinated research programs. The aim of HTR-TN cooperation is to promote high temperature reactor systems, to develop them in a long term perspective and to define their limits in terms of burn-up and operating temperature. (A.C.)

  9. 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)

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

    Directory of Open Access Journals (Sweden)

    Fernández Alonso J. L.

    1991-06-01

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

  11. Basis for the safety approach for design and assessment of Generation IV nuclear systems

    International Nuclear Information System (INIS)

    Fiorini, G.L.; Leahy, T.

    2009-01-01

    The primary objective of the RSWG is the implementation of a harmonized approach on long-term safety, and to address risk and regulatory issues in development of the next generation of nuclear systems. To this end, the group is proposing safety goals and evaluation methodology applicable for the design and assessment of future systems. The paper resumes the content of the first RSWG report which provides insights for the safety approach and assists the GIF Systems Steering Committee as well as the GIF Experts Group and the GIF Policy Group for the definition of the most adequate safety related Gen IV R and D. The document is also an essential contributor to help identifying the needed supportive crosscut R and D effort (i.e. applicable to all the innovative nuclear technologies). Although the report presents a number of thoughts and recommendations, it really represents only the start of the efforts for the RSWG. (author)

  12. Enfermedades genéticas del ADN mitocondrial humano

    Directory of Open Access Journals (Sweden)

    Solano Abelardo

    2001-01-01

    Full Text Available Las enfermedades mitocondriales son un grupo de trastornos que están producidos por un fallo en el sistema de fosforilación oxidativa (sistema Oxphos, la ruta final del metabolismo energético mitocondrial, con la consiguiente deficiencia en la biosíntesis del trifosfato de adenosina (ATP, por sus siglas en inglés. Parte de los polipéptidos que componen este sistema están codificados en el ácido desoxirribonucleico (DNA mitocondrial y, en los últimos años, se han descrito mutaciones que se han asociado con síndromes clínicos bien definidos. Las características genéticas del DNA mitocondrial, herencia materna, poliplasmia y segregación mitótica, confieren a estas enfermedades propiedades muy particulares. Las manifestaciones clínicas de estas enfermedades son muy heterogéneas y afectan a distintos órganos y tejidos por lo que su correcto diagnóstico implica la obtención de datos clínicos, morfológicos, bioquímicos y genéticos. El texto completo en inglés de este artículo está disponible en: http://www.insp.mx/salud/index.html

  13. PowerGen plc report and accounts 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    Detailed financial results are presented for the United Kingdom power generation company PowerGen for the year ended 2 April 1995. A review is given of operating and financial performance. Significant reductions in operating costs and improvements in productivity have been achieved. Diversity of fuels and plant portfolio has been enhanced by building 3000 MW of gas fired CCGT plant. Investment in coal import facilities has increased access to international coal markets. Environmental performance has improved with further reductions in SO{sub 2}, NO{sub x} and CO{sub 2} emissions. Overseas projects include construction of 990 MW CCGT power station in Portugal and a contract to build the 1200 MW Paiton 2 coal-fired power station in Indonesia. Investment in lignite mining and power generation assets of MIBRAG in Germany is contributing to profits. PowerGen`s five year contract for coal supply was assigned to RJB Mining (UK) Ltd. during the year. Stocks of coal fell during the year and further reductions are expected during 1995/96.

  14. 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

  15. Gridded precipitation dataset for the Rhine basin made with the genRE interpolation method

    NARCIS (Netherlands)

    Osnabrugge, van B.; Uijlenhoet, R.

    2017-01-01

    A high resolution (1.2x1.2km) gridded precipitation dataset with hourly time step that covers the whole Rhine basin for the period 1997-2015. Made from gauge data with the genRE interpolation scheme. See "genRE: A method to extend gridded precipitation climatology datasets in near real-time for

  16. A 48-plex autosomal SNP GenPlex™ assay for human individualization and relationship testing

    DEFF Research Database (Denmark)

    Tomas Mas, Carmen; Børsting, Claus; Morling, Niels

    2012-01-01

    SNPs are being increasingly used by forensic laboratories. Different platforms have been developed for SNP typing. We describe the GenPlex™ HID system protocol, a new SNP-typing platform developed by Applied Biosystems where 48 of the 52 SNPforID SNPs and amelogenin are included. The GenPlex™ HID...

  17. Group-IV midinfrared plasmonics

    Science.gov (United States)

    Biagioni, Paolo; Frigerio, Jacopo; Samarelli, Antonio; Gallacher, Kevin; Baldassarre, Leonetta; Sakat, Emilie; Calandrini, Eugenio; Millar, Ross W.; Giliberti, Valeria; Isella, Giovanni; Paul, Douglas J.; Ortolani, Michele

    2015-01-01

    The use of heavily doped semiconductors to achieve plasma frequencies in the mid-IR has been recently proposed as a promising way to obtain high-quality and tunable plasmonic materials. We introduce a plasmonic platform based on epitaxial n-type Ge grown on standard Si wafers by means of low-energy plasma-enhanced chemical vapor deposition. Due to the large carrier concentration achieved with P dopants and to the compatibility with the existing CMOS technology, SiGe plasmonics hold promises for mid-IR applications in optoelectronics, IR detection, sensing, and light harvesting. As a representative example, we show simulations of mid-IR plasmonic waveguides based on the experimentally retrieved dielectric constants of the grown materials.

  18. Creep resistance and material degradation of a candidate Ni–Mo–Cr corrosion resistant alloy

    Energy Technology Data Exchange (ETDEWEB)

    Shrestha, Sachin L., E-mail: sachin@ansto.gov.au [Institute of Materials Engineering, Australian Nuclear Science and Technology Organisation (ANSTO), Locked Bag 2001, Kirrawee DC, NSW 2232 (Australia); Bhattacharyya, Dhriti [Institute of Materials Engineering, Australian Nuclear Science and Technology Organisation (ANSTO), Locked Bag 2001, Kirrawee DC, NSW 2232 (Australia); Yuan, Guangzhou; Li, Zhijun J. [Center of Thorium Molten Salts Reactor System, Shanghai Institute of Applied Physics, Chinese Academy of Sciences (China); Budzakoska-Testone, Elizabeth; De Los Reyes, Massey; Drew, Michael; Edwards, Lyndon [Institute of Materials Engineering, Australian Nuclear Science and Technology Organisation (ANSTO), Locked Bag 2001, Kirrawee DC, NSW 2232 (Australia)

    2016-09-30

    This study investigated the creep deformation properties of GH3535, a Ni–Mo–Cr corrosion resistant structural alloy being considered for use in future Gen IV molten salt nuclear reactors (MSR) operating at around 700 °C. Creep testing of the alloy was conducted at 650–750 °C under applied stresses between 85–380 MPa. From the creep rupture results the long term creep strain and rupture life of the alloy were estimated by applying the Dorn Shepard and Larson Miller time-temperature parameters and the alloy's allowable ASME design stresses at the MSR's operating temperature were evaluated. The material's microstructural degradation at creep rupture was characterised using scanning electron microscopy (SEM), electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM). The microstructural study revealed that the material failure was due to wedge cracking at triple grain boundary points and cavitation at coarse secondary grain boundary precipitates, nucleated and grown during high temperature exposure, leading to intergranular crack propagation. EBSD local misorientation maps clearly show that the root cause of cavitation and crack propagation was due to large strain localisation at the grain boundaries and triple points instigated by grain boundary sliding during creep deformation. This caused the grain boundary decohesion and subsequent material failure.

  19. Research Reactors for the Development of Materials and Fuels for Innovative Nuclear Energy Systems

    International Nuclear Information System (INIS)

    2017-01-01

    This publication presents an overview of research reactor capabilities and capacities in the development of fuels and materials for innovative nuclear reactors, such as GenIV reactors. The compendium provides comprehensive information on the potential for materials and fuel testing research of 30 research reactors, both operational and in development. This information includes their power levels, mode of operation, current status, availability and historical overview of their utilization. A summary of these capabilities and capacities is presented in the overview tables of section 6. Papers providing a technical description of the research reactors, including their specific features for utilization are collected as profiles on a CD-ROM and represent an integral part of this publication. The publication is intended to foster wider access to information on existing research reactors with capacity for advanced material testing research and thus ensure their increased utilization in this particular domain. It is expected that it can also serve as a supporting tool for the establishment of regional and international networking through research reactor coalitions and IAEA designated international centres based on research reactors.

  20. 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.

  1. 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...

  2. Eustochomorpha Girault, Neotriadomerus gen. n., and Proarescon gen. n. (Hymenoptera, Mymaridae, early extant lineages in evolution of the family

    Directory of Open Access Journals (Sweden)

    John T. Huber

    2017-06-01

    Full Text Available Eustochomorpha Girault, with one described species, E. haeckeli Girault, from Australia is redescribed. Neotriadomerus Huber, gen. n., is described, together with seven new species, all from Australia: N. burwelli Huber, sp. n., N. crassus Huber, sp. n., N. darlingi Huber, sp. n., N. gloriosus Huber, sp. n., N. longiovipositor Huber, sp. n., N. longissimus Huber, sp. n. (one of the largest species of Mymaridae, and N. powerae Huber, sp. n. Proarescon Huber, gen. n., is described for P. primitivum (Huber, comb. n., transferred from Borneomymar Huber, and P. similis Huber, sp. n., from Thailand. The previously unknown male of Borneomymar madagascar Huber is described and the genus is redescribed from critical point dried and slide mounted specimens. Triadomerini, stat. n., is proposed to include six genera: Borneomymar, Eustochomorpha and Neotriadomerus, and the Cretaceous Carpenteriana Yoshimoto, Macalpinia Yoshimoto and Triadomerus Yoshimoto. Aresconini is proposed to include five (possibly six genera: Arescon Enock, Kikiki Huber and Beardsley, Proarescon Huber and Tinkerbella Huber and Noyes, and the Cretaceous Myanmymar Huber and, tentatively, also Enneagmus Yoshimoto. The two tribes are proposed as being the earliest lineages in Mymaridae, with Neotriadomerus and Triadomerus being sister genera to the remaining extant and extinct genera, respectively.

  3. Características qualitativas de genótipos de cebola Qualitative characteristics of onion genotypes

    Directory of Open Access Journals (Sweden)

    Leilson Costa Grangeiro

    2008-08-01

    Full Text Available Objetivou-se, com o trabalho, avaliar alguns atributos de qualidade de diferentes genótipos de cebola (Allium cepa L., cultivados em Mossoró-RN. O experimento foi realizado na horta experimental no Departamento de Ciências Vegetais da Universidade Federal Rural do Semi-Árido, em delineamento de blocos casualizados completos e quatro repetições. Os tratamentos foram constituídos pelos genótipos de cebola CNPH 6415, CNPH 6047, CNPH 6244, CNPH 6400 Chata, CNPH 6400 Redonda, CPACT 1, CPACT 2, CPACT 3, Granex 429, Belém IPA 9, BRS Cascata, Crioula Alto Vale, Bola Precoce, Primavera, Régia, Valeouro IPA-11, Brisa e Alfa São Francisco. As características avaliadas foram teor de sólidos solúveis totais, acidez total titulável, teor de vitamina C e teor de ácido pirúvico (pungência. Foram observadas diferenças significativas entre os genótipos para todas as características avaliadas. Os genótipos apresentaram uma variação significativa para todas as características avaliadas, confirmando dessa forma que o fator genético é determinante na caracterização de cada material. O teor de sólidos solúveis totais variou de 6,67 a 11,63 (º Brix, vitamina C de 22,7 a 46,81 (mg ácido ascórbico/100 ml de suco e a acidez total titulável de 0,19 a 0,45 (% de ácido pirúvico. Os genótipos apresentaram pungência intermediária com variação de 5,0 a 12,73 (µmol/g, sendo os menos pungentes Granex 429, CNPH 6047, Régia, Primavera e Belém IPA 9.The aim of this work was to evaluate some attributes of quality of different genotypes of onion (Allium cepa L., cultivated in Mossoró-RN. The experiment was carried out in the vegetable garden of Plant Science Department at Universidade Federal Rural do Semi-Árido. The experimental outline was of randomized complete blocks with four replications. The treatments were constituted by the genotypes of onion CNPH 6415, CNPH 6047, CNPH 6244, CNPH 6400 Chata, CNPH 6400 Redonda, CPACT 1, CPACT 2

  4. Adduct formation in Ce(IV) thenolytrifluoroacetonate

    International Nuclear Information System (INIS)

    Anufrieva, S.I.; Polyakova, G.V.; Snezhko, N.I.; Pechurova, N.I.; Martynenko, L.I.; Spitsyn, V.I.

    1982-01-01

    The literature contains no information on adduct formation in Ce(IV) β-diketonates with additional ligands. Since tetrakis-β-diketonates of Ce(IV) have four six-membered chelate rings, we can suppose that the introduction of an additional monodentate or bidentate ligand into the coordination sphere of Ce(IV) β-diketonates would lead to an increase in the coordination number (CN) of the Ce(IV) to nine or ten. The possibility of realization of such a high CN for Ce(IV) has not been proved; a study of adduct formation by Ce(IV) tetrakis-β-diketonates is thus of theoretical interest. Such an investigation might also be of practical interest, because the introduction of an additional ligand into the coordination sphere of a rare-earth β-diketonate usually increases the solubility of the β-diketonate in nonpolar solvents and increases the volatility of the compound; such a modification of the properties is important for various practical purposes. The aim of our work was to study the possibility of separating solid adducts of Ce(IV) tetrakis-thenoyltrifluoroacetonate with certain oxygen-containing and nitrogen-containing donor monodentate and bidentate ligands, and also to investigate their properties. As the β-diketone we used thenoyltrifluoroacetone (HTTFA), since in a parallel investigation it was found that Ce(TTFA) 4 has a high oxidation-reduction stability

  5. Plutonium(IV) precipitates formed in alkaline media in the presence of various anions

    Energy Technology Data Exchange (ETDEWEB)

    Krot, N.N.; Shilov, V.P.; Yusov, A.B.; Tananaev, I.G.; Grigoriev, M.S.; Garnov, A.Yu.; Perminov, V.P.; Astafurova, L.N.

    1998-09-01

    The tendency of Pu(IV) to hydrolyze and form true solutions, colloid solutions, or insoluble precipitates has been known since the Manhattan Project. Since then, specific studies have been performed to examine in detail the equilibria of Pu(IV) hydrolytic reactions in various media. Great attention also has been paid to the preparation, structure, and properties of Pu(IV) polymers or colloids. These compounds found an important application in sol-gel technology for the preparation of nuclear fuel materials. A most important result of these works was the conclusion that Pu(IV) hydroxide, after some aging, consists of very small PuO{sub 2} crystallites and should therefore be considered to be Pu(IV) hydrous oxide. However, studies of the properties and behavior of solid Pu(IV) hydroxide in complex heterogeneous systems are rare. The primary goal of this investigation was to obtain data on the composition and properties of Pu(IV) hydrous oxide or other compounds formed in alkaline media under different conditions. Such information is important to understand Pu(IV) behavior and the forms of its existence in the Hanford Site alkaline tank waste sludge. This knowledge then may be applied in assessing plutonium criticality hazards in the storage, retrieval, and treatment of Hanford Site tank wastes as well as in understanding its contribution to the transuranic waste inventory (threshold at 100 nCi/g or about 5 {times} 10{sup {minus}6} M) of the separate solution and solid phases.

  6. Plutonium(IV) precipitates formed in alkaline media in the presence of various anions

    International Nuclear Information System (INIS)

    Krot, N.N.; Shilov, V.P.; Yusov, A.B.; Tananaev, I.G.; Grigoriev, M.S.; Garnov, A.Yu.; Perminov, V.P.; Astafurova, L.N.

    1998-09-01

    The tendency of Pu(IV) to hydrolyze and form true solutions, colloid solutions, or insoluble precipitates has been known since the Manhattan Project. Since then, specific studies have been performed to examine in detail the equilibria of Pu(IV) hydrolytic reactions in various media. Great attention also has been paid to the preparation, structure, and properties of Pu(IV) polymers or colloids. These compounds found an important application in sol-gel technology for the preparation of nuclear fuel materials. A most important result of these works was the conclusion that Pu(IV) hydroxide, after some aging, consists of very small PuO 2 crystallites and should therefore be considered to be Pu(IV) hydrous oxide. However, studies of the properties and behavior of solid Pu(IV) hydroxide in complex heterogeneous systems are rare. The primary goal of this investigation was to obtain data on the composition and properties of Pu(IV) hydrous oxide or other compounds formed in alkaline media under different conditions. Such information is important to understand Pu(IV) behavior and the forms of its existence in the Hanford Site alkaline tank waste sludge. This knowledge then may be applied in assessing plutonium criticality hazards in the storage, retrieval, and treatment of Hanford Site tank wastes as well as in understanding its contribution to the transuranic waste inventory (threshold at 100 nCi/g or about 5 x 10 -6 M) of the separate solution and solid phases

  7. 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

  8. Influence of shelf life on the setting time of type IV gypsum

    Science.gov (United States)

    Hapsari, M. L.; Irawan, B.; Damiyanti, M.

    2017-08-01

    Although expired materials can exhibit a deterioration in their properties, expired type IV gypsum can still be found on the market. In order to evaluate the influence of the shelf life on its setting time, two groups of type IV gypsum (GC Fuji rock EP) with different expiration dates were used in this research. The setting time tests were done in a mold using a Vicat Needle apparatus. The results of the statistical analysis showed a significant difference (pshelf life did influence the setting time of the type IV gypsum.

  9. Market opportunities: U.S. - PADD IV

    International Nuclear Information System (INIS)

    Garner, R.P.

    1997-01-01

    The current supply and demand balance, the short and long term expectations and marketing opportunities for Canadian crude oil in PADD IV, the Rocky Mountain region in the US, were reviewed. It was suggested that market opportunities in PADD IV are derived from the following four factors: (1) crude oil declines within that area, (2) federal regulations, (3) competitive presence with markets, and (4) population growth. The overall conclusion was that Canadian producers and PADD IV refiners will be looking at an ever-growing relationship based on freight equalized world crude prices. 8 tabs., 5 figs

  10. Las bases genéticas de la longevidad y la hipótesis de las abuelas

    Directory of Open Access Journals (Sweden)

    Madrigal, Lorena

    2005-01-01

    Full Text Available La idea de que la longevidad inusual se transmita por vía materna se apoya en observaciones empíricas de que los centenarios tienen una frecuencia alta de ciertos alelos del mtADN en comparación a la población general. Estos estudios han comparado el material genético de centenarios con sujetos de la población general cuando los controles con los que se deberían de comparar los centenarios son los individuos que nacieron en la misma generación pero que no vivieron tantos años. La hipótesis que queremos investigar es si algunos haplotipos del mtADN le han dado una ventaja evolutiva a ciertas líneas mitocondriales por medio de una longevidad avanzada, particularmente a las mujeres. La hipótesis de las abuelas propone que la menopausia evolucionó para incrementar la contribución genética de las mujeres, no por medio de su propia fertilidad, sino por medio de la fertilidad de sus hijas. Es decir, la contribución genética de abuelas longevas va a ser mayor que la de aquéllas que mueren temprano. En ésta ponencia, expongo los resultados de un proyecto que incluye miembros de la University of South Florida, Universidad de Costa Rica y de la Universidad de Bologna. En éste estudio evitamos los problemas metodológicos ya citados, y comparamos el mtADN de individuos longevos y no longevos, por generación, habiendo obtenido el mtADN de 150 descendientes vivientes. Adicionalmente, sometemos a prueba la hipótesis de que la longevidad de la abuela se puede correlacionar estadísticamente con una mayor fertilidad de la hija, por generaciones.

  11. Assessment of Response to Lithium Maintenance Treatment in Bipolar Disorder: A Consortium on Lithium Genetics (ConLiGen) Report

    Science.gov (United States)

    Manchia, Mirko; Adli, Mazda; Akula, Nirmala; Ardau, Raffaella; Aubry, Jean-Michel; Backlund, Lena; Banzato, Claudio EM.; Baune, Bernhard T.; Bellivier, Frank; Bengesser, Susanne; Biernacka, Joanna M.; Brichant-Petitjean, Clara; Bui, Elise; Calkin, Cynthia V.; Cheng, Andrew Tai Ann; Chillotti, Caterina; Cichon, Sven; Clark, Scott; Czerski, Piotr M.; Dantas, Clarissa; Zompo, Maria Del; DePaulo, J. Raymond; Detera-Wadleigh, Sevilla D.; Etain, Bruno; Falkai, Peter; Frisén, Louise; Frye, Mark A.; Fullerton, Jan; Gard, Sébastien; Garnham, Julie; Goes, Fernando S.; Grof, Paul; Gruber, Oliver; Hashimoto, Ryota; Hauser, Joanna; Heilbronner, Urs; Hoban, Rebecca; Hou, Liping; Jamain, Stéphane; Kahn, Jean-Pierre; Kassem, Layla; Kato, Tadafumi; Kelsoe, John R.; Kittel-Schneider, Sarah; Kliwicki, Sebastian; Kuo, Po-Hsiu; Kusumi, Ichiro; Laje, Gonzalo; Lavebratt, Catharina; Leboyer, Marion; Leckband, Susan G.; López Jaramillo, Carlos A.; Maj, Mario; Malafosse, Alain; Martinsson, Lina; Masui, Takuya; Mitchell, Philip B.; Mondimore, Frank; Monteleone, Palmiero; Nallet, Audrey; Neuner, Maria; Novák, Tomás; O’Donovan, Claire; Ösby, Urban; Ozaki, Norio; Perlis, Roy H.; Pfennig, Andrea; Potash, James B.; Reich-Erkelenz, Daniela; Reif, Andreas; Reininghaus, Eva; Richardson, Sara; Rouleau, Guy A.; Rybakowski, Janusz K.; Schalling, Martin; Schofield, Peter R.; Schubert, Oliver K.; Schweizer, Barbara; Seemüller, Florian; Grigoroiu-Serbanescu, Maria; Severino, Giovanni; Seymour, Lisa R.; Slaney, Claire; Smoller, Jordan W.; Squassina, Alessio; Stamm, Thomas; Steele, Jo; Stopkova, Pavla; Tighe, Sarah K.; Tortorella, Alfonso; Turecki, Gustavo; Wray, Naomi R.; Wright, Adam; Zandi, Peter P.; Zilles, David; Bauer, Michael; Rietschel, Marcella; McMahon, Francis J.

    2013-01-01

    Objective The assessment of response to lithium maintenance treatment in bipolar disorder (BD) is complicated by variable length of treatment, unpredictable clinical course, and often inconsistent compliance. Prospective and retrospective methods of assessment of lithium response have been proposed in the literature. In this study we report the key phenotypic measures of the “Retrospective Criteria of Long-Term Treatment Response in Research Subjects with Bipolar Disorder” scale currently used in the Consortium on Lithium Genetics (ConLiGen) study. Materials and Methods Twenty-nine ConLiGen sites took part in a two-stage case-vignette rating procedure to examine inter-rater agreement [Kappa (κ)] and reliability [intra-class correlation coefficient (ICC)] of lithium response. Annotated first-round vignettes and rating guidelines were circulated to expert research clinicians for training purposes between the two stages. Further, we analyzed the distributional properties of the treatment response scores available for 1,308 patients using mixture modeling. Results Substantial and moderate agreement was shown across sites in the first and second sets of vignettes (κ = 0.66 and κ = 0.54, respectively), without significant improvement from training. However, definition of response using the A score as a quantitative trait and selecting cases with B criteria of 4 or less showed an improvement between the two stages (ICC1 = 0.71 and ICC2 = 0.75, respectively). Mixture modeling of score distribution indicated three subpopulations (full responders, partial responders, non responders). Conclusions We identified two definitions of lithium response, one dichotomous and the other continuous, with moderate to substantial inter-rater agreement and reliability. Accurate phenotypic measurement of lithium response is crucial for the ongoing ConLiGen pharmacogenomic study. PMID:23840348

  12. Annual report 1990 annex IV

    International Nuclear Information System (INIS)

    Smith, B.; Foskolos, K.

    1991-01-01

    The Nuclear Energy Research Department consists of three Laboratories: Reactor Physics and Systems Engineering (LRS), Thermal Hydraulics (LTH), and Materials and Nuclear Processes (LWV). There are additionally two Research Programmes: 'Waste Disposal' (PES) and LWR-Safety (PLS). The Department's activities focus on three main areas: safety and safety-related operational problems of the Swiss nuclear power plants (NPPs), contributions to the issues involved in radioactive waste disposal, future reactors. In addition, scientific-technical services are provided in the nuclear and non-nuclear sectors and for the operation of the relevant site facilities. (author) figs., tabs., refs

  13. Ion exchange characteristics of cerium (IV) and Tin(IV) antimonates and their use in rad waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Elnaggar, I M; Abdel Hamid, M M; Elabsy, M A; Aly, H F [Hot lab. centre, atomic energy authority, Cairo, (Egypt)

    1995-10-01

    Cerium (IV) and Tin(IV) antimonates cation exchangers have been synthesized. The products were characterized by powdered X-ray diffraction, thermal analysis and infrared spectrometry. The data of the distribution coefficients showed that the selectivity decreased in the order Eu{sup 3+}>Co{sup 2+}>Sr{sup 2+}>Cs{sup +} for both materials. Besides, the drying temperature of the matrices have a profound effect on their ion exchange capacities. Moreover, the obtained results of the effect of gamma radiation on the ion exchange behaviour of the samples showed that a slight decrease of the capacity and the distribution coefficient values with increasing the absorbed dose. 2 figs., 4 tabs.

  14. Structural Materials for Innovative Nuclear Systems (SMINS-3) - Workshop Proceedings, Idaho National Laboratory, Idaho Falls, United States, 7-10 October 2013

    International Nuclear Information System (INIS)

    2015-01-01

    The development of innovative nuclear systems such as Gen IV reactors or critical and subcritical transmutation systems requires a good knowledge of the properties of the materials used for designing these reactors. A common feature in developing nuclear systems is the widely recognised need for experimental programmes to select and characterise structural materials. Structural materials research, both at national and international level, can significantly contribute to the future deployment of new systems. Since 2007, the OECD Nuclear Energy Agency Nuclear Science Committee organises a series of workshop on Structural Materials for Innovative Nuclear Systems (SMINS) to stimulate an exchange of information on current materials research programmes for innovative nuclear systems with a view to identifying and developing potential synergies. The third workshop was held on 7-10 October 2013 in Idaho Falls (United States) and organised through the collaboration of the Working Party on Scientific Issues of the Fuel Cycle (WPFC) and the Working Party on Multi-Scale Modelling of Fuels and Structural Materials for Nuclear Systems (WPMM) in co-operation with the European Community (EC) and the International Atomic Energy Agency (IAEA). A total of 74 abstracts were received for either an oral and poster presentation. These proceedings include the papers presented at the workshop

  15. Marginal adaptation of large adhesive class IV composite restorations before and after artificial aging

    NARCIS (Netherlands)

    Ardu, S.; Stavridakis, M.; Feilzer, A.J.; Krejci, I.; Lefever, D.; Dietschi, D.

    2011-01-01

    Purpose: To test the marginal adaptation of Class IV restorations made of different composite materials designed for anterior use. Materials and Methods: Forty-two extracted caries-free human maxillary central incisors were randomly divided into 7 experimental groups - one per composite tested - for

  16. Irradiation of Parts of the X-Gen Nuclear Fuel Assembly made by KNF in HANARO

    International Nuclear Information System (INIS)

    Choo, K. N.; Cho, M. S.; Shin, Y. T.; Kim, B. G.; Lee, S. H.; Eom, K. B.

    2008-01-01

    An instrumented capsule has been developed at HANARO (High flux Advanced Neutron Application ReactOr) for the neutron irradiation tests of materials. The capsule system has been actively utilized for the various material irradiation tests requested by users from research institutes, universities, and the industries. As a preliminary test, some specimens made of the parts of a nuclear fuel assembly were inserted in the 05M-07U instrumented capsule and successfully irradiated at HANARO. Based on the results and experience, a new irradiation capsule of 07M-13N was designed, fabricated, and irradiated at HANARO for the evaluation of the neutron irradiation properties of the parts of the X-Gen nuclear fuel assembly made by KNF (Korea Nuclear Fuel). Specimens such as bucking and spring test specimens of spacer grid, microstructure and tensile test specimens of welded parts, tensile, irradiation growth and spring test specimens made of HANA tube, Zirlo, Zircaloy-4 and Inconel-718 were placed in the capsule. The capsule was loaded into the CT test hole of HANARO of a 30MW thermal output and the specimens were irradiated at 295 - 460 .deg. C up to a fast neutron fluence of 1.2x10 21 (n/cm 2 ) (E>1.0MeV)

  17. Diorganotin(IV) Complexes with Methionine Methyl Ester. Equilibria ...

    African Journals Online (AJOL)

    IV) (DBT) and diphenyltin(IV) (DPT) was investigated at 25 °C and 0.1 mol dm–3 ionic strength in water for dimethyltin(IV) and in 50 % dioxane–water mixture for dibutyltin(IV) and diphenyltin(IV). Methionine methyl ester forms1:1 and 1:2 ...

  18. Periodontal Disease Part IV: Periodontal Infections

    OpenAIRE

    Turnbull, Robert S.

    1988-01-01

    In Part IV of this article, the author describes two periodontal infections, acute necrotizing ulcerative gingivitis (trench mouth) and periodontal abscess, both acute painful conditions for which patients may seek advice from their family physician rather than their dentist.

  19. Safety assessment for Generation IV nuclear systems

    International Nuclear Information System (INIS)

    Leahy, T.J.

    2012-01-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Recent RSWG work has focused on the definition of an integrated safety assessment methodology (ISAM) for evaluating the safety of Generation IV systems. ISAM is an integrated 'tool-kit' consisting of 5 analytical techniques that are available and matched to appropriate stages of Generation IV system concept development: 1) qualitative safety features review - QSR, 2) phenomena identification and ranking table - PIRT, 3) objective provision tree - OPT, 4) deterministic and phenomenological analyses - DPA, and 5) probabilistic safety analysis - PSA. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time

  20. Determination of uranium (IV) by flow voltammetry

    International Nuclear Information System (INIS)

    Ding Anqing

    1987-01-01

    According to the quantitative reaction of U(IV) and Fe(III) in H 2 SO 4 as well as the relation between current and concentration of substance detected, U(IV) has been determined indirectly by measurement of the electrolysis current of residual Fe(III). The columniform electrode used is made of glass carbon particles. At the range of U(IV) from a few micrograms to 40 μg, the linear relation is excellent. The relative standard deviation is within ±4%. The interference of Fe(II), Ti(IV) and U(VI) is negligible but of Ti(III) is serious. This method has been successfully applied in the determination of actual samples (both out line and on line). Main advantages of this procedure are rapid, simple, small amount of sample (only at microgram level) and easy to realize automation, able to use for on line or process analysis

  1. IV&V Project Assessment Process Validation

    Science.gov (United States)

    Driskell, Stephen

    2012-01-01

    The Space Launch System (SLS) will launch NASA's Multi-Purpose Crew Vehicle (MPCV). This launch vehicle will provide American launch capability for human exploration and travelling beyond Earth orbit. SLS is designed to be flexible for crew or cargo missions. The first test flight is scheduled for December 2017. The SLS SRR/SDR provided insight into the project development life cycle. NASA IV&V ran the standard Risk Based Assessment and Portfolio Based Risk Assessment to identify analysis tasking for the SLS program. This presentation examines the SLS System Requirements Review/System Definition Review (SRR/SDR), IV&V findings for IV&V process validation correlation to/from the selected IV&V tasking and capabilities. It also provides a reusable IEEE 1012 scorecard for programmatic completeness across the software development life cycle.

  2. Genetics Home Reference: mucopolysaccharidosis type IV

    Science.gov (United States)

    ... enzymes, GAGs accumulate within cells, specifically inside the lysosomes . Lysosomes are compartments in the cell that break down ... that cause molecules to build up inside the lysosomes are called lysosomal storage disorders. In MPS IV, ...

  3. Els orígens de la tuberculosi

    OpenAIRE

    Bueno i Torrens, David, 1965-

    2014-01-01

    La tuberculosi és una de les primeres malalties infeccioses de la història de la humanitat. Es dedueix del registre fòssil, per les empremtes que deixa en els ossos d"algunes de les persones que l"han patit. Tradicionalment s"ha assumit que la tuberculosi ve del bestiar boví, que la va transmetre per primer cop a les persones durant el neolític. Però l"anàlisi genètica dels bacteris causants d"aquesta malaltia en diversos indrets del món i de bacteris fòssils trobats en mòmies precolombines h...

  4. Commissioning and Performance Analysis of WhisperGen Stirling Engine

    Science.gov (United States)

    Pradip, Prashant Kaliram

    Stirling engine based cogeneration systems have potential to reduce energy consumption and greenhouse gas emission, due to their high cogeneration efficiency and emission control due to steady external combustion. To date, most studies on this unit have focused on performance based on both experimentation and computer models, and lack experimental data for diversified operating ranges. This thesis starts with the commissioning of a WhisperGen Stirling engine with components and instrumentation to evaluate power and thermal performance of the system. Next, a parametric study on primary engine variables, including air, diesel, and coolant flowrate and temperature were carried out to further understand their effect on engine power and efficiency. Then, this trend was validated with the thermodynamic model developed for the energy analysis of a Stirling cycle. Finally, the energy balance of the Stirling engine was compared without and with heat recovery from the engine block and the combustion chamber exhaust.

  5. Festival du rire de Genève

    CERN Document Server

    Staff Association

    2015-01-01

    Connaissez-vous le Festival du rire de Genève ? La deuxième édition aura lieu du 25 au 28 mars 2015 au Casino-Théâtre à Carouge. Côté programmation, Marc Donnet-Monay ouvre les festivités avant trois autres soirées de folie et d’humour que nous vous laissons le soin de découvrir dans le programme : http://www.rire-geneve.ch/#programme. Réduction de 30% sur l’achat de places pour les membres du personnel du CERN. Pour cela, il suffit de se rendre sur la billetterie en ligne de notre site : www.rire-geneve.ch et d’utiliser le code promotionnel. Contacter le secrétariat de l’Association du personnel (Staff.Association@cern.ch) pour connaitre ce code promotionnel.

  6. How Gen Y and Boomers will reshape your agenda.

    Science.gov (United States)

    Hewlett, Sylvia Ann; Sherbin, Laura; Sumberg, Karen

    2009-01-01

    When it comes to workplace preferences, Generation Y workers closely resemble Baby Boomers. Because these two huge cohorts now coexist in the workforce, their shared values will hold sway in the companies that hire them. The authors, from the Center for Work-Life Policy, conducted two large-scale surveys that reveal those values. Gen Ys and Boomers are eager to contribute to positive social change, and they seek out workplaces where they can do that. They expect flexibility and the option to work remotely, but they also want to connect deeply with colleagues. They believe in employer loyalty but desire to embark on learning odysseys. Innovative firms are responding by crafting reward packages that benefit both generations of workers--and their employers.

  7. The sale of National Power and PowerGen

    International Nuclear Information System (INIS)

    1992-06-01

    In March 1991, the Secretary of State for Energy sold approximately 60 per cent of the shares in National Power and PowerGen who generate most of the electricity produced in England and Wales. The Government's overriding objective was to complete the privatisation of the electricity industry during the lifetime of the Parliament. Within that overriding objective, the Department sought: to maximise net proceeds; to deepen share ownership among individuals; to achieve the overall recognition that the sale of the two companies had been a success; and to achieve a modest premium on the issue price following the state of share dealings. This report sets out the results of a National Audit Office examination of how far the Department achieved their objectives for the sale, and how they controlled its costs. (author)

  8. Genética de las epilepsias Genetics of epilepsy

    Directory of Open Access Journals (Sweden)

    Gustavo A. Charria-Ortiz

    2007-01-01

    Full Text Available En años recientes se ha podido definir con gran exactitud la existencia de alteraciones genéticas específicas en una gran variedad de síndromes epilépticos tradicionales. Es decir, por vez primera se ha podido relacionar de manera contundente y predecible la presencia de alteraciones genómicas y/o proteómicas con síndromes epilépticos antes considerados como "idiopáticos". La gran mayoría de dichos defectos han sido encontrados en genes codificadores para canales iónicos y/o receptores de membrana, lo cual en cierto modo confirma la ya antes postulada relevancia que estas estructuras tienen en la actividad electroquímica espontánea neuronal cuyo desajuste conllevaría a ciertas formas de epilepsia. Esta revisión se centra en los aspectos genéticos y clínicos de dichas condiciones y alteraciones. También se revisarán brevemente los estudios más relevantes de la literatura médica según los cuales -aun a pesar de no haberse definido con la misma exactitud el tipo de anomalías etiológicas- puede tranquilamente inferirse el gran componente genético que parece subyacer a la etiología de las epilepsias. Por ultimo se enfatizará en que a pesar de dichos descubrimientos, su aplicación en la práctica clínica diaria aun es muy limitada, no solo por la relativa rareza de algunos de tales síndromes neurológicos sino también por la poca relevancia que hasta ahora ellos han tenido en el manejo médico rutinario de la mayoría de los pacientes. Las posibilidades inmediatas de tales avances -incluida la farmacogenómica-, así como los posibles conflictos éticos en que se podría incurrir serán también brevemente discutidos.In the last few years, the presence of specific genetic abnormalities leading to some of the classical epileptic syndromes has been clearly elucidated. This means that for the first time, it has become possible to create a strong relationship between the presence of specific genomic and/or proteomic

  9. Big Bang à Genève - French version only

    CERN Multimedia

    2005-01-01

    C'est la dernière conférence du cycle organisé par la section de physique de l'Université de Genève à l'occasion de l'Année internationale de la physique. Pour le bouquet final, la section de physique a choisi le grand boum du Big Bang. Intitulée « Big Bang à Genève », la conférence donnée par Laurent Chevalier de l'institut français CEA Saclay évoquera les expériences qui se préparent au CERN avec le LHC. Leur but est de reproduire et d'analyser les conditions qui prévalaient à l'origine de l'Univers, juste après le Big Bang. L'exposé décrira de façon simple les techniques utilisées pour cette exploration, qui démarrera en 2007. Laurent Chevalier se demandera avec le public quels phénomènes nouveaux les physiciens espèrent découvrir dans ce monde inexploré. Comme les précédentes, la conférence débutera par une démonstration de détection de rayons cosmiques dans l'auditoire et l'utilisation de ces signaux pour créer une « musique cosmique », en collaboration avec le Pr...

  10. Dsm-iv hypochondriasis in primary care

    OpenAIRE

    Escobar, JI; Gara, M; Waitzkin, H; Silver, RC; Holman, A; Compton, W

    1998-01-01

    The object of this study was to assess the prevalence and correlates of the DSM-IV diagnosis of hypochondriasis in a primary care setting. A large sample (N = 1456) of primary care users was given a structured interview to make diagnoses of mood, anxiety, and somatoform disorders and estimate levels of disability. The prevalence of hypochondriasis (DSM-IV) was about 3%. Patients with this disorder had higher levels of medically unexplained symptoms (abridged somatization) and were more impair...

  11. COBRA-IV wire wrap data comparisons

    International Nuclear Information System (INIS)

    Donovan, T.E.; George, T.L.; Wheeler, C.L.

    1979-02-01

    Thermal hydraulic analyses of hexagonally packed wire-wrapped fuel assemblies are complicated by the induced crossflow between adjacent subchannels. The COBRA-IV computer code simultaneously solves the hydrodynamics and thermodynamics of fuel assemblies. The modifications and the results are presented which are predicted by the COBRA-IV calculation. Comparisons are made with data measured in five experimental models of a wire-wrapped fuel assembly

  12. Caracterización clínico genética del síndrome Prader Willi

    Directory of Open Access Journals (Sweden)

    Anitery Travieso Tellez

    2014-12-01

    Full Text Available Introducción: el síndrome Prader Willi es un desorden genético causado por la pérdida de genes contenidos en la región 15q11-q13 del cromosoma paterno. Objetivo: describir las características clínicas y genéticas de los pacientes con síndrome Prader Willi. Material y método: se realizó un estudio descriptivo, de corte transversal, con el universo de 15 pacientes con sospecha de síndrome Prader Willi remitidos a consulta provincial de Genética Clínica durante el año 2013. Se consideraron como variables clínicas los criterios diagnósticos según Holms, y como variables genéticas los resultados de los estudios cromosómicos y moleculares. Resultados: predominó el sexo femenino en un 66.7%. Las edades estuvieron entre los tres y los 41 años. Los criterios mayores más frecuentes resultaron la obesidad troncular y el retraso del neurodesarrollo en el 100% de los pacientes. Los criterios menores más identificados fueron los disturbios del sueño y las dificultades del lenguaje con un 66.7% cada uno. En ninguno de los casos se detectaron anomalías cromosómicas por cariotipificación. Tres pacientes (60% presentaron la deleción a nivel de la región 15q11-q13 identificada por la técnica de hibridación in sito con fluorescencia. Conclusiones: la definición del diagnóstico en la provincia resulta demorada. Se requiere de reevaluación según los criterios clínicos en las diferentes etapas de la vida para diagnóstico de certeza. La presencia de hipotonía neonatal y dificultades en la alimentación son elementos asociados al diagnóstico por deleción 15q11-q13.

  13. 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.

  14. Synthesis and characterization of chiral thorium(IV) and uranium(IV) benzamidinate complexes

    Energy Technology Data Exchange (ETDEWEB)

    Schoene, Sebastian; Maerz, Juliane; Kaden, Peter; Patzschke, Michael; Ikeda-Ohno, Atsushi [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Chemistry of the F-Elements

    2017-06-01

    Two chiral benzamidinate complexes of tetravalent actinides (Th(IV) and U(IV)) were synthesized using a salt metathesis reaction of the corresponding actinide(IV) tetrachlorides and the potassium salt of the chiral benzamidine (S,S)-N,N-Bis-(1-phenylethyl)-benzamidine ((S)-HPEBA). The structure of the complexes was determined with single crystal X-ray diffraction. These are the first examples of chiral amidinate complexes of actinides.

  15. Systematic revision and palaeobiology of Rosenfeldia triasica and Rogeryon oppeli gen. et comb. nov. (Eucrustacea, Polychelida

    Directory of Open Access Journals (Sweden)

    Denis Audo

    2017-11-01

    Full Text Available Polychelidan lobsters (Decapoda: Polychelida are crustaceans with extant species which are restricted to deep water environments. Fossil species, however, used to live in more varied palaeoenvironments, from shallow water to deep water, and were more diverse morphologically. We redescribe two species of polychelidan lobsters, the Late Triassic Rosenfeldia triasica Garassino, Teruzzi & Dalla Vecchia, 1996 and the Late Jurassic Eryon oppeli Woodward, 1866, recently assigned to the same genus, Rosenfeldia, based upon only a few characters. Our investigation of all available material of both species leads us to distinguish these two species and to erect Rogeryon gen. nov. to accommodate Eryon oppeli. The palaeobiology of both species is interpreted for the first time. Rosenfeldia triasica with its stout first pereiopods and mandibles with both incisor and molar processes (documented for the first time in Polychelida was benthic and probably fed either on slow-moving sedentary preys or was a scavenger. Rogeryon oppeli gen. et comb. nov. was benthic, visually adapted to shallow water palaeoenvironments, and possibly had a diet similar to that of slipper lobsters and horseshoe crabs. The redescription of these two species highlights the palaeobiological diversity of fossil polychelidans.

  16. Light water reactor fuel analysis code FEMAXI-IV(Ver.2). Detailed structure and user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Motoe [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Saitou, Hiroaki

    1997-11-01

    A light water reactor fuel behavior analysis code FEMAXI-IV(Ver.2) was developed as an improved version of FEMAXI-IV. Development of FEMAXI-IV has been already finished in 1992, though a detailed structure and input manual of the code have not been open to users yet. Here, the basic theories and structure, the models and numerical solutions applied to FEMAXI-IV(Ver.2), and the material properties adopted in the code are described in detail. In FEMAXI-IV(Ver.2), programming bugs in previous FEMAXI-IV were eliminated, renewal of the pellet thermal conductivity was performed, and a model of thermal-stress restraint on FP gas release was incorporated. For facilitation of effective and wide-ranging application of the code, methods of input/output of the code are also described in detail, and sample output is included. (author)

  17. Peroxiredoxin IV Protects Cells From Radiation-Induced Apoptosis in Head-and-Neck Squamous Cell Carcinoma

    International Nuclear Information System (INIS)

    Park, Jung Je; Chang, Hyo Won; Jeong, Eun-Jeong; Roh, Jong-Lyel; Choi, Seung-Ho; Jeon, Sea-Yuong; Ko, Gyung Hyuck; Kim, Sang Yoon

    2009-01-01

    Purpose: Human peroxiredoxins (Prxs) are known as a family of thiol-specific antioxidant enzymes, among which Prx-I and -II play an important role in protecting cells from irradiation-induced cell death. It is not known whether Prx-IV also protects cells from ionizing radiation (IR). Methods and Materials: To evaluate the protective role of Prx-IV in IR, we transfected full-length Prx-IV cDNA into AMC-HN3 cells, which weakly express endogenous Prx-IV, and knocked down the expression of Prx-IV with siRNA methods using AMC-HN7 cells, which express high levels of endogenous Prx-IV. Radiosensitivity profiles in these cells were evaluated using clonogenic assay, FACS analysis, cell viability, and TUNEL assay. Results: Three Prx-IV expressing clones were isolated. Prx-IV regulated intracellular reactive oxygen species (ROS) levels and made cells more resistant to IR-induced apoptosis. Furthermore, the knockdown of Prx-IV with siRNA made cells more sensitive to IR-induced apoptosis. Conclusion: The results of these studies suggest that Prx-IV may play an important role in protecting cells from IR-induced apoptosis in head-and-neck squamous cell carcinoma

  18. 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...

  19. 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...

  20. 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.

  1. 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...

  2. Polimorfismos del gen ob en bovinos de raza holstein en la Comarca Lagunera, México

    OpenAIRE

    Sarai S. Mendoza-Retana; Miguel A. Gallegos-Robles; Uriel González-Salas; José L. García-Hernández; Manuel Fortis-Hernández; Cirilo Vázquez-Vázquez; Héctor I. Trejo-Escareño

    2017-01-01

    La Comarca Lagunera es la cuenca lechera más importante de México. En la actualidad se están utilizando diversas técnicas que permiten evaluar genéticamente el animal a una edad temprana, permitiendo seleccionar futuros reproductores con características deseables. Entre los genes relacionados con la producción de leche, se encuentran el gen Ob también llamado gen Leptina el cual actúa sobre el sistema nervioso central y tejidos periféricos jugando un papel muy importante ...

  3. Evidence of redshifts in the average solar line profiles of C IV and Si IV from OSO-8 observations

    Science.gov (United States)

    Roussel-Dupre, D.; Shine, R. A.

    1982-01-01

    Line profiles of C IV and Si V obtained by the Colorado spectrometer on OSO-8 are presented. It is shown that the mean profiles are redshifted with a magnitude varying from 6-20 km/s, and with a mean of 12 km/s. An apparent average downflow of material in the 50,000-100,000 K temperature range is measured. The redshifts are observed in the line center positions of spatially and temporally averaged profiles and are measured either relative to chromospheric Si I lines or from a comparison of sun center and limb profiles. The observations of 6-20 km/s redshifts place constraints on the mechanisms that dominate EUV line emission since it requires a strong weighting of the emission in regions of downward moving material, and since there is little evidence for corresponding upward moving materials in these lines.

  4. 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.

  5. Shatavarins (containing Shatavarin IV) with anticancer activity from the roots of Asparagus racemosus

    Science.gov (United States)

    Mitra, Shankar K.; Prakash, Neswi S.; Sundaram, Ramachandran

    2012-01-01

    Objectives: The anticancer activity of shatavarins (containing shatavarin IV) isolated from the roots of Asparagus racemosus (Wild) was evaluated using in vitro and in vivo experimental models. Material and Methods: The shatavarin IV was isolated from ethyl acetate insoluble fraction (AR-2B) of chloroform:methanol (2:1) (AR-2) extract of A. racemosus roots. The cytotoxicity (in vitro) of shatavarin IV and other shatavarins rich fraction was carried out using of MTT assay using MCF-7 (human breast cancer), HT-29 (human colon adenocarcinoma), and A-498 (human kidney carcinoma) cell lines. The in vivo anticancer activity of shatavarins (containing shatavarin IV) was evaluated against Ehrlich ascites carcinoma (EAC) tumor bearing mice. Results: The isolated shatavarin IV (84.69 %) along with shatavarins rich fraction, coded AR-2B containing 5.05% shatavarin IV showed potent cytotoxicity. Oral administration of AR-2B to tumor bearing mice at doses of 250 and 500 mg/kg body weight for 10 days, showed significant reduction in percent increase in body weight, tumor volume, packed cell volume, viable tumor cell count, and increased non-viable cell count when compared to the untreated mice of the EAC control group. The restoration of hematological parameters towards normalcy was also observed. Conclusion: The result suggests that the shatavarins (containing shatavarin IV) rich fraction (AR-2B) exhibits significant anticancer activity in both in vitro and in vivo experimental models. PMID:23248403

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

    International Nuclear Information System (INIS)

    Woo, Tae Ho; Lee, Soon Ho

    2012-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-11-15

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

  8. Solubility study of Tc(IV) oxides

    International Nuclear Information System (INIS)

    Liu, D.J.; Fan, X.H.

    2005-01-01

    The deep geological disposal of the high level radioactive wastes is expected to be a safer disposal method in most countries. The long-lived fission product 99 Tc is present in large quantities in nuclear wastes and its chemical behavior in aqueous solution is of considerable interest. Under oxidizing conditions technetium exists as the anionic species TcO 4 - whereas under the reducing conditions, expected to exist in a deep geological repository, it is generally predicted that technetium will be present as TcO 2 ·nH 2 O. Hence, the mobility of Tc(IV) in reducing groundwater may be limited by the solubility of TcO 2 ·nH 2 O under these conditions. Due to this fact it is important to investigate the solubility of TcO 2 ·nH 2 O. The solubility determines the release of radionuclides from waste form and is used as a source term in radionuclide migration analysis in performance assessment of radioactive waste repository. Technetium oxide was prepared by reduction of a technetate solution with Sn 2 + . The solubility of Tc(IV) oxide has been determined in simulated groundwater and redistilled water under aerobic and anaerobic conditions. The effects of pH and CO 3 2- concentration of solution on solubility of Tc(IV) oxide were studied. The concentration of total technetium and Tc(IV) species in the solutions were periodically determined by separating the oxidized and reduced technetium species using a solvent extraction procedure and counting the beta activity of the 99 Tc with a liquid scintillation counter. The experimental results show that the rate of oxidation of Tc(IV) in simulated groundwater and redistilled water is about (1.49-1.86) x 10 -9 mol/(L·d) under aerobic conditions, but Tc(IV) in simulated groundwater and redistilled water is not oxidized under anaerobic conditions. Under aerobic or anaerobic conditions the solubility of Tc(IV) oxide in simulated groundwater and redistilled water is equal on the whole after centrifugation or ultrafiltration. The

  9. Solubility of Tc(IV) oxides

    International Nuclear Information System (INIS)

    Liu, D.J.; Fan, X.H.

    2005-01-01

    Full text of publication follows: The deep geological disposal of the high level radioactive wastes is expected to be a safer disposal method in most countries. The long-lived fission product 99 Tc is present in large quantities in nuclear wastes and its chemical behavior in aqueous solution is of considerable interest. Under the reducing conditions, expected to exist in a deep geological repository, it is generally predicted that technetium will be present as TcO 2 .nH 2 O. The solubility of Tc(IV) is used as a source term in performance assessment of radioactive waste repository. Technetium oxide was prepared by reduction of a technetate solution with Sn 2+ . The solubility of Tc(IV) oxide has been determined in simulated groundwater and re-distilled water under aerobic and anaerobic conditions. The effects of pH and CO 3 2- concentration of solution on solubility of Tc(IV) oxide were studied. The concentration of total technetium and Tc(IV) species in the solutions were periodically determined by separating the oxidized and reduced technetium species using a solvent extraction procedure and counting the beta activity of the 99 Tc with a liquid scintillation counter. The experimental results show that the rate of oxidation of Tc(IV) in simulated groundwater and re-distilled water is about (1.49∼1.86) x 10 -9 mol/(L.d) under aerobic conditions, but Tc(IV) in simulated groundwater and re-distilled water is not oxidized under anaerobic conditions. Under aerobic or anaerobic conditions the solubility of Tc(IV) oxide in simulated groundwater and re-distilled water is equal on the whole after centrifugation or ultrafiltration. The solubility of Tc(IV) oxide decreases with the increase of pH at pH 10 and is pH independent in the range 2 -8 to 10 -9 mol/L at 2 3 2- concentration. These data could be used to estimate the Tc(IV) solubility for cases where solubility limits transport of technetium in reducing environments of high-level waste repositories. (authors)

  10. Max Phase Materials And Coatings For High Temperature Heat Transfer Applications

    Energy Technology Data Exchange (ETDEWEB)

    Martinez-Rodriguez, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Garcia-Diaz, B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Olson, L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fuentes, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Sindelar, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-10-19

    Molten salts have been used as heat transfer fluids in a variety of applications within proposed Gen IV nuclear designs and in advanced power system such as Concentrating Solar Power (CSP). However, operating at elevated temperatures can cause corrosion in many materials. This work developed coating technologies for MAX phase materials on Haynes-230 and characterized the corrosion of the coatings in the presence of commercial MgCl2-KCl molten salt. Cold spraying of Ti2AlC and physical vapor deposition (PVD) of Ti2AlC or Zr2AlC were tested to determine the most effective form of coating MAX phases on structural substrates. Corrosion testing at 850°C for 100 hrs showed that 3.9 μm Ti2AlC by PVD was slightly protective while 117 μm Ti2AlC by cold spray and 3.6 μm Zr2AlC by PVD were completely protective. None of the tests showed decomposition of the coating (Ti or Zr) into the salt

  11. High cost of stage IV pressure ulcers.

    Science.gov (United States)

    Brem, Harold; Maggi, Jason; Nierman, David; Rolnitzky, Linda; Bell, David; Rennert, Robert; Golinko, Michael; Yan, Alan; Lyder, Courtney; Vladeck, Bruce

    2010-10-01

    The aim of this study was to calculate and analyze the cost of treatment for stage IV pressure ulcers. A retrospective chart analysis of patients with stage IV pressure ulcers was conducted. Hospital records and treatment outcomes of these patients were followed up for a maximum of 29 months and analyzed. Costs directly related to the treatment of pressure ulcers and their associated complications were calculated. Nineteen patients with stage IV pressure ulcers (11 hospital-acquired and 8 community-acquired) were identified and their charts were reviewed. The average hospital treatment cost associated with stage IV pressure ulcers and related complications was $129,248 for hospital-acquired ulcers during 1 admission, and $124,327 for community-acquired ulcers over an average of 4 admissions. The costs incurred from stage IV pressure ulcers are much greater than previously estimated. Halting the progression of early stage pressure ulcers has the potential to eradicate enormous pain and suffering, save thousands of lives, and reduce health care expenditures by millions of dollars. Copyright © 2010 Elsevier Inc. All rights reserved.

  12. 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.)

  13. The Contribution of IVS to IGGOS

    Science.gov (United States)

    Nothnagel, A.

    2002-05-01

    Since its inauguration in 1999, the International VLBI Service for Geodesy and Astrometry has made significant progress in the coordination and utilisation of worldwide VLBI resources. Improving the visibility of the IVS components to a wider public in turn led to a higher motivation of the individuals to contribute to the global effort. Not only the number of IVS components but also their investments in terms of funds and manpower demonstrate the increased awareness of the importance of this joint international endeavour. The different demands of the users but also of the contributors often require the definition of priorities which are only being acceptable due to the existence of a strong umbrella organisation like the IVS. Significant progress has also been made in the area of routine data analysis and combination of results. By now, six IVS Analysis Centers provide the redundancy necessary for a robust combination of the results. The use of ITRF2000 station coordinates as the basis for the IVS combined EOP series is the most recent step towards the generation of a consistent chain from the quasi-inertial frame of radio sources to system Earth.

  14. Solubility studies of Np(IV)

    International Nuclear Information System (INIS)

    Zhang Yingjie; Yao Jun; Jiao Haiyang; Ren Lihong; Zhou Duo; Fan Xianhua

    2001-01-01

    The solubility of Np(IV) in simulated underground water and redistilled water has been measured with the variations of pH(6-12) and storage time (0-100 d) in the presence of reductant (Na 2 S 2 O 4 , metallic Fe). All experiments are performed in a low oxygen concentration glove box containing high purity Ar(99.99%), with an oxygen content of less than 5 x 10 -6 mol/mol. Experimental results show that the variation of pH in solution has little effect on the solubility of Np(IV) in the two kinds of water; the measured solubility of Np(IV) is affected by the composition of solution; with Na 2 S 2 O 4 as a reductant, the solubility of Np(IV) in simulated underground water is (9.23 +- 0.48) x 10 -10 mol/L, and that in redistilled water is (8.31 +- 0.35) x 10 -10 mol/L; with metallic Fe as a reductant, the solubility of Np(IV) in simulated underground water is (1.85 +- 0.56) x 10 -9 mol/L, and that in redistilled water is (1.48 +- 0.66) x 10 -9 mol/L

  15. 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

  16. Kretzoiarctos gen. nov., the oldest member of the giant panda clade.

    Directory of Open Access Journals (Sweden)

    Juan Abella

    Full Text Available The phylogenetic position of the giant panda, Ailuropoda melanoleuca (Carnivora: Ursidae: Ailuropodinae, has been one of the most hotly debated topics by mammalian biologists and paleontologists during the last century. Based on molecular data, it is currently recognized as a true ursid, sister-taxon of the remaining extant bears, from which it would have diverged by the Early Miocene. However, from a paleobiogeographic and chronological perspective, the origin of the giant panda lineage has remained elusive due to the scarcity of the available Miocene fossil record. Until recently, the genus Ailurarctos from the Late Miocene of China (ca. 8-7 mya was recognized as the oldest undoubted member of the Ailuropodinae, suggesting that the panda lineage might have originated from an Ursavus ancestor. The role of the purported ailuropodine Agriarctos, from the Miocene of Europe, in the origins of this clade has been generally dismissed due to the paucity of the available material. Here, we describe a new ailuropodine genus, Kretzoiarctos gen. nov., based on remains from two Middle Miocene (ca. 12-11 Ma Spanish localities. A cladistic analysis of fossil and extant members of the Ursoidea confirms the inclusion of the new genus into the Ailuropodinae. Moreover, Kretzoiarctos precedes in time the previously-known, Late Miocene members of the giant panda clade from Eurasia (Agriarctos and Ailurarctos. The former can be therefore considered the oldest recorded member of the giant panda lineage, which has significant implications for understanding the origins of this clade from a paleobiogeographic viewpoint.

  17. Kretzoiarctos gen. nov., the oldest member of the giant panda clade.

    Science.gov (United States)

    Abella, Juan; Alba, David M; Robles, Josep M; Valenciano, Alberto; Rotgers, Cheyenn; Carmona, Raül; Montoya, Plinio; Morales, Jorge

    2012-01-01

    The phylogenetic position of the giant panda, Ailuropoda melanoleuca (Carnivora: Ursidae: Ailuropodinae), has been one of the most hotly debated topics by mammalian biologists and paleontologists during the last century. Based on molecular data, it is currently recognized as a true ursid, sister-taxon of the remaining extant bears, from which it would have diverged by the Early Miocene. However, from a paleobiogeographic and chronological perspective, the origin of the giant panda lineage has remained elusive due to the scarcity of the available Miocene fossil record. Until recently, the genus Ailurarctos from the Late Miocene of China (ca. 8-7 mya) was recognized as the oldest undoubted member of the Ailuropodinae, suggesting that the panda lineage might have originated from an Ursavus ancestor. The role of the purported ailuropodine Agriarctos, from the Miocene of Europe, in the origins of this clade has been generally dismissed due to the paucity of the available material. Here, we describe a new ailuropodine genus, Kretzoiarctos gen. nov., based on remains from two Middle Miocene (ca. 12-11 Ma) Spanish localities. A cladistic analysis of fossil and extant members of the Ursoidea confirms the inclusion of the new genus into the Ailuropodinae. Moreover, Kretzoiarctos precedes in time the previously-known, Late Miocene members of the giant panda clade from Eurasia (Agriarctos and Ailurarctos). The former can be therefore considered the oldest recorded member of the giant panda lineage, which has significant implications for understanding the origins of this clade from a paleobiogeographic viewpoint.

  18. [The quantitative testing of V617F mutation in gen JAK2 using pyrosequencing technique].

    Science.gov (United States)

    Dunaeva, E A; Mironov, K O; Dribnokhodova, T E; Subbotina, E E; Bashmakova; Ol'hovskiĭ, I A; Shipulin, G A

    2014-11-01

    The somatic mutation V617F in gen JAK2 is a frequent cause of chronic myeloprolific diseases not conditioned by BCR/ABL mutation. The quantitative testing of relative percentage of mutant allele can be used in establishing severity of disease and its prognosis and in prescription of remedy inhibiting activity of JAK2. To quantitatively test mutation the pyrosequencing technique was applied. The developed technique permits detecting and quantitatively, testing percentage of mutation fraction since 7%. The "gray zone" is presented by samples with percentage of mutant allele from 4% to 7%. The dependence of expected percentage of mutant fraction in analyzed sample from observed value of signal is described by equation of line with regression coefficients y = - 0.97, x = -1.32 and at that measurement uncertainty consists ± 0.7. The developed technique is approved officially on clinical material from 192 patients with main forms of myeloprolific diseases not conditioned by BCR/ABL mutation. It was detected 64 samples with mautant fraction percentage from 13% to 91%. The developed technique permits implementing monitoring of therapy of myeloprolific diseases and facilitates to optimize tactics of treatment.

  19. Investigating contact toxicity of Geranium and Artemisia essential oils on Bemisia tabaci Gen.

    Directory of Open Access Journals (Sweden)

    Fatemeh Yarahmadi

    2013-04-01

    Full Text Available Objective: Sweet potato whitefly, Bemisia tabaci Gen. (B. tabaci, is one of the most important pests of various greenhouse crops in Iran. Nowadays, chemical insecticides are broadly used for control of the pests that causes risk to consumer's health. For the first time, contact toxicity of Pelargonium roseum Andrews and Artemisia sieberi Besser essential oils on B. tabaci and its possible application against the whitefly was evaluated in 2012. Materials and Methods: Essential oil with concentrations of 2500, 1250, 125, and 12 ppm were used. Infested leaves of greenhouse cucumber were treated by mentioned concentrations. After 24 hours, mortality of B. tabaci was recorded and compared after correcting by Abbot's formula. Results: Results showed that all concentrations of the essential oil could significantly reduce population of B. tabaci compared with the control treatment. Phytotoxicity of the treated leaves were recorded after 24, 48, and 72 hours and compared with the control. Concentrations of 2500, 1250, and 125 ppm caused severe phytotoxicity on greenhouse cucumber leaves and therefore are not suitable for greenhouse application. Phytotoxicity of 12 ppm was relatively low. Conclusions: This data implicated suitable protective effects of the essential oils to the pest infestation. Therefore, essential oils distillated from Geranium and Artemisia could be applied to control B. tabaci in greenhouse cucumber at V/V 12 ppm.

  20. Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Allen, T.R.; Was, G.S.; Bruemmer, S.M.; Gan, J.; Ukai, S.

    2005-12-28

    The objective of this program is to improve the radiation tolerance of both austenitic and ferritic-martensitic (F-M) alloys projected for use in Generation IV systems. The expected materials limitations of Generation IV components include: creep strength, dimensional stability, and corrosion/stress corrosion compatibility. The material design strategies to be tested fall into three main categories: (1) engineering grain boundaries; (2) alloying, by adding oversized elements to the matrix; and (3) microstructural/nanostructural design, such as adding matrix precipitates. These three design strategies were tested across both austenitic and ferritic-martensitic alloy classes

  1. Instrumentation Technologies for Improving an Irradiation Testing of Nuclear Fuels and Materials at the HANARO

    International Nuclear Information System (INIS)

    Kim, Bong Goo; Park, Sung Jae; Choo, Ki Nam

    2011-01-01

    Over 50 years of nuclear fuels and materials irradiation testing has led to many countries developing significant improvements in instrumentation to monitor physical parameters and to control the test conditions in Materials Test Reactors (MTRs) or research reactors. Recent effort to deploy new fuels and materials in existing and advanced reactors has increased the demand for well-instrumented irradiation tests. Specifically, demand has increased for tests with sensors capable of providing real-time measurement of key parameters, such as temperature, geometry changes, thermal conductivity, fission gas release, cracking, coating buildup, thermal and fast flux, etc. This review paper documents the current state of instrumentation technologies in MTRs in the world and summarizes on-going research efforts to deploy new sensors. There is increased interest to irradiate new materials and reactor fuels for advanced PWRs and the Gen-IV reactor systems, such as SFRs (Sodium-cooled Fast Reactors), VHTRs (Very-High-Temperature Reactors), SCWRs (Supercritical-Water-cooled Reactors) and GFRs (Gas-cooled Fast Reactor). This review documents the current state of instrumentation technologies in MTRs in the world, identifies challenges faced by previous testing methods and how these challenges were overcome. A wide range of sensors are available to measure key parameters of interest during fuels and materials irradiations in MTRs. Such sensors must be reliable, small size, highly accurate, and able to withstand harsh conditions. On-going development efforts are focusing on providing MTR users a wider range of parameter measurements with increased accuracy. In addition, development efforts are focusing on reducing the impact of sensor on measurements by reducing sensor size. This report includes not only status of instrumentation using research reactors in the world to irradiate nuclear fuels and materials but also future directions relating to instrumentation technologies for

  2. On the stabilization of niobium(V) solutions by zirconium(IV) and hafnium(IV)

    DEFF Research Database (Denmark)

    Sørensen, E.; Bjerre, A.B.

    1992-01-01

    Niobium cannot be separated from zirconium or hafnium when these elements occur together in solution with common anions such as chloride and sulphate. This is ascribed to the co-polymerization of niobium(V) and the hydrolysed ionic species of zirconium(IV) and hafnium(IV) to form colloidal...

  3. Complexation of the An(IV) by NTA; Complexation des An(IV) par le NTA

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, L. [Paris-11 Univ., 91 - Orsay (France)]|[CEA Valrho, Lab. de Chimie des Actinides (LCA), 30 - Marcoule (France)

    2006-07-01

    In the framework of the Nuclear and Environmental Toxicology program, developed in France, it has been decided to take again the studies concerning the actinides decorporation. A similar study of the neptunium complexation by the citrate ions has been carried out on the complexation of Np(IV) with the nitrilotriacetic acid (NTA). The NTA can be considered as a model molecule of the de-corporating molecules (amino-carboxy- ligand). The results of the spectrophotometric measurements being encouraging, the behaviour of several actinides at the same oxidation state (+IV) (Th(IV), U(IV), Np(IV), and Pu(IV)) has been determined. The experimental results are presented. In order to determine the structure of the complexes of stoichiometry 1:2 An(IV)-(NTA){sub 2} in solution, quantic chemistry calculations and EXAFS measurements have been carried out in parallel. These studies confirm the presence of An(IV)-nitrogen bonds whose length decreases from thorium to plutonium and indicate the presence of a water molecule bound to the thorium and the uranium (coordination number 8 for Np/Pu, 9 for Th/U). The evolution of the complexation constants determined in this study in terms of 1/r (r ionic radius of the cation taking into account its coordination number 8 or 9) confirms the change of the coordination number between Th/U and Np/Pu. (O.M.)

  4. Transuranium perrhenates: Np(IV), Pu(IV) and (III), Am (III)

    International Nuclear Information System (INIS)

    Silvestre, Jean-Paul; Freundlich, William; Pages, Monique

    1977-01-01

    Synthesis in aqueous solution and by solid state reactions, crystallographical characterization and study of the stability of some transuranium perrhenates: Asup(n+)(ReO 4 - )sub(n) (A=Np(IV), Pu(IV), Pu(III), Am(III) [fr

  5. Siamia luxuriosa gen. et sp. nov., a new synnematous hyphomycete from Thailand

    NARCIS (Netherlands)

    Robert, Vincent; Decock, Cony; Castañeda Ruíz, Rafael F.

    2000-01-01

    A new synnematous hyphomycete, Siamia luxuriosa gen. et sp. nov., is described from Khao Yai National Park, Thailand. The genus is characterised by having long, dark synnemata, conidiogenous cells with numerous protuberant, cylindrical, thickened unilaterally arranged scars, and long, slightly

  6. Download - 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 ...access [here]. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us Download - GenLibi | LSDB Archive ...

  7. License - 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 ...nse Update History of This Database Site Policy | Contact Us License - GenLibi | LSDB Archive ...

  8. 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...

  9. A Software-Assurance Design Approach for NextGen Enabling Technologies, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — The Next Generation Air Transportation System (NextGen) brings significant advancements to the current management of the National Airspace (NAS). These fundamental...

  10. 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.

  11. Neofomitella polyzonata gen. et sp. nov., and N. fumosipora and N. rhodophaea transferred from Fomitella

    Czech Academy of Sciences Publication Activity Database

    Li, H.J.; Li, X.C.; Vlasák, Josef; Dai, Y.C.

    2014-01-01

    Roč. 129, č. 1 (2014), s. 7-20 ISSN 0093-4666 Institutional support: RVO:60077344 Keywords : Basidiomycota * phylogeny * polyporaceae * taxonomy Subject RIV: EB - Gen etics ; Molecular Biology Impact factor: 0.705, year: 2014

  12. 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.

  13. 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

  14. 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

  15. Extending the Use of Highly Porous and Functionalized MOFs to Th(IV) Capture.

    Science.gov (United States)

    Zhang, Nan; Yuan, Li-Yong; Guo, Wen-Lu; Luo, Shi-Zhong; Chai, Zhi-Fang; Shi, Wei-Qun

    2017-08-02

    Thorium separation has recently become a hot topic because of the potential application of thorium as a future nuclear fuel, while metal-organic framework (MOF) materials have received much attention in the separation field due to their unique properties. Herein, a highly porous and stable MOF, UiO-66, and its carboxyl derivatives (UiO-66-COOH and UiO-66-(COOH) 2 ) were synthesized and explored for the first time for Th(IV) capture from a weak acidic solution. Although the introduction of carboxyl groups into UiO-66 leads to an obvious decrease in the surface area and pore volume, the adsorbability toward Th(IV) is greatly enhanced. At pH = 3.0, the saturated sorption capacity for Th(IV) into UiO-66-(COOH) 2 reached 350 mg/g, representing one of the largest values for Th(IV) capture by solid extraction. Moreover, the functionalized MOFs show fast sorption kinetics and desirable selectivity toward Th(IV) over a range of competing metal ions. A possible mechanism for the selective recognition of Th(IV) by these MOFs was explored on the basis of extended X-ray absorption fine structure and Fourier transform infrared analysis. It is concluded that UiO-66-COOH and UiO-66-(COOH) 2 sorb Th(IV) through the coordination of carboxyl anions in the pores of the MOFs, whereas in the case of UiO-66, both the precipitation and the exchange with the organic solvent contribute to the Th(IV) uptake. This study contributes to the assessment of the feasibility of MOFs applied in actinides separation and better understanding of actinides sorption behavior in this kind of hybrid porous solid materials.

  16. Oxochloroalkoxide of the Cerium (IV and Titanium (IV as oxides precursor

    Directory of Open Access Journals (Sweden)

    Machado Luiz Carlos

    2002-01-01

    Full Text Available The Cerium (IV and Titanium (IV oxides mixture (CeO2-3TiO2 was prepared by thermal treatment of the oxochloroisopropoxide of Cerium (IV and Titanium (IV. The chemical route utilizing the Cerium (III chloride alcoholic complex and Titanium (IV isopropoxide is presented. The compound Ce5Ti15Cl16O30 (iOPr4(OH-Et15 was characterized by elemental analysis, FTIR and TG/DTG. The X-ray diffraction patterns of the oxides resulting from the thermal decomposition of the precursor at 1000 degreesC for 36 h indicated the formation of cubic cerianite (a = 5.417Å and tetragonal rutile (a = 4.592Å and (c = 2.962 Å, with apparent crystallite sizes around 38 and 55nm, respectively.

  17. Deferribacter thermophilus gen. nov., sp. nov., a novel thermophilic manganese- and iron-reducing bacterium isolated from a petroleum reservoir.

    Science.gov (United States)

    Greene, A C; Patel, B K; Sheehy, A J

    1997-04-01

    A thermophilic anaerobic bacterium, designated strain BMAT (T = type strain), was isolated from the production water of Beatrice oil field in the North Sea (United Kingdom). The cells were straight to bent rods (1 to 5 by 0.3 to 0.5 microns) which stained gram negative. Strain BMAT obtained energy from the reduction of manganese (IV), iron(III), and nitrate in the presence of yeast extract, peptone, Casamino Acids, tryptone, hydrogen, malate, acetate, citrate, pyruvate, lactate, succinate, and valerate. The isolate grew optimally at 60 degrees C (temperature range for growth, 50 to 65 degrees C) and in the presence of 2% (wt/vol) NaCl (NaCl range for growth, 0 to 5% [wt/vol]). The DNA base composition was 34 mol% G + C. Phylogenetic analyses of the 16S rRNA gene indicated that strain BMAT is a member of the domain Bacteria. The closest known bacterium is the moderate thermophile Flexistipes sinusarabici (similarity value, 88%). Strain BMAT possesses phenotypic and phylogenetic traits that do not allow its classification as a member of any previously described genus; therefore, we propose that this isolate should be described as a member of a novel species of a new genus, Deferribacter thermophilus gen. nov., sp. nov.

  18. Measurement of Ce(IV) Concentration in Foam Decontaminant containing Fluorosurfactant

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Chong Hun; Yang, H. B.; Yoon, I. H.; Choi, W. K.; Moon, J. K. [KAERI, Daejeon (Korea, Republic of); Lee, J. S. [Gachon University, Seongnam (Korea, Republic of)

    2016-05-15

    To improve the stability of the foam, surfactants and inorganic materials such as nanoparticles can be added. A nanoparticle-based foam decontaminant is composed of a surfactant and nanoparticles for the generation and maintenance of foam, and a chemical decontamination agent made of Ce(IV) dissolved in nitric acid. Ce(IV) will be reduced to Ce(III) through the decontamination process. Oxidizing the cerium (III) can be reused as a decontamination agent, Ce(IV). Oxidation treatment technology by ozone uses its strong oxidizing power. It can be regarded as an environmentally friendly process, because ozone cannot be stored and transported like other industrial gases (because it quickly decays into diatomic oxygen) and must therefore be produced on site, and used ozone can be decomposed immediately. A concentration analysis of Ce(IV) in foam decontaminant containing a surfactant is necessary prior to the derivation of optimal conditions for the regeneration of Ce(III) through ozonation treatment. A UV spectrometric method using the absorbance or potentiometric method with a potential difference in Ce(III)/Ce(IV), or a potentiometric titration method using Fe (II), can be used for a Ce(IV) concentration analysis. A UV spectrometric method has a problem receiving the influence of the surfactant, and a potentiometric method is difficult to use because of the problem of an insignificant change in the potential difference value of the Ce(III)/Ce(IV). Thus, the present study was undertaken to determine whether the potentiometric titration method can be used for an analysis of the Ce(IV) concentration in the nanoparticle-based foam decontaminant containing surfactant. It will be effectively used for the Ce(IV) concentration measurement, in relation to the subsequent research on the derivation of optimal conditions for the regeneration of Ce(III) through ozonation treatment.

  19. Spectroscopy and chemistry of uranium IV

    International Nuclear Information System (INIS)

    Folcher, G.; Rigny, P.

    1980-06-01

    Different fundamental research papers on uranium IV are presented, some were never edited. Molecular spectroscopy was used for identification and structural study of uranium IV in aqueous or organic solutions. The fields studied are: coordination, stereochemistry, electronic structure and chemical properties. For interpretation of results some studies were made with solid compounds or with thorium compounds or thorium complexes. Knowledge of actinides chemistry is improved, uranium and thorium being models for 5 f ions, extractive chemistry is better understood and new applications are possible [fr

  20. Vectorization at the KENO-IV code

    International Nuclear Information System (INIS)

    Asai, K.; Higuchi, K.; Katakura, J.

    1986-01-01

    The multigroup criticality safety code KENO-IV has been vectorized and tested on the FACOM VP-100 vector processor. At first, the vectorized KENO-IV on a scalar processor was slower than the original one by a factor of 1.4 because of the overhead introduced by vectorization. Making modifications of algorithms and techniques for vectorization, the vectorized version has become faster than the original one by a factor of 1.4 on the vector processor. For further speedup of the code, some improvements on compiler and hardware, especially on addition of Monte Carlo pipelines to the vector processor, are discussed