WorldWideScience

Sample records for advanced nuclear technology

  1. Advanced technology for nuclear powerplants

    International Nuclear Information System (INIS)

    Rohm, H.H.

    1987-01-01

    Advanced technology offers significant potential benefit to the nuclear industry. Improvements can be anticipated in plant performance, reliability, and overall plant safety as well as reduced life cycle costs. Utilizing artificial intelligence and expert systems, robotics, advanced instruments and controls, and modularization technologies can enhance plant operations and provide new insights and perspectives to plant risk and thus focus resources to areas of importance. Plant reliability, operability, availability, accident interdiction and limitation, and plant recovery are expected to improve. However, utilizing these technologies is not an automatic process. In addition to the actual costs associated with developing and implementing the technologies, operator training and acceptance represents a potential significant problem. Traditional plant operators have little or no experience with computer technology. There has already been some difficulty getting nuclear plant operators to accept and use the new technologies that have been implemented to accept and use the new technologies that have been implemented thus far

  2. Advanced nuclear energy analysis technology

    International Nuclear Information System (INIS)

    Gauntt, Randall O.; Murata, Kenneth K.; Romero, Vicente Josce; Young, Michael Francis; Rochau, Gary Eugene

    2004-01-01

    A two-year effort focused on applying ASCI technology developed for the analysis of weapons systems to the state-of-the-art accident analysis of a nuclear reactor system was proposed. The Sandia SIERRA parallel computing platform for ASCI codes includes high-fidelity thermal, fluids, and structural codes whose coupling through SIERRA can be specifically tailored to the particular problem at hand to analyze complex multiphysics problems. Presently, however, the suite lacks several physics modules unique to the analysis of nuclear reactors. The NRC MELCOR code, not presently part of SIERRA, was developed to analyze severe accidents in present-technology reactor systems. We attempted to: (1) evaluate the SIERRA code suite for its current applicability to the analysis of next generation nuclear reactors, and the feasibility of implementing MELCOR models into the SIERRA suite, (2) examine the possibility of augmenting ASCI codes or alternatives by coupling to the MELCOR code, or portions thereof, to address physics particular to nuclear reactor issues, especially those facing next generation reactor designs, and (3) apply the coupled code set to a demonstration problem involving a nuclear reactor system. We were successful in completing the first two in sufficient detail to determine that an extensive demonstration problem was not feasible at this time. In the future, completion of this research would demonstrate the feasibility of performing high fidelity and rapid analyses of safety and design issues needed to support the development of next generation power reactor systems

  3. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1976-01-01

    Advances in Nuclear Science and Technology, Volume 9 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of the possible consequences of a large-scale release of radioactivity from a nuclear reactor in the event of a serious accident. This text then discusses the extension of conventional perturbation techniques to multidimensional systems and to high-order approximations of the Boltzmann equation.

  4. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1972-01-01

    Advances in Nuclear Science and Technology, Volume 6 provides information pertinent to the fundamental aspects of nuclear science and technology. This book covers a variety of topics, including nuclear steam generator, oscillations, fast reactor fuel, gas centrifuge, thermal transport system, and fuel cycle.Organized into six chapters, this volume begins with an overview of the high standards of technical safety for Europe's first nuclear-propelled merchant ship. This text then examines the state of knowledge concerning qualitative results on the behavior of the solutions of the nonlinear poin

  5. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1962-01-01

    Advances in Nuclear Science and Technology, Volume 1 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book covers a variety of topics, including nuclear power stations, graft polymerization, diffusion in uranium alloys, and conventional power plants.Organized into seven chapters, this volume begins with an overview of the three stages of the operation of a power plant, either nuclear or conventionally fueled. This text then examines the major problems that face the successful development of commercial nuclear power plants. Other chapters consider

  6. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1970-01-01

    Advances in Nuclear Science and Technology, Volume 5 presents the underlying principles and theory, as well as the practical applications of the advances in the nuclear field. This book reviews the specialized applications to such fields as space propulsion.Organized into six chapters, this volume begins with an overview of the design and objective of the Fast Flux Test Facility to provide fast flux irradiation testing facilities. This text then examines the problem in the design of nuclear reactors, which is the analysis of the spatial and temporal behavior of the neutron and temperature dist

  7. Advances in nuclear science and technology

    CERN Document Server

    Greebler, Paul

    1966-01-01

    Advances in Nuclear Science and Technology, Volume 3 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book presents the advances in the atomic energy field.Organized into six chapters, this volume begins with an overview of the use of pulsed neutron sources for the determination of the thermalization and diffusion properties of moderating as well as multiplying media. This text then examines the effect of nuclear radiation on electronic circuitry and its components. Other chapters consider radiation effects in various inorganic solids, with empha

  8. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1973-01-01

    Advances in Nuclear Science and Technology, Volume 7 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of irradiation-induced void swelling in austenitic stainless steels. This text then examines the importance of various transport processes for fission product redistribution, which depends on the diffusion data, the vaporization properties, and the solubility in the fuel matrix. Other chapters co

  9. Advances in nuclear science and technology

    CERN Document Server

    Greebler, Paul

    1968-01-01

    Advances in Nuclear Science and Technology Volume 4 provides information pertinent to the fundamental aspects of advanced reactor concepts. This book discusses the advances in various areas of general applicability, including modern perturbation theory, optimal control theory, and industrial application of ionizing radiations.Organized into seven chapters, this volume begins with an overview of the technology of sodium-cooled fast breeder power reactors and gas-cooled power reactors. This text then examines the key role of reactor safety in the development of fast breeder reactors. Other chapt

  10. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1975-01-01

    Advances in Nuclear Science and Technology, Volume 8 discusses the development of nuclear power in several countries throughout the world. This book discusses the world's largest program of land-based electricity production in the United States.Organized into six chapters, this volume begins with an overview of the phenomenon of quasi-exponential behavior by examining two mathematical models of the neutron field. This text then discusses the finite element method, which is a method for obtaining approximate solutions to integral or differential equations. Other chapters consider the status of

  11. Advanced pyrochemical technologies for minimizing nuclear waste

    International Nuclear Information System (INIS)

    Bronson, M.C.; Dodson, K.E.; Riley, D.C.

    1994-01-01

    The Department of Energy (DOE) is seeking to reduce the size of the current nuclear weapons complex and consequently minimize operating costs. To meet this DOE objective, the national laboratories have been asked to develop advanced technologies that take uranium and plutonium, from retired weapons and prepare it for new weapons, long-term storage, and/or final disposition. Current pyrochemical processes generate residue salts and ceramic wastes that require aqueous processing to remove and recover the actinides. However, the aqueous treatment of these residues generates an estimated 100 liters of acidic transuranic (TRU) waste per kilogram of plutonium in the residue. Lawrence Livermore National Laboratory (LLNL) is developing pyrochemical techniques to eliminate, minimize, or more efficiently treat these residue streams. This paper will present technologies being developed at LLNL on advanced materials for actinide containment, reactors that minimize residues, and pyrochemical processes that remove actinides from waste salts

  12. Radioactive waste management and advanced nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

    2007-01-01

    In 2007 ENEA's Department of Nuclear Fusion and Fission, and Related Technologies acted according to national policy and the role assigned to ENEA FPN by Law 257/2003 regarding radioactive waste management and advanced nuclear fuel cycle technologies

  13. Advanced nuclear reactor types and technologies

    Energy Technology Data Exchange (ETDEWEB)

    Ignatiev, V [ed.; Feinberg, O; Morozov, A [Russian Research Centre ` Kurchatov Institute` , Moscow (Russian Federation); Devell, L [Studsvik Eco and Safety AB, Nykoeping (Sweden)

    1995-07-01

    The document is a comprehensive world-wide catalogue of concepts and designs of advanced fission reactor types and fuel cycle technologies. Two parts have been prepared: Part 1 Reactors for Power Production and Part 2 Heating and Other Reactor Applications. Part 3, which will cover advanced waste management technology, reprocessing and disposal for different nuclear fission options is planned for compilation during 1995. The catalogue was prepared according to a special format which briefly presents the project title, technical approach, development status, application of the technology, reactor type, power output, and organization which developed these designs. Part 1 and 2 cover water cooled reactors, liquid metal fast reactors, gas-cooled reactors and molten salt reactors. Subcritical accelerator-driven systems are also considered. Various reactor applications as power production, heat generation, ship propulsion, space power sources and transmutation of such waste are included. Each project is described within a few pages with the main features of an actual design using a table with main technical data and figure as well as references for additional information. Each chapter starts with an introduction which briefly describes main trends and approaches in this field. Explanations of terms and abbreviations are provided in a glossary.

  14. Advanced nuclear reactor types and technologies

    International Nuclear Information System (INIS)

    Ignatiev, V.; Devell, L.

    1995-01-01

    The document is a comprehensive world-wide catalogue of concepts and designs of advanced fission reactor types and fuel cycle technologies. Two parts have been prepared: Part 1 Reactors for Power Production and Part 2 Heating and Other Reactor Applications. Part 3, which will cover advanced waste management technology, reprocessing and disposal for different nuclear fission options is planned for compilation during 1995. The catalogue was prepared according to a special format which briefly presents the project title, technical approach, development status, application of the technology, reactor type, power output, and organization which developed these designs. Part 1 and 2 cover water cooled reactors, liquid metal fast reactors, gas-cooled reactors and molten salt reactors. Subcritical accelerator-driven systems are also considered. Various reactor applications as power production, heat generation, ship propulsion, space power sources and transmutation of such waste are included. Each project is described within a few pages with the main features of an actual design using a table with main technical data and figure as well as references for additional information. Each chapter starts with an introduction which briefly describes main trends and approaches in this field. Explanations of terms and abbreviations are provided in a glossary

  15. Materials technologies for advanced nuclear energy concepts

    International Nuclear Information System (INIS)

    DiStefano, J.; Harms, B.

    1983-01-01

    High-performance, advanced nuclear power plant concepts have emerged with major emphasis on lower capital costs, inherent safety, and increased reliability. The materials problems posed by these concepts are discussed and how the scientists and technologists at ORNL plan to solve them is described

  16. Technology readiness levels for advanced nuclear fuels and materials development

    Energy Technology Data Exchange (ETDEWEB)

    Carmack, W.J., E-mail: jon.carmack@inl.gov [Idaho National Laboratory, Idaho Falls, ID (United States); Braase, L.A.; Wigeland, R.A. [Idaho National Laboratory, Idaho Falls, ID (United States); Todosow, M. [Brookhaven National Laboratory, Upton, NY (United States)

    2017-03-15

    Highlights: • Definition of nuclear fuels system technology readiness level. • Identification of evaluation criteria for nuclear fuel system TRLs. • Application of TRLs to fuel systems. - Abstract: The Technology Readiness process quantitatively assesses the maturity of a given technology. The National Aeronautics and Space Administration (NASA) pioneered the process in the 1980s to inform the development and deployment of new systems for space applications. The process was subsequently adopted by the Department of Defense (DoD) to develop and deploy new technology and systems for defense applications. It was also adopted by the Department of Energy (DOE) to evaluate the maturity of new technologies in major construction projects. Advanced nuclear fuels and materials development is needed to improve the performance and safety of current and advanced reactors, and ultimately close the nuclear fuel cycle. Because deployment of new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the assessment process to advanced fuel development is useful as a management, communication, and tracking tool. This article provides definition of technology readiness levels (TRLs) for nuclear fuel technology as well as selected examples regarding the methods by which TRLs are currently used to assess the maturity of nuclear fuels and materials under development in the DOE Fuel Cycle Research and Development (FCRD) Program within the Advanced Fuels Campaign (AFC).

  17. Advanced Filter Technology For Nuclear Thermal Propulsion

    Science.gov (United States)

    Castillon, Erick

    2015-01-01

    The Scrubber System focuses on using HEPA filters and carbon filtration to purify the exhaust of a Nuclear Thermal Propulsion engine of its aerosols and radioactive particles; however, new technology may lend itself to alternate filtration options, which may lead to reduction in cost while at the same time have the same filtering, if not greater, filtering capabilities, as its predecessors. Extensive research on various types of filtration methods was conducted with only four showing real promise: ionization, cyclonic separation, classic filtration, and host molecules. With the four methods defined, more research was needed to find the devices suitable for each method. Each filtration option was matched with a device: cyclonic separators for the method of the same name, electrostatic separators for ionization, HEGA filters, and carcerands for the host molecule method. Through many hours of research, the best alternative for aerosol filtration was determined to be the electrostatic precipitator because of its high durability against flow rate and its ability to cleanse up to 99.99% of contaminants as small as 0.001 micron. Carcerands, which are the only alternative to filtering radioactive particles, were found to be non-existent commercially because of their status as a "work in progress" at research institutions. Nevertheless, the conclusions after the research were that HEPA filters is recommended as the best option for filtering aerosols and carbon filtration is best for filtering radioactive particles.

  18. Cost estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

    Hudson, C.R. II.

    1986-07-01

    To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies

  19. Cost estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

    Delene, J.G.; Hudson, C.R. II.

    1990-03-01

    To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies. 10 refs., 8 figs., 32 tabs

  20. Cost estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

    Hudson, C.R. II.

    1987-07-01

    To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies

  1. Advances in nuclear fuel technology. 3. Development of advanced nuclear fuel recycle systems

    International Nuclear Information System (INIS)

    Arie, Kazuo; Abe, Tomoyuki; Arai, Yasuo

    2002-01-01

    Fast breeder reactor (FBR) cycle technology has a technical characteristics flexibly easy to apply to diverse fuel compositions such as plutonium, minor actinides, and so on and fuel configurations. By using this characteristics, various feasibilities on effective application of uranium resources based on breeding of uranium of plutonium for original mission of FBR, contribution to radioactive wastes problems based on amounts reduction of transuranium elements (TRU) in high level radioactive wastes, upgrading of nuclear diffusion resistance, extremely upgrading of economical efficiency, and so on. In this paper, were introduced from these viewpoints, on practice strategy survey study on FBR cycle performed by cooperation of the Japan Nuclear Cycle Development Institute (JNC) with electric business companies and so on, and on technical development on advanced nuclear fuel recycle systems carried out at the Central Research Institute of Electric Power Industry, Japan Atomic Energy Research Institute, and so on. Here were explained under a vision on new type of fuels such as nitride fuels, metal fuels, and so on as well as oxide fuels, a new recycle system making possible to use actinides except uranium and plutonium, an 'advanced nuclear fuel cycle technology', containing improvement of conventional wet Purex method reprocessing technology, fuel manufacturing technology, and so on. (G.K.)

  2. Cost-estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

    Delene, J.G.; Hudson, C.R.

    1993-01-01

    Various advanced power plant concepts are currently under development. These include several advanced light water reactors as well as the modular high-temperature gas-cooled reactor and the advanced liquid-metal reactor. One measure-of the attractiveness of a new concept is cost. Invariably, the cost of a new type of power plant will be compared with other alternative forms of electric generation. In order to make reasonable comparative assessments of competing technologies, consistent ground rules and assumptions must be applied when developing cost estimates. This paper describes the cost-estimate guidelines developed by Oak Ridge National Laboratory for the U.S. Department of Energy (DOE) to be used in developing cost estimates for the advanced nuclear reactors and how these guidelines relate to the DOE cost verification process

  3. Advanced digital technology - improving nuclear power plant performance through maintainability

    International Nuclear Information System (INIS)

    Ford, J.L.; Senechal, R.R.; Altenhein, G.D.; Harvey, R.P.

    1998-01-01

    In today's energy sector there is ever increasing pressure on utilities to operate power plants at high capacity factors. To ensure nuclear power is competitive into the next century, it is imperative that strategic design improvements be made to enhance the performance of nuclear power plants. There are a number of factors that affect a nuclear power plant's performance; lifetime maintenance is one of the major contributors. The maturing of digital technology has afforded ABB the opportunity to make significant design improvements in the area of maintainability. In keeping with ABB's evolutionary advanced nuclear plant design approach, digital technology has systematically been incorporated into the control and protection systems of the most recent Korean nuclear units in operation and under construction. One example of this was the multi-functional design team approach that was utilized for the development of ABB's Digital Plant Protection System (DPPS). The design team consisted of engineers, maintenance technicians, procurement specialists and manufacturing personnel in order to provide a complete perspective on all facets of the design. The governing design goals of increased reliability and safety, simplicity of design, use of off-the-shelf products and reduced need for periodic surveillance testing were met with the selection of proven ABB-Advant Programmable Logic Controllers (PLCs) as the heart of the DPPS. The application of digital PLC technology allows operation for extended periods without requiring routine maintenance or re-calibration. A well documented commercial dedication program approved by the United States Nuclear Regulatory Commission (US NRC) as part of the System 80+ TM Advanced Light Water Reactor Design Certification Program, allowed the use of off-the shelf products in the design of the safety protection system. In addition, a number of mechanical and electrical improvements were made which support maintainability. The result is a DPPS

  4. Indian Nuclear Society annual conference-1994 on advanced technologies related to nuclear power: proceedings

    International Nuclear Information System (INIS)

    Grover, R.B.

    1994-01-01

    The focal theme of the conference is advanced technologies related to nuclear power. Over the past three decades civilian nuclear power plants around the world have accumulated about 6000 reactor years of experience and have performed quite well. Overall safety record has been satisfactory. However, nuclear community is trying to compete with its own record by trying to enhance the safety characteristics of the best operating plant. A safety culture has been established in the nuclear establishments, which is providing impetus to advances in all aspects of nuclear technology all over the world. India has ongoing programmes for the development of advanced reactors and related advanced technologies. Evolution of pressurised heavy water reactors in India, developments made in the design of advanced heavy water reactor and the fast reactor programme, are some of the topics covered in addition to highlighting worldwide developments for the next generation of light water reactors. India is one of the few countries in the world where expertise about complete fuel cycle is available. Developments in the back end of the fuel cycle, use of thorium and plutonium and other related issues are also discussed. Technology control regimes being advocated and adopted by developed nations make it imperative for us to indigenise every equipment and component that goes into a power plant. In view of this, some aspects of manufacturing technologies, inspection techniques and maintenance problems are also covered. Relevant papers are processed separately for INIS. (M.K.V.)

  5. Advanced nuclear reactor safety design technology research in NPIC

    International Nuclear Information System (INIS)

    Yu, H.

    2014-01-01

    After the Fukushima accident happen, Nuclear Power Plants (NPPs) construction has been suspended in China for a time. Now the new regulatory rule has been proposed that the most advanced safety standard must be adopted for the new NPPs and practical elimination of large fission product release by design during the next five plans period. So the advanced reactor research is developing in China. NPIC is engaging on the ACP1000 and ACP100 (Small Module Reactor) design. The main design character will be introduced in this paper. The Passive Combined with Active (PCWA) design was adopted during the ACP1000 design to reduce the core damage frequency (CDF); the Cavity Injection System (CIS) is design to mitigation the consequence of the severe accident. Advance passive safety system was designed to ensure the long term residual heat removal during the Small Module Reactor (SMR). The SMR will be utilized to be the floating reactors, district heating reactor and so on. Besides, the Science and Technology on Reactor System Design Technology Laboratory (LRSDT) also engaged on the fundamental thermal-hydraulic characteristic research in support of the system validation. (author)

  6. Advancement of safeguards inspection technology for CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Sung; Park, W S; Cha, H R; Ham, Y S; Lee, Y G; Kim, K P; Hong, Y D

    1999-04-01

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  7. Experiences and Trends of Manufacturing Technology of Advanced Nuclear Fuels

    International Nuclear Information System (INIS)

    2012-08-01

    The 'Atoms for Peace' mission initiated in the mid-1950s paved the way for the development and deployment of nuclear fission reactors as a source of heat energy for electricity generation in nuclear power reactors and as a source of neutrons in non-power reactors for research, materials irradiation, and testing and production of radioisotopes. The fuels for nuclear reactors are manufactured from natural uranium (∼99.3% 238 U + ∼0.7% 235 U) and natural thorium (∼100% 232 Th) resources. Currently, most power and research reactors use 235 U, the only fissile isotope found in nature, as fuel. The fertile isotopes 238 U and 232 Th are transmuted in the reactor to human-made 239 Pu and 233 U fissile isotopes, respectively. Likewise, minor actinides (MA) (Np, Am and Cm) and other plutonium isotopes are also formed by a series of neutron capture reactions with 238 U and 235 U. Long term sustainability of nuclear power will depend to a great extent on the efficient, safe and secure utilization of fissile and fertile materials. Light water reactors (LWRs) account for more than 82% of the operating reactors, followed by pressurized heavy water reactors (PHWRs), which constitute ∼10% of reactors. LWRs will continue to dominate the nuclear power market for several decades, as long as economically viable natural uranium resources are available. Currently, the plutonium obtained from spent nuclear fuel is subjected to mono recycling in LWRs as uranium-plutonium mixed oxide (MOX), containing up to 12% PuO 2 , in a very limited way. The reprocessed uranium (RepU) is also re-enriched and recycled in LWRs in a few countries. Unfortunately, the utilization of natural uranium resources in thermal neutron reactors is 2 and MOX fuel technology has matured during the past five decades. These fuels are now being manufactured, used and reprocessed on an industrial scale. Mixed uranium- plutonium monocarbide (MC), mononitride (MN) and U-Pu-Zr alloys are recognized as advanced fuels

  8. Current Status of Advanced Nuclear Fuel Cycle technologies

    International Nuclear Information System (INIS)

    Hwang, Yong Soo; Lee, Jong Hyun

    2009-07-01

    To expand the use of nuclear energy, SNF from nuclear power plants must be managed in a safe and environmental friendly and the problem of decreasing uranium should be solved. To resolve this, a dry processing technology Pyroprocessing is focused on. The government started to develop of Pyroprocessing technology in 1997. According to the decision of government based of Atomic Energy Commission in December 2008, the Korea Atomic Energy Research Institute will construct PRIDE (Pyroprocess Integrated Inactive DEmonstration Facility) by 2011 to prove a consistent process. If Pyroprocessing technology will be developed in the near future, the size of radioactive waste disposal site can be reduced to 100 times compared to the direct disposal. When this technology will be connected to Fast Reactor. high level nuclear waste management of Hundreds of thousands of years may be reduced to hundreds years. However for the commercialization of Pyroprocessing technology, there are some problems to solve. First, because of none commercial facilities in the world of executive experience, so that the facility design, measurement. management and material flow, the critical need for data accumulation. Second, High-level nuclear waste have been known to generate more than the wet methods, it should continue to reduce technology development. In addition, a careful consideration of the residual uranium generating on process also can maximize the efficiency of reducing. The new concept is being developed in Korea Atomic Energy Research Institute Pyroprocessing technology and nuclear waste processing technology to overcome these drawbacks sUQQested a way

  9. Advances in zirconium technology for nuclear reactor application

    International Nuclear Information System (INIS)

    Ganguly, C.

    2002-01-01

    Zirconium alloys are extensively used as a material for cladding nuclear fuels and for making core structurals of water-cooled nuclear power reactors all over the world for generation of nearly 16 percent of the worlds electricity. Only four countries in the world, namely France, USA, Russia and India, have large zirconium industry and capability to manufacture reactor grade zirconium sponge, a number of zirconium alloys and a wide variety of structural components for water cooled nuclear reactor. The present paper summarises the status of zirconium technology and highlights the achievement of Nuclear Fuel Complex during the last ten years in developing a wide variety of zirconium alloys and components for water-cooled nuclear power programme

  10. Technological Advances, Human Performance, and the Operation of Nuclear Facilities

    Science.gov (United States)

    Corrado, Jonathan K.

    Many unfortunate and unintended adverse industrial incidents occur across the United States each year, and the nuclear industry is no exception. Depending on their severity, these incidents can be problematic for people, the facilities, and surrounding environments. Human error is a contributing factor in many such incidents. This dissertation first explored the hypothesis that technological changes that affect how operators interact within the systems of the nuclear facilities exacerbate the cost of incidents caused by human error. I conducted a review of nuclear incidents in the United States from 1955 through 2010 that reached Level 3 (serious incident) or higher on the International Nuclear Events Scale (INES). The cost of each incident at facilities that had recently undergone technological changes affecting plant operators' jobs was compared to the cost of events at facilities that had not undergone changes. A t-test determined a statistically significant difference between the two groups, confirming the hypothesis. Next, I conducted a follow-on study to determine the impact of the incorporation of new technologies into nuclear facilities. The data indicated that spending more money on upgrades increased the facility's capacity as well as the number of incidents reported, but the incident severity was minor. Finally, I discuss the impact of human error on plant operations and the impact of evolving technology on the 21st-century operator, proposing a methodology to overcome these challenges by applying the systems engineering process.

  11. A brief review of advances in complex networks of nuclear science and technology field

    International Nuclear Information System (INIS)

    Fang Jinqing

    2010-01-01

    A brief review of advances in complex networks of nuclear science and technology field at home and is given and summarized. These complex networks include: nuclear energy weapon network, network centric warfare, beam transport networks, continuum percolation evolving network associated with nuclear reactions, global nuclear power station network, (nuclear) chemistry reaction networks, radiological monitoring and anti-nuclear terror networks, and so on. Some challenge issues and development prospects of network science are pointed out finally. (authors)

  12. Life cycle analysis of advanced nuclear power generation technologies

    International Nuclear Information System (INIS)

    Uchiyama, Yoji; Yokoyama, Hayaichi

    1996-01-01

    In this research, as for light water reactors and fast breeder reactors, for the object of all the processes from the mining, transport and refining of fuel, electric power generation to the treatment and disposal of waste, the amount of energy input and the quantity of CO 2 emission over the life cycle were analyzed, and regarding the influence that the technical progress of nuclear power generation exerted to environment, the effect of improvement was elucidated. Attention has been paid to nuclear power generation as its CO 2 emission is least, and the effect of global warming is smallest. In order to reduce the quantity of radioactive waste generation in LWRs and the cost of fuel cycle, and to extend the operation cycle, the technical development for heightening fuel burnup is in progress. The process of investigation of the new technologies of nuclear power generation taken up in this research is described. The analysis of the energy balance of various power generation methods is discussed. In the case of pluthermal process, the improvement of energy balance ratio is dependent on uranium enrichment technology. Nuclear power generation requires much materials and energy for the construction, and emits CO 2 indirectly. The CO 2 unit emission based on the analysis of energy balance was determined for the new technologies of nuclear power generation, and the results are shown. (K.I.)

  13. Public Information on the Nuclear Energy and Advanced Technology Agency of Cuba

    International Nuclear Information System (INIS)

    Contreras Izquierdo, Marta Alicia

    2007-01-01

    The mission of the Nuclear Energy and Advanced Technology Agency of Cuba is the promoting and controlling of the peaceful use of nuclear energy and radiation application; additionally, they have to inform the general public about those technologies. The main of this work is to expose the methodology and results of the studies of the attitudes toward the nuclear applications of the users of the nuclear techniques

  14. Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle

    Energy Technology Data Exchange (ETDEWEB)

    Park, Byung Heung [Chungju National University, Chungju (Korea, Republic of); Ko, Won IL [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-12-15

    The nuclear fuel cycle (NFC) analysis is a study to set a NFC policy and to promote systematic researches by analyzing technologies and deriving requirements at each stage of a fuel cycle. System analysis techniques are utilized for comparative analysis and assessment of options on a considered system. In case that NFC is taken into consideration various methods of the system analysis techniques could be applied depending on the range of an interest. This study presented NFC analysis strategies for the development of a domestic advanced NFC and analysis techniques applicable to different phases of the analysis. Strategically, NFC analysis necessitates the linkage with technology analyses, domestic and international interests, and a national energy program. In this respect, a trade-off study is readily applicable since it includes various aspects on NFC as metrics and then analyzes the considered NFC options according to the derived metrics. In this study, the trade-off study was identified as a method for NFC analysis with the derived strategies and it was expected to be used for development of an advanced NFC. A technology readiness level (TRL) method and NFC simulation codes could be utilized to obtain the required metrics and data for assessment in the trade-off study. The methodologies would guide a direction of technology development by comparing and assessing technological, economical, environmental, and other aspects on the alternatives. Consequently, they would contribute for systematic development and deployment of an appropriate advanced NFC.

  15. Nuclear Fuel Cycle Analysis Technology to Develop Advanced Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Park, Byung Heung; Ko, Won IL

    2011-01-01

    The nuclear fuel cycle (NFC) analysis is a study to set a NFC policy and to promote systematic researches by analyzing technologies and deriving requirements at each stage of a fuel cycle. System analysis techniques are utilized for comparative analysis and assessment of options on a considered system. In case that NFC is taken into consideration various methods of the system analysis techniques could be applied depending on the range of an interest. This study presented NFC analysis strategies for the development of a domestic advanced NFC and analysis techniques applicable to different phases of the analysis. Strategically, NFC analysis necessitates the linkage with technology analyses, domestic and international interests, and a national energy program. In this respect, a trade-off study is readily applicable since it includes various aspects on NFC as metrics and then analyzes the considered NFC options according to the derived metrics. In this study, the trade-off study was identified as a method for NFC analysis with the derived strategies and it was expected to be used for development of an advanced NFC. A technology readiness level (TRL) method and NFC simulation codes could be utilized to obtain the required metrics and data for assessment in the trade-off study. The methodologies would guide a direction of technology development by comparing and assessing technological, economical, environmental, and other aspects on the alternatives. Consequently, they would contribute for systematic development and deployment of an appropriate advanced NFC.

  16. Advanced passive technology: A global standard for nuclear plant requirements

    International Nuclear Information System (INIS)

    Novak, V.

    1994-01-01

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

  17. Efficiency improvement of nuclear power plant operation: the significant role of advanced nuclear fuel technologies

    International Nuclear Information System (INIS)

    Velde Van de, A.; Burtak, F.

    2001-01-01

    Due to the increased liberalisation of the power markets, nuclear power generation is being exposed to high cost reduction pressure. In this paper we highlight the role of advanced nuclear fuel technologies to reduce the fuel cycle costs and therefore increase the efficiency of nuclear power plant operation. The key factor is a more efficient utilisation of the fuel and present developments at Siemens are consequently directed at (i) further increase of batch average burnup, (ii) improvement of fuel reliability, (iii) enlargement of fuel operation margins and (iv) improvement of methods for fuel design and core analysis. As a result, the nuclear fuel cycle costs for a typical LWR have been reduced during the past decades by about US$ 35 million per year. The estimated impact of further burnup increases on the fuel cycle costs is expected to be an additional saving of US$10 - 15 million per year. Due to the fact that the fuel will operate closer to design limits, a careful approach is required when introducing advanced fuel features in reload quantities. Trust and co-operation between the fuel vendors and the utilities is a prerequisite for the common success. (authors)

  18. Nuclear techniques in the development of advanced ceramic technologies

    International Nuclear Information System (INIS)

    Axe, J.D.; Hewat, A.W.; Maier, J.; Margaca, F.M.A.; Rauch, H.

    1999-01-01

    The importance of research, development and application of advanced materials is well understood by all developed and most developing countries. Amongst advanced materials, ceramics play a prominent role due to their specific chemical and physical properties. According to performance and importance, advanced ceramics can be classified as structural ceramics (mechanical function) and the so-called functional ceramics. In the latter class of materials, special electrical, chemical, thermal, magnetic and optical properties are of interest. The most valuable materials are multifunctional, for example, when structural ceramics combine beneficial mechanical properties with thermal and chemical sensitivity. Multifunctionality is characteristic of many composite materials (organic/inorganic composite). Additionally, properties of material can be changed by reducing its dimension (thin films, nanocrystalline ceramics). Nuclear techniques, found important applications in research and development of advanced ceramics. The use of neutron techniques has increased dramatically in recent years due to the development of advanced neutron sources, instrumentation and improved data analysis. Typical neutron techniques are neutron diffraction, neutron radiography, small angle neutron scattering and very small angle neutron scattering. Neutrons can penetrate deeply into most materials thus sampling their bulk properties. In determination of the crystal structure of HTSC, YBa 2 Cu 2 O 7 , XRD located the heavy metal atoms, but failed in finding many of the oxygen atoms, while the neutron diffraction located all atoms equally well in the crystal structure. Neutron diffraction is also unique for the determination of the magnetic structure of materials since the neutrons themselves have a magnetic moment. Application of small angle neutron scattering for the determination of the size of hydrocarbon aggregates within the zeolite channels is illustrated. (author)

  19. Advancing nuclear technology and research. The advanced test reactor national scientific user facility

    Energy Technology Data Exchange (ETDEWEB)

    Benson, Jeff B; Marshall, Frances M [Idaho National Laboratory, Idaho Falls, ID (United States); Allen, Todd R [Univ. of Wisconsin, Madison, WI (United States)

    2012-03-15

    The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is one of the world's premier test reactors for providing the capability for studying the effects of intense neutron and gamma radiation on reactor materials and fuels. The INL also has several hot cells and other laboratories in which irradiated material can be examined to study material radiation effects. In 2007 the US Department of Energy (DOE) designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR and the associated INL laboratories for material testing research. The mission of the ATR NSUF is to provide access to world-class facilities, thereby facilitating the advancement of nuclear science and technology. Cost free access to the ATR, INL post irradiation examination facilities, and partner facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to United States Department of Energy. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. (author)

  20. Advanced passive technology: A global standard for nuclear plant requirements

    Energy Technology Data Exchange (ETDEWEB)

    Novak, V

    1994-12-31

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy` (DOE). The preliminary design was cornpleved in 1989. AP6OO`s Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance.

  1. Technology Roadmap Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs

    Energy Technology Data Exchange (ETDEWEB)

    Donald D Dudenhoeffer; Burce P Hallbert

    2007-03-01

    Instrumentation, Controls, and Human-Machine Interface (ICHMI) technologies are essential to ensuring delivery and effective operation of optimized advanced Generation IV (Gen IV) nuclear energy systems. In 1996, the Watts Bar I nuclear power plant in Tennessee was the last U.S. nuclear power plant to go on line. It was, in fact, built based on pre-1990 technology. Since this last U.S. nuclear power plant was designed, there have been major advances in the field of ICHMI systems. Computer technology employed in other industries has advanced dramatically, and computing systems are now replaced every few years as they become functionally obsolete. Functional obsolescence occurs when newer, more functional technology replaces or supersedes an existing technology, even though an existing technology may well be in working order.Although ICHMI architectures are comprised of much of the same technology, they have not been updated nearly as often in the nuclear power industry. For example, some newer Personal Digital Assistants (PDAs) or handheld computers may, in fact, have more functionality than the 1996 computer control system at the Watts Bar I plant. This illustrates the need to transition and upgrade current nuclear power plant ICHMI technologies.

  2. Human factors design review guidelines for advanced nuclear control room technologies

    International Nuclear Information System (INIS)

    O'Hara, J.; Brown, W.; Granda, T.; Baker, C.

    1991-01-01

    Advanced control rooms (ACRs) for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline. 20 refs., 1 fig

  3. 2. JAPAN-IAEA workshop on advanced safeguards technology for the future nuclear fuel cycle. Abstracts

    International Nuclear Information System (INIS)

    2009-01-01

    This international workshop addressed issues and technologies associated with safeguarding the future nuclear fuel cycle. The workshop discussed issues of interest to the safeguards community, facility operators and State Systems of accounting and control of nuclear materials. Topic areas covered were as follows: Current Status and Future Prospects of Developing Safeguards Technologies for Nuclear Fuel Cycle Facilities, Technology and Instrumentation Needs, Advanced Safeguards Technologies, Guidelines on Developing Instrumentation to Lead the Way for Implementing Future Safeguards, and Experiences and Lessons learned. This workshop was of interest to individuals and organizations concerned with future nuclear fuel cycle technical developments and safeguards technologies. This includes representatives from the nuclear industry, R and D organizations, safeguards inspectorates, State systems of accountancy and control, and Member States Support Programmes

  4. The advanced test reactor national scientific user facility advancing nuclear technology

    International Nuclear Information System (INIS)

    Allen, T.R.; Thelen, M.C.; Meyer, M.K.; Marshall, F.M.; Foster, J.; Benson, J.B.

    2009-01-01

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team

  5. The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology

    International Nuclear Information System (INIS)

    Allen, T.R.; Benson, J.B.; Foster, J.A.; Marshall, F.M.; Meyer, M.K.; Thelen, M.C.

    2009-01-01

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team

  6. Technology Advancement and the CTBT: Taking One Step Back from the Nuclear Brink

    Science.gov (United States)

    Perry, W. J.

    2016-12-01

    Technology plays a pivotal role in international nuclear security and technological advancement continues to support a path toward stability. One near-term and readily-obtainable step back from the nuclear brink is the Comprehensive Nuclear-test Ban Treaty (CTBT). The technology to independently verify adherence to the CTBT has matured in the 20 years since the Treaty was opened for signature. Technology has also improved the safety and reliability of the US nuclear stockpile in the absence of testing. Due to these advances over the past two decades neither verification nor stockpiles effectiveness should be an impediment to the Treaty's entry into force. Other technical and geo-political evolution in this same period has changed the perceived benefit of nuclear weapons as instruments of security. Recognizing the change technology has brought to deliberation of nuclear security, nations are encouraged to take this one step away from instability.This presentation will reflect on the history and assumptions that have been used to justify the build-up and configuration of nuclear stockpiles, the changes in technology and conditions that alter the basis of these original assumptions, and the re-analysis of security using current and future assumptions that point to the need for revised nuclear policies. The author has a unique and well informed perspective as both the most senior US Defense Official and a technologist.

  7. Research and development on the application of advanced control technologies to advanced nuclear reactor systems: A US national perspective

    International Nuclear Information System (INIS)

    White, J.D.; Monson, L.R.; Carrol, D.G.; Dayal, Y.

    1989-01-01

    Control system designs for nuclear power plants are becoming more advanced through the use of digital technology and automation. This evolution is taking place because of: (1) the limitations in analog based control system performance and maintenance and availability and (2) the promise of significant improvement in plant operation and availability due to advances in digital and other control technologies. Digital retrofits of control systems in US nuclear plants are occurring now. Designs of control and protection systems for advanced LWRs are based on digital technology. The use of small inexpensive, fast, large-capacity computers in these designs is the first step of an evolutionary process described in this paper. Under the sponsorship of the US Department of Energy (DOE), Oak Ridge National Laboratory, Argonne National Laboratory, GE Nuclear Energy and several universities are performing research and development in the application of advances in control theory, software engineering, advanced computer architectures, artificial intelligence, and man-machine interface analysis to control system design. The target plant concept for the work described in this paper is the Power Reactor Inherently Safe Module reactor (PRISM), an advanced modular liquid metal reactor concept. This and other reactor designs which provide strong passive responses to operational upsets or accidents afford good opportunities to apply these advances in control technology. 18 refs., 5 figs

  8. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Woong; Cho, Jae Wan; Lee, Nam Ho; Kim, Woong Ki; Moon, Byung Soo; Lee, Young Jae; Kim, Chang Hoi; Kim, Seung Ho; Hwang, Seok Yong; Kim, Byung Soo; Moon, Jae Sun; Lee, Young Kwang; Choi, Kap Joo

    1996-07-01

    The comparison study of 3 kinds of stereo camera modules done in this final year of 4 year's longterm project shows that regenerating characteristics of stereo image of stereo camera using horizontally moving lens axis method is superior to the other two modules. Base on this comparison result, stereo camera module using horizontally moving lens method is developed. Also, stereo-Boom unit, high definition polarized stereo monitor(KAERI-PSM II) and 10.4sec. auto-stereogram TV using parallax barrier method are developed. These developed systems can be used for people involved in extremely hazardous working area to give vivid reality image of work environment. In the recognition and tracking section, auto-vergencing technology using focus fixation and cepstral filter, stereo camera calibration, range measurement technology using stereo camera module are developed. And active target tracking technology is developed also. In the sensing and intelligent control research part, active radioactivity image monitoring unit is developed. The spatial resolution of monitoring unit is 10cm at 1m distance, FOV is 60x40 deg [HXV], and radioactivity detection limit is 1mR/hr. Also, radiation-resistant inspection camera for nuclear facilities is designed. In the intelligent control section, fuzzy control algorithm for obstacle detouring navigation of mobile robot is developed. The smoothing techniques by fuzzy set is adapted to raise the pliability of obstacle detouring navigation of mobile robot. In order to raise robustness of developed fuzzy algorithm, fuzzy control algorithm is applied to 'Truck Backer Upper' problem and tuned. These advanced critical robot technology and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, can be used to realize unmanned remotelization of nozzle-dam installation/removal task in steam generator of nuclear power plant, which can be contributed for people involved in extremely hazardous

  9. Advanced Safeguards Technology Road-map for the Global Nuclear Energy Partnership

    International Nuclear Information System (INIS)

    Miller, M.C.; Tobin, S.; Smith, L.E.; Ehinger, M.; Dougan, A.; Cipiti, B.; Bakel, A.; Bean, R.

    2008-01-01

    Strengthening the nonproliferation regime, including advanced safeguards, is a cornerstone of the Global Nuclear Energy Partnership (GNEP). To meet these challenges, the Safeguards Campaign was formed, whose mission is to provide research and technology development for the foundation of next generation safeguards systems for implementation in U.S. GNEP facilities. The Safeguards Campaign works closely with the Nuclear Nonproliferation and International Security department (NA-24) of NNSA (National Nuclear Safety Administration) to ensure that technology developed for domestic safeguards applications are optimum with respect to international safeguards use. A major milestone of the program this year has been the development of the advanced safeguards technology road-map. This paper will broadly describe the road-map, which provides a path to next generation safeguards systems including advanced instrumentation; process monitoring; data integration, protection, and analysis; and system level evaluation and knowledge extraction for real time applications. (authors)

  10. Proceedings of chemical engineering in nuclear technology - national seminar on recent advances in fuel cycle technologies: book of abstracts

    International Nuclear Information System (INIS)

    2014-01-01

    Kalpakkam Regional Centre of Indian Institute of Chemical Engineers is embarking on conducting a series of national seminars on Chemical Engineering in Nuclear Technology 2014. For CHEMENT-2014 the theme was Seminar on recent advances in fuel cycle technologies. The topics covered included research and development, modeling and simulation and equipment development. Papers relevant to INIS are indexed separately

  11. Nuclear technologies

    International Nuclear Information System (INIS)

    Toyama, Makoto; Hamasaki, Manabu; Kobayashi, Masahiko; Hoshide, Akihiko; Katayama, Kimio; Nozawa, H.; Karigome, Satoshi

    2010-01-01

    In recent days, energy security is becoming a major global concern and it has been recognized that a major reduction in greenhouse-gas emissions is required to combat climate change. Considerable expansion and new introduction of nuclear power generation are currently being planned and considered for the further in various parts of the world. Nuclear technologies of the latest 10 years in Japan were reviewed with their characteristics, advancement and future perspective. Steady efforts have been made to construct new nuclear power stations with computer-aided engineering system and modular and prefabricated structures, extend the interval of periodic inspections under the new inspection system that should improve both safety and reliability, implement advanced measures against aging and develop the next-generation light water reactors including a medium small reactor. Export of nuclear power plants has been promoted with international business alliance or cooperation. Activities to close nuclear fuel cycle to ensure sustainable nuclear energy utilization have been promoted. Decommissioning technologies for Tokai power station have been developed and accumulated know-how will be utilized in light water reactors. (T. Tanaka)

  12. IAEA activities in technology development for advanced water-cooled nuclear power plants

    International Nuclear Information System (INIS)

    Juhn, Poong Eil; Kupitz, Juergen; Cleveland, John; Lyon, Robert; Park, Je Won

    2003-01-01

    As part of its Nuclear Power Programme, the IAEA conducts activities that support international information exchange, co-operative research and technology assessments and advancements with the goal of improving the reliability, safety and economics of advanced water-cooled nuclear power plants. These activities are conducted based on the advice, and with the support, of the IAEA Department of Nuclear Energy's Technical Working Groups on Advanced Technologies for Light Water Reactors (LWRs) and Heavy Water Reactors (HWRs). Assessments of projected electricity generation costs for new nuclear plants have shown that design organizations are challenged to develop advanced designs with lower capital costs and short construction times, and sizes, including not only large evolutionary plants but also small and medium size plants, appropriate to grid capacity and owner financial investment capability. To achieve competitive costs, both proven means and new approaches should be implemented. The IAEA conducts activities in technology development that support achievement of improved economics of water-cooled nuclear power plants (NPPs). These include fostering information sharing and cooperative research in thermo-hydraulics code validation; examination of natural circulation phenomena, modelling and the reliability of passive systems that utilize natural circulation; establishment of a thermo-physical properties data base; improved inspection and diagnostic techniques for pressure tubes of HWRs; and collection and balanced reporting from recent construction and commissioning experiences with evolutionary water-cooled NPPs. The IAEA also periodically publishes Status Reports on global development of advanced designs. (author)

  13. A Study on planning of the international collaboration foundation for the Advanced Nuclear Technology Development Project

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-03-15

    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 aimed 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. Futhermore, 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.

  14. A Study on planning of the international collaboration foundation for the Advanced Nuclear Technology Development Project

    International Nuclear Information System (INIS)

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

    2005-03-01

    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 aimed 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. Futhermore, 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

  15. Cost estimate guidelines for advanced nuclear power technologies

    International Nuclear Information System (INIS)

    Delene, J.G.; Hudson, C.R. II.

    1993-05-01

    Several advanced power plant concepts are currently under development. These include the Modular High Temperature Gas Cooled Reactors, the Advanced Liquid Metal Reactor and the Advanced Light Water Reactors. One measure of the attractiveness of a new concept is its cost. Invariably, the cost of a new type of power plant will be compared with other alternative forms of electrical generation. This report provides a common starting point, whereby the cost estimates for the various power plants to be considered are developed with common assumptions and ground rules. Comparisons can then be made on a consistent basis. This is the second update of these cost estimate guidelines. Changes have been made to make the guidelines more current (January 1, 1992) and in response to suggestions made as a result of the use of the previous report. The principal changes are that the reference site has been changed from a generic Northeast (Middletown) site to a more central site (EPRI's East/West Central site) and that reference bulk commodity prices and labor productivity rates have been added. This report is designed to provide a framework for the preparation and reporting of costs. The cost estimates will consist of the overnight construction cost, the total plant capital cost, the operation and maintenance costs, the fuel costs, decommissioning costs and the power production or busbar generation cost

  16. The role of advanced nuclear power technologies in developing countries: Criteria and design requirements

    International Nuclear Information System (INIS)

    1990-02-01

    The document includes the papers presented at the following two technical committee meetings organized by the IAEA: Technical Committee Meeting and Workshop on Criteria for the Introduction of Advanced Nuclear Power Technologies for Specific Applications in Developing Countries, Vienna, 27-30 June 1988 (14 papers) and Technical Committee Meeting and Workshop on Design Requirements for the Application of Advanced Concepts in Developing Countries, Vienna, 6-9 December 1988 (16 papers). A separate abstract was prepared for each of these papers

  17. Research on Elemental Technology of Advanced Nuclear Fuel Performance Verification

    International Nuclear Information System (INIS)

    Kim, Yong Soo; Lee, Dong Uk; Jean, Sang Hwan; Koo, Min

    2003-04-01

    Most of current properties models and fuel performance models used in the performance evaluation codes are based on the in-pile data up to 33,000 MWd/MtU. Therefore, international experts are investigating the properties changes and developing advanced prediction models for high burn-up application. Current research is to develop high burn-up fission gas release model for the code and to support the code development activities by collecting data and models, reviewing/assessing the data and models together, and benchmarking the selected models against the appropriate in-pile data. For high burn-up applications, two stage two step fission gas release model is developed based on the real two diffusion process in the grain lattice and grain boundaries of the fission gases and the observation of accelerated release rate in the high burn-up. It is found that the prediction of this model is in excellent agreement with the in-pile measurement results, not only in the low burn-up but also in the high burn-up. This research is found that the importance of thermal conductivity of oxide fuel, especially in the high burn-up, is focused again. It is found that even the temperature dependent models differ from one to another and most of them overestimate the conductivity in the high burn-up. An in-pile data benchmarking of high LHGR fuel rod shows that the difference can reach 30%∼40%, which predicts 400 .deg. C lower than the real fuel centerline temperature. Recent models on the thermal expansion and heat capacity of oxide fuel are found to be well-defined. Irradiation swelling of the oxide fuel are now well-understood that in most cases in LWRs solid fission product swelling is dominant. Thus, the accumulation of in-pile data can enhance the accuracy of the model prediction, rather than theoretical modeling works. Thermo-physical properties of Zircaloy cladding are also well-defined and well-understood except the thermal expansion. However, it turns out that even the

  18. Nuclear microbeam study of advanced materials for fusion reactor technology

    International Nuclear Information System (INIS)

    Alves, L.C.; Alves, E.; Grime, G.W.; Silva, M.F. da; Soares, J.C.

    1999-01-01

    The Oxford scanning proton microprobe was used to study SiC fibres, SiC/SiC ceramic composites and Be pebbles, which are some of the most important materials for fusion technology. For the SiC materials, although the results reveal a high degree of homogeneity and purity in the composition of the fibres, some grains containing heavy metals were detected in the composites. Rutherford backscattering analysis further allowed establishing that at least some of these grains are not on the surface of the material but rather distributed throughout the bulk of the SiC composites. The two different types of Be pebbles analysed also showed very different levels of contaminants. The information obtained with the microbeam analysis is confronted with the one resulting from the broad beam PIXE and RBS analysis

  19. NRC research on the application of advanced I and C technology to commercial nuclear power plants

    International Nuclear Information System (INIS)

    Gollei, K.R.; Hon, A.L.

    1983-01-01

    The operational safety and efficiency of commercial nuclear power plants (NPP's) could possibly be enhanced by utilizing advanced instrumentation and control technology developed by other industries. The NRC is interested in learning about new I and C technology that probably will or could be applied to new or existing plants. This would enable the NRC to be better prepared to evaluate the application without undue delays. It would also help identify any appropriate changes in NRC regulations or guidance necessary to facilitate the application of advanced IandC technology to NPP's. The NRC has initiated a project to work cooperatively with the advanced technology industry, power industry, EPRI, and technical organizations such as ISA toward this goal. This paper describes the objectives and plans of this cooperative effort. It summarizes the highlights of some of the advanced technology already being evaluated by NRC such as microprocessor applications, instruments to detect inadequate core cooling and other two-phase flow measurements, reactor noise surveillance and diagnostic techniques. This paper also suggests potential candidates for consideration such as utilization of advanced instruments for LOCA experiments. It also identifies some of the potential challenges facing the application of advanced technology to NPP's. It concludes that close cooperation between NRC and industry is essential for the success of such applications

  20. Advanced nuclear materials development -Development of superconductor application technology-

    International Nuclear Information System (INIS)

    Hong, Kye Won; Lee, Heui Kyoon; Lee, Hoh Jin; Kim, Chan Joong; Jang, Kun Ik; Kim, Kee Baek; Kwon, Sun Chil; Park, Hae Woong; Yoo, Jae Keun; Kim, Jong Jin; Jang, Joong Chul; Yang, Suk Woo

    1995-07-01

    Fabrication of high Tc bulk superconductor and its application, fabrication of superconducting wire for electric power device and analysis for cryogenic system were carried out for developing superconductor application technologies for electric power system. High quality YBaCuO bulk superconductor was fabricated by controlling initial powder preparation process and prototype fly wheel energy storage device was designed basically. The superconducting levitation force measuring device was made to examine the property of prepared superconductor specimen. Systematic studies on the method of starting powder preparation, mechanical fabrication process, heat treatment condition and analysis of plastic deformation were carried out to increase the stability and reproducibility of superconducting wire. A starting powder with good reactivity and fine particle size was obtained by emulsion drying method. Ag/BSCCO tape with good cross sectional shape and Tc of 16,000 A/cm 2 was fabricated by applying CIP packing procedure. Multifilamentary wire with the Jc of approx. 10000 A/cm 2 was fabricated by rolling method using square billet as starting shape. The joining of the multifilament wire was done by etching and pressing process and showed 50% of joining efficiency. Analysis on the heat loss in cryostat for high Tc superconducting device was carried out for optimum design of the future cryogenic system. 126 figs, 14 tabs, 214 refs. (Author)

  1. Advanced nuclear materials development -Development of superconductor application technology-

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Kye Won; Lee, Heui Kyoon; Lee, Hoh Jin; Kim, Chan Joong; Jang, Kun Ik; Kim, Kee Baek; Kwon, Sun Chil; Park, Hae Woong; Yoo, Jae Keun; Kim, Jong Jin; Jang, Joong Chul; Yang, Suk Woo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Fabrication of high Tc bulk superconductor and its application, fabrication of superconducting wire for electric power device and analysis for cryogenic system were carried out for developing superconductor application technologies for electric power system. High quality YBaCuO bulk superconductor was fabricated by controlling initial powder preparation process and prototype fly wheel energy storage device was designed basically. The superconducting levitation force measuring device was made to examine the property of prepared superconductor specimen. Systematic studies on the method of starting powder preparation, mechanical fabrication process, heat treatment condition and analysis of plastic deformation were carried out to increase the stability and reproducibility of superconducting wire. A starting powder with good reactivity and fine particle size was obtained by emulsion drying method. Ag/BSCCO tape with good cross sectional shape and Tc of 16,000 A/cm{sup 2} was fabricated by applying CIP packing procedure. Multifilamentary wire with the Jc of approx. 10000 A/cm{sup 2} was fabricated by rolling method using square billet as starting shape. The joining of the multifilament wire was done by etching and pressing process and showed 50% of joining efficiency. Analysis on the heat loss in cryostat for high Tc superconducting device was carried out for optimum design of the future cryogenic system. 126 figs, 14 tabs, 214 refs. (Author).

  2. A Study on intensifying efficiency for international collaborative development of Advanced Nuclear Energy Technology

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Dohee; Park, Seongwon; Chang, Moonhee

    2013-08-15

    All the countries of the world are promoting the use of atomic energy to provide against high oil prices, climatic changes, and energy security initiative. A domestic and foreign environment for nuclear energy is changing rapidly and 13 leading countries including Korea are trying to develop advanced technologies on Gen IV nuclear energy system through Gen IV International Forum (GIF). To enhance the effectiveness of the future nuclear energy system development plan, a strategic approach is necessary for GIF program and the connection process with the 4th Nuclear Energy Promotion Program and Nuclear Energy R and D Medium and Long Term 5 year Plan for 2012 ∼ 2016 needs to be prepared. This study was to analyze the global nuclear trends of 2012 and the status of GIF program which is international cooperation activities. Also we examined the domestic R and D status of future nuclear energy systems for developing core technology and commercialization of Gen-IV nuclear energy system. A successful performance of this project enables the effective national cooperation with GIF and promotes the public acceptance by suggesting the technical alternatives for the nuclear safety and the spent fuel management.

  3. Efficiency and cost advantages of an advanced-technology nuclear electrolytic hydrogen-energy production facility

    Science.gov (United States)

    Donakowski, T. D.; Escher, W. J. D.; Gregory, D. P.

    1977-01-01

    The concept of an advanced-technology (viz., 1985 technology) nuclear-electrolytic water electrolysis facility was assessed for hydrogen production cost and efficiency expectations. The facility integrates (1) a high-temperature gas-cooled nuclear reactor (HTGR) operating a binary work cycle, (2) direct-current (d-c) electricity generation via acyclic generators, and (3) high-current-density, high-pressure electrolyzers using a solid polymer electrolyte (SPE). All subsystems are close-coupled and optimally interfaced for hydrogen production alone (i.e., without separate production of electrical power). Pipeline-pressure hydrogen and oxygen are produced at 6900 kPa (1000 psi). We found that this advanced facility would produce hydrogen at costs that were approximately half those associated with contemporary-technology nuclear electrolysis: $5.36 versus $10.86/million Btu, respectively. The nuclear-heat-to-hydrogen-energy conversion efficiency for the advanced system was estimated as 43%, versus 25% for the contemporary system.

  4. A Study on intensifying efficiency for international collaborative development of Advanced Nuclear Energy Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Moon Hee; Kim, H. R.; Kim, H. J.; Chang, J. H.; Hahn, D. H.; Bae, Y. Y.; Kim, W. W.; Jeong, I.; Lee, D. S.; Lee, J. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-06-15

    Generation IV International Forum(GIF), where 13 countries including Korea collaborate to develop future nuclear energy systems, put into force 'Generation IV International Forum Project Arrangement' in 2007 for the international research and development of Gen IV Systems, following the entry into force of Framework Agreement in 2005. The International Nuclear Research Initiative(I-NERI) between Korea and United States and the International Project on Innovative Nuclear Energy Systems and Fuel Cycles(INPRO) of IAEA are continued in this year, produced lots of visible outcomes. These international activities have a common goal of the collaborative development of advanced nuclear system technologies but differ in the main focusing areas and aspects, so Korea needs to establish the integrated strategy based on the distinguished and complementary approach for the participation of each international programs, as examples the GIF for the advanced system technology development, INPRO for the set-up of institution and infra-structure, and I-NERI for the access of the core technologies and acquisition of the transparency of nuclear R and D.

  5. A Study on intensifying efficiency for international collaborative development of Advanced Nuclear Energy Technology

    International Nuclear Information System (INIS)

    Chang, Moon Hee; Kim, H. R.; Kim, H. J.; Chang, J. H.; Hahn, D. H.; Bae, Y. Y.; Kim, W. W.; Jeong, I.; Lee, D. S.; Lee, J. H.

    2008-06-01

    Generation IV International Forum(GIF), where 13 countries including Korea collaborate to develop future nuclear energy systems, put into force 'Generation IV International Forum Project Arrangement' in 2007 for the international research and development of Gen IV Systems, following the entry into force of Framework Agreement in 2005. The International Nuclear Research Initiative(I-NERI) between Korea and United States and the International Project on Innovative Nuclear Energy Systems and Fuel Cycles(INPRO) of IAEA are continued in this year, produced lots of visible outcomes. These international activities have a common goal of the collaborative development of advanced nuclear system technologies but differ in the main focusing areas and aspects, so Korea needs to establish the integrated strategy based on the distinguished and complementary approach for the participation of each international programs, as examples the GIF for the advanced system technology development, INPRO for the set-up of institution and infra-structure, and I-NERI for the access of the core technologies and acquisition of the transparency of nuclear R and D

  6. Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

    Energy Technology Data Exchange (ETDEWEB)

    Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Yoshiuji, Takahiro

    1998-12-01

    The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

  7. Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

    International Nuclear Information System (INIS)

    Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki; Yoshiuji, Takahiro

    1998-01-01

    The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

  8. The development of advanced robotic technology -The development of advanced robotics for the nuclear industry-

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Bum; Kim, Woong Ki; Park, Soon Yong; Kim, Seung Ho; Kim, Chang Hoi; Hwang, Suk Yeoung; Kim, Byung Soo; Lee, Young Kwang

    1994-07-01

    In this year (the second year of this project), researches and development have been carried out to establish the essential key technologies applied to robot system for nuclear industry. In the area of robot vision, in order to construct stereo vision system necessary to tele-operation, stereo image acquisition camera module and stereo image displayer have been developed. Stereo matching and storing programs have been developed to analyse stereo images. According to the result of tele-operation experiment, operation efficiency has been enhanced about 20% by using the stereo vision system. In a part of object recognition, a tele-operated robot system has been constructed to evaluate the performance of the stereo vision system and to develop the vision algorithm to automate nozzle dam operation. A nuclear fuel rod character recognition system has been developed by using neural network. As a result of perfomance evaluation of the recognition system, 99% recognition rate has been achieved. In the area of sensing and intelligent control, temperature distribution has been measured by using the analysis of thermal image histogram and the inspection algorithm has been developed to determine of the state be normal or abnormal, and the fuzzy controller has been developed to control the compact mobile robot designed for path moving on block-typed path. (Author)

  9. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology-

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Yong; Cho, Jae Wan; Lee, Nam Hoh; Kim, Woong Kee; Moon, Byung Soo; Kim, Seung Hoh; Kim, Chang Heui; Kim, Byung Soo; Hwang, Suk Yong; Lee, Yung Kwang; Moon, Je Sun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Main activity in this year is to develop both remote handling system and telepresence techniques, which can be used for people involved in extremely hazardous working area to alleviate their burden. In the robot vision technology part, KAERI-PSM system, stereo imaging camera module, stereo BOOM/MOLLY unit, and stereo HMD unit are developed. Also, autostereo TV system which falls under the category of next generation stereo imaging technology has been studied. The performance of KAERI-PSM system for remote handling task is evaluated and compared with other stereo imaging systems as well as general TV imaging system. The result shows that KAERI-PSM system is superior to the other stereo imaging systems about remote operation speedup and accuracy. The automatic recognition algorithm of instrument panel is studied and passive visual target tracking system is developed. The 5 DOF camera serving unit has been designed and fabricated. It is designed to function like human`s eye. In the sensing and intelligent control research part, thermal image database system for thermal image analysis is developed and remote temperature monitoring technique using fiber optics is investigated. And also, two dimensional radioactivity sensor head for radiation profile monitoring system is designed. In the part of intelligent robotics, mobile robot is fabricated and its autonomous navigation using fuzzy control logic is studied. These remote handling and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, reactor inspection unit, underwater nuclear pellet inspection and pipe abnormality inspection. And these developed remote handling and telepresence techniques will be applied in general industry, medical science, and military as well as nuclear facilities. 203 figs, 12 tabs, 72 refs. (Author).

  10. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology-

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Yong; Cho, Jae Wan; Lee, Nam Hoh; Kim, Woong Kee; Moon, Byung Soo; Kim, Seung Hoh; Kim, Chang Heui; Kim, Byung Soo; Hwang, Suk Yong; Lee, Yung Kwang; Moon, Je Sun

    1995-07-01

    Main activity in this year is to develop both remote handling system and telepresence techniques, which can be used for people involved in extremely hazardous working area to alleviate their burden. In the robot vision technology part, KAERI-PSM system, stereo imaging camera module, stereo BOOM/MOLLY unit, and stereo HMD unit are developed. Also, autostereo TV system which falls under the category of next generation stereo imaging technology has been studied. The performance of KAERI-PSM system for remote handling task is evaluated and compared with other stereo imaging systems as well as general TV imaging system. The result shows that KAERI-PSM system is superior to the other stereo imaging systems about remote operation speedup and accuracy. The automatic recognition algorithm of instrument panel is studied and passive visual target tracking system is developed. The 5 DOF camera serving unit has been designed and fabricated. It is designed to function like human's eye. In the sensing and intelligent control research part, thermal image database system for thermal image analysis is developed and remote temperature monitoring technique using fiber optics is investigated. And also, two dimensional radioactivity sensor head for radiation profile monitoring system is designed. In the part of intelligent robotics, mobile robot is fabricated and its autonomous navigation using fuzzy control logic is studied. These remote handling and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, reactor inspection unit, underwater nuclear pellet inspection and pipe abnormality inspection. And these developed remote handling and telepresence techniques will be applied in general industry, medical science, and military as well as nuclear facilities. It has been looking for these techniques to expand the working area of human, raise the working efficiencies of remote task to the highest degree, and enhance the industrial

  11. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Woong; Cho, Jae Wan; Lee, Nam Ho; Kim, Woong Ki; Moon, Byung Soo; Lee, Young Jae; Kim, Chang Hoi; Kim, Seung Ho; Hwang, Seok Yong; Kim, Byung Soo; Moon, Jae Sun; Lee, Young Kwang; Choi, Kap Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-07-01

    The comparison study of 3 kinds of stereo camera modules done in this final year of 4 year`s longterm project shows that regenerating characteristics of stereo image of stereo camera using horizontally moving lens axis method is superior to the other two modules. Base on this comparison result, stereo camera module using horizontally moving lens method is developed. Also, stereo-Boom unit, high definition polarized stereo monitor(KAERI-PSM II) and 10.4sec. auto-stereogram TV using parallax barrier method are developed. These developed systems can be used for people involved in extremely hazardous working area to give vivid reality image of work environment. In the recognition and tracking section, auto-vergencing technology using focus fixation and cepstral filter, stereo camera calibration, range measurement technology using stereo camera module are developed. And active target tracking technology is developed also. In the sensing and intelligent control research part, active radioactivity image monitoring unit is developed. The spatial resolution of monitoring unit is 10cm at 1m distance, FOV is 60x40 deg [HXV], and radioactivity detection limit is 1mR/hr. Also, radiation-resistant inspection camera for nuclear facilities is designed. In the intelligent control section, fuzzy control algorithm for obstacle detouring navigation of mobile robot is developed. The smoothing techniques by fuzzy set is adapted to raise the pliability of obstacle detouring navigation of mobile robot. In order to raise robustness of developed fuzzy algorithm, fuzzy control algorithm is applied to `Truck Backer Upper` problem and tuned. (Abstract Truncated)

  12. Indian advanced nuclear reactors

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2005-01-01

    For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

  13. Assessment of fiber optic sensors and other advanced sensing technologies for nuclear power plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    1996-01-01

    As a result of problems such as calibration drift in nuclear plant pressure sensors and the recent oil loss syndrome in some models of Rosemount pressure transmitters, the nuclear industry has become interested in fiber optic pressure sensors. Fiber optic sensing technologies have been considered for the development of advanced instrumentation and control (I ampersand C) systems for the next generation of reactors and in older plants which are retrofitted with new I ampersand C systems. This paper presents the results of a six-month Phase I study to establish the state-of-the-art in fiber optic pressure sensing. This study involved a literature review, contact with experts in the field, an industrial survey, a site visit to a fiber optic sensor manufacturer, and laboratory testing of a fiber optic pressure sensor. The laboratory work involved both static and dynamic performance tests. This initial Phase I study has recently been granted a two-year extension by the U.S. Nuclear Regulatory Commission (NRC). The next phase will evaluate fiber optic pressure sensors in specific nuclear plant applications in addition to other advanced methods for monitoring critical nuclear plant equipment

  14. Book of extended synopses. International symposium on advanced nuclear power systems. Design, technology, safety and strategies for their deployment

    International Nuclear Information System (INIS)

    1993-01-01

    During the symposium the design, technology, safety and strategy for the development of advanced nuclear power systems were discussed. 20 papers were presented at the symposium. A separate abstract was prepared for each of these papers. Refs

  15. INIS as an information and knowledge resource for advanced nuclear technology studies

    International Nuclear Information System (INIS)

    Rashkova, N.

    2009-01-01

    INIS is, at present, the leading reference database for scientific literature on the peaceful uses of nuclear science and technology. It operates at the IAEA - INIS and NKM Section and coordinates nuclear information management activities: maintains INIS database and the access to the database, prepares the IAEA input; controls the input from the Member States and assists them in establishing information centers and exchanging nuclear information. The INIS DB covers all types of literature, published worldwide: journal articles, conference proceedings, legal documents, scientific and technical documents etc. The non-conventional collection (NCL) contains more than 200 000 full text documents. INIS provides free access to the bibliographic database for registered users and other information resources, such as database on CD-ROM, topical CDs, full text database, links to other databases, web pages, authority list etc. INIS database offers structured and easy searchable information. The information is grouped in subject categories, under the INIS-ETDE subject classification scheme, which is periodically updated to reflect the new developments in the specific area. The main INIS areas are: nuclear physics, reactor physics and engineering, material science, nuclear fuels, plasma physics and fusion technology, particle accelerators radiation protection, nuclear medicine. The database grows rapidly - currently contains over 3 million records. The material science, reactor design and engineering, new reactor technologies and plasma applications are among the most rapidly growing subject categories. INIS database offers different search options, depending on the needs of the user: simple search; advanced search in abstract, author, place and date of publication, source, document type, subject, descriptors etc.; search by descriptors and predefined queries; combining queries by logical operators. The export from the database is available in html, text, formatted text; XML

  16. Advanced scientific computational methods and their applications to nuclear technologies. (3) Introduction of continuum simulation methods and their applications (3)

    International Nuclear Information System (INIS)

    Satake, Shin-ichi; Kunugi, Tomoaki

    2006-01-01

    Scientific computational methods have advanced remarkably with the progress of nuclear development. They have played the role of weft connecting each realm of nuclear engineering and then an introductory course of advanced scientific computational methods and their applications to nuclear technologies were prepared in serial form. This is the third issue showing the introduction of continuum simulation methods and their applications. Spectral methods and multi-interface calculation methods in fluid dynamics are reviewed. (T. Tanaka)

  17. Development of demonstration facility design technology for advanced nuclear fuel cycle process

    International Nuclear Information System (INIS)

    Cho, Il Je; You, G. S.; Choung, W. M.; Lee, E. P.; Hong, D. H.; Lee, W. K.; Ku, J. H.; Moon, S. I.; Kwon, K. C.; Lee, K. I. and other

    2012-04-01

    PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. It is essential to develop design technologies for the advanced nuclear fuel cycle demonstration facilities and complete the detailed design of PRIDE facility with capabilities of the stringent inert atmosphere control, fully remote operation which are necessary to develop the high-temperature molten salts technology. For these, it is necessary to design the essential equipment of large scale inert cell structure and the control system to maintain the inert atmosphere, and evaluate the safety. To construct the hot cell system which is appropriate for pyroprocess, some design technologies should be developed, which include safety evaluation for effective operation and maintenance, radiation safety analysis for hot cell, structural analysis, environmental evaluation, HVAC systems and electric equipment

  18. Advanced Reactor Technology Options for Utilization and Transmutation of Actinides in Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    2009-09-01

    Renewed interest in the potential of nuclear energy to contribute to a sustainable worldwide energy mix is strengthening the IAEA's statutory role in fostering the peaceful uses of nuclear energy, in particular the need for effective exchanges of information and collaborative research and technology development among Member States on advanced nuclear power technologies (Articles III-A.1 and III-A.3). The major challenges facing the long term development of nuclear energy as a part of the world's energy mix are improvement of the economic competitiveness, meeting increasingly stringent safety requirements, adhering to the criteria of sustainable development, and public acceptability. The concern linked to the long life of many of the radioisotopes generated from fission has led to increased R and D efforts to develop a technology aimed at reducing the amount of long lived radioactive waste through transmutation in fission reactors or accelerator driven hybrids. In recent years, in various countries and at an international level, more and more studies have been carried out on advanced and innovative waste management strategies (i.e. actinide separation and elimination). Within the framework of the Project on Technology Advances in Fast Reactors and Accelerator Driven Systems (http://www.iaea.org/inisnkm/nkm/aws/fnss/index.html), the IAEA initiated a number of activities on utilization of plutonium and transmutation of long lived radioactive waste, accelerator driven systems, thorium fuel options, innovative nuclear reactors and fuel cycles, non-conventional nuclear energy systems, and fusion/fission hybrids. These activities are implemented under the guidance and with the support of the IAEA Nuclear Energy Department's Technical Working Group on Fast Reactors (TWG-FR). This publication compiles the analyses and findings of the Coordinated Research Project (CRP) on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste (2002

  19. Human factors survey of advanced instrumentation and controls technologies in nuclear plants

    International Nuclear Information System (INIS)

    Carter, R.J.

    1992-01-01

    A survey of advanced instrumentation and controls (I ampersand C) technologies and associated human factors issues in the US and Canadian nuclear industries was carried out by a team from Oak Ridge national laboratory to provide background for the development of regulatory policy, criteria, and guides for review of advanced I ampersand C systems as well as human engineering guidelines for evaluating these systems. The survey found those components of the US nuclear industry surveyed to be quite interested in advanced I ampersand C, but very cautious in implementing such systems in nuclear facilities and power plants. The trend in the facilities surveyed is to experiment cautiously when there is an intuitive advantage or short-term payoff. In the control room, the usual practice is direct substitution of digital and microprocessor-based instruments or systems that are functionally identical to the analog instruments or systems being replaced. The most advanced I ampersand C systems were found in the Canadian CANDU plants, where the newest plant has digital system in almost 100% of its control systems and in over 70% of its plant protection system. The hypothesis that properly 'introducing digital systems increases safety' is supported by the Canadian experience. The performance of these digital systems was achieved using an appropriate quality assurance program for the software development. The ability of digital systems to detect impending failures and initiate a fail-safe action, is a significant safety issue that should be of special interest to every US utility as well as to the US Nuclear Regulatory Commission. (orig.)

  20. Advances in processing technologies for titanium heat exchanger tubes of fossil and nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Likhareva, T.P.; Tchizhik, A.A.; Chavchanidze, N.N. [Polzanov Central Boiler and Turbine Institute, St. Petersburg (Russian Federation)

    1998-12-31

    The advances in processing technologies for titanium heat exchangers with rolled and welded tubes of fossil and nuclear power plants in Russia are presented. The special methodology of investigations with constant small strain rate have been used to study the effects of mixed corrosion and creep processes in condensers cooled by sea or synthetic sea waters. The results of corrosion creep tests and K1scc calculations are given. The Russian science activities concerning condensers manufactured from titanium show the possibilities for designing structures with very high level service reliability in different corrosion aggressive mediums with high total salt, Cl-ion and oxygen contents. (orig.)

  1. Advances in processing technologies for titanium heat exchanger tubes of fossil and nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Likhareva, T P; Tchizhik, A A; Chavchanidze, N N [Polzanov Central Boiler and Turbine Institute, St. Petersburg (Russian Federation)

    1999-12-31

    The advances in processing technologies for titanium heat exchangers with rolled and welded tubes of fossil and nuclear power plants in Russia are presented. The special methodology of investigations with constant small strain rate have been used to study the effects of mixed corrosion and creep processes in condensers cooled by sea or synthetic sea waters. The results of corrosion creep tests and K1scc calculations are given. The Russian science activities concerning condensers manufactured from titanium show the possibilities for designing structures with very high level service reliability in different corrosion aggressive mediums with high total salt, Cl-ion and oxygen contents. (orig.)

  2. Advanced computational tools and methods for nuclear analyses of fusion technology systems

    International Nuclear Information System (INIS)

    Fischer, U.; Chen, Y.; Pereslavtsev, P.; Simakov, S.P.; Tsige-Tamirat, H.; Loughlin, M.; Perel, R.L.; Petrizzi, L.; Tautges, T.J.; Wilson, P.P.H.

    2005-01-01

    An overview is presented of advanced computational tools and methods developed recently for nuclear analyses of Fusion Technology systems such as the experimental device ITER ('International Thermonuclear Experimental Reactor') and the intense neutron source IFMIF ('International Fusion Material Irradiation Facility'). These include Monte Carlo based computational schemes for the calculation of three-dimensional shut-down dose rate distributions, methods, codes and interfaces for the use of CAD geometry models in Monte Carlo transport calculations, algorithms for Monte Carlo based sensitivity/uncertainty calculations, as well as computational techniques and data for IFMIF neutronics and activation calculations. (author)

  3. Application of Advanced Technology to Improve Plant Performance in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2011-01-01

    Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

  4. Public perception of the activities of the Nuclear Energy and Advanced Technologies Agency of Cuba

    Energy Technology Data Exchange (ETDEWEB)

    Contreras, Marta; Arencibia, Alois; Alvarado, Jorge; Garcia, Dulce; Rodriguez, Ingrids; Hernandez, Noslen [Centro de Gestion de la Informacion y Desarrollo de la Energia (CUBAENERGIA), La Habana (Cuba); Aguilar, Aurora; Perera, Maricela [Centro de Investigaciones Psicologicas y Sociologicas (CIPS), La Habana, (Cuba); Rodriguez, Ramon [Agencia de Energia Nuclear y Tecnologias de Avanzada (AENTA), La Habana, (Cuba); Alonso, Ivonne [Centro Nacional de Seguridad Nuclear (CNSN), La Habana, (Cuba); Quintana, Natacha [Centro de Aplicaciones Tecnologicas y Desarrollo Nuclear (CEADEN), La Habana, (Cuba); Cardenas, Juan; Ramos, Odalys [Centro de Proteccion e Higiene de las Radiaciones (CPHR), La Habana, (Cuba); Elias, Lidia Lauren [Instituto Superior de Tecnologias y Ciencias Aplicadas (InSTEC), La Habana, (Cuba)

    2013-07-01

    The work presents the results of a study of perception of the nuclear activities of the Nuclear Energy and Advanced Technologies Agency of Cuba, carried out by means of a study of image. The public object was a wide group of clients, providers, journalists and experts of the governing and regulatory organs which constitute its external public. For the investigation a methodology was prepared with a questionnaire and a semi structured interview, which allowed to obtain complementary information of qualitative character. In general, the perception of the Agency turned out to be positive and the human resources were the best evaluated aspect. Nevertheless, the visibility of the Agency in the public day pupils is considered to be insufficient. The study provided the necessary information so as to design the strategy of communication of the Agency. (author)

  5. Public perception of the activities of the Nuclear Energy and Advanced Technologies Agency of Cuba

    International Nuclear Information System (INIS)

    Contreras, Marta; Arencibia, Alois; Alvarado, Jorge; Garcia, Dulce; Rodriguez, Ingrids; Hernandez, Noslen; Aguilar, Aurora; Perera, Maricela; Rodriguez, Ramon; Alonso, Ivonne; Quintana, Natacha; Cardenas, Juan; Ramos, Odalys; Elias, Lidia Lauren

    2013-01-01

    The work presents the results of a study of perception of the nuclear activities of the Nuclear Energy and Advanced Technologies Agency of Cuba, carried out by means of a study of image. The public object was a wide group of clients, providers, journalists and experts of the governing and regulatory organs which constitute its external public. For the investigation a methodology was prepared with a questionnaire and a semi structured interview, which allowed to obtain complementary information of qualitative character. In general, the perception of the Agency turned out to be positive and the human resources were the best evaluated aspect. Nevertheless, the visibility of the Agency in the public day pupils is considered to be insufficient. The study provided the necessary information so as to design the strategy of communication of the Agency. (author)

  6. The Nuclear Energy Advanced Modeling and Simulation Enabling Computational Technologies FY09 Report

    Energy Technology Data Exchange (ETDEWEB)

    Diachin, L F; Garaizar, F X; Henson, V E; Pope, G

    2009-10-12

    In this document we report on the status of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Enabling Computational Technologies (ECT) effort. In particular, we provide the context for ECT In the broader NEAMS program and describe the three pillars of the ECT effort, namely, (1) tools and libraries, (2) software quality assurance, and (3) computational facility (computers, storage, etc) needs. We report on our FY09 deliverables to determine the needs of the integrated performance and safety codes (IPSCs) in these three areas and lay out the general plan for software quality assurance to meet the requirements of DOE and the DOE Advanced Fuel Cycle Initiative (AFCI). We conclude with a brief description of our interactions with the Idaho National Laboratory computer center to determine what is needed to expand their role as a NEAMS user facility.

  7. Technology Roadmap on Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs

    International Nuclear Information System (INIS)

    Donald D Dudenhoeffer; Burce P Hallbert

    2007-01-01

    Instrumentation, Controls, and Human-Machine Interface (ICHMI) technologies are essential to ensuring delivery and effective operation of optimized advanced Generation IV (Gen IV) nuclear energy systems. In 1996, the Watts Bar I nuclear power plant in Tennessee was the last U.S. nuclear power plant to go on line. It was, in fact, built based on pre-1990 technology. Since this last U.S. nuclear power plant was designed, there have been major advances in the field of ICHMI systems. Computer technology employed in other industries has advanced dramatically, and computing systems are now replaced every few years as they become functionally obsolete. Functional obsolescence occurs when newer, more functional technology replaces or supersedes an existing technology, even though an existing technology may well be in working order. Although ICHMI architectures are comprised of much of the same technology, they have not been updated nearly as often in the nuclear power industry. For example, some newer Personal Digital Assistants (PDAs) or handheld computers may, in fact, have more functionality than the 1996 computer control system at the Watts Bar I plant. This illustrates the need to transition and upgrade current nuclear power plant ICHMI technologies

  8. A study on intensifying efficiency for international collaborative development of advanced nuclear energy technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. H.; Hahn, D. H.; Song, K. C.; Chang, J. H.; Kim, H. J.; Kim, H. J.; Lim, C. Y.; Lee, D. S.; Lee, Y. J. [KAERI, Daejeon (Korea, Republic of)

    2011-03-15

    The objective of the study was to participate the GIF for the efficient propulsion of future nuclear system development. For achieving the objective of this study, the followings were carried out. {Omicron} Analyze the international/domestic trends in the future nuclear energy system {Omicron} Analyze the domestic long-term R and D program for the future nuclear system and assist its implementation - Review the agenda of the executive committee, the technical committee, and sub-technical committee - Assist the committee meetings and workshops related to the future nuclear energy system {Omicron} Develop the participation strategy for the collaborative development of Gen-IV technology and conducting the international cooperation activities - Support the delegation by reviewing the agenda of GIF meetings in the technical and legal perspective - Research the system R and D arrangement and report its progress - Participate in the SFR SIA PA negotiation meeting and report its progress {Omicron} Support the activities related to I-NERI between Korea and U.S. - Support a delegation by reviewing the agenda in the technical/legal point of view - Participate in the BINERIC meetings and Support the related activities The result of this study may be used for 1) contribution to establishing the effective foundation and broadening the cooperation activities between the advanced countries and Korea and 2) contribution effective management of Gen IV international collaboration by technical/legal supporting

  9. A study on intensifying efficiency for international collaborative development of advanced nuclear energy technology

    International Nuclear Information System (INIS)

    Lee, J. H.; Hahn, D. H.; Song, K. C.; Chang, J. H.; Kim, H. J.; Kim, H. J.; Lim, C. Y.; Lee, D. S.; Lee, Y. J.

    2011-03-01

    The objective of the study was to participate the GIF for the efficient propulsion of future nuclear system development. For achieving the objective of this study, the followings were carried out. Ο Analyze the international/domestic trends in the future nuclear energy system Ο Analyze the domestic long-term R and D program for the future nuclear system and assist its implementation - Review the agenda of the executive committee, the technical committee, and sub-technical committee - Assist the committee meetings and workshops related to the future nuclear energy system Ο Develop the participation strategy for the collaborative development of Gen-IV technology and conducting the international cooperation activities - Support the delegation by reviewing the agenda of GIF meetings in the technical and legal perspective - Research the system R and D arrangement and report its progress - Participate in the SFR SIA PA negotiation meeting and report its progress Ο Support the activities related to I-NERI between Korea and U.S. - Support a delegation by reviewing the agenda in the technical/legal point of view - Participate in the BINERIC meetings and Support the related activities The result of this study may be used for 1) contribution to establishing the effective foundation and broadening the cooperation activities between the advanced countries and Korea and 2) contribution effective management of Gen IV international collaboration by technical/legal supporting

  10. Providing Policy Implication Based on the R and D Portfolio Analysis in Advanced Countries in the Nuclear Technology

    International Nuclear Information System (INIS)

    Moon, K. H.; Lee, M. K.; Won, B. C.; Kim, S. S.; Lee, J. H.; Yun, S. W.; Jeong, I. K.; Lee, Y. C.; Lee, Y. J.; Kim, Y. S.

    2013-08-01

    This study is to provide the investment direction of nuclear R and D, which is the most efficient and reasonable integrating the various aspects comprehensively. This study includes four parts. In the first part, we extracted Mega-trend and driving forces of nuclear R and D field by using various reports published by National Intelligence Council of US, UN, etc. Also, in this part we established the linkage between megatrend factors focussing on nuclear and the five aspects including society, technology, ecology, economics and politics. In the second part, we analyzed the nuclear R and D investment directions of major advanced countries including US, Japan, EU and China for comparing the investment portfolio in the specific research area. In the third part, domestic investment of nuclear R and D was reviewed by analyzing the investment trend of nuclear R and D in the past, with their connection to nuclear policy, and to the levels and capacities of national technologies of nuclear. In the final part, the desirable directions of nuclear R and D investment were suggested comprehensively taking into consideration various aspects including the Mega-trend associated with nuclear, nuclear R and D directions of major advanced countries, and the level and capacities of the domestic nuclear technologies

  11. Providing Policy Implication Based on the R and D Portfolio Analysis in Advanced Countries in the Nuclear Technology

    Energy Technology Data Exchange (ETDEWEB)

    Moon, K. H.; Lee, M. K.; Won, B. C.; Kim, S. S.; Lee, J. H.; Yun, S. W.; Jeong, I. K.; Lee, Y. C.; Lee, Y. J.; Kim, Y. S.

    2013-08-15

    This study is to provide the investment direction of nuclear R and D, which is the most efficient and reasonable integrating the various aspects comprehensively. This study includes four parts. In the first part, we extracted Mega-trend and driving forces of nuclear R and D field by using various reports published by National Intelligence Council of US, UN, etc. Also, in this part we established the linkage between megatrend factors focussing on nuclear and the five aspects including society, technology, ecology, economics and politics. In the second part, we analyzed the nuclear R and D investment directions of major advanced countries including US, Japan, EU and China for comparing the investment portfolio in the specific research area. In the third part, domestic investment of nuclear R and D was reviewed by analyzing the investment trend of nuclear R and D in the past, with their connection to nuclear policy, and to the levels and capacities of national technologies of nuclear. In the final part, the desirable directions of nuclear R and D investment were suggested comprehensively taking into consideration various aspects including the Mega-trend associated with nuclear, nuclear R and D directions of major advanced countries, and the level and capacities of the domestic nuclear technologies.

  12. Comprehensive support for nuclear decommissioning based on 3D simulation and advanced user interface technologies

    International Nuclear Information System (INIS)

    Szőke, István; Louka, Michael N.; Bryntesen, Tom-Robert; Edvardsen, Svein-Tore; Bratteli, Joachim

    2015-01-01

    There is an increasing international focus on the need to optimise decommissioning strategies, driven by the anticipation of high costs and major effort for the decommissioning of nuclear facilities in the coming decades. The goals are to control and mitigate costs and negative impacts on workers, the general public, and the environment. The methods presently employed for many decommissioning tasks do not apply the latest advancements of science and technology. Therefore, there is growing interest in research and development into the adoption of novel techniques for improving safety, reducing costs, and increasing transparency. This paper provides a comprehensive overview of the authors' results from investigating how current and emerging technologies can be applied to enhance the international decommissioning strategy, focussing in particular on three-dimensional simulation, virtual reality, advanced user interfaces, mobile and wearable devices, and geographical information systems. Our results demonstrate that emerging technologies have great potential for supporting adoption of new instrumentation, improving data and knowledge management, optimising project plans, briefing and training field operators, and for communication, surveillance, and education in general. (author)

  13. Recent advances in medical device triage technologies for chemical, biological, radiological, and nuclear events.

    Science.gov (United States)

    Lansdowne, Krystal; Scully, Christopher G; Galeotti, Loriano; Schwartz, Suzanne; Marcozzi, David; Strauss, David G

    2015-06-01

    In 2010, the US Food and Drug Administration (Silver Spring, Maryland USA) created the Medical Countermeasures Initiative with the mission of development and promoting medical countermeasures that would be needed to protect the nation from identified, high-priority chemical, biological, radiological, or nuclear (CBRN) threats and emerging infectious diseases. The aim of this review was to promote regulatory science research of medical devices and to analyze how the devices can be employed in different CBRN scenarios. Triage in CBRN scenarios presents unique challenges for first responders because the effects of CBRN agents and the clinical presentations of casualties at each triage stage can vary. The uniqueness of a CBRN event can render standard patient monitoring medical device and conventional triage algorithms ineffective. Despite the challenges, there have been recent advances in CBRN triage technology that include: novel technologies; mobile medical applications ("medical apps") for CBRN disasters; electronic triage tags, such as eTriage; diagnostic field devices, such as the Joint Biological Agent Identification System; and decision support systems, such as the Chemical Hazards Emergency Medical Management Intelligent Syndromes Tool (CHEMM-IST). Further research and medical device validation can help to advance prehospital triage technology for CBRN events.

  14. Advanced technologies of cardiovascular nuclear medicine and their evaluation in clinical practice

    International Nuclear Information System (INIS)

    Murata, Hajime; Iio, Masahiro; Toyama, Hinako.

    1981-01-01

    Currently available advanced methods of cardiovascular nuclear medicine for the diagnosis of ischemic heart disease were studied. The methods included the multigate method by a large capacity gamma camera-computer (128 KW memory with multilayer disc) system which made it possible to acquire the data of either the first pass study or the equilibrium study in ''image mode''. Analyzed data were displayed on a color CRT using our moving image system (MIS) and dynamic image thus obtained serve to help for the high sensitive observation of the regional wall motion as well as the global function of the ventricles. Myocardial tomography by a 7 pinhole collimator designed by us was also reported. The myocardial tomogram obtained was proven to show more sensitivity than two dimensional myocardial scan by the conventional collimator to detect smaller lesion and the lesions at the inferior or posterior wall of the left ventricle. The cardiovascular nuclear medicine with recent advanced technologies was thought to be sensitive and useful method for the diagnosis of the ventricular performance and the myocardial ischemia. (author)

  15. United States advanced technologies

    International Nuclear Information System (INIS)

    Longenecker, J.R.

    1985-01-01

    In the United States, the advanced technologies have been applied to uranium enrichment as a means by which it can be assured that nuclear fuel cost will remain competitive in the future. The United States is strongly committed to the development of advanced enrichment technology, and has brought both advanced gas centrifuge (AGC) and atomic vapor laser isotope separation (AVLIS) programs to a point of significant technical refinement. The ability to deploy advanced technologies is the basis for the confidence in competitive future price. Unfortunately, the development of advanced technologies is capital intensive. The year 1985 is the key year for advanced technology development in the United States, since the decision on the primary enrichment technology for the future, AGC or AVLIS, will be made shortly. The background on the technology selection process, the highlights of AGC and AVLIS programs and the way to proceed after the process selection are described. The key objective is to maximize the sales volume and minimize the operating cost. This will help the utilities in other countries supply low cost energy on a reliable, long term basis. (Kako, I.)

  16. Radioactive waste management: the relation between geological disposal and advanced nuclear technologies

    International Nuclear Information System (INIS)

    Schroder, Jantine

    2013-01-01

    Throughout this paper we aim to scope the most pregnant themes, issues and research questions concerning the relation between geological disposal and advanced nuclear technologies in the broad context of radioactive waste management. Especially from a socio-technical point of view the mutual impacts, divergences and complementarities between both strategies seem to have received limited dedicated examination up until today. Specific attention is paid to the main arguments that seem to underpin both research streams, related to how the issue of radioactive waste is contextualized and which problems and solutions are consequently identified and proposed. Ultimately we aim to encourage scientifically integer communication and constructive dialogue between both fields, to investigate the common possibilities of enhancing radioactive waste management as a whole. (authors)

  17. Nuclear technology

    International Nuclear Information System (INIS)

    1983-03-01

    This report examines nuclear technology in Canada, with emphasis on Quebec, as a means of revitilizing industry. The historical, present day, and future states of Atomic Energy of Canada Limited are examined. Future research programs are discussed in greatest detail. These range from disposal of porcine wastes to new applications for electricity to nuclear medical techniques (to cite only a few examples). The executive summary is written in English. (23 fig., 16 tab.)

  18. Efficiency improvement of nuclear power plant operation: the significant role of advanced nuclear fuel technologies

    International Nuclear Information System (INIS)

    Van Velde, AA. de; Burtak, F.

    2000-01-01

    In this paper authors deals with nuclear fuel cycle and their economic aspects. At Siemens, the developments focusing on the reduction of fuel cycle costs are currently directed on .further batch average burnup increase, .improvement of fuel reliability, .enlargement of fuel operation margins, .improvement of methods for fuel design and core analysis. These items will be presented in detail in the full paper and illustrated by the global operating experience of Siemens fuel for both PWRs and BWRs. (authors)

  19. Advanced nuclear technologies. Hearing before a subcommittee of the Committee on Appropriations, United States Senate, One Hundred Fifth Congress, First Session, Special Hearing

    International Nuclear Information System (INIS)

    1999-01-01

    This hearing focuses on the subject of advanced nuclear technologies; in particular, two aspects are of interest: The renewal of nuclear power in this country and furthering technologies for the future use of nuclear power. Several witnesses testified. Some topics covered by the witnesses were: reactor technologies; proliferation; and radioactive waste management

  20. Development of preventive maintenance technology and advanced service equipment for operating nuclear power plants

    International Nuclear Information System (INIS)

    Abe, Kazuhiro; Sumikawa, Masaharu; Hirakawa, Hiromasa; Arakawa, Tadao; Hasegawa, Kunio; Kato, Kanji.

    1990-01-01

    Hitachi Ltd. as a manufacturer of nuclear power plants has carried out the consistent general preventive maintenance activities from the planning of the plants and the design of maintainability in the construction phase to the planning and working of preventive maintenance in the operation and maintenance phase, and exerted efforts to heighten the capacity ratio and reliability of the plants. For the purpose, the steady activities of reliability improvement have been carried out throughout the whole company, and the rationalization of the planning and management of the preventive maintenance with a computer and the development of the robots to which Al is applied have been promoted. As the technology of upgrading the facilities, boron racks, the control rods having long life and so on were developed, and their practical use is advanced. Moreover for the future, the development of the diagnostic technology on material deterioration using superconductive quantum interference devices (SQUID) is in progress. The preventive maintenance activities in Hitachi Ltd., the technical development for the purpose and the upgrading of the plant facilities are reported. (K.I.)

  1. CANDU nuclear reactor technology

    International Nuclear Information System (INIS)

    Kakaria, B. K.

    1994-01-01

    AECL has over 40 years of experience in the nuclear field. Over the past 20 years, this unique Canadian nuclear technology has made a worldwide presence, In addition to 22 CANDU reactors in Canada, there are also two in India, one in Pakistan, one in Argentina, four in Korea and five in Romania. CANDU advancements are based on evolutionary plant improvements. They consist of system performance improvements, design technology improvements and research and development in support of advanced nuclear power. Given the good performance of CANOU plants, it is important that this CANDU operating experience be incorporated into new and repeat designs

  2. Nuclear technology in Peru

    International Nuclear Information System (INIS)

    Montoya, M.

    1993-01-01

    This book deals with the Nuclear Energy in Peru. It consists of ten chapters. In the first chapter is presented a rapid overview on nuclear science history. The second chapter describes the nuclear proliferation and the nuclear competition in South America. The nuclear organization in Peru, the Peruvian Institute of Nuclear Energy, and the main centers are described in the third chapter. The following chapters deals with peruvian advances in nuclear medicine, agriculture and food, nuclear application to industry, hydrology, earth sciences and environmental considerations. In the last chapter, the perspectives for nuclear science and technology in Peru are described from the inter institutional cooperation point of view. This book also includes appendix and bibliography. (author)

  3. Incentives to strengthen international co-operation in R and D for advanced nuclear power technology

    International Nuclear Information System (INIS)

    Balthesen, E.; Bakunyaev, A.D.; Gibson, I.H.; Hosemann, J.P.; Tavoni, R.; Versteegh, A.M.

    1993-01-01

    This paper is concerned with the need for International Co-operation in R and D for Advanced Reactors in order to maintain options for the future deployment of nuclear power against the current background of declining R and D capability in Europe

  4. Some strategic considerations on the development of advance nuclear fuel cycle technologies in China

    International Nuclear Information System (INIS)

    Gu Zhongmao

    2006-01-01

    The characteristics of the different fuel cycle options are analyzed from the view point of sustainable development of nuclear fission energy. It is pointed out that the 'once-through' option of fuel cycle does not comply with the sustainability of the nuclear energy development. For the sake of full utilization of uranium resources and the minimization of nuclear waste, the closed fuel cycle of fast breeder reactor is the fundamental way out for the sustainable development of nuclear fission energy. Based on the wide investigations on the present status and R and D trends of the key technologies of fuel cycle both at home and abroad, the strategy for developing China's fuel cycle technologies is explored, some important measures to be taken for achieving the above strategic goal are suggested. (authors)

  5. Advanced nuclear power systems: Design, technology, safety and strategies for their deployment

    International Nuclear Information System (INIS)

    1994-01-01

    The objectives of the symposium were to provide high level decision makers with an overview of the discussion concerning the need for nuclear power and salient features of advanced nuclear power systems; a forum for discussing the design objectives and safety approaches for such systems and the views of regulatory bodies; a forum for identifying barriers to the deployment of these systems and for reviewing strategies to overcome these barriers; and a forum for reviewing options for international cooperation in the development and deployment of such systems. Refs, figs and tabs

  6. Development of Advanced Technologies to Reduce Design, Fabrication and Construction Costs for Future Nuclear Power Plants

    International Nuclear Information System (INIS)

    DiNunzio, Camillo A.; Gupta, Abhinav; Golay, Michael; Luk, Vincent; Turk, Rich; Morrow, Charles; Geum-Taek Jin

    2002-01-01

    OAK-B135 This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies

  7. Development of Advanced Technologies to Reduce Design, Fabrication and Construction Costs for Future Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    DiNunzio, Camillo A. [Framatome ANP DE& S, Marlborough, MA (United States); Gupta, Abhinav [Univ. of North Carolina, Raleigh, NC (United States); Golay, Michael [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Luk, Vincent [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Turk, Rich [Westinghouse Electric Company Nuclear Systems, Windsor, CT (United States); Morrow, Charles [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jin, Geum-Taek [Korea Power Engineering Company Inc., Yongin-si, Gyeonggi-do (Korea, Republic of)

    2002-11-30

    This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

  8. Strategic plan for the development of core technologies for the Korean advanced nuclear power reactor for export

    International Nuclear Information System (INIS)

    Moon, Joo Hyun; Cho, Young Ho

    2010-01-01

    With the soaring oil price and worsening global warming, nuclear power has attracted considerable attention on a global scale and a new large market of nuclear power plants (NPPs) is expected. The Korean government aims to export up to 10 NPPs by 2012, based on the successful export of 2 NPPs to the UAE in 2009. It is also going to develop a follow-up model of the Advanced Power Reactor (APR) 1400, and join the world's NPP market under the banner of Korea's original reactor type. For this, it promulgated the strategic plan, NuTech 2012, a technology development plan intended for the early acquisition of core technologies for the Korean advanced NPP design and domestic production of the main components in NPP. This paper introduces the strategic plan of NuTech 2012. (orig.)

  9. Nuclear technology international 1987

    International Nuclear Information System (INIS)

    Geary, Neville

    1987-01-01

    A total of 59 articles cover a wide range of subjects within the scope of nuclear power generation. The first 13 are concerned with the design and construction of nuclear reactors - PWRs, AGRs, Magnox reactors, fast reactors. The final article in this section is on reactor decommissioning. The next 33 papers all concern services to the nuclear power industry. These include the supply of uranium, uranium enrichment, fuel fabrication, reprocessing, spent fuel storage, robotics and remote handling and radioactive waste disposal. The 13 articles in the safety and public acceptability section concern fears over the Chernobyl accident, safety aspects of nuclear power including risk assessment, fire protection, quality assurance, earthquake tolerance, non-proliferation of nuclear weapons and finally, general problems of balancing advances in nuclear technology and economic desirability against a lack of public confidence in the industry. All reactor and fuel types are represented. Most of the articles concern nuclear power in Europe or North America. All are indexed separately. (UK)

  10. Development of Demonstration Facility Design Technology for Advanced Nuclear Fuel Cycle Process

    International Nuclear Information System (INIS)

    Cho, Il Je; You, G. S.; Choung, W. M.

    2010-04-01

    The main objective of this R and D is to develop the PRIDE (PyRoprocess Integrated inactive DEmonstration) facility for engineering-scale inactive test using fresh uranium, and to establish the design requirements of the ESPF (Engineering Scale Pyroprocess Facility) for active demonstration of the pyroprocess. Pyroprocess technology, which is applicable to GEN-IV systems as one of the fuel cycle options, is a solution of the spent fuel accumulation problems. PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. The PRIDE evaluation data, such as performance evaluation data of equipment and operation experiences, will be directly utilized for the design of ESPF

  11. ACR-700 advanced technologies

    International Nuclear Information System (INIS)

    Tapping, R.L.; Turner, C.W.; Yu, S.K.W.; Olmstead, R.; Speranzini, R.A.

    2004-01-01

    A successful advanced reactor plant will have optimized economics including reduced operating and maintenance costs, improved performance, and enhanced safety. Incorporating improvements based on advanced technologies ensures cost, safety and operational competitiveness of the ACR-700. These advanced technologies include modern configuration management; construction technologies; operational technology for the control centre and information systems for plant monitoring and analysis. This paper summarizes the advanced technologies used to achieve construction and operational improvements to enhance plant economic competitiveness, advances in the operational technology used for reactor control, and presents the development of the Smart CANDU suite of tools and its application to existing operating reactors and to the ACR-700. (author)

  12. A Study on intensifying efficiency for international collaborative development of Advanced Nuclear Energy Technology

    International Nuclear Information System (INIS)

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

    2009-08-01

    The objective of the study was to participate the GIF for the efficient propulsion of future nuclear system development. For achieving the objective of this study, the followings were carried out. · Investigation and analysis of the international and domestic trends related to future nuclear system · To maximize the national interests by the strategic participation of GIF meeting - To participate of GIF meeting and to support of relative work - To investigate the System R and D Arrangement and to inform its progress situation · To maximize the propulsion results of Korea/U.S nuclear energy joint research(I-NERI) - To support a delegation by the review of agenda in aspect of the technical/legal point - To participate of BINERIC meeting and to support of relative work · Streamline the nuclear energy R and D due to the effective connection between domestic R and D and international collaboration The result of this study may be used for 1) contribution to establishing the effective foundation and broadening the cooperation activities between the advanced countries and Korea and 2) contribution effective management of Gen IV international collaboration by technical/legal supporting

  13. Technology readiness level (TRL) assessment of cladding alloys for advanced nuclear fuels

    International Nuclear Information System (INIS)

    Shepherd, Daniel

    2015-01-01

    Reliable fuel claddings are essential for the safe, sustainable and economic operation of nuclear stations. This paper presents a worldwide TRL assessment of advanced claddings for Gen III and IV reactors following an extensive literature review. Claddings include austenitic, ferritic/martensitic (F/M), reduced activation (RA) and oxide dispersion strengthened (ODS) steels as well as advanced iron-based alloys (Kanthal alloys). Also assessed are alloys of zirconium, nickel (including Hastelloy R ), titanium, chromium, vanadium and refractory metals (Nb, Mo, Ta and W). Comparison is made with Cf/C and SiCf/SiC composites, MAX phase ceramics, cermets and TRISO fuel particle coatings. The results show in general that the higher the maximum operating temperature of the cladding, the lower the TRL. Advanced claddings were found to have lower TRLs than the corresponding fuel materials, and therefore may be the limiting factor in the deployment of advanced fuels and even possibly the entire reactor in the case of Gen IV. (authors)

  14. Advanced technologies and atomic energy

    International Nuclear Information System (INIS)

    1995-01-01

    The expert committee on the research 'Application of advanced technologies to nuclear power' started the activities in fiscal year 1994 as one of the expert research committees of Atomic Energy Society of Japan. The objective of its foundation is to investigate the information on the advanced technologies related to atomic energy and to promote their practice. In this fiscal year, the advanced technologies in the fields of system and safety, materials and measurement were taken up. The second committee meeting was held in March, 1995. In this report, the contents of the lectures at the committee meeting and the symposium are compiled. The topics in the symposium were the meaning of advanced technologies, the advanced technologies and atomic energy, human factors and control and safety systems, robot technology and microtechnology, and functionally gradient materials. Lectures were given at two committee meetings on the development of atomic energy that has come to the turning point, the development of advanced technologies centering around ULSI, the present problems of structural fine ceramics and countermeasures of JFCC, the material analysis using laser plasma soft X-ray, and the fullerene research of advanced technology development in Power Reactor and Nuclear Fuel Development Corporation. (K.I.)

  15. Advanced scientific computational methods and their applications of nuclear technologies. (1) Overview of scientific computational methods, introduction of continuum simulation methods and their applications (1)

    International Nuclear Information System (INIS)

    Oka, Yoshiaki; Okuda, Hiroshi

    2006-01-01

    Scientific computational methods have advanced remarkably with the progress of nuclear development. They have played the role of weft connecting each realm of nuclear engineering and then an introductory course of advanced scientific computational methods and their applications to nuclear technologies were prepared in serial form. This is the first issue showing their overview and introduction of continuum simulation methods. Finite element method as their applications is also reviewed. (T. Tanaka)

  16. Advanced fuel technology and performance

    International Nuclear Information System (INIS)

    1985-10-01

    The purpose of the Advisory Group Meeting on Advanced Fuel Technology and Performance was to review the experience of advanced fuel fabrication technology, its performance, peculiarities of the back-end of the nuclear fuel cycle with regard to all types of reactors and to outline the future trends. As a result of the meeting recommendations were made for the future conduct of work on advanced fuel technology and performance. A separate abstract was prepared for each of the 20 papers in this issue

  17. Fabrication of advanced targets for laser driven nuclear fusion reactions through standard microelectronics technology approaches.

    Czech Academy of Sciences Publication Activity Database

    Picciotto, A.; Crivellari, M.; Bellutti, P.; Barozzi, M.; Kucharik, M.; Krása, Josef; Swidlovsky, A.; Malinowska, A.; Velyhan, Andriy; Ullschmied, Jiří; Margarone, Daniele

    2017-01-01

    Roč. 12, October (2017), č. článku P10001. ISSN 1748-0221 Grant - others:OP VK 2 LaserGen(XE) CZ.1.07/2.3.00/20.0087; LaserZdroj (OP VK 3)(XE) CZ.1.07/2.3.00/20.0279 Institutional support: RVO:61389021 ; RVO:68378271 Keywords : Nuclear instruments and methods for hot plasma diagnostics * Plasma generation (laserproduced, RF, x ray-produced) * Plasma diagnostics - charged-particle spectroscopy Subject RIV: BL - Plasma and Gas Discharge Physics; BL - Plasma and Gas Discharge Physics (FZU-D) OBOR OECD: 2.11 Other engineering and technologies; 2.11 Other engineering and technologies (FZU-D) Impact factor: 1.220, year: 2016 http://iopscience.iop.org/article/10.1088/1748-0221/12/10/P10001/meta

  18. Advanced Manufacturing Technologies

    Science.gov (United States)

    Fikes, John

    2016-01-01

    Advanced Manufacturing Technologies (AMT) is developing and maturing innovative and advanced manufacturing technologies that will enable more capable and lower-cost spacecraft, launch vehicles and infrastructure to enable exploration missions. The technologies will utilize cutting edge materials and emerging capabilities including metallic processes, additive manufacturing, composites, and digital manufacturing. The AMT project supports the National Manufacturing Initiative involving collaboration with other government agencies.

  19. Editorial: Advanced learning technologies

    Directory of Open Access Journals (Sweden)

    Yu-Ju Lan

    2012-03-01

    Full Text Available Recent rapid development of advanced information technology brings high expectations of its potential to improvement and innovations in learning. This special issue is devoted to using some of the emerging technologies issues related to the topic of education and knowledge sharing, involving several cutting edge research outcomes from recent advancement of learning technologies. Advanced learning technologies are the composition of various related technologies and concepts such as mobile technologies and social media towards learner centered learning. This editorial note provides an overview of relevant issues discussed in this special issue.

  20. Contributions of the National Institute of Nuclear Research to the advance of Science and Technology in Mexico. Commemorative edition 2010

    International Nuclear Information System (INIS)

    Duque M, G.; Jimenez R, M.; Monroy G, F.; Romero H, S.; Serment G, J.

    2010-01-01

    From the second decade of the X X century the applications of the nuclear energy have been important part of the scientific and technological patrimony in Mexico. Records exist with regard to the use of the radioisotopes and the radiations in our country in that time, and in a formal way until the year of 1950, in a process that culminates with the creation of the Comision Nacional de Energia Nuclear (CNEN. January 1, 1956). In January 12, 1972 were published the Organic Law that created to the Instituto Nacional de Energia Nuclear, being responsible for the works that the CNEN developed. The current Instituto Nacional de Investigaciones Nucleares (ININ) was constituted starting from the Regulation Law of the constitutional Article 27 in nuclear matter of January 26, 1979, abrogated and substituted by the Law in force of February 4, 1985. In this lapse they were undertaken multitude of projects with results and diverse achievements. From their creation, the mission of the ININ and the previous institutions has been to realize research in science and nuclear technology, to promote their peaceful uses and to diffuse the achieved advances, always searching for to link them to the economic, social, scientific and technological development of the country. In this occasion with the purpose of participating in the commemoration of the bicentennial of the independence and centennial of the Mexican revolution in our country, the ININ decided to publish this work, directed to a wide public, with the intention of providing a vision the most complete and appropriate possible of the activities in research and technology that it is carries out at the moment. This work also seeks to be a diffusion instrument of the tasks that they are carried out in the institute, in diverse subjects as: the basic research, the nuclear applications in the health, the agriculture and the industry, the studies on the contamination and the environment; the dosimetry; the radiological protection; as

  1. Application technology of Data Free-Way for advanced nuclear materials

    International Nuclear Information System (INIS)

    Fujita, Mitsutane; Yagi, Koichi; Kinugawa, Junichi; Noda, Tetsuji; Kitajima, Masahiro; Nagakawa, Josei; Yamamoto, Norikazu

    2000-01-01

    In order to promote efficiency of survey on material property change and of selection and development on new materials, four organizations of the National Research Institute for Metals (NRIM), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Cycle Development Institute (JNC), and the Japan Science and Technology Corporation (JST) have constructed each data base on their strong fields to develop a huge dispersion type data base system by connecting them through a network. In 1998 fiscal year, together with storing fatigue property data of stainless steel, the four organizations under their cooperation carried out investigation on a method to make structure of the data base with less retrieving time possible, and reformed it to an easier system to use. And, NRIM collected diffusion data on metal, attempted to digitalising its documents, and made possible to supply its high degree informations. In future, they plans to promote their development for their data free way system so as to be used not only for nuclear power field but also for wide and common information system. (G.K.)

  2. GE's advanced nuclear reactor designs

    International Nuclear Information System (INIS)

    Berglund, R.C.

    1993-01-01

    The excess of US electrical generating capacity which has existed for the past 15 years is coming to an end as we enter the 1990s. Environmental and energy security issues associated with fossil fuels are kindling renewed interest in the nuclear option. The importance of these issues are underscored by the National Energy Strategy (NES) which calls for actions which open-quotes are designed to ensure that the nuclear power option is available to utilities.close quotes Utilities, utility associations, and nuclear suppliers, under the leadership of the Nuclear Power Oversight Committee (NPOC), have jointly developed a 14-point strategic plan aimed at establishing a predictable regulatory environment, standardized and pre-licensed Advanced Light Water Reactor (ALWR) nuclear plants, resolving the long-term waste management issue, and other open-quotes enabling conditions.close quotes GE is participating in this national effort and GE's family of advanced nuclear power plants feature two reactor designs, developed on a common technology base, aimed at providing a new generation of nuclear plants to provide safe, clean, economical electricity to the world's utilities in the 1990s and beyond. Together, the large-size (1300 MWe) Advanced Boiling Water Reactor (ABWR) and the small-size (600 MWe) Simplified Boiling Water Reactor (SBWR) are innovative, near-term candidates for expanding electrical generating capacity in the US and worldwide. Both possess the features necessary to do so safety, reliably, and economically

  3. Advanced uranium enrichment technologies

    International Nuclear Information System (INIS)

    Merriman, R.

    1983-01-01

    The Advanced Gas Centrifuge and Atomic Vapor Laser Isotope Separation methods are described. The status and potential of the technologies are summarized, the programs outlined, and the economic incentives are noted. How the advanced technologies, once demonstrated, might be deployed so that SWV costs in the 1990s can be significantly reduced is described

  4. Nuclear technology options

    International Nuclear Information System (INIS)

    Salvatores, Massimo

    2013-01-01

    Different strategies and motivations in different countries have led to diverse options. In Europe the SNETP (Sustainable Nuclear Energy Technology Platform) has the objective of developing R&D supporting GEN-II (present) and GEN-III nuclear systems under development; allowing sustainability and minimisation of waste burden, promoting advanced Gen-IV Fast Reactors; and accounting for a Nuclear Cogeneration Industrial Initiative. A remarkable initiative in the USA has been the promotion of small modular reactors (SMRs) – at less than 300 MWe in capacity, much smaller than typical reactors – which can be an ideal choice for (remote) areas which cannot support a larger reactor. Compact scalable design offers a host of potential safety, construction and economic benefits. More “upbeat” strategies are expected in other areas of the world where significant increase in nuclear energy demand is predicted in the next decades. If this growth materialises, future fuel cycles characteristics, feasibility and acceptability will be crucial. This paper will discuss different scenarios for future fuel cycles, resources optimisation and/or waste minimization, the range from full fast reactor deployment to phase-out, management of spent nuclear fuel and the significant potential benefits of advanced cycles. The next 45 years will be dominated by deployment of standard large or medium size plants operating for 60 years. Available resources do allow it. However, fuel cycle will be a growing and most challenging issue and early assessments will be needed for public acceptance and policy decisions.

  5. Advanced Nuclear Magnetic Resonance

    OpenAIRE

    Alonso, Diego A.

    2014-01-01

    Transparencias en inglés de la asignatura "Resonancia Magnética Nuclear Avanzada" (Advanced Nuclear Magnetic Resonance) (36643) que se imparte en el Máster de Química Médica como asignatura optativa de 3 créditos ECTS. En esta asignatura se completa el estudio iniciado en la asignatura de quinto curso de la licenciatura en Química "Determinación estructural" (7448) y en la del Grado de Química de tercer curso "Determinación estructural de los compuestos orgánicos" (26030) en lo referente a té...

  6. Advancing against nuclear terrorism

    International Nuclear Information System (INIS)

    Allison, G.

    2006-01-01

    Meeting a day before the summit, Bush and Putin announced a new Global Initiative to Combat Nuclear Terrorism; a plan for multiple, multilateral guaranteed suppliers of nuclear fuel to States that forgo building their own enrichment plants; and a Civil Nuclear Agreement that will lift restrictions on cooperation between the two countries in developing peaceful nuclear power. Each of these initiatives provides a framework for dozens of specific actions that can measurably reduce the risk of terrorists acquiring a nuclear weapon. The significance of the Global Initiative against Nuclear Terrorism lies not only in its substance but in Russia's visible joint ownership of the Initiative. After years in which Washington lectured Moscow about this threat, Putin's joint leadership in securing nuclear material worldwide should give added impetus to this undertaking inside Russia as well. Globally, this initiative calls for work plans in five arenas: prevention, detection, disruption, mitigation of consequences after an attack, and strengthening domestic laws and export controls against future A.Q. Khans. The guaranteed nuclear fuel supply tightens the noose around Iran as it seeks to exploit a loophole in the global Nuclear Non-Proliferation Treaty. By guaranteeing States that six separate international suppliers will provide backup guarantees against interruption of supply for any reason other that breech of commitments under the NPT, this proposal eliminates Iran's excuse for Natanz-the enrichment plant it is rushing to finish today. This system for supply will be subject to the supervision by the IAEA, which will also have nuclear fuel reserves that allow it to be a supplier of last resort. The Civil Nuclear Agreement will allow joint research on next-generation, proliferation-proof reactors, including technologies where Russian science is the best in the world. It will permit sale to Russia of US technologies that can improve the safety and efficiency of Russian nuclear

  7. Advanced nuclear systems. Review study

    International Nuclear Information System (INIS)

    Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

    1999-04-01

    The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

  8. Nuclear imaging: Advances and trends

    International Nuclear Information System (INIS)

    Herk, G. van

    1986-01-01

    In this article, nuclear imaging instruments that are likely to be of interest to the nuclear medicine community of developing countries are emphasized. The advances, trends, developments, and future directions in the field of nuclear imaging are mentioned

  9. Advanced scientific computational methods and their applications to nuclear technologies. (4) Overview of scientific computational methods, introduction of continuum simulation methods and their applications (4)

    International Nuclear Information System (INIS)

    Sekimura, Naoto; Okita, Taira

    2006-01-01

    Scientific computational methods have advanced remarkably with the progress of nuclear development. They have played the role of weft connecting each realm of nuclear engineering and then an introductory course of advanced scientific computational methods and their applications to nuclear technologies were prepared in serial form. This is the fourth issue showing the overview of scientific computational methods with the introduction of continuum simulation methods and their applications. Simulation methods on physical radiation effects on materials are reviewed based on the process such as binary collision approximation, molecular dynamics, kinematic Monte Carlo method, reaction rate method and dislocation dynamics. (T. Tanaka)

  10. Nuclear technology review 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-08-15

    Cadarache, France.The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) grew to 24 members, with the addition in 2005 of Ukraine and the United States of America. Current INPRO activities include completion of a user manual on the INPRO methodology, application of the methodology to assessing innovative nuclear energy systems (INSs) in national and multinational studies, analyses of the role and structure of INSs in meeting energy demands in a sustainable manner, and selection of the most suitable areas for collaborative development. Developments in accelerator based techniques, production of radioisotopes and some novel uses of nanotechnology are also reported. Nuclear technologies continue to play key and often unique roles in food production and safety, in human and animal health, in water resource management and in the environment. Mutation breeding of crops, for example, has led to the use of previously unusable land in many countries for rice production. In human health, the use of stable isotopes is becoming an accepted tool for the development of nutrition programmes. Nuclear medicine is benefiting from technological advances in computing. Sustainable water management and desalination remain high on the international agenda. New developments in isotopic analysis of hydrological samples hold promise for increasing the use of isotopes in water resources management. Advances in sampling and analytical techniques have assisted in better understanding of the environment. Developments in all these areas are also reported.

  11. Nuclear technology review 2006

    International Nuclear Information System (INIS)

    2006-08-01

    Cadarache, France.The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) grew to 24 members, with the addition in 2005 of Ukraine and the United States of America. Current INPRO activities include completion of a user manual on the INPRO methodology, application of the methodology to assessing innovative nuclear energy systems (INSs) in national and multinational studies, analyses of the role and structure of INSs in meeting energy demands in a sustainable manner, and selection of the most suitable areas for collaborative development. Developments in accelerator based techniques, production of radioisotopes and some novel uses of nanotechnology are also reported. Nuclear technologies continue to play key and often unique roles in food production and safety, in human and animal health, in water resource management and in the environment. Mutation breeding of crops, for example, has led to the use of previously unusable land in many countries for rice production. In human health, the use of stable isotopes is becoming an accepted tool for the development of nutrition programmes. Nuclear medicine is benefiting from technological advances in computing. Sustainable water management and desalination remain high on the international agenda. New developments in isotopic analysis of hydrological samples hold promise for increasing the use of isotopes in water resources management. Advances in sampling and analytical techniques have assisted in better understanding of the environment. Developments in all these areas are also reported

  12. Recent advances in nuclear cardiology

    International Nuclear Information System (INIS)

    Lee, Won Woo

    2016-01-01

    Nuclear cardiology is one of the major fields of nuclear medicine practice. Myocardial perfusion studies using single-photon emission computed tomography (SPECT) have played a crucial role in the management of coronary artery diseases. Positron emission tomography (PET) has also been considered an important tool for the assessment of myocardial viability and perfusion. However, the recent development of computed tomography (CT)/magnetic resonance imaging (MRI) technologies and growing concerns about the radiation exposure of patients remain serious challenges for nuclear cardiology. In response to these challenges, remarkable achievements and improvements are currently in progress in the field of myocardial perfusion imaging regarding the applicable software and hardware. Additionally, myocardial perfusion positron emission tomography (PET) is receiving increasing attention owing to its unique capability of absolute myocardial blood flow estimation. An F-18-labeled perfusion agent for PET is under clinical trial with promising interim results. The applications of F-18 fluorodeoxyglucose (FDG) and F-18 sodium fluoride (NaF) to cardiovascular diseases have revealed details on the basic pathophysiology of ischemic heart diseases. PET/MRI seems to be particularly promising for nuclear cardiology in the future. Restrictive diseases, such as cardiac sarcoidosis and amyloidosis, are effectively evaluated using a variety of nuclear imaging tools. Considering these advances, the current challenges of nuclear cardiology will become opportunities if more collaborative efforts are devoted to this exciting field of nuclear medicine

  13. Incentives to strengthen international co-operation in R and D for advanced nuclear power technology

    International Nuclear Information System (INIS)

    Versteegh, A.M.; Balthesen, E.; Bakunyaev, A.D.; Gibson, I.H.; Tavoni, R.

    1993-09-01

    The paper identifies the main areas which need strong international collaboration: development of innovative safety features; improvement of fuel characteristics and efficiency; dose reduction techniques; use of technology developed for other purposes; common assessments of design proposals. (orig./HP)

  14. The categorization of the impacts of the results of scientific and technological innovation in the Agency of Nuclear energy and advanced technologies (AENTA)

    International Nuclear Information System (INIS)

    Rodriguez Cardona, R.; Cobas Aranda, M.

    2010-01-01

    Science and technology are essential to the development of contemporary societies, however, there are different concepts and methodologies internationally to assess the economic and social impact of science and technology. In our country he has worked intensely with this aim and has established a national nomenclature of impact of science, technology and innovation. The Agency of Nuclear energy and advanced technologies (AEN-TA) is intended to improve the management of the programmes and projects management system framed within the system of science and technological innovation of the Republic of Cuba (SCIT) and one of the aspects of your special attention is the proper selection and follow-up (ex - before and during) projects to ensure that they contribute to improving the level of economic and social of our country one of his fundamental premises. This work has aims to show how the bases of the categorization of the impacts of the projects were established in the AEN-Mt management programs, as a management tool for the selection and monitoring of them, and which are characterized by a flexibility that keeping their identity do not differ from the established in the country. (author)

  15. Nuclear technology review 2002

    International Nuclear Information System (INIS)

    2002-08-01

    The unifying theme of the Nuclear Technology Review 2002 (NTR-2002) is the importance of innovation. Innovation makes it possible to step beyond incremental evolutionary improvements constrained by diminishing returns. For crop production and public health, for example, the sterile insect technique created a whole new path for future improvements, distinctly different from applying ever larger amounts of pesticides. Nuclear techniques offer a new and safer approach to removing the world's estimated 60,000,000 abandoned land mines. New precision techniques create the potential for ever less intrusive and more effective radiation treatments for cancer. For nuclear power continuing innovation will be a key factor in closing the projection gap between long term global energy scenarios in which nuclear power expands substantially and near term scenarios with only modest expansion or even decline. While the NTR-2002 presents a worldwide review of the state-of-the-art of nuclear science and technology, and not an annual report on IAEA activities, it notes areas where the Agency has a particularly important role to play. Part I of the NTR-2002 'Fundamentals of Nuclear Development', reviews developments in the field of nuclear, atomic and molecular data. Research reactors remain essential to progress in nuclear science and technology. Part I reviews advances in radioisotope production, the use of accelerators and neutron activation analysis relevant to applications ranging from medicine particularly the light against cancer to industry. Part I also reviews developments in nuclear instrumentation and nuclear fusion, particularly in connection with the International Thermonuclear Experimental Reactor. Part II begins with a summary of nuclear power production in 2001. At the end of 2001 there were 438 nuclear power plants (NPPs) in operation, corresponding to a total capacity of 353 GW(e), more than 10000 reactor-years of cumulative operating experience and about 16% of global

  16. The international nuclear technology

    International Nuclear Information System (INIS)

    Remick, F.J.

    1992-01-01

    With today's technology, isolationism is virtually impossible. The world's economies are so strongly intertwined that what affects one country will, in some way, influence another. Nuclear technology is no exception. If anything, nuclear technology is a catalyst for international cooperation. In the United States of America, nuclear technology is undergoing significant changes. Many of these changes are being greatly influenced by programs of international cooperation

  17. Commercialization of nuclear power plant decommissioning technology

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

    The commercialization of nuclear power plant decommissioning is presented as a step in the commercialization of nuclear energy. Opportunities for technology application advances are identified. Utility planning needs are presented

  18. Advanced exhaust nozzle technology

    Energy Technology Data Exchange (ETDEWEB)

    Glidewell, R J; Warburton, R E

    1981-01-01

    Recent developments in turbine engine exhaust nozzle technology include nonaxisymmetric nozzles, thrust reversing, and thrust vectoring. Trade studies have been performed to determine the impact of these developments on the thrust-to-weight ratio and specific fuel consumption of an advanced high performance, augmented turbofan engine. Results are presented in a manner which provides an understanding of the sources and magnitudes of differences in the basic elements of nozzle internal performance and weight as they relate to conventional, axisymmetric nozzle technology. Conclusions are presented and recommendations are made with regard to future directions of advanced development and demonstration. 5 refs.

  19. Advanced Surface Technology

    DEFF Research Database (Denmark)

    Møller, Per; Nielsen, Lars Pleht

    of the components. It covers everything from biocompatible surfaces of IR absorbent or reflective surfaces to surfaces with specific properties within low friction, hardness, corrosion, colors, etc. The book includes more than 400 pages detailing virtually all analysis methods for examining at surfaces.......This new significant book on advanced modern surface technology in all its variations, is aimed at both teaching at engineering schools and practical application in industry. The work covers all the significant aspects of modern surface technology and also describes how new advanced techniques make...

  20. Advanced manufacturing: Technology diffusion

    Energy Technology Data Exchange (ETDEWEB)

    Tesar, A.

    1995-12-01

    In this paper we examine how manufacturing technology diffuses rom the developers of technology across national borders to those who do not have the capability or resources to develop advanced technology on their own. None of the wide variety of technology diffusion mechanisms discussed in this paper are new, yet the opportunities to apply these mechanisms are growing. A dramatic increase in technology diffusion occurred over the last decade. The two major trends which probably drive this increase are a worldwide inclination towards ``freer`` markets and diminishing isolation. Technology is most rapidly diffusing from the US In fact, the US is supplying technology for the rest of the world. The value of the technology supplied by the US more than doubled from 1985 to 1992 (see the Introduction for details). History shows us that technology diffusion is inevitable. It is the rates at which technologies diffuse to other countries which can vary considerably. Manufacturers in these countries are increasingly able to absorb technology. Their manufacturing efficiency is expected to progress as technology becomes increasingly available and utilized.

  1. A study on the planning to promote the advanced nuclear technology development project

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chang Kue; Hahn, Do Hee; Kim, Young J. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-03-01

    Korea has participated in GIF from early stage, and played an important role in GIF as an original signatory of the GIF Charter. Korea has dispatched two representatives of GIF Policy Group and Expert Group respectively. Korea submitted 10 concepts of Gen IV for Gen IV technology roadmap. Korea's KALIMER and SMART concepts have stood higher in technological evaluation. 7 Korean experts were dispatched for Gen IV technology roadmap (4 from institution, 3 from industry and 1 form academia). Furthermore, USA's NTD (Near term Deployment) will be expanded to I-NTD (International NTD). This study suggested that Korea should propose APR-1400 as I-NTD concept for I-NTD discussion in GIF. Finally, Korea and USA jointly decided to fund 2 million dollars respectively for 2001 I-ERI program and selected 6 projects for the program, which are composed of 4 for LWR area and 2 for I and C area. 27 refs., 6 figs., 11 tabs. (Author)

  2. Advanced Environmental Monitoring Technologies

    Science.gov (United States)

    Jan, Darrell

    2004-01-01

    Viewgraphs on Advanced Environmental Monitoring Technologies are presented. The topics include: 1) Monitoring & Controlling the Environment; 2) Illustrative Example: Canary 3) Ground-based Commercial Technology; 4) High Capability & Low Mass/Power + Autonomy = Key to Future SpaceFlight; 5) Current Practice: in Flight; 6) Current Practice: Post Flight; 7) Miniature Mass Spectrometer for Planetary Exploration and Long Duration Human Flight; 8) Hardware and Data Acquisition System; 9) 16S rDNA Phylogenetic Tree; and 10) Preview of Porter.

  3. Nuclear Technology applications

    International Nuclear Information System (INIS)

    Cibils Machado, W. E- mail: wrcibils@adinet.com.uy

    2002-01-01

    The present work tries on the applications of the nuclear technology in the life daily, such as agriculture and feeding, human health, industry, non destructive essays, isotopic hydrology, and the nuclear power stations for electricity production and radioisotopes production

  4. Primatology: advanced ape technology.

    Science.gov (United States)

    McGrew, W C

    2004-12-29

    New findings from African rainforests show chimpanzees to have impressively advanced technology. They make tools of vegetation to harvest termites as in East and West Africa, but some apes in Central Africa show different techniques and tool sets geared for different tasks.

  5. Nuclear Technology Review 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-08-15

    The year 2006 saw increasing activities in the field of nuclear power. Significant plans for expansion were announced in some countries and plans for introducing nuclear power in some others. The year began with announcements by both the Russian Federation and the United States of America of international fuel cycle proposals in anticipation of a substantial expansion of nuclear power worldwide. In January, Russian President Vladimir Putin outlined a proposal to create 'a system of international centres providing nuclear fuel cycle services, including enrichment, on a non-discriminatory basis and under the control of the IAEA'. In February, the USA proposed a Global Nuclear Energy Partnership to develop advanced recycling technologies that would not separate pure plutonium; international collaboration in supplying fuel for States which agree not to pursue enrichment and reprocessing; advanced reactors to consume recycled spent fuel while providing energy; and safe and secure small reactors suited to the needs of developing countries. New medium-term projections by the IAEA and the International Energy Agency present a picture with opportunities for substantial nuclear expansion, but still with notable uncertainty. A number of countries have announced plans for significant expansion: China, India, Japan, Pakistan, the Russian Federation and the Republic of Korea. Announcements of planned license applications by US companies and consortia mentioned approximately 25 new reactors. Two site preparation applications were submitted in Canada. A major energy review by the United Kingdom concluded that new nuclear power stations would make a significant contribution to meeting the UK's energy policy goals. Utilities from Estonia, Lithuania and Latvia launched a joint feasibility study of a new nuclear power plant to serve all three countries, and Belarus, Egypt, Indonesia, Nigeria and Turkey made announcements of steps they are taking toward their first nuclear power plants

  6. Nuclear Technology Review 2007

    International Nuclear Information System (INIS)

    2007-08-01

    The year 2006 saw increasing activities in the field of nuclear power. Significant plans for expansion were announced in some countries and plans for introducing nuclear power in some others. The year began with announcements by both the Russian Federation and the United States of America of international fuel cycle proposals in anticipation of a substantial expansion of nuclear power worldwide. In January, Russian President Vladimir Putin outlined a proposal to create 'a system of international centres providing nuclear fuel cycle services, including enrichment, on a non-discriminatory basis and under the control of the IAEA'. In February, the USA proposed a Global Nuclear Energy Partnership to develop advanced recycling technologies that would not separate pure plutonium; international collaboration in supplying fuel for States which agree not to pursue enrichment and reprocessing; advanced reactors to consume recycled spent fuel while providing energy; and safe and secure small reactors suited to the needs of developing countries. New medium-term projections by the IAEA and the International Energy Agency present a picture with opportunities for substantial nuclear expansion, but still with notable uncertainty. A number of countries have announced plans for significant expansion: China, India, Japan, Pakistan, the Russian Federation and the Republic of Korea. Announcements of planned license applications by US companies and consortia mentioned approximately 25 new reactors. Two site preparation applications were submitted in Canada. A major energy review by the United Kingdom concluded that new nuclear power stations would make a significant contribution to meeting the UK's energy policy goals. Utilities from Estonia, Lithuania and Latvia launched a joint feasibility study of a new nuclear power plant to serve all three countries, and Belarus, Egypt, Indonesia, Nigeria and Turkey made announcements of steps they are taking toward their first nuclear power plants

  7. Development of Hi-Tech ceramics fabrication technologies - Development of advanced nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Thae Kap; Park, Ji Youn; Kim, Sun Jae; Kim, Kyong Ho; Jung, Choong Hwan; Oh, Seok Jin [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1994-07-15

    The objective of the present work is to prepare the foundation of hi-tech ceramics fabrication technologies through developing important processes i.e., tape casting, sol-gel, single crystal growing, compacting and sintering, and grinding and machining processes. Tape casting process is essential to manufacture hard and functional thin plates and structural elements for some composite materials. For the fabrication of spherical mono-sized micropowders of oxides, sol-gel process has widely been used. Piezoelectric elements that are the core parts of the sensors of LPMS (loose part monitoring system) and ALMS (acoustic leakage monitoring system) are used in single crystal forms. Compacting and sintering processes are general methods for fabricating structural parts using powders. Grinding and machining processes are important to achieve the final dimensions and surface properties of the parts. (Author).

  8. Advanced breaking technology on the Mochovce nuclear power plant building site

    International Nuclear Information System (INIS)

    Mraz, M.; Podel, R.; Vojta, A.

    1982-01-01

    Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m 3 of rock, the required output was derived for the 7th five year plan to the value of 200,000 m 3 per month, i.e., 10,000 m 3 per day and 700 m 3 per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m 2 which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m 3 the combination was used of 6 excavators with a shovel volume of 2.5 m 3 ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m 3 and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m 3 of excavated and removed rock. (B.S.)

  9. Advanced breaking technology on the Mochovce nuclear power plant building site

    Energy Technology Data Exchange (ETDEWEB)

    Mraz, M; Podel, R; Vojta, A [Vyskumny Ustav Inzinierskych Stavieb, Bratislava (Czechoslovakia)

    1982-10-01

    Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m/sup 3/ of rock, the required output was derived for the 7th five year plan to the value of 200,000 m/sup 3/ per month, i.e., 10,000 m/sup 3/ per day and 700 m/sup 3/ per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m/sup 2/ which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m/sup 3/ the combination was used of 6 excavators with a shovel volume of 2.5 m/sup 3/ ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m/sup 3/ and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m/sup 3/ of excavated and removed rock.

  10. R and D on robots for nuclear power plants in 'advanced robot technology' project

    International Nuclear Information System (INIS)

    Ando, Hiroaki

    1987-01-01

    The project aims at developing a safe man-robot system of high mobility and workability, highly adaptable to the working environment, and readily and reliably remote-controlled. The plan is to develop 'multi-purpose robots' that can do monitoring, inspection and light work quickly and correctly in areas where access of humans is difficult (e.g. hot spots and the inner space of the primary containment vessel), and 'robots used exclusively for valves, pumps, and other equipment, multi-functional to be used only for specific purposes'. This can be expected to be completed on the basis of results in research and development for the multi-purpose robots. R and D on the total system means manufacturing an optimum system with sufficient functions and performance required for the robot by combining existing technologies most adequately on the basis of the results of research and development on the project. After conceptual drawing and conceptual design, the system will be manufactured and demonstration tests will be completed by fiscal 1987 or 1988. This report describes the total image of the robots concerning the shape, locomotion, manipulation, perception, communication, control management, reliability and environmental durability, and then outlines the research and development activities regarding locomotion, manipulator, tectile sensor, actuator, single-eye three-dimensional measurement, visual data processing, optical spacial transmission, failure repair controller, functional reduction, robot health care and radiation resistance. (Nogami, K.)

  11. Advances in desalination technology

    International Nuclear Information System (INIS)

    Pankratz, T.M.

    2005-01-01

    Seawater desalination has been the cornerstone of the Middle East's water supply strategy since the mid-1950s, and most of the installed desalination capacity is still provided by multistage flash evaporators. But, desalination is changing. In fact, the term 'desalination' is no longer limited to seawater applications; desalination technologies are now routinely employed to desalinate brackish groundwater and repurify municipal effluents. Recent advances in desalination technology have simultaneously reduced costs while dramatically improving performance and reliability to the point where desalination technologies now compete with 'conventional' treatment processes in many applications. New commercial strategies and a realisation of the economies-of-scale have led to further improvements in plant economics, and an increase in the size of plants now being developed and constructed. This presentation reviews advances in membrane and membrane pretreatment systems, energy recovery devices, materials of construction, hybrid process configurations, increased unit capacities, and the use of public-private partnerships; all of which have led to reduced capital and operating costs, enabling desalination to be economically competitive with traditional treatment options. Advances in desalination technology have resulted in better performances, lower capital and operating costs, and increased application of desalination systems. In the face of increased water shortages and growing costs of 'conventional treatment', this trend will certainly continue. (author)

  12. Technology Roadmaps: Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This nuclear energy roadmap has been prepared jointly by the IEA and the OECD Nuclear Energy Agency (NEA). Unlike most other low-carbon energy sources, nuclear energy is a mature technology that has been in use for more than 50 years. The latest designs for nuclear power plants build on this experience to offer enhanced safety and performance, and are ready for wider deployment over the next few years. Several countries are reactivating dormant nuclear programmes, while others are considering nuclear for the first time. China in particular is already embarking on a rapid nuclear expansion. In the longer term, there is great potential for new developments in nuclear energy technology to enhance nuclear's role in a sustainable energy future.

  13. Nuclear Technology Review 2008

    International Nuclear Information System (INIS)

    2008-08-01

    , on a non-discriminatory basis and under the control of the IAEA. Nineteen countries signed a statement of principles of the Global Nuclear Energy Partnership, which aims at accelerating development and deployment of advanced fuel cycle technologies to foster development, improve the environment, and reduce the risk of nuclear proliferation. The NRC approved the release of most of the Big Rock Point nuclear power plant site and most of the Yankee Rowe nuclear power plant site for unrestricted public use. Thus, ten power plants around the world have been completely decommissioned with their sites released for unconditional use. Seventeen plants have been partially dismantled and safely enclosed. Thirty-two are being dismantled prior to eventual site release, and thirty-four reactors are undergoing minimum dismantling prior to long term enclosure. In September, the IAEA launched a new Network of Centres of Excellence for Decommissioning to improve the flow of knowledge and experience among those engaged in decommissioning and to encourage organizations in developed Member States to contribute to the activities of Member States requiring decommissioning assistance. Nuclear and isotopic techniques continue to make substantive contributions in agriculture, human health, the marine and terrestrial environments as well as in water resource management. In food and agriculture, plant mutation breeding is supporting the development of new varieties of crops that bring enhanced yields while also providing significant environmental benefits through reduced requirements for fertilizers and increased resistance to biotic and abiotic stresses. The genetic enhancement of biomass crops is useful in responding to increasing demands for biofuels. In addition to the continuing use of irradiation for sanitary purposes, the use of irradiation for phytosanitary applications, especially those applications related to quarantine measures, is increasing.

  14. Nuclear Technology Review 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-08-15

    , on a non-discriminatory basis and under the control of the IAEA. Nineteen countries signed a statement of principles of the Global Nuclear Energy Partnership, which aims at accelerating development and deployment of advanced fuel cycle technologies to foster development, improve the environment, and reduce the risk of nuclear proliferation. The NRC approved the release of most of the Big Rock Point nuclear power plant site and most of the Yankee Rowe nuclear power plant site for unrestricted public use. Thus, ten power plants around the world have been completely decommissioned with their sites released for unconditional use. Seventeen plants have been partially dismantled and safely enclosed. Thirty-two are being dismantled prior to eventual site release, and thirty-four reactors are undergoing minimum dismantling prior to long term enclosure. In September, the IAEA launched a new Network of Centres of Excellence for Decommissioning to improve the flow of knowledge and experience among those engaged in decommissioning and to encourage organizations in developed Member States to contribute to the activities of Member States requiring decommissioning assistance. Nuclear and isotopic techniques continue to make substantive contributions in agriculture, human health, the marine and terrestrial environments as well as in water resource management. In food and agriculture, plant mutation breeding is supporting the development of new varieties of crops that bring enhanced yields while also providing significant environmental benefits through reduced requirements for fertilizers and increased resistance to biotic and abiotic stresses. The genetic enhancement of biomass crops is useful in responding to increasing demands for biofuels. In addition to the continuing use of irradiation for sanitary purposes, the use of irradiation for phytosanitary applications, especially those applications related to quarantine measures, is increasing.

  15. Advances in diaper technology

    Directory of Open Access Journals (Sweden)

    Sahana M Srinivas

    2016-01-01

    Full Text Available Diapering practices vary among different countries from the use of cloth diapers to the modern disposable diaper. In the last few decades, diaper technology has advanced significantly thus decreasing the prevalence of diaper dermatitis. Recent innovative techniques used in the manufacturing of diapers include incorporation of superabsorbent polymer gel that can absorb 30 times its weight in liquid. Recently, smart diapers have been developed which not only prevents diaper dermatitis but significantly has reduced the burden on parents. This article reviews how changes in disposable diaper technology have improved diapering practices.

  16. Nuclear energy technology

    Science.gov (United States)

    Buden, David

    1992-01-01

    An overview of space nuclear energy technologies is presented. The development and characteristics of radioisotope thermoelectric generators (RTG's) and space nuclear power reactors are discussed. In addition, the policy and issues related to public safety and the use of nuclear power sources in space are addressed.

  17. Advances in nuclear desalination

    International Nuclear Information System (INIS)

    Misra, B.M.

    2003-01-01

    available in the moderator systems of the 220 and 500 MWe PHWR respectively. A significant part of this waste heat can be utilized for seawater desalination for in-house consumption. The Low Temperature Evaporation (LTE) technology for producing low conductivity water from seawater has been demonstrated at BARC on 30 m 3 /d scale by using waste heat. This plant is being connected to the CIRUS reactor for demonstration of coupling to a nuclear research reactor. The product water from this plant after minor polishing will meet the make up water requirement of the research reactor. (author)

  18. Technological advances at Pelindaba

    International Nuclear Information System (INIS)

    De Jesus, A.S.M.

    1983-01-01

    NUCOR has recently established the Nuclear Techniques Industrial Service (NTIS) with the specific purpose of providing a professional service to industry on a commercial basis. In the article some investigations conducted for industry will be briefly described, with neutron radiography as a complementary technique to conventional industrial radiography being dealt with in greater detail. The applications of nuclear technology in industry are very versatile, both in range of applications as well as in the variety of techniques which can be used. It's applications include the following: i) rapid assay of gold purity; behaviour of potassium in a blast furnace; performance of continuous massecuite crystalysers; air-flow measurement in mine shafts; monitoring of electrode length in an electrical arc furnace; monitoring of termite damage in wooden utility poles; behaviour of pollutants in the Crocodile river; distribution of boron in steel and in measuring the dynamic behaviour of materials in processing plants

  19. Advances in light water reactor technologies

    CERN Document Server

    Saito, Takehiko; Ishiwatari, Yuki; Oka, Yoshiaki

    2010-01-01

    ""Advances in Light Water Reactor Technologies"" focuses on the design and analysis of advanced nuclear power reactors. This volume provides readers with thorough descriptions of the general characteristics of various advanced light water reactors currently being developed worldwide. Safety, design, development and maintenance of these reactors is the main focus, with key technologies like full MOX core design, next-generation digital I&C systems and seismic design and evaluation described at length. This book is ideal for researchers and engineers working in nuclear power that are interested

  20. Graduate diplomas in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Bereznai, G. [Univ. of Ontario Inst. of Tech., Oshawa, Ontario (Canada)

    2009-07-01

    The University of Ontario Institute of Technology (UOIT) offers a graduate diploma program in nuclear technology that consists of a suite of six sub-specialties: Fuel, Materials and Chemistry; Reactor Systems; Operation and Maintenance; Safety, Licensing and Regulatory Affairs; Health Physics; and Radiological Applications. Four courses selected from a list that covers the knowledge and skill set of each sub-specialty have to be completed in order to gain a graduate diploma in the specific area. The program is designed to accommodate the needs of people working in the nuclear industry to upgrade their knowledge and skills, to promote career advancement and to provide a framework for lifelong learning. (author)

  1. A Pilot Study Investigating the Effects of Advanced Nuclear Power Plant Control Room Technologies: Methods and Qualitative Results

    Energy Technology Data Exchange (ETDEWEB)

    BLanc, Katya Le [Idaho National Lab. (INL), Idaho Falls, ID (United States); Powers, David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Brandon [Idaho National Lab. (INL), Idaho Falls, ID (United States); Fitzgerald, Kirk [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-08-01

    Control room modernization is an important part of life extension for the existing light water reactor fleet. None of the 99 currently operating commercial nuclear power plants in the U.S. has completed a full-scale control room modernization to date. Nuclear power plant main control rooms for the existing commercial reactor fleet remain significantly analog, with only limited digital modernizations. Upgrades in the U.S. do not achieve the full potential of newer technologies that might otherwise enhance plant and operator performance. The goal of the control room upgrade benefits research is to identify previously overlooked benefits of modernization, identify candidate technologies that may facilitate such benefits, and demonstrate these technologies through human factors research. This report describes a pilot study to test upgrades to the Human Systems Simulation Laboratory at INL.

  2. Advanced transport aircraft technology

    Energy Technology Data Exchange (ETDEWEB)

    Winblade, R L

    1980-06-01

    Various elements of the NASA aircraft energy efficiency program are described. Regarding composite structures, the development of three secondary and three medium-primary components to validate structural and fabrication technology is discussed. In laminar flow control, the design of advanced airfoils having large regions of supercritical flow with features which simplify laminarization are considered. Emphasis is placed on engine performance improvement, directed at developing advanced components to reduce fuel consumption in current production engines, and engine diagnostics aimed at identifying the sources and causes of performance deterioration in high-bypass turbofan engines. In addition, the results of propeller aerodynamic and acoustic tests have substantiated the feasibility of achieving the propeller efficiency goal of 80% and confirmed that the effect of blade sweep on reducing propeller source noise was 5-6 dB.

  3. Advanced nuclear reactor and nuclear fusion power generation

    International Nuclear Information System (INIS)

    2000-04-01

    This book comprised of two issues. The first one is a advanced nuclear reactor which describes nuclear fuel cycle and advanced nuclear reactor like liquid-metal reactor, advanced converter, HTR and extra advanced nuclear reactors. The second one is nuclear fusion for generation energy, which explains practical conditions for nuclear fusion, principle of multiple magnetic field, current situation of research on nuclear fusion, conception for nuclear fusion reactor and economics on nuclear fusion reactor.

  4. Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility

    International Nuclear Information System (INIS)

    Seya, M.; Hajima, R.; Nishimori, N.; Hayakawa, T.; Kikuzawa, N.; Shizuma, T.; Fujiwara, M.

    2010-01-01

    Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)

  5. Buildings for advanced technology

    CERN Document Server

    Teague, E; Murday, James

    2015-01-01

    This book deals with the design and construction of buildings for nanoscale science and engineering research. The information provided in this book is useful for designing and constructing buildings for such advanced technologies as nanotechnology, nanoelectronics and biotechnology. The book outlines the technology challenges unique to each of the building environmental challenges outlined below and provides best practices and examples of engineering approaches to address them: • Establishing and maintaining critical environments: temperature, humidity, and pressure • Structural vibration isolation • Airborne vibration isolation (acoustic noise) • Isolation of mechanical equipment-generated vibration/acoustic noise • Cost-effective power conditioning • Grounding facilities for low electrical interference • Electromagnetic interference (EMI)/Radio frequency interference (RFI) isolation • Airborne particulate contamination • Airborne organic and chemical contamination • Environment, safety a...

  6. Nuclear technology and beyond

    International Nuclear Information System (INIS)

    Akiyama, Mamoru

    1997-01-01

    After the confrontation of East and West, and the problem of North and South, we are now facing the era of Globalization in the presence of twenty-first century. Tracing the history of civilization, human being has progressed along with the accumulation of experience, and the development of science and technology. Science and technology bloomed in modern ages, especially, energy technology showed the giant leap in this century. Nuclear science and technology has been developed for peaceful purposes, and for the benefit of humanity. As a result, today, its progress led nuclear science and technology to have the great applicability to the development of the society. Toward the twenty-first century and Globalization, the science and technology developed in nuclear field is hoped to play a great contribution in various area of the society. (author)

  7. Pakistan's experience in transfer of nuclear technology

    International Nuclear Information System (INIS)

    Ahmad Khan, Nunir

    1977-01-01

    Of all technologies, nuclear technology is perhaps the most interdisciplinary in character as it encompasses such varied fields as nuclear physics, reactor physics, mechanical, electrical electronics controls, metallurgical and even civil and geological engineering. When we speak of transfer of acquisition of nuclear technology we imply cumulative know-how in many fields, most of which are not nuclear per se but are essential for building the necessry infrastructure and back-up facilities for developing and implementing any nuclear energy program. In Pakistan, efforts on utilization of nuclear energy for peaceful applications were initiated about twenty years ago. During these years stepwise development of nuclear technology has taken place. The experience gained by Pakistan so far in transfer of nuclear technology is discussed. Suggestions have been made for continuing the transfer of this most essential technology from the advanced to the developing countries while making sure that necessary safeguard requirements are fullfilled

  8. Advanced optical instruments technology

    Science.gov (United States)

    Shao, Mike; Chrisp, Michael; Cheng, Li-Jen; Eng, Sverre; Glavich, Thomas; Goad, Larry; Jones, Bill; Kaarat, Philip; Nein, Max; Robinson, William

    1992-08-01

    The science objectives for proposed NASA missions for the next decades push the state of the art in sensitivity and spatial resolution over a wide range of wavelengths, including the x-ray to the submillimeter. While some of the proposed missions are larger and more sensitive versions of familiar concepts, such as the next generation space telescope, others use concepts, common on the Earth, but new to space, such as optical interferometry, in order to provide spatial resolutions impossible with other concepts. However, despite their architecture, the performance of all of the proposed missions depends critically on the back-end instruments that process the collected energy to produce scientifically interesting outputs. The Advanced Optical Instruments Technology panel was chartered with defining technology development plans that would best improve optical instrument performance for future astrophysics missions. At this workshop the optical instrument was defined as the set of optical components that reimage the light from the telescope onto the detectors to provide information about the spatial, spectral, and polarization properties of the light. This definition was used to distinguish the optical instrument technology issues from those associated with the telescope, which were covered by a separate panel. The panel identified several areas for optical component technology development: diffraction gratings; tunable filters; interferometric beam combiners; optical materials; and fiber optics. The panel also determined that stray light suppression instruments, such as coronagraphs and nulling interferometers, were in need of general development to support future astrophysics needs.

  9. State Technologies Advancement Collaborative

    Energy Technology Data Exchange (ETDEWEB)

    David S. Terry

    2012-01-30

    The U. S. Department of Energy (DOE), National Association of State Energy Officials (NASEO), and Association of State Energy Research and Technology Transfer Institutions (ASERTTI) signed an intergovernmental agreement on November 14, 2002, that allowed states and territories and the Federal Government to better collaborate on energy research, development, demonstration and deployment (RDD&D) projects. The agreement established the State Technologies Advancement Collaborative (STAC) which allowed the states and DOE to move RDD&D forward using an innovative competitive project selection and funding process. A cooperative agreement between DOE and NASEO served as the contracting instrument for this innovative federal-state partnership obligating funds from DOE's Office of Energy Efficiency and Renewable Energy and Office of Fossil Energy to plan, fund, and implement RDD&D projects that were consistent with the common priorities of the states and DOE. DOE's Golden Field Office provided Federal oversight and guidance for the STAC cooperative agreement. The STAC program was built on the foundation of prior Federal-State efforts to collaborate on and engage in joint planning for RDD&D. Although STAC builds on existing, successful programs, it is important to note that it was not intended to replace other successful joint DOE/State initiatives such as the State Energy Program or EERE Special Projects. Overall the STAC process was used to fund, through three competitive solicitations, 35 successful multi-state research, development, deployment, and demonstration projects with an overall average non-federal cost share of 43%. Twenty-two states were awarded at least one prime contract, and organizations in all 50 states and some territories were involved as subcontractors in at least one STAC project. Projects were funded in seven program areas: (1) Building Technologies, (2) Industrial Technologies, (3) Transportation Technologies, (4) Distributed Energy

  10. Introduction to nuclear technology

    International Nuclear Information System (INIS)

    Goldsmith, M.W.

    1985-01-01

    In the late 1940s and early 1950s when nuclear technology emerged, there was no oil embargo or any obvious signs of an energy crisis. The driving forces for the rapid development of the atom were its fuel efficiency and its potential cost-effectiveness compared to its alternatives. Uranium was a cheap and abundant domestic fuel and the development of the technology provided new vistas and challenges for the engineering community. It was the goal of providing environmentally clean, abundant, and reasonably priced energy that motivated engineers then as now. Nuclear technology developed under a mixture of government regulation and promotion and utility industry commercialization. This paper discusses the development and implementation of a technology largely resulting from the efforts of government to make the production of nuclear-powered electricity a commercial enterprise. This effort has largely succeeded, as greater than 10% of the electricity generated nationally is now provided by nuclear power

  11. Chemistry and nuclear technology

    International Nuclear Information System (INIS)

    De Wet, W.J.

    1977-01-01

    The underlying principles of nuclear sciece and technology as based on the two basic phenomena, namely, radioactivity and nuclear reactions, with their relatively large associated energy changes, are outlined. The most important contributions by chemists in the overall historical development are mentioned and the strong position chemistry has attained in these fields is indicated. It is concluded that chemistry as well as many other scientific discplines (apart from general benefits) have largely benefitted from these nuclear developments [af

  12. Advances in nuclear physics

    CERN Document Server

    Vogt, Erich

    1975-01-01

    Review articles on three topics of considerable current interest make up the present volume. The first, on A-hypernuclei, was solicited by the editors in order to provide nuclear physicists with a general description of the most recent developments in a field which this audience has largely neglected or, perhaps, viewed as a novelty in which a bizarre nuclear system gave some information about the lambda-nuclear intersection. That view was never valid. The very recent developments reviewed here-particularly those pertaining to hypernuclear excitations and the strangeness exchange reactions-emphasize that this field provides important information about the models and central ideas of nuclear physics. The off-shell behavior of the nucleon-nucleon interaction is a topic which was at first received with some embarrassment, abuse, and neglect, but it has recently gained proper attention in many nuclear problems. Interest was first focused on it in nuclear many-body theory, but it threatened nuclear physicists'comf...

  13. Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

    Directory of Open Access Journals (Sweden)

    Wang Qiu-kuan

    2012-01-01

    Full Text Available The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation methods for nuclear installations and the applications of these instruments and methods.

  14. Nuclear industry technology boomerang

    International Nuclear Information System (INIS)

    Scholler, R.W.

    1987-01-01

    The benefits to the medical, pharmaceutical, semiconductor, computer, video, bioscience, laser, defense, and numerous high-tech industries from nuclear technology development fallout are indeed numerous and increase every day. Now those industries have made further progress and improvements that, in return, benefit the nuclear industry. The clean-air and particle-free devices and enclosures needed for protection and decontamination are excellent examples

  15. Advances in nuclear imaging

    International Nuclear Information System (INIS)

    Gelfand, M.J.

    1989-01-01

    Emission computed tomography such as positron emission tomography and single-photon emission computed tomography may have use in the diagnosis of acute cerebral and myocardial lesions. The technology, as well as its possible applications, is discussed.33 references

  16. Nuclear technology and society

    International Nuclear Information System (INIS)

    Suzuki, Tatsujiro; Tanaka, Yutaka; Taniguchi, Taketoshi; Oyama, Kosuke

    1999-01-01

    This special issue of Journal of the Atomic Energy Society of Japan deals with the relation between nuclear technology and society, and is composed of four papers: (1) Nuclear energy and international politics - sociotechnics around plutonium utilization; (2) Risk recognition and benefit recognition of nuclear facilities and social acceptance; (3) Environmental risk management and radioactive waste problem; and, (4) Public administration around the relation between nuclear energy and society. (1) describes the historical development of nuclear energy since its birth, focusing on how the leading countries tried to control nuclear proliferation. Peaceful utilization of nuclear energy is closely connected with the Non-proliferation problem. (1) also discusses the relation of plutonium utilization of Japan with international society. (2) discusses how nuclear facilities can be accepted by society, analyzing the background of risk recognition, in particular, of psychological character of mass society. (3) introduces an new approach (risk-based or risk-informed regulation) of environmental risk management for radioactive waste disposal problem, focusing on HLW (high-level waste). (4) explains the approach from public administration to nuclear energy and general energy policy and introduces PPA (participatory policy analysis) as a means for policy making. (M.M.)

  17. Requirements for a Dynamic Solvent Extraction Module to Support Development of Advanced Technologies for the Recycle of Used Nuclear Fuel

    International Nuclear Information System (INIS)

    Law, Jack; Rutledge, Veronica; Pereira, Candido; Copple, Jackie; Frey, Kurt; Krebs, John; Maggos, Laura; Nichols, Kevin; Wardle, Kent; Sadasivan, Pratap; DeAlmieda, Valmor; Depaoli, David

    2011-01-01

    The Department of Energy's Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program has been established to create and deploy next generation, verified and validated nuclear energy modeling and simulation capabilities for the design, implementation, and operation of future nuclear energy systems to improve the U.S. energy security. As part of the NEAMS program, Integrated Performance and Safety Codes (IPSC's) are being produced to significantly advance the status of modeling and simulation of energy systems beyond what is currently available to the extent that the new codes be readily functional in the short term and extensible in the longer term. The four IPSC areas include Safeguards and Separations, Reactors, Fuels, and Waste Forms. As part of the Safeguards and Separations (SafeSeps) IPSC effort, interoperable process models are being developed that enable dynamic simulation of an advanced separations plant. A SafeSepss IPSC 'toolkit' is in development to enable the integration of separation process modules and safeguards tools into the design process by providing an environment to compose, verify and validate a simulation application to be used for analysis of various plant configurations and operating conditions. The modules of this toolkit will be implemented on a modern, expandable architecture with the flexibility to explore and evaluate a wide range of process options while preserving their stand-alone usability. Modules implemented at the plant-level will initially incorporate relatively simple representations for each process through a reduced modeling approach. Final versions will incorporate the capability to bridge to subscale models to provide required fidelity in chemical and physical processes. A dynamic solvent extraction model and its module implementation are needed to support the development of this integrated plant model. As a stand-alone application, it will also support solvent development of extraction flowsheets and integrated

  18. Requirements for a Dynamic Solvent Extraction Module to Support Development of Advanced Technologies for the Recycle of Used Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Jack Law; Veronica Rutledge; Candido Pereira; Jackie Copple; Kurt Frey; John Krebs; Laura Maggos; Kevin Nichols; Kent Wardle; Pratap Sadasivan; Valmor DeAlmieda; David Depaoli

    2011-06-01

    The Department of Energy's Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program has been established to create and deploy next generation, verified and validated nuclear energy modeling and simulation capabilities for the design, implementation, and operation of future nuclear energy systems to improve the U.S. energy security. As part of the NEAMS program, Integrated Performance and Safety Codes (IPSC's) are being produced to significantly advance the status of modeling and simulation of energy systems beyond what is currently available to the extent that the new codes be readily functional in the short term and extensible in the longer term. The four IPSC areas include Safeguards and Separations, Reactors, Fuels, and Waste Forms. As part of the Safeguards and Separations (SafeSeps) IPSC effort, interoperable process models are being developed that enable dynamic simulation of an advanced separations plant. A SafeSepss IPSC 'toolkit' is in development to enable the integration of separation process modules and safeguards tools into the design process by providing an environment to compose, verify and validate a simulation application to be used for analysis of various plant configurations and operating conditions. The modules of this toolkit will be implemented on a modern, expandable architecture with the flexibility to explore and evaluate a wide range of process options while preserving their stand-alone usability. Modules implemented at the plant-level will initially incorporate relatively simple representations for each process through a reduced modeling approach. Final versions will incorporate the capability to bridge to subscale models to provide required fidelity in chemical and physical processes. A dynamic solvent extraction model and its module implementation are needed to support the development of this integrated plant model. As a stand-alone application, it will also support solvent development of extraction flowsheets

  19. A study on the nuclear technology policy

    International Nuclear Information System (INIS)

    Kim, H. J.; Oh, K. B.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik

    2005-01-01

    This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. Acknowledging the importance of the relationship between the external environment and the national nuclear R and D strategic planning for changing of environment of surrounding nuclear technology and development in the world, this study focused on the three major subjects: (1) investigation and analysis of international nuclear environmental and technological change; (2) developing nuclear R and D strategy based on the analysis of national and global environment surrounding nuclear technology development and diffusion; (3) the evaluation of role of nuclear technology and environment from the point of views of environmental effects. In order to enhance the role of national nuclear R and D program and to cope with the environmental and technological change surrounding nuclear energy, it is recommended that active participation should be done in ongoing international collaboration on future innovative nuclear technology for absorption of advanced technologies and strategic R and D planning should be centered on core technology field based on long-term vision and suggested NuTRM considering future energy-environmental surroundings for maximized use of domestic technology capabilities and resources

  20. Recent nuclear technology advances of GE-H and GNF in partnership with CFE's Laguna Verde 2

    International Nuclear Information System (INIS)

    Cuevas V, G.; Iwamoto, T.; Banfield, J.; Calleros M, G.

    2015-09-01

    This paper is presented based on work stemming from the long-standing technical partnership between Comision Federal de Electricidad (CFE) and Global Nuclear Fuel - Americas LLC (GNF), and this paper's purpose is to provide valuable information for the nuclear industry. First, a one-to-one comparison of measurements from Gamma Thermometers (G Ts) installed in Laguna Verde 2 (LV-2) core against axially corresponding Traverse In-core Probe (Tip) measurements is remarkably close. This longest running G T plant validation for the Economic Simplified Boiling Water Reactor (ESBWR) power monitoring devices is also proving that the devices have the potential to simplify power measurements in Boiling Water Reactors (BWRs). Second, code validation results show remarkable reduction of radial power uncertainty with respect to current technology when new GNF codes for three-dimensional core simulations are compared to Tip power measurements. The LV-2 core is of paramount importance for BWR data analysis since the core has been loaded from the start of operation with different GNF fuel bundle types, fuel management has been designed with GNF codes and on-line core monitoring has been performed with GNF's 3-Dimensional Monicore system. This validation is also reliable since gamma Tips are used for local power measurements rather than thermal neutron Tips, which are more sensitive to local turbulence and positional changes. A nuclear/thermal-hydraulic core simulation of GNF fuel is undertaken from the beginning of operation of LV-2 (cycle 1) through the range of different power scenarios including low power, original licensed thermal power, power up rate and extended power up rate. Results confirm the conclusions from previous validations in different BWRs and support GNF efforts for licensing the new generation of nuclear engineering codes. (Author)

  1. Recent nuclear technology advances of GE-H and GNF in partnership with CFE's Laguna Verde 2

    Energy Technology Data Exchange (ETDEWEB)

    Cuevas V, G.; Iwamoto, T.; Banfield, J. [GE-Hitachi Nuclear Energy Americas LLC, Global Nuclear Fuel - Americas LLC, 3901 Castle Hayne Road, Wilmington, 28401 North Carolina (United States); Calleros M, G., E-mail: Gabriel.Cuevas-Vivas@age.com [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Veracruz-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2015-09-15

    This paper is presented based on work stemming from the long-standing technical partnership between Comision Federal de Electricidad (CFE) and Global Nuclear Fuel - Americas LLC (GNF), and this paper's purpose is to provide valuable information for the nuclear industry. First, a one-to-one comparison of measurements from Gamma Thermometers (G Ts) installed in Laguna Verde 2 (LV-2) core against axially corresponding Traverse In-core Probe (Tip) measurements is remarkably close. This longest running G T plant validation for the Economic Simplified Boiling Water Reactor (ESBWR) power monitoring devices is also proving that the devices have the potential to simplify power measurements in Boiling Water Reactors (BWRs). Second, code validation results show remarkable reduction of radial power uncertainty with respect to current technology when new GNF codes for three-dimensional core simulations are compared to Tip power measurements. The LV-2 core is of paramount importance for BWR data analysis since the core has been loaded from the start of operation with different GNF fuel bundle types, fuel management has been designed with GNF codes and on-line core monitoring has been performed with GNF's 3-Dimensional Monicore system. This validation is also reliable since gamma Tips are used for local power measurements rather than thermal neutron Tips, which are more sensitive to local turbulence and positional changes. A nuclear/thermal-hydraulic core simulation of GNF fuel is undertaken from the beginning of operation of LV-2 (cycle 1) through the range of different power scenarios including low power, original licensed thermal power, power up rate and extended power up rate. Results confirm the conclusions from previous validations in different BWRs and support GNF efforts for licensing the new generation of nuclear engineering codes. (Author)

  2. Quantitative study on the significance of FR cycle. Interim report of JNC/CEA joint study on advanced technology R and D for nuclear energy

    International Nuclear Information System (INIS)

    Fiorini, G.L.; Shinoda, Yoshihiko; Kofuji, Hirohide; Hirao, Kazunori

    2001-09-01

    This study on quantitative study on significance of FR cycle was carried out under the agreement between JNC and CEA in the field of advanced technology R and D for nuclear energy. JNC has been developing the quantitative evaluation method to be constructed by combining Analytic Hierarchy Process (AHP) and Multi-Attribute Utility Theory (MAUT). CEA has been caring out the qualitative evaluation from expert judgement from viewpoint of sustainability such as the response to the energetic demand, the saving of the resources and the minimization of the environmental impact. (author)

  3. A Study on the Nuclear Technology Policy

    International Nuclear Information System (INIS)

    Lim, C. Y.; Lee, K. S.; Jeong, I.; Lee, J. H.

    2009-04-01

    The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, recent changes of international nuclear energy policy and trends of nuclear technology R and D was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed the trends of nuclear technology policies and (2) discussed the mid and long term strategy of nuclear energy R and D. To put it in more detail, each subject was further explored as follows; (1) analyzed the trends of nuclear technology policies - Trend and prospects of the international and domestic nuclear policies - Investigation of development of small and medium sized policies - International collaboration for advanced nuclear technologies (2) discussed the mid and long term strategy of nuclear energy R and D - The long term development plan for future nuclear energy system - The facilitation of technology commercialization

  4. Nuclear technology and societal needs

    International Nuclear Information System (INIS)

    2004-11-01

    This volume aims to review the present status of development of nuclear technologies and their applications in the country and also to make projections for future requirements. This will also cover state-of-the-art technologies in these areas. The following topics are covered in detail: nuclear technologies for water desalination, water resources development and management using nuclear technology, industrial applications of isotopes and radiation technology, radiation technology in health care, nuclear technology for food preservation, agricultural applications of nuclear technology. Papers relevant to INIS are indexed separately

  5. Nuclear technology in Canada

    International Nuclear Information System (INIS)

    1983-01-01

    This pamphlet provides a summary of the research being carried out by Atomic Energy of Canada Limited. The design and development of the CANDU type reactor are highlighted and the contribution of nuclear technology to medicine, agriculture and the Canadian economy is briefly discussed

  6. Assessment report of research and development on 'the abolition measures of nuclear facilities and associated technology development' and 'radioactive waste treatment and disposal and associated technology development' (result evaluation, in advance evaluation) and 'technology development related to reprocessing of nuclear fuel material' (In advance evaluation)

    International Nuclear Information System (INIS)

    2015-07-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consulted the 'Evaluation Committee for Decommissioning and Radioactive Waste Management ' for result evaluation and in advance evaluation of 'The abolition measures of nuclear facilities and associated technology development' project and 'Radioactive waste treatment and disposal and associated technology development' project and 'Technology development related to reprocessing of nuclear fuel material' project in accordance with the 'Guideline for evaluation of government R and D activities', the 'Guideline for evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology (MEXT)' and the 'Operational rule for evaluation of R and D activities' by JAEA. In response to the JAEA's request, the Evaluation Committee for Decommissioning and Radioactive Waste Management, in accordance with the evaluation method as defined in the Committee deliberations and oral report and deliberation of material about the R and D project of three was conducted. This report summarizes the results of the assessment by the Committee with the Committee report. (author)

  7. Marketing technologically advanced products

    NARCIS (Netherlands)

    Bender, Horst

    1989-01-01

    This paper calls for a merger of technology and marketing under a customer value perspective; for an enhancement of the traditional technological innovation orientation of the technology-based firm with a market thrust. It establishes technology-based products as product-service offerings that are

  8. Kazakhstan innovation projects in nuclear technologies field

    International Nuclear Information System (INIS)

    Shkol'nik, V.S.; Tukhvatulin, Sh.T.

    2005-01-01

    At present in the Republic of Kazakhstan in preparation and realization stage there are several innovation projects related with use of advanced nuclear technologies. Projects are as follows: 'Implementation of Kazakhstan thermonuclear reactor tokamak (KTM)'; 'Implementation at the L.N. Gumilev Eurasian National University the inter-disciplinary research complex on the heavy ions accelerator base'; 'Development of the Technological Park 'Nuclear Technologies Center in Kurchatov city'; 'Development the first in the Central-Asian region Center of Nuclear Medicine and Biophysics'. The initiator and principal operator of these projects is the National Nuclear Center of the Republic of Kazakhstan

  9. Recent advances in nuclear cardiology

    DEFF Research Database (Denmark)

    Gutte, H.; Petersen, C. Leth; Kjaer, A.

    2008-01-01

    Nuclear cardiology is an essential part of functional, non-invasive, cardiac imaging. Significant advances have been made in nuclear cardiology since planar (201)thallium ((201)TI) scintigraphy was introduced for the evaluation of left ventricular (LV) perfusion nearly 40 years ago. The use...... of nuclear cardiology has been steadily increasing over the last 20 years with important steps being the introduction of (99m)technetium- ((99m)Tc)-labelled perfusion radiotracers, the change from only planar to now much more single photon emission computed tomography (SPECT) and positron emission tomography...... (PET), electrocardiogram gating of nuclear perfusion imaging, and finally introducing nuclear hybrid imaging using either SPECT or PET together with either computed tomography or magnetic resonance imaging. The indications have extended from nearly only coronary artery diseases to several non...

  10. Coordinating Space Nuclear Research Advancement and Education

    International Nuclear Information System (INIS)

    Bess, John D.; Webb, Jonathon A.; Gross, Brian J.; Craft, Aaron E.

    2009-01-01

    The advancement of space exploration using nuclear science and technology has been a goal sought by many individuals over the years. The quest to enable space nuclear applications has experienced many challenges such as funding restrictions; lack of political, corporate, or public support; and limitations in educational opportunities. The Center for Space Nuclear Research (CSNR) was established at the Idaho National Laboratory (INL) with the mission to address the numerous challenges and opportunities relevant to the promotion of space nuclear research and education.1 The CSNR is operated by the Universities Space Research Association and its activities are overseen by a Science Council comprised of various representatives from academic and professional entities with space nuclear experience. Program participants in the CSNR include academic researchers and students, government representatives, and representatives from industrial and corporate entities. Space nuclear educational opportunities have traditionally been limited to various sponsored research projects through government agencies or industrial partners, and dedicated research centers. Centralized research opportunities are vital to the growth and development of space nuclear advancement. Coordinated and focused research plays a key role in developing the future leaders in the space nuclear field. The CSNR strives to synchronize research efforts and provide means to train and educate students with skills to help them excel as leaders.

  11. Advanced teleoperation in nuclear applications

    International Nuclear Information System (INIS)

    Hamel, W.R.; Feldman, M.J.; Martin, H.L.

    1984-01-01

    A new generation of integrated remote maintenance systems is being developed to meet the needs of future nuclear fuel reprocessing at the Oak Ridge National Laboratory. Development activities cover all aspects of an advanced teleoperated maintenance system with particular emphasis on a new force-reflecting servomanipulator concept. The new manipulator, called the advanced servomanipulator, is microprocessor controlled and is designed to achieve force-reflection performance near that of mechanical master/slave manipulators. The advanced servomanipulator uses a gear-drive transmission which permits modularization for remote maintainability (by other advanced servomanipulators) and increases reliability. Human factors analysis has been used to develop an improved man/machine interface concept based upon colorgraphic displays and menu-driven tough screens. Initial test and evaluation of two advanced servomanipulator slave arms and several other development components have begun. 9 references, 5 figures

  12. Advanced research technology transfer

    International Nuclear Information System (INIS)

    Naraghi, Masud

    1977-01-01

    The importance of advanced research in the less developed countries of the world is described. Advanced research is a way of building from the top; it helps industrial development; it provides ''know-how'' economically; it enhances international understanding; it prevents the brain drain to developed countries and is of mutual benefit. The problems concerned with this type of research are pointed out

  13. Advancement in Engineering Technology

    DEFF Research Database (Denmark)

    Kalia, Kartik; Rehman, M. Atiqur; Hussain, Dil muhammed Akbar

    2016-01-01

    In this paper we will be discussing about the impact of technology on our daily lives. How everybody is dependent upon technology in one or other way. Methods/Statistical Analysis: Technology has played a significant role in the evolution of the society. Science has produced many new ideas...... but to harvest those ideas, technology is a must. With the huge requirement of engineering equipment's, the industry needs specialists who can manage and operate these technologies. Detailed information about the merits and demerits of technology is also mentioned in this paper. Findings: Technology has affected...... the environment on a great scale; in some cases, technology is even replacing human being or use of manpower. So proper counter measures have been mentioned, which can be used to control and limit harmful effect....

  14. Nuclear Technology Review 2015

    International Nuclear Information System (INIS)

    2015-08-01

    With 438 reactors operating at the end of 2014, nuclear energy had a global generating capacity of 376.2 GW(e). There was only one permanent shutdown. There were five new grid connections and three construction starts on new reactors. Near and long term growth prospects remained centred in Asia, particularly in China. Of the 70 reactors under construction, 46 were in Asia, as were 32 of the last 40 reactors that have been connected to the grid since 2004. Thirty countries currently use nuclear power and about the same number are considering, planning or actively working to include it as part of their energy mix. Of the 30 operating countries, 13 are either constructing new plants or actively completing previously suspended construction projects, and 12 are planning either to construct new plants or to complete suspended construction projects. Several countries that have decided to introduce nuclear power are at advanced stages of infrastructure preparation. The IAEA’s 2014 projections show a growth between 8% and 88% in nuclear power capacity by the year 2030. Growth of population and demand for electricity in the developing world, recognition of the role nuclear power plays in reducing greenhouse gas emissions, the importance of security of energy supply and the volatility of fossil fuel prices point to nuclear energy playing an important role in the energy mix in the long run. Safety improvements have continued to be made at nuclear power plants (NPPs) throughout the world. These have included identifying and applying lessons learned from the accident at the Fukushima Daiichi Nuclear Power Plant, improving the effectiveness of defence in depth, strengthening emergency preparedness and response capabilities, enhancing capacity building, and protecting people and the environment from ionizing radiation

  15. A Study on the Nuclear Technology Policy

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. J.; Lim, C. Y.; Yang, M. H. (and others)

    2008-03-15

    The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, changes of international nuclear energy policy environment and trends of nuclear technology development was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy environment surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed trends of nuclear technology policies and (2) developed the nuclear energy R and D innovation strategies. To put it in more detail, each subject was further explored as follows; (1) themes to analyze trends of nuclear policies: nuclear Renaissance and forecast for nuclear power plant, International collaboration for advanced nuclear technologies in GIF, INPRO and I-NERI, The present situation and outlook for world uranium market (2) themes to develop of nuclear energy R and D innovation strategies: The mid-term strategy plan of the KAERI, The technological innovation case of the KAERI.

  16. A Study on the Nuclear Technology Policy

    International Nuclear Information System (INIS)

    Kim, H. J.; Lim, C. Y.; Yang, M. H.

    2008-03-01

    The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, changes of international nuclear energy policy environment and trends of nuclear technology development was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy environment surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed trends of nuclear technology policies and (2) developed the nuclear energy R and D innovation strategies. To put it in more detail, each subject was further explored as follows; (1) themes to analyze trends of nuclear policies: nuclear Renaissance and forecast for nuclear power plant, International collaboration for advanced nuclear technologies in GIF, INPRO and I-NERI, The present situation and outlook for world uranium market (2) themes to develop of nuclear energy R and D innovation strategies: The mid-term strategy plan of the KAERI, The technological innovation case of the KAERI

  17. Why nuclear technology

    International Nuclear Information System (INIS)

    Vieira, Wilson J.; Ishiguro, Yuji; Urbina, Ligia M. Soto

    1996-01-01

    The importance of nuclear energy in the global society implies the nacional need to give priority and maintain an effective technology policy for nuclear science. In this work, it is considered three points that, although do not represent all the problems in the nuclear sector, were chosen because of their importance and need of change that require: evaluation of the Brazilian scientific policy, which is directed towards the publication in international periodicals, yielding more benefits to the developed countries; evaluation of the few and small investment in laboratories and research institutes, which are the natural producers of technology for the industry and service sectors; evaluation of the lack of concrete of concrete objectives in the universities and research institutes, whose policies are elaborated with-out the due consideration of the collective benefits. It is necessary a national plan for the nuclear are that makes investments in technology development, investments in the laboratories and research institutes, and that makes these universities and research institutes accountable for the success or failure to accomplish the proposed objectives. (author)

  18. International nuclear technology transfer

    International Nuclear Information System (INIS)

    Cartwright, P.; Rocchio, J.P.

    1978-01-01

    Light water reactors (LWRs), originally developed in the United States, became the nuclear workhorses for utilities in Europe and Japan largely because the U.S. industry was willing and able to transfer its nuclear know-how abroad. In this international effort, the industry had the encouragement and support of the U.S. governement. In the case of the boiling water reactor (BWR) the program for technology transfer was developed in response to overseas customer demands for support in building local designs and manufacturing capabilities. The principal vehicles have been technology exchange agreements through which complete engineering and manufacturing information is furnished covering BWR systems and fuel. Agreements are held with companies in Germany, Japan, Italy, and Sweden. In recent years, a comprehensive program of joint technology development with overseas manufacturers has begun. The rapidly escalating cost of nuclear research and development make it desirable to minimize duplication of effort. These joint programs provide a mechanism for two or more parties jointly to plan a development program, assign work tasks among themselves, and exchange test results. Despite a slower-than-hoped-for start, nuclear power today is playing a significant role in the economic growth of some developing countries, and can continue to do so. Roughly half of the 23 free world nations that have adopted LWRs are developing countries

  19. Advanced nuclear precleaner

    Energy Technology Data Exchange (ETDEWEB)

    Wright, S.R. [InnovaTech, Inc., Durham, NC (United States)

    1997-10-01

    This Phase II Small Business Innovation Research (SBIR) program`s goal is to develop a dynamic, self-cleaning air precleaner for high-efficiency particulate air (HEPA) filtration systems that would extend significantly the life of HEPA filter banks by reducing the particulate matter that causes filter fouling and increased pack pressure. HEPA filters are widely used in DOE, Department of Defense, and a variety of commercial facilities. InnovaTech, Inc. (Formerly Micro Composite materials Corporation) has developed a proprietary dynamic separation device using a concept called Boundary Layer Momentum Transfer (BLMT) to extract particulate matter from fluid process streams. When used as a prefilter in the HVAC systems or downstream of waste vitrifiers in nuclear power plants, fuel processing facilities, and weapons decommissioning factories, the BLMT filter will dramatically extend the service life and increase the operation efficiency of existing HEPA filtration systems. The BLMT filter is self cleaning, so there will be no degraded flow or increased pressure drop. Because the BLMT filtration process is independent of temperature, it can be designed to work in ambient, medium, or high-temperature applications. During Phase II, the authors are continuing development of the computerized flow simulation model to include turbulence and incorporate expansion into a three-dimensional model that includes airflow behavior inside the filter housing before entering the active BLMT device. A full-scale (1000 ACFM) prototype filter is being designed to meet existing HEPA filter standards and will be fabricated for subsequent testing. Extensive in-house testing will be performed to determine a full range of performance characteristics. Final testing and evaluation of the prototype filter will be conducted at a DOE Quality Assurance Filter Test Station.

  20. Advanced nuclear precleaner

    International Nuclear Information System (INIS)

    Wright, S.R.

    1997-01-01

    This Phase II Small Business Innovation Research (SBIR) program's goal is to develop a dynamic, self-cleaning air precleaner for high-efficiency particulate air (HEPA) filtration systems that would extend significantly the life of HEPA filter banks by reducing the particulate matter that causes filter fouling and increased pack pressure. HEPA filters are widely used in DOE, Department of Defense, and a variety of commercial facilities. InnovaTech, Inc. (Formerly Micro Composite materials Corporation) has developed a proprietary dynamic separation device using a concept called Boundary Layer Momentum Transfer (BLMT) to extract particulate matter from fluid process streams. When used as a prefilter in the HVAC systems or downstream of waste vitrifiers in nuclear power plants, fuel processing facilities, and weapons decommissioning factories, the BLMT filter will dramatically extend the service life and increase the operation efficiency of existing HEPA filtration systems. The BLMT filter is self cleaning, so there will be no degraded flow or increased pressure drop. Because the BLMT filtration process is independent of temperature, it can be designed to work in ambient, medium, or high-temperature applications. During Phase II, the authors are continuing development of the computerized flow simulation model to include turbulence and incorporate expansion into a three-dimensional model that includes airflow behavior inside the filter housing before entering the active BLMT device. A full-scale (1000 ACFM) prototype filter is being designed to meet existing HEPA filter standards and will be fabricated for subsequent testing. Extensive in-house testing will be performed to determine a full range of performance characteristics. Final testing and evaluation of the prototype filter will be conducted at a DOE Quality Assurance Filter Test Station

  1. Nuclear Technology Programs

    International Nuclear Information System (INIS)

    Harmon, J.E.

    1990-10-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product 99 Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

  2. Nuclear Technology Programs

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. (ed.)

    1990-10-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  3. Nuclear technology programs

    International Nuclear Information System (INIS)

    Harmon, J.E.

    1992-01-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

  4. Advanced Manufacturing Technologies (AMT): Advanced Near Net Shape Technology

    Data.gov (United States)

    National Aeronautics and Space Administration — The objective of the Advanced Near Net Shape Technology (ANNST) project is to radically improve near net shape manufacturing methods from the current...

  5. Nuclear technology review 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-08-15

    The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

  6. Nuclear technology review 2004

    International Nuclear Information System (INIS)

    2004-08-01

    The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

  7. Korean experiences on nuclear power technology

    International Nuclear Information System (INIS)

    Kim, H.; Yang, H.

    1994-01-01

    This paper describes the outstanding performance of the indigenous development program of nuclear power technology such as the design and fabrication of both CANDU and PWR fuel and in the design and construction of nuclear steam supply system in Korea. The success has been accomplished through the successful technology transfer from foreign suppliers and efficient utilization of R and D manpower in the design and engineering of nuclear power projects. In order to implement the technology transfer successfully, the joint design concept has been introduced along with effective on-the-job training and the transfer of design documents and computer codes. Korea's successful development of nuclear power program has resulted in rapid expansion of nuclear power generation capacity in a short time, and the nuclear power has contributed to the national economy through lowering electricity price by about 50 % as well as stabilizing electricity supply in 1980s. The nuclear power is expected to play a key role in the future electricity supply in Korea. Now Korea is under way of taking a step toward advanced nuclear technology. The national electricity system expansion plan includes 18 more units of NPPs to be constructed by the year 2006. In this circumstance, the country has fixed the national long-term nuclear R and D program (lgg2-2001) to enhance the national capability of nuclear technology. This paper also briefly describes future prospects of nuclear technology development program in Korea

  8. Advanced fabrication technology

    International Nuclear Information System (INIS)

    Sheely, W.F.

    1986-01-01

    The Fuel Cycle Plant is a multipurpose nuclear facility located on the Hanford Nuclear Reservation in eastern Washington state. The facility is part of the Hanford Engineering Development Laboratory which is operated by Westinghouse Hanford Company for the Department of Energy. The Fuel Cycle Plant is currently being prepared to support the Liquid Metal Reactors Program with fuel fabrication services for the Fast Flux Test Facility and other LMR programs. This report describes the technical innovations to be utilized in the operation of this plant

  9. Local AREA networks in advanced nuclear reactors

    International Nuclear Information System (INIS)

    Bicknell, J.; Keats, A.B.

    1984-01-01

    The report assesses Local Area Network Communications with a view to their application in advanced nuclear reactor control and protection systems. Attention is focussed on commercially available techniques and systems for achieving the high reliability and availability required. A basis for evaluating network characteristics in terms of broadband or baseband type, medium, topology, node structure and access method is established. The reliability and availability of networks is then discussed. Several commercial networks are briefly assessed and a distinction made between general purpose networks and those suitable for process control. The communications requirements of nuclear reactor control and protection systems are compared with the facilities provided by current technology

  10. Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems

    International Nuclear Information System (INIS)

    2007-01-01

    In keeping with the 12-year history of this conference, GLOBAL 2007 focuses on future nuclear energy systems and fuel cycles. With the increasing public acceptance and political endorsement of nuclear energy, it is a pivotal time for nuclear energy research. Significant advances have been made in development of advanced nuclear fuels and materials, reactor designs, partitioning, transmutation and reprocessing technologies, and waste management strategies. In concert with the technological advances, it is more important than ever to develop sensible nuclear proliferation policies, to promote sustainability, and to continue to increase international collaboration. To further these aims, GLOBAL 2007 highlights recent developments in the following areas: advanced integrated fuel cycle concepts, spent nuclear fuel reprocessing, advanced reprocessing technology, advanced fuels and materials, advanced waste management technology, novel concepts for waste disposal and repository development, advanced reactors, partitioning and transmutation, developments in nuclear non-proliferation technology, policy, and implementation, sustainability and expanded global utilization of nuclear energy, and international collaboration on nuclear energy

  11. Advances in production technology

    CERN Document Server

    2015-01-01

    This edited volume contains the selected papers presented at the scientific board meeting of the German Cluster of Excellence on “Integrative Production Technology for High-Wage Countries”,  held in November 2014. The topical structure of the book is clustered in six sessions: Integrative Production Technology, Individualised Production, Virtual Production Systems, Integrated Technologies, Self-Optimising Production Systems and Human Factors in Production Technology. The Aachen perspective on a holistic theory of production is complemented by conference papers from external leading researchers in the fields of production, materials science and bordering disciplines. The target audience primarily comprises research experts and practitioners in the field but the book may also be beneficial for graduate students.

  12. Current status and future potential for advanced volume reduction technologies

    International Nuclear Information System (INIS)

    Rutland, L.; Naughton, M.D.; Papaiya, N.C.

    1984-01-01

    With escalating costs for disposal of low-level radioactive waste (LLW) from nuclear power plants, and the possibility of unavailability of disposal space, some nuclear power utilities responded by commiting to implementing advanced volume reduction (VR) systems. This paper presents recent experience to implement advanced volume reduction technologies; their performance and typical operating and capital costs. This experience in the light of current economic conditions may enable us to predict the direction that future advanced VR technology commitments is taking

  13. The dynomak: An advanced spheromak reactor concept with imposed-dynamo current drive and next-generation nuclear power technologies

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, D.A., E-mail: das1990@uw.edu; Jarboe, T.R.; Morgan, K.D.; Pfaff, M.; Lavine, E.S.; Kamikawa, Y.; Hughes, M.; Andrist, P.; Marklin, G.; Nelson, B.A.

    2014-04-15

    A high-β spheromak reactor concept has been formulated with an estimated overnight capital cost that is competitive with conventional power sources. This reactor concept utilizes recently discovered imposed-dynamo current drive (IDCD) and a molten salt (FLiBe) blanket system for first wall cooling, neutron moderation and tritium breeding. Currently available materials and ITER-developed cryogenic pumping systems were implemented in this concept from the basis of technological feasibility. A tritium breeding ratio (TBR) of greater than 1.1 has been calculated using a Monte Carlo N-Particle (MCNP5) neutron transport simulation. High temperature superconducting tapes (YBCO) were used for the equilibrium coil set, substantially reducing the recirculating power fraction when compared to previous spheromak reactor studies. Using zirconium hydride for neutron shielding, a limiting equilibrium coil lifetime of at least thirty full-power years has been achieved. The primary FLiBe loop was coupled to a supercritical carbon dioxide Brayton cycle due to attractive economics and high thermal efficiencies. With these advancements, an electrical output of 1000 MW from a thermal output of 2486 MW was achieved, yielding an overall plant efficiency of approximately 40%.

  14. Operational Leadership and Advancing Technology

    Science.gov (United States)

    2009-05-04

    leadership , most agree that leadership , especially military leadership , is not synonymous with “ management .” 9 Managers often focus solely on...FINAL 3. DATES COVERED (From - To) 9 Feb – 4 May 2009 4. TITLE AND SUBTITLE Operational Leadership and Advancing Technology 5a...operational leader must use his authority and leadership skills to get by in from all concerned to maximize technological advances. 15. SUBJECT TERMS

  15. Advanced technology composite aircraft structures

    Science.gov (United States)

    Ilcewicz, Larry B.; Walker, Thomas H.

    1991-01-01

    Work performed during the 25th month on NAS1-18889, Advanced Technology Composite Aircraft Structures, is summarized. The main objective of this program is to develop an integrated technology and demonstrate a confidence level that permits the cost- and weight-effective use of advanced composite materials in primary structures of future aircraft with the emphasis on pressurized fuselages. The period from 1-31 May 1991 is covered.

  16. Experience in transfer of nuclear technology

    International Nuclear Information System (INIS)

    Beckurts, K.H.

    1977-01-01

    Nuclear energy development in the Federal Republic of Germany was initiated in 1955. In spite of this late start, the country now has a broad potential in all branches of peaceful nuclear technology. Turkey nuclear power plants are erected by German industry, and the country has the basic technology at its disposal for all stages of the nuclear fuel cycle. In the areas of uranium enrichment and reprocessing, multilateral joint ventures with European countries have been formed. The country also has an active development program for advanced reactors. In general areas of technology transfer and development aid, in the nuclear field, there are interrelated activities of both government and industry. The government has concluded bilateral agreements with a number of countires e.g. Argentina, Brazil, India, Iran and Pakistan, covering the general field of nuclear science; in the framework of these agreements, which are being carried out mainly by the nuclear research centers at Juelich and Karlsruhe, active cooperation in research, development, education, and training are being pursued. The nonproliferation of nuclear weapons is a major objective of the Federal government which strongly affects its policies for international nuclear trade. The paper describes the nuclear technology potential available in the Federal Republic of Germany and reviews experience gathered in cooperation with developing countries. Future policies for nuclear technology transfer are discussed with special reference to the role of national R and D laboratories

  17. Technological Advances in Joining

    Science.gov (United States)

    1981-08-01

    joint with the progressively advancing laser beam. Surface tension forces support the molten metal and close the keyhole behind the moving be:zm. Deep... keyhole welds in much the same manner as the electron beam which it so closely resembles. Low-power lasers rated at 1000 watts or less are used for...welding, the arc penetrates through the base metal to form the keyhole . Surface tension forces close the keyhole behind the arc as it progresses along

  18. Nuclear power reactor technology

    International Nuclear Information System (INIS)

    1978-09-01

    Risoe National Laboratory was established more than twenty years ago with research and development of nuclear reactor technology as its main objective. The Laboratory has by now accumulated many years of experience in a number of areas vital to nuclear reactor technology. The work and experience of, and services offered by the Laboratory within the following fields are described: Health physics site supervision; Treatment of low and medium level radioactive waste; Core performance evaluation; Transient analysis; Accident analysis; Fuel management; Fuel element design, fabrication and performance evaluation; Non-destructive testing of nuclear fuel; Theoretical and experimental structural analysis; Reliability analysis; Site evaluation. Environmental risk and hazard calculation; Review and analysis of safety documentation. Risoe has already given much assistance to the authorities, utilities and industries in such fields, carrying out work on both light and heavy water reactors. The Laboratory now offers its services to others as a consultant, in education and training of staff, in planning, in qualitative and quantitative analysis, and for the development and specification of fabrication techniques. (author)

  19. Non-proliferation and advances in nuclear science

    International Nuclear Information System (INIS)

    Iyengar, P.K.

    1995-01-01

    So far, the non-proliferation treaty (NPT) has concentrated on safeguard regimes based on technologies relating to the production of uranium and plutonium in nuclear reactors, and on their potential diversion for use in nuclear weapons. As nuclear science advances, however, nuclear technology both peaceful and for weapons will change, and for the NPT to remain relevant, it must reflect these changes. At this juncture, when the NPT is coming up for review in a year's time, it is important for physicists to take a fresh look at recent advances in nuclear science, and inform the policy-makers and the public at large about their potential for impacting nuclear technology in the future. In this article a few such advances are highlighted and their implications for the NPT are considered. (author). 4 refs

  20. Advanced technology in neurosurgery

    International Nuclear Information System (INIS)

    Pluchino, F.; Broggi, G.

    1987-01-01

    Technological improvements in neurosurgery are discussed. The use of surgical lasers, ultrasound aspirators, bipolar coagulator and operative microscopes for surgery of deep-seated neoplasms and vascular malformations is discussed. Intraoperative monitoring, chronotherapy, chronic neurostimulation and stereotactic interstitial irradiation are covered and indications for interventional neuroradiology are reviewed

  1. New technologies deployment for advanced power plants

    International Nuclear Information System (INIS)

    Kiyoshi, Yamauchi

    2007-01-01

    Mitsubishi Heavy Industries, Ltd. (MHI) has been the total engineering and manufacturing company of pressurized water reactors (PWRs) in Japan since the commencement of commercial operations of Mihama Unit 1 of the Kansai Electric Power Company in 1970. Over these decades, MHI has endeavored to develop a broad spread of nuclear technology, from design, manufacturing, and construction, to plant maintenance services. More recently, with the ever rising need for nuclear power generation around the world to prevent global warming and to cope with surging oil prices, MHI is striving to expand its nuclear power business in the world market, such as US-APWR (Advanced Pressurized Water Reactor) in the U.S., as well as to develop technology for advanced reactors and nuclear fuel cycles to ensure energy security in the future. This paper introduces these approaches, especially focused on new technologies deployment for the global needs, and clarifies the current status and future prospects of MHI as the world's leading nuclear company. (author)

  2. Nuclear energy and nuclear technology

    International Nuclear Information System (INIS)

    Luescher, E.

    1982-01-01

    This book originated in the training courses for teachers of grammar- and secondary schools in Dillingen (Bavaria). The aim of these courses is to become informed about the latest state in one field of physics. The lectures are well-known experts in the respective fields. In the latest study (1980) of the National Academy of Sciences the experts came to the conclusion that without further development nuclear power plants the utilization of too much coal would become necessary and involve irreversible environmental damage (see chapter 6). There are two important obstacles impeding the further extension of nuclear energy. The first problem to be solved is the processing and storage of radioactive waste. This is a more technical task and can be treated in a satisfactory way. The second obstacle is less easy to take as the population has to be convinced that a nuclear power plant can be operated with almost unbelievable safety (see chapter 5) and be shut down safely in the case of incidents. The most promising possibility of controlled nuclear fusion as energy source is still many decades- if feasible at all- away from being performed (see chapter. 7). In the Soviet Union 25% of the electric energy production shall be proceed from nuclear power plants by the year 1990. (orig./GL) [de

  3. Analysis on Japanese nuclear industrial technologies and their military implications

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H S; Yang, M H; Kim, H J. and others

    2000-10-01

    This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months.

  4. Analysis on Japanese nuclear industrial technologies and their military implications

    International Nuclear Information System (INIS)

    Kim, H. S.; Yang, M. H.; Kim, H. J. and others

    2000-10-01

    This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months

  5. Analysis on Japanese nuclear industrial technologies and their military implications

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. S.; Yang, M. H.; Kim, H. J. and others

    2000-10-01

    This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months.

  6. Equipment system for advanced nuclear fuel development

    International Nuclear Information System (INIS)

    Kwon, Hyuk Il; Ji, C. G.; Bae, S. O.

    2002-11-01

    The purpose of the settlement of equipment system for nuclear Fuel Technology Development Facility(FTDF) is to build a seismic designed facility that can accommodate handling of nuclear materials including <20% enriched Uranium and produce HANARO fuel commercially, and also to establish the advanced common research equipment essential for the research on advanced fuel development. For this purpose, this research works were performed for the settlement of radiation protection system and facility special equipment for the FTDF, and the advanced common research equipment for the fuel fabrication and research. As a result, 11 kinds of radiation protection systems such as criticality detection and alarm system, 5 kinds of facility special equipment such as environmental pollution protection system and 5 kinds of common research equipment such as electron-beam welding machine were established. By the settlement of exclusive domestic facility for the research of advanced fuel, the fabrication and supply of HANARO fuel is possible and also can export KAERI-invented centrifugal dispersion fuel materials and its technology to the nations having research reactors in operation. For the future, the utilization of the facility will be expanded to universities, industries and other research institutes

  7. A Study on Nuclear Technology Policy

    International Nuclear Information System (INIS)

    Oh, K. B.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik; Lee, J. H.

    2006-02-01

    This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. In the investigation and analysis of international environmental and technological change 1. Viability of Nuclear Renaissance 2. Recent of Nuclear Technology Policy in Japan 3. Collaboration for Advanced Nuclear Technologies in GIF, INPRO and INERI 4. Nuclear Energy Utilization and Development in Europe. In the evaluation of nuclear technology and sustainable development from the point of views of environmental change 5. External Cost of Environmental Impact in Electric Power Sector 6. Nuclear Technology Development Direction Considering Changes of the Science and Technology Policy Environment 7. Nuclear Energy Development Strategy for a Sustainable National Energy Supply

  8. A Study on Nuclear Technology Policy

    Energy Technology Data Exchange (ETDEWEB)

    Oh, K B; Chung, W S; Lee, T J; Yun, S W; Jeong, Ik; Lee, J H

    2006-02-15

    This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. In the investigation and analysis of international environmental and technological change 1. Viability of Nuclear Renaissance 2. Recent of Nuclear Technology Policy in Japan 3. Collaboration for Advanced Nuclear Technologies in GIF, INPRO and INERI 4. Nuclear Energy Utilization and Development in Europe. In the evaluation of nuclear technology and sustainable development from the point of views of environmental change 5. External Cost of Environmental Impact in Electric Power Sector 6. Nuclear Technology Development Direction Considering Changes of the Science and Technology Policy Environment 7. Nuclear Energy Development Strategy for a Sustainable National Energy Supply.

  9. Advances in Machine Technology.

    Science.gov (United States)

    Clark, William R; Villa, Gianluca; Neri, Mauro; Ronco, Claudio

    2018-01-01

    Continuous renal replacement therapy (CRRT) machines have evolved into devices specifically designed for critically ill over the past 40 years. In this chapter, a brief history of this evolution is first provided, with emphasis on the manner in which changes have been made to address the specific needs of the critically ill patient with acute kidney injury. Subsequently, specific examples of technology developments for CRRT machines are discussed, including the user interface, pumps, pressure monitoring, safety features, and anticoagulation capabilities. © 2018 S. Karger AG, Basel.

  10. Nuclear science and technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Program on Nuclear Science and Technology comprehends Nuclear and Condensed Matter Physics, Neutron Activation Analysis, Radiation Metrology, Radioprotection and Radioactive Waste Management. These activities are developed at the Research Reactor Center, the Radiation Metrology Center and the Radioactive Waste Management Laboratory. The Radioprotection activities are developed at all radioactive and nuclear facilities of IPEN-CNEN/SP. The Research Reactor Center at IPEN-CNEN/SP is responsible for the operation and maintenance of the Research Reactor IEA-R1 and has a three-fold mission: promoting basic and applied research in nuclear and neutron related sciences, providing educational opportunities for students in these fields and providing services and applications resulting from the reactor utilization. Specific research programs include nuclear structure study from beta and gamma decay of radioactive nuclei and nuclear reactions, nuclear and neutron metrology, neutron diffraction and neutron multiple-diffraction study for crystalline and magnetic structure determination, perturbed -angular correlation (PAC) using radioactive nuclear probes to study the nuclear hyperfine interactions in solids and instrumental neutron activation analysis, with comparative or ko standardization applied to the fields of health, agriculture, environment, archaeology, reference material production, geology and industry. The research in the areas of applied physics includes neutron radiography, scientific computation and nuclear instrumentation. During the last several years a special effort was made to refurbish the old components and systems of the reactor, particularly those related with the reactor safety improvement, in order to upgrade the reactor power. The primary objective was to modernize the IEA-R1 reactor for safe and sustainable operation to produce primary radioisotopes, such as {sup 99}Mo and {sup 131}I, among several others, used in nuclear medicine, by operating

  11. Nuclear science and technology

    International Nuclear Information System (INIS)

    2014-01-01

    The Program on Nuclear Science and Technology comprehends Nuclear and Condensed Matter Physics, Neutron Activation Analysis, Radiation Metrology, Radioprotection and Radioactive Waste Management. These activities are developed at the Research Reactor Center, the Radiation Metrology Center and the Radioactive Waste Management Laboratory. The Radioprotection activities are developed at all radioactive and nuclear facilities of IPEN-CNEN/SP. The Research Reactor Center at IPEN-CNEN/SP is responsible for the operation and maintenance of the Research Reactor IEA-R1 and has a three-fold mission: promoting basic and applied research in nuclear and neutron related sciences, providing educational opportunities for students in these fields and providing services and applications resulting from the reactor utilization. Specific research programs include nuclear structure study from beta and gamma decay of radioactive nuclei and nuclear reactions, nuclear and neutron metrology, neutron diffraction and neutron multiple-diffraction study for crystalline and magnetic structure determination, perturbed -angular correlation (PAC) using radioactive nuclear probes to study the nuclear hyperfine interactions in solids and instrumental neutron activation analysis, with comparative or ko standardization applied to the fields of health, agriculture, environment, archaeology, reference material production, geology and industry. The research in the areas of applied physics includes neutron radiography, scientific computation and nuclear instrumentation. During the last several years a special effort was made to refurbish the old components and systems of the reactor, particularly those related with the reactor safety improvement, in order to upgrade the reactor power. The primary objective was to modernize the IEA-R1 reactor for safe and sustainable operation to produce primary radioisotopes, such as 99 Mo and 131 I, among several others, used in nuclear medicine, by operating the reactor

  12. An overview of advanced power generation technologies

    International Nuclear Information System (INIS)

    Gardner, D.; Shaw, P.

    1993-01-01

    This paper is intended as a brief review of the technologies currently applied in Australian electricity generation and the technologies which are likely to be employed in the future. The paper opens with a review of the primary energy resources available for the generation of electricity in Australia, and the technologies currently employed. The development of advanced generation technologies around the world is reviewed, and the most likely technologies to be employed in Australia are described. There are a number of renewable and alternative technologies, such as generation from sewage digester, landfill or mine gases. Their impact would, however, be disproportionate because of the strong climate forcing effect of methane. Of the wide range of other emerging renewable technologies examined, solar thermal offers the best prospect of maturing into a financially-competitive technology for large scale generation in the next 20 years. However, will remain unable to compete with non-renewable technologies in normal financial terms, at least until 2005 and probably well beyond that date. Generation using the fission of nuclear fuels is a mature, proven technology. Based on the most likely fuel and other assumptions made in this study, the costs of nuclear generation are only moderately higher than conventional coal-fired options. Nuclear generation is thus a relatively low cost route to reductions in carbon dioxide emission for new plant, at $19/tonne CO 2 saved, in comparison with conventional black coal technology, and $13/tonne CO 2 compared with conventional brown coal firing. While major considerations of societal acceptance clearly exist, nuclear generation has the necessary technical and financial qualifications for serious consideration as an element in any greenhouse strategy. 5 tab., 2 figs

  13. [Technological advances in neurorehabilitation].

    Science.gov (United States)

    Gutiérrez-Martínez, Josefina; Núñez-Gaona, Marco Antonio; Carrillo-Mora, Paul

    2014-07-01

    Neurological rehabilitation arose as formal method in the 60's, for the therapeutic treatment of patients with stroke or spinal cord injury, which develop severe sequelae that affect their motor and sensory abilities. Although the Central Nervous System has plasticity mechanisms for spontaneous recovery, a high percentage of patients should receive specialized therapies to regain motor function, such as Constraint Induced Movement Therapy or Upright physical Therapy. The neurorehabilitation has undergone drastic changes over the last two decades due to the incorporation of computer and robotic electronic devices, designed to produce positive changes in cortical excitability of the cerebral hemisphere damaged and so to improve neuroplasticity. Among equipment, we can mention those for electrotherapy devices, apparatus for transcranial magnetic stimulation, the robotic lower limb orthoses, robot for upper limb training, systems for functional electrical stimulation, neuroprosthesis and brain computer interfaces. These devices have caused controversy because of its application and benefits reported in the literature. The aim of Neurorehabilitation technologies is to take advantage of the functional neuromuscular structures preserved, and they compensate or re-learn the functions that previously made the damaged areas. The purpose of this article is to mention some clinical applications and benefits that these technologies offer to patients with neuronal injury.

  14. Recent Advances in Ocean Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Kang-Heon Lee

    2015-10-01

    Full Text Available In this paper, recent advances in Ocean Nuclear Power Plants (ONPPs are reviewed, including their general arrangement, design parameters, and safety features. The development of ONPP concepts have continued due to initiatives taking place in France, Russia, South Korea, and the United States. Russia’s first floating nuclear power stations utilizing the PWR technology (KLT-40S and the spar-type offshore floating nuclear power plant designed by a research group in United States are considered herein. The APR1400 and SMART mounted Gravity Based Structure (GBS-type ONPPs proposed by a research group in South Korea are also considered. In addition, a submerged-type ONPP designed by DCNS of France is taken into account. Last, issues and challenges related to ONPPs are discussed and summarized.

  15. Advances in chemical engineering in nuclear and process industries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    Symposium on Advances in Chemical Engineering in Nuclear and Process Industries dealt with a wide spectrum of areas encompassing various industries such as nuclear, fertilizer, petrochemical, refinery and cement. The topics covered in the symposium dealt with the advancements in the existing fields of science and technologies as well as in some of the emerging technologies such as membrane technology, bio-chemical and photo-chemical engineering etc. with a special emphasis on nuclear related aspects. Papers relevant to INIS are indexed separately.

  16. Advances in chemical engineering in nuclear and process industries

    International Nuclear Information System (INIS)

    1994-06-01

    Symposium on Advances in Chemical Engineering in Nuclear and Process Industries dealt with a wide spectrum of areas encompassing various industries such as nuclear, fertilizer, petrochemical, refinery and cement. The topics covered in the symposium dealt with the advancements in the existing fields of science and technologies as well as in some of the emerging technologies such as membrane technology, bio-chemical and photo-chemical engineering etc. with a special emphasis on nuclear related aspects. Papers relevant to INIS are indexed separately

  17. Advanced information technology

    International Nuclear Information System (INIS)

    Andersen, V.

    1988-06-01

    The potential risk of critical situations at hazardous industrial plants has drawn increased attention to emergency organisations. The emphasis on these organisations is to minimise the environmental effects of serious, although unlikely, disturbances in operation. Experience gained from previous incidents and emergency drills has revealed the complexity that must be faced in making these organisations work properly. Modern information technology may be used in order to develop more reliable preparedness systems. These problems are being treated in a joint Nordic project, NKA/INF, with participating research institutes from Denmark, Finland, Norway, and Sweden. The project started in 1985 and is expected to be finished in 1989. This report gives an overview of the project and a short description of the conceptual ideas behind the project. (author)

  18. Proceedings of national symposium on advanced instrumentation for nuclear research

    International Nuclear Information System (INIS)

    1993-01-01

    The National Symposium on Advanced Instrumentation for Nuclear Research was held in Bombay during January 27-29, 1993 at BARC. Progress of modern nuclear research is closely related to the availability of state of the art instruments and systems. With the advancements in experimental techniques and sophisticated detector developments, the performance specifications have become more stringent. State of the art techniques and diverse applications of sophisticated nuclear instrumentation systems are discussed along with indigenous efforts to meet the specific instrumentation needs of research programs in nuclear sciences. Papers of relevance to nuclear science and technology are indexed separately. (original)

  19. Innovation in nuclear technology

    International Nuclear Information System (INIS)

    Bertel, E.

    2007-01-01

    Innovation has been a driving force for the success of nuclear energy and remains essential for its future. For the continued safe and economically effective operation and maintenance of existing nuclear systems, and to meet the goals set out by projects aiming at designing and implementing advanced systems for the future, efficient innovation systems are needed. Consequently, analysing innovation systems is essential to understand their characteristics and enhance their performance in the nuclear sector. Lessons learnt from innovation programmes that have already been completed can help enhance the effectiveness of future programmes. The analysis of past experience provides a means for identifying causes of failure as well as best practices. Although national and local conditions are important factors, the main drivers for the success of innovative endeavors are common to all countries. Cooperation and coordination among the various actors are major elements promoting success. All interested stakeholders, including research organisations, industrial actors, regulators and civil society, have a role to play in supporting the success of innovation, but governments are an essential trigger, especially for projects with long durations and very ambitious objectives. Governments have a major role to play in promoting innovation because they are responsible for the overall national energy policy which sets the stage for the eventual deployment of innovative products and processes. Moreover, only governments can create the stable legal and regulatory framework favourable to the undertaking and successful completion of innovation programmes. International organisations such as the NEA may help enhance the effectiveness of national policies and innovation programmes by providing a forum for exchanging information, facilitating multilateral collaboration and joint endeavors, and offering technical support for the management of innovative programmes

  20. Nuclear medicine technology study guide

    CERN Document Server

    Patel, Dee

    2011-01-01

    Nuclear Medicine Technology Study Guide presents a comprehensive review of nuclear medicine principles and concepts necessary for technologists to pass board examinations. The practice questions and content follow the guidelines of the Nuclear Medicine Technology Certification Board (NMTCB) and American Registry of Radiological Technologists (ARRT), allowing test takers to maximize their success in passing the examinations. The book is organized by sections of increasing difficulty, with over 600 multiple-choice questions covering all areas of nuclear medicine, including radiation safety; radi

  1. Contributions of the National Institute of Nuclear Research to the advance of Science and Technology in Mexico. Commemorative edition 2010; Contribuciones del Instituto Nacional de Investigaciones Nucleares al avance de la ciencia y la tecnologia en Mexico. Edicion conmemorativa 2010

    Energy Technology Data Exchange (ETDEWEB)

    Duque M, G.; Jimenez R, M.; Monroy G, F.; Romero H, S.; Serment G, J. (ed.) [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    From the second decade of the X X century the applications of the nuclear energy have been important part of the scientific and technological patrimony in Mexico. Records exist with regard to the use of the radioisotopes and the radiations in our country in that time, and in a formal way until the year of 1950, in a process that culminates with the creation of the Comision Nacional de Energia Nuclear (CNEN. January 1, 1956). In January 12, 1972 were published the Organic Law that created to the Instituto Nacional de Energia Nuclear, being responsible for the works that the CNEN developed. The current Instituto Nacional de Investigaciones Nucleares (ININ) was constituted starting from the Regulation Law of the constitutional Article 27 in nuclear matter of January 26, 1979, abrogated and substituted by the Law in force of February 4, 1985. In this lapse they were undertaken multitude of projects with results and diverse achievements. From their creation, the mission of the ININ and the previous institutions has been to realize research in science and nuclear technology, to promote their peaceful uses and to diffuse the achieved advances, always searching for to link them to the economic, social, scientific and technological development of the country. In this occasion with the purpose of participating in the commemoration of the bicentennial of the independence and centennial of the Mexican revolution in our country, the ININ decided to publish this work, directed to a wide public, with the intention of providing a vision the most complete and appropriate possible of the activities in research and technology that it is carries out at the moment. This work also seeks to be a diffusion instrument of the tasks that they are carried out in the institute, in diverse subjects as: the basic research, the nuclear applications in the health, the agriculture and the industry, the studies on the contamination and the environment; the dosimetry; the radiological protection; as

  2. To MARS and Beyond with Nuclear Power - Design Concept of Korea Advanced Nuclear Thermal Engine Rocket

    International Nuclear Information System (INIS)

    Nam, Seung Hyun; Chang, Soon Heung

    2013-01-01

    The President Park of ROK has also expressed support for space program promotion, praising the success of NARO as evidence of a positive outlook. These events hint a strong signal that ROK's space program will be accelerated by the national eager desire. In this national eager desire for space program, the policymakers and the aerospace engineers need to pay attention to the advanced nuclear technology of ROK that is set to a major world nuclear energy country, even exporting the technology. The space nuclear application is a very much attractive option because its energy density is the most enormous among available energy sources in space. This paper presents the design concept of Korea Advanced Nuclear Thermal Engine Rocket (KANuTER) that is one of the advanced nuclear thermal rocket engine developing in Korea Advanced Institute of Science and Technology (KAIST) for space application. Solar system exploration relying on CRs suffers from long trip time and high cost. In this regard, nuclear propulsion is a very attractive option for that because of higher performance and already demonstrated technology. Although ROK was a late entrant into elite global space club, its prospect as a space racer is very bright because of the national eager desire and its advanced technology. Especially it is greatly meaningful that ROK has potential capability to launch its nuclear technology into space as a global nuclear energy leader and a soaring space adventurer. In this regard, KANuTER will be a kind of bridgehead for Korean space nuclear application

  3. To MARS and Beyond with Nuclear Power - Design Concept of Korea Advanced Nuclear Thermal Engine Rocket

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Seung Hyun; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2013-05-15

    The President Park of ROK has also expressed support for space program promotion, praising the success of NARO as evidence of a positive outlook. These events hint a strong signal that ROK's space program will be accelerated by the national eager desire. In this national eager desire for space program, the policymakers and the aerospace engineers need to pay attention to the advanced nuclear technology of ROK that is set to a major world nuclear energy country, even exporting the technology. The space nuclear application is a very much attractive option because its energy density is the most enormous among available energy sources in space. This paper presents the design concept of Korea Advanced Nuclear Thermal Engine Rocket (KANuTER) that is one of the advanced nuclear thermal rocket engine developing in Korea Advanced Institute of Science and Technology (KAIST) for space application. Solar system exploration relying on CRs suffers from long trip time and high cost. In this regard, nuclear propulsion is a very attractive option for that because of higher performance and already demonstrated technology. Although ROK was a late entrant into elite global space club, its prospect as a space racer is very bright because of the national eager desire and its advanced technology. Especially it is greatly meaningful that ROK has potential capability to launch its nuclear technology into space as a global nuclear energy leader and a soaring space adventurer. In this regard, KANuTER will be a kind of bridgehead for Korean space nuclear application.

  4. Advanced digital I and C technology in nuclear power plants. A success story from Finland and China

    International Nuclear Information System (INIS)

    Liebschner, T.; Heidowitzsch, B.

    2005-01-01

    FRAMATOME ANP together with Siemens PGL have just commissioned the I and C systems for the Chinese Nuclear Power Plant Tianwan Unit 1, design the I and C systems for the first European Pressurized Water Reactor Olkiluoto 3 in Finland and started one of the most extensive and ambitious modernization project in a nuclear power plant for Loviisa NPP in Finland. The presentation delivers an insight into the problematic of digital I and C systems integration and focuses on aspects regarding design criteria, Structure and test approaches. (author)

  5. Advanced Operating System Technologies

    Science.gov (United States)

    Cittolin, Sergio; Riccardi, Fabio; Vascotto, Sandro

    . Our work started in the second half of 1994, with a research agreement between CERN and Chorus Systemes (France), world leader in the micro-kernel OS technology. The Chorus OS is targeted to distributed real-time applications, and it can very efficiently support different "OS personalities" in the same environment, like Posix, UNIX, and a CORBA compliant distributed object architecture. Projects are being set-up to verify the suitability of our work for LHC applications, we are building a scaled-down prototype of the DAQ system foreseen for the CMS experiment at LHC, where we will directly test our protocols and where we will be able to make measurements and benchmarks, guiding our development and allowing us to build an analytical model of the system, suitable for simulation and large scale verification.

  6. Advanced design and construction technology for ABWR

    International Nuclear Information System (INIS)

    Kawahara, Akira

    2003-01-01

    Recently, many countries start planning to construct nuclear plants, and the electric power companies and the plant suppliers are acutely aware of the importance of the technical infrastructure required for construction planning and execution as this has a significant influence on construction costs. Plant suppliers in Japan have been focusing its attention on the efficiency of construction from earlier, because of its significant role in determining overall construction costs. Through continuous efforts to reduce fieldwork costs, we have developed unique technologies, especially the 3D-CAD system and other advanced construction technologies including modularization. We, plant suppliers are now turning its attention to overseas nuclear plants construction also, and are developing more rational, economical, and global construction based on its vast experience in construction techniques. In this report, the evolution of plant engineering methods and construction technologies, the present level of progress in construction, and technical developments for the future, are described. (author)

  7. Advanced Technology for Engineering Education

    Science.gov (United States)

    Noor, Ahmed K. (Compiler); Malone, John B. (Compiler)

    1998-01-01

    This document contains the proceedings of the Workshop on Advanced Technology for Engineering Education, held at the Peninsula Graduate Engineering Center, Hampton, Virginia, February 24-25, 1998. The workshop was jointly sponsored by the University of Virginia's Center for Advanced Computational Technology and NASA. Workshop attendees came from NASA, other government agencies, industry and universities. The objectives of the workshop were to assess the status of advanced technologies for engineering education and to explore the possibility of forming a consortium of interested individuals/universities for curriculum reform and development using advanced technologies. The presentations covered novel delivery systems and several implementations of new technologies for engineering education. Certain materials and products are identified in this publication in order to specify adequately the materials and products that were investigated in the research effort. In no case does such identification imply recommendation or endorsement of products by NASA, nor does it imply that the materials and products are the only ones or the best ones available for this purpose. In many cases equivalent materials and products are available and would probably produce equivalent results.

  8. Advanced nuclear reactor safety issues and research needs

    International Nuclear Information System (INIS)

    2002-01-01

    On 18-20 February 2002, the OECD Nuclear Energy Agency (NEA) organised, with the co-sponsorship of the International Atomic Energy Agency (IAEA) and in collaboration with the European Commission (EC), a Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Currently, advanced nuclear reactor projects range from the development of evolutionary and advanced light water reactor (LWR) designs to initial work to develop even further advanced designs which go beyond LWR technology (e.g. high-temperature gas-cooled reactors and liquid metal-cooled reactors). These advanced designs include a greater use of advanced technology and safety features than those employed in currently operating plants or approved designs. The objectives of the workshop were to: - facilitate early identification and resolution of safety issues by developing a consensus among participating countries on the identification of safety issues, the scope of research needed to address these issues and a potential approach to their resolution; - promote the preservation of knowledge and expertise on advanced reactor technology; - provide input to the Generation IV International Forum Technology Road-map. In addition, the workshop tried to link advancement of knowledge and understanding of advanced designs to the regulatory process, with emphasis on building public confidence. It also helped to document current views on advanced reactor safety and technology, thereby contributing to preserving knowledge and expertise before it is lost. (author)

  9. The United States Advanced Reactor Technologies Research and Development Program

    International Nuclear Information System (INIS)

    O’Connor, Thomas J.

    2014-01-01

    The following aspects are addressed: • Nuclear energy mission; • Reactor research development and deployment (RD&D) programs: - Light Water Reactor Sustainability Program; - Small Modular Reactor Licensing Technical Support; - Advanced Reactor Technologies (ART)

  10. Advanced LWR Nuclear Fuel Cladding Development

    International Nuclear Information System (INIS)

    Bragg-Sitton, S.; Griffith, G.

    2012-01-01

    The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R and D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental enhancements are required in the areas of nuclear fuel composition, cladding integrity, and fuel/cladding interaction to allow improved fuel economy via power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an 'accident tolerant' fuel system that would offer improved coping time under accident scenarios. In a staged development approach, the LWRS program will engage stakeholders throughout the development process to ensure commercial viability of the investigated technologies. Applying minimum performance criteria, several of the top-ranked materials and fabrication concepts will undergo a rigorous series of mechanical, thermal and chemical characterization tests to better define their properties and operating potential in a relatively low-cost, nonnuclear test series. A reduced number of options will be recommended for test rodlet fabrication and in-pile nuclear testing under steady-state, transient and accident conditions. (author)

  11. Advanced nuclear plant control complex

    International Nuclear Information System (INIS)

    Scarola, K.; Jamison, S.; Manazir, R.M.; Rescorl, R.L.; Harmon, D.L.

    1991-01-01

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

  12. Next generation advanced nuclear reactor designs

    International Nuclear Information System (INIS)

    Turgut, M. H.

    2009-01-01

    Growing energy demand by technological developments and the increase of the world population and gradually diminishing energy resources made nuclear power an indispensable option. The renewable energy sources like solar, wind and geothermal may be suited to meet some local needs. Environment friendly nuclear energy which is a suitable solution to large scale demands tends to develop highly economical, advanced next generation reactors by incorporating technological developments and years of operating experience. The enhancement of safety and reliability, facilitation of maintainability, impeccable compatibility with the environment are the goals of the new generation reactors. The protection of the investment and property is considered as well as the protection of the environment and mankind. They became economically attractive compared to fossil-fired units by the use of standard designs, replacing some active systems by passive, reducing construction time and increasing the operation lifetime. The evolutionary designs were introduced at first by ameliorating the conventional plants, than revolutionary systems which are denoted as generation IV were verged to meet future needs. The investigations on the advanced, proliferation resistant fuel cycle technologies were initiated to minimize the radioactive waste burden by using new generation fast reactors and ADS transmuters.

  13. National Nuclear Technology Map Development

    International Nuclear Information System (INIS)

    Shin, J. I.; Lee, T. J.; Yoon, S. W.

    2005-03-01

    The objective of NuTRM is to prepare a plan of nuclear R and D and technological innovations which is very likely to make nuclear technology a promising power source for future national developments. The NuTRM finds out systematically the nuclear R and D vision and the high-value-added strategic technologies to be developed by the efficient cooperation of actors including government, industry, academy and research institute by 2020. In other words, NuTRM aims at a long-term strategic planning of nuclear R and D and technological innovation in order to promote the socio-economic contributions of nuclear science and technology for the nation's future competitiveness and sustainable development and to raise the global status of the Korean nuclear R and D and Industry

  14. Proceedings of the conference on recent advances in information technology

    International Nuclear Information System (INIS)

    1999-10-01

    Twentieth century has witnessed remarkable advancements that have brought out lasting changes in all the fields of science and technology. The most important advancements are in the field of information technology (IT), which has revolutionized the entire fabric of our life, including nuclear science and technology. It is clear that IT will continue to be one of the fertile areas for scientific and technological developments and this conference proceedings deal with the latest trends in IT applied to information centres dealing with nuclear technology. Papers relevant to INIS are indexed separately

  15. Modern Imaging Technology: Recent Advances

    International Nuclear Information System (INIS)

    Welch, Michael J.; Eckelman, William C.

    2004-01-01

    This 2-day conference is designed to bring scientist working in nuclear medicine, as well as nuclear medicine practitioners together to discuss the advances in four selected areas of imaging: Biochemical Parameters using Small Animal Imaging, Developments in Small Animal PET Imaging, Cell Labeling, and Imaging Angiogenesis Using Multiple Modality. The presentations will be on molecular imaging applications at the forefront of research, up to date on the status of molecular imaging in nuclear medicine as well as in related imaging areas. Experts will discuss the basic science of imaging techniques, and scheduled participants will engage in an exciting program that emphasizes the current status of molecular imaging as well as the role of DOE funded research in this area

  16. Handbook of advanced lighting technology

    CERN Document Server

    Sun, Ching-Cherng; Zissis, Georges; Ma, Ruiqing

    2017-01-01

    The Handbook of Advanced Lighting Technology is a major reference work on the subject of light source science and technology, with particular focus on solid-state light sources – LEDs and OLEDs – and the development of 'smart' or 'intelligent' lighting systems; and the integration of advanced light sources, sensors, and adaptive control architectures to provide tailored illumination which is 'fit to purpose.' The concept of smart lighting goes hand-in-hand with the development of solid-state light sources, which offer levels of control not previously available with conventional lighting systems. This has impact not only at the scale of the individual user, but also at an environmental and wider economic level. These advances have enabled and motivated significant research activity on the human factors of lighting, particularly related to the impact of lighting on healthcare and education, and the Handbook provides detailed reviews of work in these areas. The potential applications for smart lighting span ...

  17. An Effective Method For Nuclear Technology Transfer

    International Nuclear Information System (INIS)

    Jeon, Jan Pung

    1987-01-01

    Three basic entities involved in the implementation of nuclear projects are the Owner, Regulatory Authority and Nuclear Industry. Their ultimate objective is to secure the safe, reliable and economical nuclear energy. For s successful nuclear power program, the owner should maintain a good relationship with the other entities and pursue an optimization of the objectives. On the other hand, he should manage projects along the well - planned paths in order to effectively learn the nuclear technology. One of the problems in the nuclear projects of developing countries was the absence of long - term technology development program, a limited local participation and the technical incapability. For the effective technology transfer, a motivation of the technology supplier and a readiness of the recipient to accommodate such technologies are required. Advanced technology is usually developed at considerable expense with the expectation that the developer will use it in furthering his own business. Therefore, he tends to be reluctant to transfer it to the others, particularly, to the potential competitors. There is a disinclination against further technology transfer beyond the minimum contractual obligation or the requirements by Government Regulatory. So, an additional commercial incentive must be provided to the developer

  18. Introduction to nuclear technology

    International Nuclear Information System (INIS)

    Rodriguez Pasques, R.H.

    1978-01-01

    In the 14 chapters of this text book intended for Spanish speaking university students, basic information is given on the different topics of Nucleonics, subdivided into: nuclear structure, stable and radioactive nucleids, nuclear and secondary radiations, radioactivity measurements, bombarding particles (accelerated ions, neutrons, photons), accelerators, elements of radiological physics, nuclear reactions, fissionable materials, nuclear reactors, production of radioactive materials, nucleonic applications, and a description of nuclear activities in Latin America. (M.E.L.) [es

  19. Cooperative technology development: An approach to advancing energy technology

    International Nuclear Information System (INIS)

    Stern, T.

    1989-09-01

    Technology development requires an enormous financial investment over a long period of time. Scarce national and corporate resources, the result of highly competitive markets, decreased profit margins, wide currency fluctuations, and growing debt, often preclude continuous development of energy technology by single entities, i.e., corporations, institutions, or nations. Although the energy needs of the developed world are generally being met by existing institutions, it is becoming increasingly clear that existing capital formation and technology transfer structures have failed to aid developing nations in meeting their growing electricity needs. This paper will describe a method for meeting the electricity needs of the developing world through technology transfer and international cooperative technology development. The role of nuclear power and the advanced passive plant design will be discussed. (author)

  20. International Nuclear Science and Technology Conference 2016

    International Nuclear Information System (INIS)

    2017-01-01

    Conference Nuclear technology has played an important role in many aspects of our lives, including agriculture, medicine and healthcare, materials, environment, forensics, energy, and frontier advancement. The International Nuclear Science and Technology Conference (INST) aims to bring together scientists, engineers, academics and students to share knowledge and experiences about all aspects of nuclear sciences. INST2016 was the second of the INST conference series organized by Thailand Institute of Nuclear Technology. INST has evolved from a national conference series on nuclear science and technology that was held every two years in Bangkok for over a twenty-year period. INST2016 was held from 4 - 6 August 2016 in Bangkok, Thailand, under the central theme “Nuclear for Better Life”. The conference working language was English. The oral and poster research presentations covered seven major topics: • Nuclear physics and engineering (PHY) • Nuclear and radiation safety (SAF) • Medical and nutritional applications (MED) • Environmental applications (ENV) • Radiation processing and industrial applications (IND) • Agriculture and food applications (AGR) • Instrumentation and other related topics (INS) The welcome addresses, committees, program of the conference and the list of presentations can be found in the PDF. (paper)

  1. 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.

  2. Developing countries' motivation to use nuclear technology

    International Nuclear Information System (INIS)

    Ratsch, U.

    1990-01-01

    Governments of various developing countries see nuclear energy as an important tool for at least three political goals: Firstly, the expected rise in future energy demand, so they argue, can only be met if nuclear electricity production in the Third World is expanded. Fossil sources are supposed to become increasingly scarce and expensive, and they are also seen to be ecologically damaging. Technologies to harness renewable energy sources are not yet mature and still too costly. Secondly, nuclear technology is seen as one of the most advanced technologies. Mastering of it might help to diminish the technological gap between the First and the Third World. Thirdly, scientific progress in developing countries is hoped to be accelerated by operating research reactors in these countries. All of these arguments ought to be taken as serious motivations. (orig./HSCH) [de

  3. Nuclear medical technology

    International Nuclear Information System (INIS)

    Daga, Avinash; Sharma, Smita; Sharma, K.S.

    2012-01-01

    Nuclear medical technology helps to use radiopharmaceuticals (drugs that give off radiation) to diagnose and treat illness. A more recent development is Positron Emission Tomography (PET) which is a more precise and sophisticated technique that uses isotopes produced in a cyclotron. F-18 in FDG (fluorodeoxyglucose) is one such positron-emitting radionuclide. Chemically, it is 2-deoxy-2-( 18 F) fluoro-D-glucose, a glucose analog with the positron-emitting radioactive isotope fluorine-18 substituted for the normal hydroxyl group at the 2' position in the glucose molecule. It is introduced, usually by injection, and then it gets accumulated in the target tissue. As it decays it emits a positron, which promptly combines with a nearby electron resulting in the simultaneous emission of two identifiable gamma rays in opposite directions. These are detected by a PET camera when the patient is placed in the PET scanner for a series of one or more scans which may take from 20 minutes to as long as an hour. It gives very precise indication of their origin. 18 F in FDG (fluorodeoxyglucose) has become very important in detection of cancers and the monitoring of progress in their treatment, using PET. (author)

  4. Cryogenics in nuclear reactor technology

    International Nuclear Information System (INIS)

    Dharmadurai, G.

    1982-01-01

    The cryogenic technology has significantly contributed to the development of several proven techniques for use in the nuclear power industry. A noteworthy feature is the unique role of cryogenics in minimising the release of radioactive and some chemical pollutants to the environment during the operation of various plants associated with this industry. The salient technological features of several cryogenic processes relevant to the nuclear reactor technology are discussed. (author)

  5. Advanced technologies, systems, and applications

    CERN Document Server

    Avdaković, Samir

    2017-01-01

    This volume spans a wide range of technical disciplines and technologies, including complex systems, biomedical engineering, electrical engineering, energy, telecommunications, mechanical engineering, civil engineering, and computer science. The papers included in this volume were presented at the International Symposium on Innovative and Interdisciplinary Applications of Advanced Technologies (IAT), held in Neum, Bosnia and Herzegovina on June 26 and 27, 2016. This highly interdisciplinary volume is devoted to various aspects and types of systems. Systems thinking is crucial for successfully building and understanding man-made, natural, and social systems. .

  6. Nuclear Technology Review 2013. Report by the Director General

    International Nuclear Information System (INIS)

    2013-01-01

    In response to requests by Member States, the Secretariat produces a comprehensive Nuclear Technology Review each year. Attached is this year's report, which highlights notable developments principally in 2012. The Nuclear Technology Review 2013 covers the following areas: power applications, atomic and nuclear data, accelerators and research reactors, and nuclear sciences and applications. Additional documentation associated with the Nuclear Technology Review 2013 is available on the Agency's website1 in English on nuclear hydrogen production technology and preliminary lessons learned from the Fukushima Daiichi accident for advanced nuclear power plant technology development. Information on the IAEA's activities related to nuclear science and technology can also be found in the IAEA's Annual Report 2012 (GC(57)/3), in particular the Technology section, and the Technical Cooperation Report for 2012 (GC(57)/INF/4). The document has been modified to take account, to the extent possible, of specific comments by the Board of Governors and other comments received from Member States. (author)

  7. Future nuclear systems technology

    International Nuclear Information System (INIS)

    Brooks, H.

    1979-01-01

    Five directions can be identified for evolution of nuclear systems, possibly a sixth. These are, first, and perhaps most important, toward a means of extending fissile resources through improvement of the efficiency of their use; second, improvements in nuclear safety; third, reduction in the environmental impacts of nuclear electric power generation, particularly water requirements; fourth, improvements in proliferation resistance of the nuclear fuel cycle; and fifth, improvements in economics. And added in a sixth, and somewhat more speculative direction, the use of nuclear power for purposes other than the direct generation of electricity

  8. Center for Advanced Computational Technology

    Science.gov (United States)

    Noor, Ahmed K.

    2000-01-01

    The Center for Advanced Computational Technology (ACT) was established to serve as a focal point for diverse research activities pertaining to application of advanced computational technology to future aerospace systems. These activities include the use of numerical simulations, artificial intelligence methods, multimedia and synthetic environments, and computational intelligence, in the modeling, analysis, sensitivity studies, optimization, design and operation of future aerospace systems. The Center is located at NASA Langley and is an integral part of the School of Engineering and Applied Science of the University of Virginia. The Center has four specific objectives: 1) conduct innovative research on applications of advanced computational technology to aerospace systems; 2) act as pathfinder by demonstrating to the research community what can be done (high-potential, high-risk research); 3) help in identifying future directions of research in support of the aeronautical and space missions of the twenty-first century; and 4) help in the rapid transfer of research results to industry and in broadening awareness among researchers and engineers of the state-of-the-art in applications of advanced computational technology to the analysis, design prototyping and operations of aerospace and other high-performance engineering systems. In addition to research, Center activities include helping in the planning and coordination of the activities of a multi-center team of NASA and JPL researchers who are developing an intelligent synthesis environment for future aerospace systems; organizing workshops and national symposia; as well as writing state-of-the-art monographs and NASA special publications on timely topics.

  9. Large floating structures technological advances

    CERN Document Server

    Wang, BT

    2015-01-01

    This book surveys key projects that have seen the construction of large floating structures or have attained detailed conceptual designs. This compilation of key floating structures in a single volume captures the innovative features that mark the technological advances made in this field of engineering, and will provide a useful reference for ideas, analysis, design, and construction of these unique and emerging urban projects to offshore and marine engineers, urban planners, architects and students.

  10. Advanced Situation Awareness Technologies, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Advanced Situation Awareness Technologies (ASAT) will facilitate exploration of the moon surface, and other planetary bodies. ASAT will create an Advanced Situation...

  11. Development of advanced neutron beam technology

    Energy Technology Data Exchange (ETDEWEB)

    Seong, B S; Lee, J S; Sim, C M [and others

    2007-06-15

    The purpose of this work is to timely support the national science and technology policy through development of the advanced application techniques for neutron spectrometers, built in the previous project, in order to improve the neutron spectrometer techniques up to the world-class level in both quantity and quality and to reinforce industrial competitiveness. The importance of the research and development (R and D) is as follows: 1. Technological aspects - Development of a high value-added technology through performing the advanced R and D in the broad research areas from basic to applied science and from hard to soft condensed matter using neutron scattering technique. - Achievement of an important role in development of the new technology for the following industries aerospace, defense industry, atomic energy, hydrogen fuel cell etc. by the non-destructive inspection and analysis using neutron radiography. - Development of a system supporting the academic-industry users for the HANARO facility 2. Economical and Industrial Aspects - Essential technology in the industrial application of neutron spectrometer, in the basic and applied research of the diverse materials sciences, and in NT, BT, and IT areas - Broad impact on the economics and the domestic and international collaborative research by using the neutron instruments in the mega-scale research facility, HANARO, that is a unique source of neutron in Korea. 3. Social Aspects - Creating the scientific knowledge and contributing to the advanced industrial society through the neutron beam application - Improving quality of life and building a national consensus on the application of nuclear power by developing the RT fusion technology using the HANARO facility. - Widening the national research area and strengthening the national R and D capability by performing advanced R and D using the HANARO facility.

  12. Development of advanced neutron beam technology

    International Nuclear Information System (INIS)

    Seong, B. S.; Lee, J. S.; Sim, C. M.

    2007-06-01

    The purpose of this work is to timely support the national science and technology policy through development of the advanced application techniques for neutron spectrometers, built in the previous project, in order to improve the neutron spectrometer techniques up to the world-class level in both quantity and quality and to reinforce industrial competitiveness. The importance of the research and development (R and D) is as follows: 1. Technological aspects - Development of a high value-added technology through performing the advanced R and D in the broad research areas from basic to applied science and from hard to soft condensed matter using neutron scattering technique. - Achievement of an important role in development of the new technology for the following industries aerospace, defense industry, atomic energy, hydrogen fuel cell etc. by the non-destructive inspection and analysis using neutron radiography. - Development of a system supporting the academic-industry users for the HANARO facility 2. Economical and Industrial Aspects - Essential technology in the industrial application of neutron spectrometer, in the basic and applied research of the diverse materials sciences, and in NT, BT, and IT areas - Broad impact on the economics and the domestic and international collaborative research by using the neutron instruments in the mega-scale research facility, HANARO, that is a unique source of neutron in Korea. 3. Social Aspects - Creating the scientific knowledge and contributing to the advanced industrial society through the neutron beam application - Improving quality of life and building a national consensus on the application of nuclear power by developing the RT fusion technology using the HANARO facility. - Widening the national research area and strengthening the national R and D capability by performing advanced R and D using the HANARO facility

  13. Nuclear Technology Review 2014

    International Nuclear Information System (INIS)

    2014-08-01

    With 434 nuclear power reactors in operation worldwide at the end of 2013, nuclear energy had a global generating capacity of 371.7 GW(e). There were four new grid connections and ten construction starts on new reactors. Belarus became the second nuclear ‘newcomer’ State in three decades to start building its first nuclear power plant. Near and long term growth prospects remained centred in Asia, particularly in China. The 72 reactors under construction in 2013 represented the highest number since 1989. Of these, 48 were in Asia, as were 42 of the last 52 new reactors to have been connected to the grid since 2000. Thirty States currently use nuclear power and about the same number are considering including it as part of their energy mix. Of the 30 States already operating nuclear power plants, 13 are either constructing new plants or actively completing previously suspended constructions, and 12 are planning to either construct new plants or to complete suspended constructions. The IAEA Ministerial Conference on Nuclear Power in the 21st Century, held in June 2013, reaffirmed that nuclear power remains an important option for many States to improve energy security, reduce the impact of volatile fossil fuels prices and mitigate the effects of climate change. The Concluding Statement said that “nuclear power, as a stable base-load source of electricity in an era of ever increasing global energy demands, complements other energy sources including renewables.” In the IAEA’s 2013 projections, nuclear power is expected to grow by between 17% as the low projection and 94% as the high projection by 2030. These figures are slightly lower than projected in 2012, reflecting the continued impact of the Fukushima Daiichi accident, the low prices of natural gas and the increasing use of renewable energy. Additional information focuses on the linkages between nuclear power and climate change, as nuclear power, hydropower and wind energy have the lowest life cycle

  14. Nuclear technology is dead - long live nuclear technology

    International Nuclear Information System (INIS)

    Mayer, G.

    1976-01-01

    While a group of German scientists asked for a moratorium for nuclear power plants in the Heidelberg memorandum, lecturers at the Reaktortagung in Duesseldorf offered convincing arguments in favour of nuclear technology and for the necessity of safety. Almost 2,000 participants, about 200 of those from 26 different countries, listened to 235 individual lectures on the state of science and technology. Main topics were activities in reactor safety research carried out in industry and in various institutes. (orig./RW) [de

  15. Slovakian-Russian partnership as a part of the supply chain for nuclear power plants and advanced Russian technology for nuclear power plants

    International Nuclear Information System (INIS)

    Ivanov, T.; Chernyakhovskaya, Y.

    2009-01-01

    The first nuclear power project in the Slovak Republic was launched in 1958 through close cooperation with the Russian nuclear industry. Since then the Slovak and Russian nuclear branches were never separated. Technical and economic performances of the NPP units constructed with participation of Russian specialists were and continue being one of the best globally. The culture of business and competence of ASE is based on about 40 years of experience in construction of 29 NPP power units abroad with 20 GW total capacity. ASE strives to present to the Customers line of NPP designs ready for implementation and well-developed network of the multi-functional alliances and JVs. Currently, large-scale NPP projects involve public-private partnership (PPP) more and more. ASE development vision is to flexibly conform to Customers' requirements and needs and to diversify in related segments of EPC-business, namely designing, manufacturing, electric power trade, etc. Systematical approach to the fostering of mutual relations under the new economic conditions and nuclear renaissance, the Slovak-Russian cooperation in NPP engineering, manufacturing and construction are once again promising and long-term oriented. (authors)

  16. Nuclear technology review 2005 update

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-08-15

    The year 2004 marked the 50th anniversary of civilian nuclear power generation. While the current outlook for nuclear energy remains mixed, there is clearly a sense of rising expectations. Both the OECD International Energy Agency and the IAEA adjusted their medium-term projections for nuclear power upwards. The IAEA now projects 423 - 592 GW(e) of nuclear power installed worldwide in 2030, compared to 366 GW(e) at the end of 2004. This is driven by nuclear power's performance record, by growing energy needs around the world coupled with rising oil and natural gas prices, by new environmental constraints including entry-into-force of the Kyoto Protocol, by concerns about energy supply security in a number of countries, and by ambitious expansion plans in several key countries. National research on advanced reactor designs continues on all reactor categories - water cooled, gas cooled, liquid metal cooled, and hybrid systems. Five members of the US-initiated Generation IV International Forum (GIF) signed a framework agreement on international collaboration in research and development on Generation IV nuclear energy systems in February 2005. The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) grew to 23 members. It completed a series of case studies testing its assessment methodology and the final report on the updated INPRO methodology was published in December. The realization of the International Thermonuclear Experimental Reactor, ITER, came closer with the announcement on 28 June 2005 by the ITER parties. The aim of ITER is to demonstrate the scientific and technological feasibility of fusion energy by constructing a functional fusion power plant. Nuclear technology developments are rapid and cover many fields of application. Not all can be covered in this update review, but certain key areas and trends are covered where these are seen to be of significant interest to IAEA Member States, and which are of relevance to and have

  17. Nuclear technology review 2005 update

    International Nuclear Information System (INIS)

    2005-08-01

    The year 2004 marked the 50th anniversary of civilian nuclear power generation. While the current outlook for nuclear energy remains mixed, there is clearly a sense of rising expectations. Both the OECD International Energy Agency and the IAEA adjusted their medium-term projections for nuclear power upwards. The IAEA now projects 423 - 592 GW(e) of nuclear power installed worldwide in 2030, compared to 366 GW(e) at the end of 2004. This is driven by nuclear power's performance record, by growing energy needs around the world coupled with rising oil and natural gas prices, by new environmental constraints including entry-into-force of the Kyoto Protocol, by concerns about energy supply security in a number of countries, and by ambitious expansion plans in several key countries. National research on advanced reactor designs continues on all reactor categories - water cooled, gas cooled, liquid metal cooled, and hybrid systems. Five members of the US-initiated Generation IV International Forum (GIF) signed a framework agreement on international collaboration in research and development on Generation IV nuclear energy systems in February 2005. The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) grew to 23 members. It completed a series of case studies testing its assessment methodology and the final report on the updated INPRO methodology was published in December. The realization of the International Thermonuclear Experimental Reactor, ITER, came closer with the announcement on 28 June 2005 by the ITER parties. The aim of ITER is to demonstrate the scientific and technological feasibility of fusion energy by constructing a functional fusion power plant. Nuclear technology developments are rapid and cover many fields of application. Not all can be covered in this update review, but certain key areas and trends are covered where these are seen to be of significant interest to IAEA Member States, and which are of relevance to and have

  18. Advances in single chain technology.

    Science.gov (United States)

    Gonzalez-Burgos, Marina; Latorre-Sanchez, Alejandro; Pomposo, José A

    2015-10-07

    The recent ability to manipulate and visualize single atoms at atomic level has given rise to modern bottom-up nanotechnology. Similar exquisite degree of control at the individual polymeric chain level for producing functional soft nanoentities is expected to become a reality in the next few years through the full development of so-called "single chain technology". Ultra-small unimolecular soft nano-objects endowed with useful, autonomous and smart functions are the expected, long-term valuable output of single chain technology. This review covers the recent advances in single chain technology for the construction of soft nano-objects via chain compaction, with an emphasis in dynamic, letter-shaped and compositionally unsymmetrical single rings, complex multi-ring systems, single chain nanoparticles, tadpoles, dumbbells and hairpins, as well as the potential end-use applications of individual soft nano-objects endowed with useful functions in catalysis, sensing, drug delivery and other uses.

  19. Nuclear Forensics Technologies in Japan

    International Nuclear Information System (INIS)

    Shinohara, N.; Kimura, Y.; Okubo, A.; Tomikawa, H.

    2015-01-01

    Nuclear forensics is the analysis of intercepted illicit nuclear or radioactive material and any associated material to provide evidence for nuclear attribution by determining origin, history, transit routes and purpose involving such material. Nuclear forensics activities include sampling of the illicit material, analysis of the samples and evaluation of the attribution by comparing the analysed data with database or numerical simulation. Because the nuclear forensics methodologies provide hints of the origin of the nuclear materials used in illegal dealings or nuclear terrorism, it contributes to identify and indict offenders, hence to enhance deterrent effect against such terrorism. Worldwide network on nuclear forensics can lead to strengthening global nuclear security regime. In the ESARDA Symposium 2015, the results of research and development of fundamental nuclear forensics technologies performed in Japan Atomic Energy Agency during the term of 2011-2013 were reported, namely (1) technique to analyse isotopic composition of nuclear material, (2) technique to identify the impurities contained in the material, (3) technique to determine the age of the purified material by measuring the isotopic ratio of daughter thorium to parent uranium, (4) technique to make image data by observing particle shapes with electron microscope, and (5) prototype nuclear forensics library for comparison of the analysed data with database in order to evaluate its evidence such as origin and history. Japan’s capability on nuclear forensics and effective international cooperation are also mentioned for contribution to the international nuclear forensics community.

  20. Development of essential system technologies for advanced reactor

    International Nuclear Information System (INIS)

    Bae, Y. Y.; Hwang, Y. D.; Cho, B. H. and others

    1999-03-01

    Basic design of SMART adopts the new advanced technologies which were not applied in the existing 1000MWe PWR. However, the R and D experience on these advanced essential technologies is lacking in domestic nuclear industry. Recently, a research on these advanced technologies has been performed as a part of the mid-and-long term nuclear R and D program, but the research was limited only for the small scale fundamental study. The research on these essential technologies such as helically coiled tube steam generator, self pressurizer, core cooling by natural circulation required for the development of integral reactor SMART have not been conducted in full scale. This project, therefore, was performed for the development of analysis models and methodologies, system analysis and thermal hydraulic experiments on the essential technologies to be applied to the 300MWe capacity of integral reactor SMART and the advanced passive reactor expected to be developed in near future with the emphasis on experimental investigation. (author)

  1. Center for Advanced Separation Technology

    Energy Technology Data Exchange (ETDEWEB)

    Honaker, Rick

    2013-09-30

    The U.S. is the largest producer of mining products in the world. In 2011, U.S. mining operations contributed a total of $232 billion to the nation’s GDP plus $138 billion in labor income. Of this the coal mining industry contributed a total of $97.5 billion to GDP plus $53 billion in labor income. Despite these contributions, the industry has not been well supported with research and development funds as compared to mining industries in other countries. To overcome this problem, the Center for Advanced Separation Technologies (CAST) was established to develop technologies that can be used by the U.S. mining industry to create new products, reduce production costs, and meet environmental regulations. Originally set up by Virginia Tech and West Virginia University, CAST is now a five-university consortium – Virginia Tech, West Virginia University, University of Kentucky, University of Utah and Montana Tech, - that is supported through U.S. DOE Cooperative Agreement No. DE-FE0000699, Center for Advanced Separation Technology. Much of the research to be conducted with Cooperative Agreement funds will be longer term, high-risk, basic research and will be carried out in two broad areas: Advanced Pre-Combustion Clean Coal Technologies and Gas-Gas Separations. Distribution of funds is handled via competitive solicitation of research proposals through Site Coordinators at the five member universities. These were reviewed and the selected proposals were forwarded these to the DOE/NETL Project Officer for final review and approval. The successful projects are listed below by category, along with abstracts from their final reports.

  2. Technology of high-level nuclear waste disposal. Advances in the science and engineering of the management of high-level nuclear wastes. Volume 1

    International Nuclear Information System (INIS)

    Hofmann, P.L.; Breslin, J.J.

    1981-01-01

    The papers in this volume cover the following subjects: waste isolation and the natural geohydrologic system; repository perturbations of the natural system; radionuclide migration through the natural system; and repository design technology. Individual papers are abstracted

  3. Technology of high-level nuclear waste disposal. Advances in the science and engineering of the management of high-level nuclear wastes. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Hofmann, P.L.; Breslin, J.J. (eds.)

    1981-01-01

    The papers in this volume cover the following subjects: waste isolation and the natural geohydrologic system; repository perturbations of the natural system; radionuclide migration through the natural system; and repository design technology. Individual papers are abstracted.

  4. A project in support of Nuclear Technology Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho [and others

    2005-12-15

    Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate.

  5. A project in support of Nuclear Technology Cooperation

    International Nuclear Information System (INIS)

    Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho

    2005-12-01

    Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate

  6. Advanced technologies: Trends and implications for security

    International Nuclear Information System (INIS)

    Shaw, A.

    1990-01-01

    's advantages. If conventional force reductions are properly managed, the resulting balance can probably be made fairly insensitive to technological advances. This task may be much more difficult in attempting reductions of nuclear weapons to very low levels; there the prospects for disruption of a stable balance through technological advance are more profound. Stability will be aided by agreements that control the use of technology; discovery is hard to control. Emphasis on advances that impede surprise and attack momentum can aid stability. We should not be complacent because of the fact that the super-Powers are getting along better. The presence of sophisticated military technology in many of the world's trouble-spots threatens the security of all. The potential for regional conflict is likely to get worse, not better. Moreover, so much technology available on the world market for 'peaceful purposes' can be turned to military purposes. Indeed, the United States has found that even its most advanced defence equipment increasingly depends on 'dual use' technology developed for civilian applications. The big story is that the world has begun to move in the direction of a global interdependent economy based on trade in the manufacture of high technology and other goods. This is a 'sea change' in history. And with it comes shifting economic and political power, carrying the seeds of harmony as well as those of discord

  7. Advanced PWR technology development -Development of advanced PWR system analysis technology-

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Moon Heui; Hwang, Yung Dong; Kim, Sung Oh; Yoon, Joo Hyun; Jung, Bub Dong; Choi, Chul Jin; Lee, Yung Jin; Song, Jin Hoh [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    The primary scope of this study is to establish the analysis technology for the advanced reactor designed on the basis of the passive and inherent safety concepts. This study is extended to the application of these technology to the safety analysis of the passive reactor. The study was performed for the small and medium sized reactor and the large sized reactor by focusing on the development of the analysis technology for the passive components. Among the identified concepts the once-through steam generator, the natural circulation of the integral reactor, heat pipe for containment cooling, and hydraulic valve were selected as the high priority items to be developed and the related studies are being performed for these items. For the large sized passive reactor, the study plans to extend the applicability of the best estimate computer code RELAP5/MOD3 which is widely used for the safety analyses of the reactor system. The improvement and supplementation study of the analysis modeling and the methodology is planned to be carried out for these purpose. The newly developed technologies are expected to be applied to the domestic advanced reactor design and analysis and these technologies will play a key role in extending the domestic nuclear base technology and consolidating self-reliance in the essential nuclear technology. 72 figs, 15 tabs, 124 refs. (Author).

  8. Advanced USC technology in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Fukuda, Masafumi [National Institute for Materials Science, Tsukuba, Ibaraki (Japan). High Temperature Materials Center

    2010-07-01

    The 600deg-C class Ultra Super-Critical(USC) steam condition technology was mainly developed through projects led by J-Power in the '80s and 90s'. In 2001, the project was successfully finished with newly developed 9-12% chromium steels. These materials were selected for the major parts of the USC power plants in Japan and almost half of the coal power plants have the USC steam condition today. However, aged plants, which were built in the '70s and early '80s will reach the point where they will need to be rebuilt or refurbished in the near future. The steam temperatures of the older plants are 538 deg-C or 566deg-C. We did a case study, retrofitting these plants with the USC and an advanced USC technology that takes a 700deg-C class steam temperature to increase thermal efficiency and to reduce CO{sub 2} emissions. The study showed that the advanced USC Technology(A-USC) is suitable for the retrofitting of aged plants and can reduce CO{sub 2} emissions by about 15%. The Japanese government launched the ''Cool Earth-Innovative Energy Technology Program'' in 2008 March to promote international cooperation and actively contribute to substantial global greenhouse gas emissions reductions. 21 technologies that will contribute to substantial reductions in CO{sub 2} emissions by efficiency improvement and low carbonization were selected. The A-USC that aims at 46% (net, HHV) thermal efficiency of coal power generation is included in the technologies. We started a large-scale development project of the A-USC technology in 2008 August. 700deg-C class boiler, turbine and valve technologies, which include high temperature material technology, will be developed. Some candidate materials for boilers are being tested. Turbine rotor and casing materials are being developed and tested, as well. Two years from the beginning of the project, we have obtained some useful test results regarding the candidate materials. (orig.)

  9. Advanced Reactor Technology -- Regulatory Technology Development Plan (RTDP)

    Energy Technology Data Exchange (ETDEWEB)

    Moe, Wayne Leland [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-05-01

    This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However, it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory

  10. Advanced Reactor Technology -- Regulatory Technology Development Plan (RTDP)

    International Nuclear Information System (INIS)

    Moe, Wayne Leland

    2015-01-01

    This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a ''critical path'' for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However, it is also important to remember that certain ''minimum'' levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial ''first step'' in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by

  11. Advanced Reactor Technologies - Regulatory Technology Development Plan (RTDP)

    Energy Technology Data Exchange (ETDEWEB)

    Moe, Wayne L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-08-23

    This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However, it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory

  12. Radiation chemistry in nuclear technology

    International Nuclear Information System (INIS)

    Katsumura, Yosuke

    2006-01-01

    The importance of radiation chemistry in the field of nuclear technology including reactor chemistry, spent fuel reprocessing and radioactive high level waste repository, is summarized and, in parallel, our research activity will be briefly presented. (author)

  13. Nuclear Proliferation Technology Trends Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Zentner, Michael D.; Coles, Garill A.; Talbert, Robert J.

    2005-10-04

    A process is underway to develop mature, integrated methodologies to address nonproliferation issues. A variety of methodologies (both qualitative and quantitative) are being considered. All have one thing in common, a need for a consistent set of proliferation related data that can be used as a basis for application. One approach to providing a basis for predicting and evaluating future proliferation events is to understand past proliferation events, that is, the different paths that have actually been taken to acquire or attempt to acquire special nuclear material. In order to provide this information, this report describing previous material acquisition activities (obtained from open source material) has been prepared. This report describes how, based on an evaluation of historical trends in nuclear technology development, conclusions can be reached concerning: (1) The length of time it takes to acquire a technology; (2) The length of time it takes for production of special nuclear material to begin; and (3) The type of approaches taken for acquiring the technology. In addition to examining time constants, the report is intended to provide information that could be used to support the use of the different non-proliferation analysis methodologies. Accordingly, each section includes: (1) Technology description; (2) Technology origin; (3) Basic theory; (4) Important components/materials; (5) Technology development; (6) Technological difficulties involved in use; (7) Changes/improvements in technology; (8) Countries that have used/attempted to use the technology; (9) Technology Information; (10) Acquisition approaches; (11) Time constants for technology development; and (12) Required Concurrent Technologies.

  14. Development of nuclear fuel cycle technology

    International Nuclear Information System (INIS)

    Kawahara, Akira; Sugimoto, Yoshikazu; Shibata, Satoshi; Ikeda, Takashi; Suzuki, Kazumichi; Miki, Atsushi.

    1990-01-01

    In order to establish the stable supply of nuclear fuel as an important energy source, Hitachi ltd. has advanced the technical development aiming at the heightening of reliability, the increase of capacity, upgrading and the heightening of performance of the facilities related to nuclear fuel cycle. As for fuel reprocessing, Japan Nuclear Fuel Service Ltd. is promoting the construction of a commercial fuel reprocessing plant which is the first in Japan. The verification of the process performance, the ensuring of high reliability accompanying large capacity and the technical development for recovering effective resources from spent fuel are advanced. Moreover, as for uranium enrichment, Laser Enrichment Technology Research Association was founded mainly by electric power companies, and the development of the next generation enrichment technology using laser is promoted. The development of spent fuel reprocessing technology, the development of the basic technology of atomic process laser enrichment and so on are reported. In addition to the above technologies recently developed by Hitachi Ltd., the technology of reducing harm and solidification of radioactive wastes, the molecular process laser enrichment and others are developed. (K.I.)

  15. Materials Advance Chemical Propulsion Technology

    Science.gov (United States)

    2012-01-01

    In the future, the Planetary Science Division of NASA's Science Mission Directorate hopes to use better-performing and lower-cost propulsion systems to send rovers, probes, and observers to places like Mars, Jupiter, and Saturn. For such purposes, a new propulsion technology called the Advanced Materials Bipropellant Rocket (AMBR) was developed under NASA's In-Space Propulsion Technology (ISPT) project, located at Glenn Research Center. As an advanced chemical propulsion system, AMBR uses nitrogen tetroxide oxidizer and hydrazine fuel to propel a spacecraft. Based on current research and development efforts, the technology shows great promise for increasing engine operation and engine lifespan, as well as lowering manufacturing costs. In developing AMBR, ISPT has several goals: to decrease the time it takes for a spacecraft to travel to its destination, reduce the cost of making the propulsion system, and lessen the weight of the propulsion system. If goals like these are met, it could result in greater capabilities for in-space science investigations. For example, if the amount (and weight) of propellant required on a spacecraft is reduced, more scientific instruments (and weight) could be added to the spacecraft. To achieve AMBR s maximum potential performance, the engine needed to be capable of operating at extremely high temperatures and pressure. To this end, ISPT required engine chambers made of iridium-coated rhenium (strong, high-temperature metallic elements) that allowed operation at temperatures close to 4,000 F. In addition, ISPT needed an advanced manufacturing technique for better coating methods to increase the strength of the engine chamber without increasing the costs of fabricating the chamber.

  16. Nuclear Technology Review 2012

    International Nuclear Information System (INIS)

    2012-09-01

    In 2011, nuclear energy continued to play an important role in global electricity production despite the accident at the Fukushima Daiichi nuclear power plant (NPP). Total generating nuclear power capacity was slightly lower than in previous years due to the permanent shutdown of 13 reactors in 2011, including 8 in Germany and 4 in Japan in the wake of the accident. However, there were 7 new grid connections compared to 5 in 2010, 2 in 2009 and none in 2008. Significant growth in the use of nuclear energy worldwide is still anticipated - between 35% and 100% by 2030 - although the Agency projections for 2030 are 7-8% lower than projections made in 2010. The factors that have contributed to an increased interest in nuclear power did not change: an increasing global demand for energy, concerns about climate change, energy security and uncertainty about fossil fuel supplies. Most of the growth is still expected in countries that already have operating NPPs, especially in Asia, with China and India remaining the main centres of expansion while the Russian Federation will also remain a centre of strong growth. The 7-8% drop in projected growth for 2030 reflects an accelerated phase-out of nuclear power in Germany, some immediate shutdowns and a government review of the planned expansion in Japan, as well as temporary delays in expansion in several other countries. Measures taken by countries as a result of the Fukushima Daiichi nuclear accident have been varied. A number of countries announced reviews of their programmes. Belgium, Germany and Switzerland took additional steps to phase out nuclear power entirely while others re-emphasized their expansion plans. Many Member States carried out national safety assessment reviews in 2011 (often called 'stress tests'), and commitments were made to complete any remaining assessments promptly and to implement the necessary corrective action. In countries considering the introduction of nuclear power, interest remained strong

  17. Technology of high-level nuclear waste disposal. Advances in the science and engineering of the management of high-level nuclear wastes. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Hofmann, P.L. (ed.)

    1982-01-01

    The twenty papers in this volume are divided into three parts: site exploration and characterization; repository development and design; and waste package development and design. These papers represent the status of technology that existed in 1981 and 1982. Individual papers were processed for inclusion in the Energy Data Base.

  18. Technology of high-level nuclear waste disposal. Advances in the science and engineering of the management of high-level nuclear wastes. Volume 2

    International Nuclear Information System (INIS)

    Hofmann, P.L.

    1982-01-01

    The twenty papers in this volume are divided into three parts: site exploration and characterization; repository development and design; and waste package development and design. These papers represent the status of technology that existed in 1981 and 1982. Individual papers were processed for inclusion in the Energy Data Base

  19. Technology of nuclear war

    International Nuclear Information System (INIS)

    Broda, E.

    1973-01-01

    This Article is the Note of a lecture, which was hold by Engelbert Borda at the Catholic-Theological Faculty of the University of Vienna in 27. 03. 1973. The author describes the development of modern nuclear weapon systems and the resulting war strategies. He is concerned about a possible end of the ‚balance of terror’ and the development in automation of nuclear strike back strategies. (rössner) [de

  20. Advanced Artificial Intelligence Technology Testbed

    Science.gov (United States)

    Anken, Craig S.

    1993-01-01

    The Advanced Artificial Intelligence Technology Testbed (AAITT) is a laboratory testbed for the design, analysis, integration, evaluation, and exercising of large-scale, complex, software systems, composed of both knowledge-based and conventional components. The AAITT assists its users in the following ways: configuring various problem-solving application suites; observing and measuring the behavior of these applications and the interactions between their constituent modules; gathering and analyzing statistics about the occurrence of key events; and flexibly and quickly altering the interaction of modules within the applications for further study.

  1. Advances in cervical screening technology.

    Science.gov (United States)

    Stoler, M H

    2000-03-01

    The Pap smear unquestionably is a successful screening test for cervical cancer. However, recent advances in technology have raised questions regarding whether the conventional Pap smear is still the standard of care. This article relates issues of screening and cost-effectiveness to the state of the art in thin layer preparations, cytology automation, human papillomavirus screening, human papillomavirus vaccines, and other cervical screening adjuncts. Perhaps nowhere in medicine is clinical decision making being more strongly influenced by market and other external forces than in cervical cytopathology.

  2. New nuclear technologies

    International Nuclear Information System (INIS)

    Bouchard, J.; Thomas, J.B.

    2001-01-01

    The potential of nuclear energy for sustainable development is based on its competitiveness, environmental friendliness and sustainability of natural resources. The improvements to be achieved relate to cleanliness (by reducing the production of long lived radioactive waste), safety demonstration and sobriety which contributes to minimise the consumption of natural resources. The current level of competitiveness, which is fairly good, has to be maintained. The required improvements benefit from a high efficiency and a simpler architecture of industrial systems; they imply the recycling of nuclear materials and a high efficiency of nuclear combustion. The latter requires a hardened spectrum using fast neutrons, which makes the nuclear core 'omnivorous' as for transuranics. The studies must take into account reactor design, nuclear fuel and fuel cycle. Diverse coolants (water, gas, liquid metals) are considered, with solid fuel (pins, particles) and reprocessing by hydrometallurgical or pyrochemical processes, as well as liquid fuel reactors. Several ways of combining options look promising. The required time before industrial implementation is highly variable. A nuclear fleet can include diversified, specialized components and new applications (hydrogen production) can be envisaged. The R and D programme will rely on the development of simulation power and will imply a strong international cooperation. (authors)

  3. Nuclear technology and Latin America

    International Nuclear Information System (INIS)

    Raja Mohan, C.

    1980-01-01

    Developments in nuclear technology in Latin American countries, particularly in Argentina and Brazil, have been surveyed. In their efforts to acquire self-reliance in the nuclear field independently i.e. without seeking help from U.S.A., Argentina and Brazil came to accept stringent foreign controls on their nuclear programmes which envisage having a complete nuclear fuel cycle. Their struggle against the discriminatory nature of the NPT has become more or less theoretical. Moreover, the Latin American countries have signed the Tlatelolco treaty which prohibits testing, use, manufacture or acquisition of nuclear weapons. An encouraging feature is, however, growing bilateral and multilateral cooperation in the nuclear energy sector. It is illustrated by citing the example of the Argentina-Brazil nuclear cooperation agreement. The political significance of this development for the third world is discussed. (M.G.B.)

  4. Nuclear Technology Review 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-09-15

    In 2009, construction started on 12 new nuclear power reactors, the largest number since 1985, and projections of future nuclear power growth were once again revised upwards. However, only two new reactors were connected to the grid, and, with three reactors retired during the year, the total nuclear power capacity around the world dropped slightly for the second year in a row. Current expansion, as well as near term and long term growth prospects, remain centred in Asia. Ten of the 12 construction starts were in Asia, as were both of the new grid connections. Although the global financial crisis that started in the second half of 2008 did not dampen overall projections for nuclear power, it was cited as a contributing factor in near-term delays or postponements affecting nuclear projects in some regions of the world. In some European countries where previously there were restrictions on the future use of nuclear power, there was a trend towards reconsidering these policies. Interest in starting new nuclear power programmes remained high. Over 60 Member States have expressed to the IAEA interest in considering the introduction of nuclear power, and, in 2009, the IAEA conducted its first Integrated Nuclear Infrastructure Review missions in Jordan, Indonesia and Vietnam. Estimates of identified conventional uranium resources (at less than $130/kg U) increased slightly, due mainly to increases reported by Australia, Canada and Namibia. Uranium spot prices declined, and final data for 2009 are expected to show a consequent decrease in uranium exploration and development. The Board of Governors has authorized the IAEA Director General to sign an agreement with the Russian Federation to establish an international reserve of low enriched uranium (LEU). It would contain 120 tonnes of LEU that could be made available to a country affected by a non-commercial interruption of its LEU supply. The agreement between the IAEA and the Russian Federation was signed in March 2010

  5. Nuclear Technology Review 2010

    International Nuclear Information System (INIS)

    2010-09-01

    In 2009, construction started on 12 new nuclear power reactors, the largest number since 1985, and projections of future nuclear power growth were once again revised upwards. However, only two new reactors were connected to the grid, and, with three reactors retired during the year, the total nuclear power capacity around the world dropped slightly for the second year in a row. Current expansion, as well as near term and long term growth prospects, remain centred in Asia. Ten of the 12 construction starts were in Asia, as were both of the new grid connections. Although the global financial crisis that started in the second half of 2008 did not dampen overall projections for nuclear power, it was cited as a contributing factor in near-term delays or postponements affecting nuclear projects in some regions of the world. In some European countries where previously there were restrictions on the future use of nuclear power, there was a trend towards reconsidering these policies. Interest in starting new nuclear power programmes remained high. Over 60 Member States have expressed to the IAEA interest in considering the introduction of nuclear power, and, in 2009, the IAEA conducted its first Integrated Nuclear Infrastructure Review missions in Jordan, Indonesia and Vietnam. Estimates of identified conventional uranium resources (at less than $130/kg U) increased slightly, due mainly to increases reported by Australia, Canada and Namibia. Uranium spot prices declined, and final data for 2009 are expected to show a consequent decrease in uranium exploration and development. The Board of Governors has authorized the IAEA Director General to sign an agreement with the Russian Federation to establish an international reserve of low enriched uranium (LEU). It would contain 120 tonnes of LEU that could be made available to a country affected by a non-commercial interruption of its LEU supply. The agreement between the IAEA and the Russian Federation was signed in March 2010

  6. Directions in advanced reactor technology

    International Nuclear Information System (INIS)

    Golay, M.W.

    1990-01-01

    Successful nuclear power plant concepts must simultaneously performance in terms of both safety and economics. To be attractive to both electric utility companies and the public, such plants must produce economical electric energy consistent with a level of safety which is acceptable to both the public and the plant owner. Programs for reactor development worldwide can be classified according to whether the reactor concept pursues improved safety or improved economic performance as the primary objective. When improved safety is the primary goal, safety enters the solution of the design problem as a constraint which restricts the set of allowed solutions. Conversely, when improved economic performance is the primary goal, it is allowed to be pursued only to an extent which is compatible with stringent safety requirements. The three major reactor coolants under consideration for future advanced reactor use are water, helium and sodium. Reactor development programs focuses upon safety and upon economics using each coolant are being pursued worldwide. These programs are discussed

  7. Advanced Mirror & Modelling Technology Development

    Science.gov (United States)

    Effinger, Michael; Stahl, H. Philip; Abplanalp, Laura; Maffett, Steven; Egerman, Robert; Eng, Ron; Arnold, William; Mosier, Gary; Blaurock, Carl

    2014-01-01

    The 2020 Decadal technology survey is starting in 2018. Technology on the shelf at that time will help guide selection to future low risk and low cost missions. The Advanced Mirror Technology Development (AMTD) team has identified development priorities based on science goals and engineering requirements for Ultraviolet Optical near-Infrared (UVOIR) missions in order to contribute to the selection process. One key development identified was lightweight mirror fabrication and testing. A monolithic, stacked, deep core mirror was fused and replicated twice to achieve the desired radius of curvature. It was subsequently successfully polished and tested. A recently awarded second phase to the AMTD project will develop larger mirrors to demonstrate the lateral scaling of the deep core mirror technology. Another key development was rapid modeling for the mirror. One model focused on generating optical and structural model results in minutes instead of months. Many variables could be accounted for regarding the core, face plate and back structure details. A portion of a spacecraft model was also developed. The spacecraft model incorporated direct integration to transform optical path difference to Point Spread Function (PSF) and between PSF to modulation transfer function. The second phase to the project will take the results of the rapid mirror modeler and integrate them into the rapid spacecraft modeler.

  8. The broad view of nuclear technology for aerospace

    International Nuclear Information System (INIS)

    Buden, D.; Angelo, J.A. Jr.

    1991-01-01

    Nuclear technologies can directly support advanced space initiatives. For near-Earth missions, nuclear technology can be used to power air traffic control, communications and manufacturing platforms, provide emergency power for manned platforms, provide power for maneuvering units, move asteroids for mining, measure the natural radiation environment, provide radiation protection instruments, and design radiation hardened robotic systems. For the Lunar and Mars surfaces, nuclear technology can be used for base stationary, mobile, and emergency power, energy storage, process heat, nuclear thermal and electric rocket propulsion, excavation and underground engineering, water and sewage treatment and sterilization, food processing and preservation, mineral exploration, self-luminous systems, radiation protection instrumentation, radiation environmental warning systems, and habitat shielding design. Outer planet missions can make use of nuclear technology for power and propulsion. Programs need to be initiated to ensure the full beneficial use of nuclear technologies in advanced space missions

  9. Canada's commitment to nuclear technology

    International Nuclear Information System (INIS)

    Stewart, Murray J.

    1998-01-01

    This paper gives a broad update on all facets of the Canadian nuclear industry and demonstrates Canada's continuing commitment to nuclear technology. Canada has developed a global leadership position in nuclear technology for power generation, uranium production and isotope supply. This commitment is being further enhanced by successes in international markets with Candu technology, new uranium mine developments in our province of Saskatchewan, and expanding isotope capabilities including the construction of two new production reactors. Korea's economy is benefiting through collaboration with Canada's leading nuclear companies, both in Korea and Canada. These collaborations have the potential to expand considerably with the implementation of the Kyoto Framework Convention on Climate Change and the anticipated increased demand for new nuclear power generation installations in all major global markets. Much has been publicized about the situation surrounding Ontario Hydro Nuclear and its nuclear recovery program. This paper gives the background and highlights the actions within Ontario and Ontario Hydro designed to ensure the long term recovery of all twenty nuclear units in Ontario. The presentation at the conference will bring the audience completely up-to-date on recent events. (author)

  10. Development of pressure boundaries leak detection technology for nuclear reactor

    International Nuclear Information System (INIS)

    Zhang Yao; Zhang Dafa; Chen Dengke; Zhang Liming

    2008-01-01

    The leak detection for the pressure boundaries is an important safeguard in nuclear reactor operation. In the paper, the status and the characters on the development of the pressure boundaries leak detection technology for the nuclear reactor were reviewed, especially, and the advance of the radiation leak detection technology and the acoustic emission leak detection technology were analyzed. The new advance trend of the leak detection technology was primarily explored. According to the analysis results, it is point out that the advancing target of the leak detection technology is to enhance its response speed, sensitivity, and reliability, and to provide effective information for operator and decision-maker. The realization of the global leak detection and the whole life cycle health monitoring for the nuclear boundaries is a significant advancing tendency of the leak detection technology. (authors)

  11. Doubts on nuclear technology

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    The conversation is concerned with the pros and cons of nuclear power with regard to growth of the economy, use of energy, energy policy and the social point of view. First of all one should cover the present energy demand with a very wide spectrum, in order to save natural oil as primary energy source. The rate of growth is predicted at too high a rate (German model). A certain undercapacity in the base load region (water power or brown coal fired and nuclear power stations) with a high excess capacity in the medium load range (hard coal or oil fired power stations with full use of refining capacity) limits the construction of nuclear power stations, but contradicts the policy using coal. The scientists cannot evade the requirement of helping the politicians to decide. (GL) [de

  12. Technology of nuclear reactors

    International Nuclear Information System (INIS)

    Ravelet, F.

    2016-01-01

    This academic report for graduation in engineering first presents operation principles of a nuclear reactor core. It presents core components, atomic nuclei, the notions of transmutation and radioactivity, quantities used to characterize ionizing radiations, the nuclear fission, statistical aspects of fission and differences between fast and slow neutrons, a comparison between various heat transfer fluids, the uranium enrichment process, and different types of reactor (boiling water, natural uranium and heavy water, pressurized water, and fourth generation). Then, after having recalled the French installed power, the author proposes an analysis of a typical 900 MWe nuclear power plant: primary circuit, reactor, fuel, spent fuel, pressurizer and primary pump, secondary circuit, aspects related to control-command, regulation, safety and exploitation. The last part proposes a modelling of the thermodynamic cycle of a pressurized water plant by using an equivalent Carnot cycle, a Rankine cycle, and a two-phase expansion cycle with drying-overheating

  13. The status of nuclear fuel cycle system analysis for the development of advanced nuclear fuel cycles

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il; Kim, Seong Ki; Lee, Hyo Jik; Chang, Hong Rae; Kwon, Eun Ha; Lee, Yoon Hee; Gao, Fanxing [KAERI, Daejeon (Korea, Republic of)

    2011-11-15

    The system analysis has been used with different system and objectives in various fields. In the nuclear field, the system can be applied from uranium mining to spent fuel reprocessing or disposal which is called the nuclear fuel cycle. The analysis of nuclear fuel cycle can be guideline for development of advanced fuel cycle through integrating and evaluating the technologies. For this purpose, objective approach is essential and modeling and simulation can be useful. In this report, several methods which can be applicable for development of advanced nuclear fuel cycle, such as TRL, simulation and trade analysis were explained with case study

  14. Industrial applications of nuclear technology

    International Nuclear Information System (INIS)

    Vargas, Celso

    2010-01-01

    Industrial applications of nuclear technology have been very diverse worldwide. This type of technology has begun to introduce in Costa Rica to evaluate and improve different industrial processes. These applications have been classified into two or three categories, according to the criteria used. Nucleonic control systems, the gamma logging and radiotracers are determined. (author) [es

  15. Proliferation Persuasion. Coercive Bargaining with Nuclear Technology

    Energy Technology Data Exchange (ETDEWEB)

    Volpe, Tristan A. [George Washington Univ., Washington, DC (United States)

    2015-08-31

    Why do states wait for prolonged periods of time with the technical capacity to produce nuclear weapons? Only a handful of countries have ever acquired the sensitive nuclear fuel cycle technology needed to produce fissile material for nuclear weapons. Yet the enduring trend over the last five decades is for these states to delay or forgo exercising the nuclear weapons option provided by uranium enrichment or plutonium reprocessing capabilities. I show that states pause at this threshold stage because they use nuclear technology to bargain for concessions from both allies and adversaries. But when does nuclear latency offer bargaining benefits? My central argument is that challengers must surmount a dilemma to make coercive diplomacy work: the more they threaten to proliferate, the harder it becomes to reassure others that compliance will be rewarded with nuclear restraint. I identify a range of mechanisms able to solve this credibility problem, from arms control over breakout capacity to third party mediation and confidence building measures. Since each step towards the bomb raises the costs of implementing these policies, a state hits a sweet spot when it first acquires enrichment and/or reprocessing (ENR) technology. Subsequent increases in proliferation capability generate diminishing returns at the bargaining table for two reasons: the state must go to greater lengths to make a credible nonproliferation promise, and nuclear programs exhibit considerable path dependency as they mature over time. Contrary to the conventional wisdom about power in world politics, less nuclear latency thereby yields more coercive threat advantages. I marshal new primary source evidence from archives and interviews to identify episodes in the historical record when states made clear decisions to use ENR technology as a bargaining chip, and employ this theory of proliferation persuasion to explain how Japan, North Korea, and Iran succeeded and failed to barter concessions from the

  16. Westinghouse AP600 advanced nuclear plant design

    International Nuclear Information System (INIS)

    Gangloff, W.

    1999-01-01

    As part of the cooperative US Department of Energy (DOE) Advanced Light Water Reactor (ALWR) Program and the Electric Power Research Institute (EPRI), the Westinghouse AP600 team has developed a simplified, safe, and economic 600-megawatt plant to enter into a new era of nuclear power generation. Designed to satisfy the standards set by DOE and defined in the ALWR Utility Requirements Document (URD), the Westinghouse AP600 is an elegant combination of innovative safety systems that rely on dependable natural forces and proven technologies. The Westinghouse AP600 design simplifies plant systems and significant operation, inspections, maintenance, and quality assurance requirements by greatly reducing the amount of valves, pumps, piping, HVAC ducting, and other complex components. The AP600 safety systems are predominantly passive, depending on the reliable natural forces of gravity, circulation, convection, evaporation, and condensation, instead of AC power supplies and motor-driven components. The AP600 provides a high degree of public safety and licensing certainty. It draws upon 40 years of experience in light water reactor components and technology, so no demonstration plant is required. During the AP600 design program, a comprehensive test program was carried out to verify plant components, passive safety systems components, and containment behavior. When the test program was completed at the end of 1994, the AP600 became the most thoroughly tested advanced reactor design ever reviewed by the US Nuclear Regulatory Commission (NRC). The test results confirmed the exceptional behavior of the passive systems and have been instrumental in facilitating code validations. Westinghouse received Final Design Approval from the NRC in September 1998. (author)

  17. Church - Technology - Nuclear Power

    International Nuclear Information System (INIS)

    May, H.

    1982-01-01

    In order to cope with the problems causing a great deal of trouble today, i.e. with fear and with the ethical substantiation of technology, the author considers an integration model necessary which is to link science and technology and religion and philosophy. (RW) [de

  18. Church - Technology - Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    May, H

    1982-03-01

    In order to cope with the problems causing a great deal of trouble today, i.e. with fear and with the ethical substantiation of technology, the author considers an integration model necessary which is to link science and technology and religion and philosophy.

  19. Nuclear safeguards technology handbook

    Energy Technology Data Exchange (ETDEWEB)

    1977-12-01

    The purpose of this handbook is to present to United States industrial organizations the Department of Energy's (DOE) Safeguards Technology Program. The roles and missions for safeguards in the U.S. government and application of the DOE technology program to industry safeguards planning are discussed. A guide to sources and products is included. (LK)

  20. Nuclear safeguards technology handbook

    International Nuclear Information System (INIS)

    1977-12-01

    The purpose of this handbook is to present to United States industrial organizations the Department of Energy's (DOE) Safeguards Technology Program. The roles and missions for safeguards in the U.S. government and application of the DOE technology program to industry safeguards planning are discussed. A guide to sources and products is included

  1. Nuclear Technology Review 2009

    International Nuclear Information System (INIS)

    2009-08-01

    The year 2008 was paradoxical for nuclear power. Projections of future growth were revised upwards, but no new reactors were connected to the grid. It was the first year since 1955 without at least one new reactor coming on-line. There were, however, ten construction starts, the most since 1985. At least until the global financial crisis, cost estimates reported for new nuclear reactors were often higher than those in previous years, particularly in regions with less recent experience in new construction. However, growth targets for nuclear power were raised in the Russian Federation, and similar considerations were under review in China. India negotiated a safeguards agreement with the Agency in August, and the Nuclear Suppliers Group subsequently exempted India from previous restrictions on nuclear trade, which should allow India to accelerate its planned expansion of nuclear power. In the USA, the Nuclear Regulatory Commission (NRC) received combined licence (COL) applications for 26 new reactors. The US Department of Energy (USDOE) received 19 'Part I applications' for Federal loan guarantees to build 21 new reactors. Nonetheless, current expansion, as well as near term and long term growth prospects, remain centred in Asia. Of the ten construction starts in 2008, eight were in Asia. Twenty-eight of the 44 reactors under construction at the end of the year were in Asia, as were 28 of the last 39 new reactors to have been connected to the grid. Armenia joined the Russian Federation and Kazakhstan as members of the International Uranium Enrichment Centre in Angarsk, Siberia. The Ukrainian Government announced that Ukraine would also join. AREVA and USEC applied to the USDOE for loan guarantees for the construction of AREVA's proposed Eagle Rock Enrichment Facility and USEC's American Centrifuge Plant. Construction of an underground repository for low and medium level radioactive waste began at the former Konrad iron mine in Germany. The USDOE submitted a formal

  2. Nuclear Technology Review 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-08-15

    The year 2008 was paradoxical for nuclear power. Projections of future growth were revised upwards, but no new reactors were connected to the grid. It was the first year since 1955 without at least one new reactor coming on-line. There were, however, ten construction starts, the most since 1985. At least until the global financial crisis, cost estimates reported for new nuclear reactors were often higher than those in previous years, particularly in regions with less recent experience in new construction. However, growth targets for nuclear power were raised in the Russian Federation, and similar considerations were under review in China. India negotiated a safeguards agreement with the Agency in August, and the Nuclear Suppliers Group subsequently exempted India from previous restrictions on nuclear trade, which should allow India to accelerate its planned expansion of nuclear power. In the USA, the Nuclear Regulatory Commission (NRC) received combined licence (COL) applications for 26 new reactors. The US Department of Energy (USDOE) received 19 'Part I applications' for Federal loan guarantees to build 21 new reactors. Nonetheless, current expansion, as well as near term and long term growth prospects, remain centred in Asia. Of the ten construction starts in 2008, eight were in Asia. Twenty-eight of the 44 reactors under construction at the end of the year were in Asia, as were 28 of the last 39 new reactors to have been connected to the grid. Armenia joined the Russian Federation and Kazakhstan as members of the International Uranium Enrichment Centre in Angarsk, Siberia. The Ukrainian Government announced that Ukraine would also join. AREVA and USEC applied to the USDOE for loan guarantees for the construction of AREVA's proposed Eagle Rock Enrichment Facility and USEC's American Centrifuge Plant. Construction of an underground repository for low and medium level radioactive waste began at the former Konrad iron mine in Germany. The USDOE submitted a formal

  3. URENCO. Uranium enrichment with advanced technology

    International Nuclear Information System (INIS)

    2011-01-01

    URENCO Deutschland is a subsidiary of URENCO Enrichment Company Limited, an international enterprise founded in 1970 in the State Treaty of Almelo, which offers uranium enrichment for nuclear power plants all over the world with the use of advanced technology. URENCO facilities at present are operated in the United Kingdom, the Netherlands, USA, and in Germany. The German URENCO location is Gronau, Westphalia, where cascades have been in operation since 1985 using centrifuge technology to enrich nuclear fuel to up to 5% uranium-235. The URENCO Group supplies nuclear power plants in Europe and overseas countries with a world market share, at present, of more than 25% with a rising tendency. The first uranium separation plant in Gronau (UTA-1) attained its full separation performance of 1,800 t USW/a in late 2005. In February 2005, construction and operation of another plant had been licensed, which can raise the aggregate capacity on site to 4,500 t USW per annum. Construction of the new plant (UTA-2) was begun in summer 2005. UTA-2 will use the latest, most powerful URENCO centrifuge. URENCO has more than 3,500 visitors a year at its German location alone, thus demonstrating its pro-active information policy and offering to the public a maximum of opportunities to acquire information by attending presentations and tours of the plant. (orig.)

  4. Development of advanced diagnostic technologies for motor-operated valves

    International Nuclear Information System (INIS)

    Hegi, Kotaro; Shimizu, Shunichi; Higuma, Koji; Nishino, Koji; Osaki, Kenji; Watanabe, Kazumi; Hamano, Frank

    2010-01-01

    As use of condition-based maintenance is allowed in the new regulatory inspection system employed in Japan's nuclear power plants in 2009, development of advanced diagnostic technologies for motor-operated valves (MOVs) is now required. This report discusses advanced technologies in valve-setup verification, valve performance evaluation, monitoring of valve/actuator conditions by performance diagnostic system and moreover detection of stem crack by ultrasonic diagnostic system. (author)

  5. Nuclear Technology Review 2011

    International Nuclear Information System (INIS)

    2011-09-01

    The accident at the Fukushima-Daiichi Nuclear Power Plant, caused by the extraordinary natural disasters of the earthquake and tsunamis that struck Japan on 11 March 2011, continues to be assessed. As this report focuses on developments in 2010, the accident and its implications are not addressed here, but will be addressed in future reports of the Agency. In 2010, construction started on sixteen new nuclear power reactors, the largest number since 1985. With five new reactors connected to the grid and only one reactor retired during the year, total nuclear power capacity around the world increased to 375 GW(e). Revised projections in 2010 of future nuclear power growth still indicated high expectations for nuclear power expansion. Expansion and near and long term growth prospects remained centred in Asia. Two thirds of the reactors currently under construction are in Asia, as were thirteen of the sixteen construction starts. Of these, ten construction starts were in China alone. Trends of uprates and renewed or extended licences for operating reactors continued in 2010, particularly in some European countries where the trend towards reconsidering policies that restricted the future use of nuclear power continued. Interest in starting new nuclear power programmes remained high, with over 60 Member States having indicated to the Agency their interest in considering the introduction of nuclear power. In the 2010 edition of the OECD/NEA-IAEA 'Red Book', estimates of identified conventional uranium resources at less than $130/kg U decreased slightly compared to the previous edition, but uranium production worldwide significantly increased due largely to increased production in Kazakhstan. Uranium spot prices, which declined in 2009, reached at the end of 2010 their highest levels in over two years topping $160/kg U, despite early and mid-year prices fluctuating between $105/kg U and $115/kg U. The Board of Governors, in December 2010, approved the establishment of an

  6. Nuclear Technology Review 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-15

    The accident at the Fukushima-Daiichi Nuclear Power Plant, caused by the extraordinary natural disasters of the earthquake and tsunamis that struck Japan on 11 March 2011, continues to be assessed. As this report focuses on developments in 2010, the accident and its implications are not addressed here, but will be addressed in future reports of the Agency. In 2010, construction started on sixteen new nuclear power reactors, the largest number since 1985. With five new reactors connected to the grid and only one reactor retired during the year, total nuclear power capacity around the world increased to 375 GW(e). Revised projections in 2010 of future nuclear power growth still indicated high expectations for nuclear power expansion. Expansion and near and long term growth prospects remained centred in Asia. Two thirds of the reactors currently under construction are in Asia, as were thirteen of the sixteen construction starts. Of these, ten construction starts were in China alone. Trends of uprates and renewed or extended licences for operating reactors continued in 2010, particularly in some European countries where the trend towards reconsidering policies that restricted the future use of nuclear power continued. Interest in starting new nuclear power programmes remained high, with over 60 Member States having indicated to the Agency their interest in considering the introduction of nuclear power. In the 2010 edition of the OECD/NEA-IAEA 'Red Book', estimates of identified conventional uranium resources at less than $130/kg U decreased slightly compared to the previous edition, but uranium production worldwide significantly increased due largely to increased production in Kazakhstan. Uranium spot prices, which declined in 2009, reached at the end of 2010 their highest levels in over two years topping $160/kg U, despite early and mid-year prices fluctuating between $105/kg U and $115/kg U. The Board of Governors, in December 2010, approved the establishment of an

  7. Current status of Chinese nuclear power industry and technology

    International Nuclear Information System (INIS)

    Kim, Hyun Min; Kim, Min; Jeong, Hee Jong; Hwang, Jeong Ki; Cho, Chung Hee

    1996-10-01

    China has been carrying out active international cooperation aiming to be a country where is to be an economical super power and an advanced country in nuclear power technology by the year early 2000, and China also has begun to be recognized as the largest potential market for the construction of nuclear power plants(NPPs) expecting to construct more than thirty nuclear power units by the year 2020. China has advanced technology in the basic nuclear science including liquid metal breeder reactor technology, nuclear material, medium and small size power plants, and isotope production technology, and also China has complete nuclear fuel cycle technology. However, China still has low NPP technology. Therefore, it is expected that China may have complementary cooperative relationship with China, it is expected that Korea may have an access to the advanced Chinese nuclear science technology, and may have a good opportunity to explore the Chinese market actively exporting excellent Korean NPP technology, and further may have a good position to the neighboring Asian countries' NPP markets. From this perspective, general Chinese social status, major nuclear R and D activity status, and correct NPP and technology status have been analyzed in this report, and this report is expected to be a useful resource for cooperating with China in future. 10 tabs., 6 figs., 16 refs. (Author)

  8. Advances in fluidized bed technologies

    International Nuclear Information System (INIS)

    Mutanen, K.

    1992-01-01

    Atmospheric fluidized bed combustion (AFBC) has advanced into industrial cogeneration and utility-scale electric generation. During the 1980's AFBC became the dominant technology in the United States for power generation systems fired with solid fuels. Development of pressurized fluidized bed combustion/gasification (PFB/G) has grown rapidly from small bench-scale rigs to large pilot and demonstration plants. AFBC as large as 160 MWe in capacity are now in operation, while pressurized combustion systems generating 80 MWe have started up two years ago. The major driving forces behind development of fluidized bed technologies are all the time strictening emission control regulations, need for fuel flexibility, repowering of older power plants and need for higher efficiency in electricity generation. Independent power producers (IPP) and cogenerators were the first ones in the United States who accepted AFBC for wide commercial use. Their role will be dominant in the markets of the 1990's also. Developers of AFBC systems are working on designs that reduce investment costs, decrease emissions and offer even higher reliability and availability in utility-scale applications while developers of PFBC/G work on designs that increase plant efficiencies, allow modular construction, decrease emissions further and reduce the cost of generating power. This paper presents technological background, commercial status, boiler performance, emissions and future developments for both AFBC and PFBC/G systems

  9. Future of nuclear energy technology in Switzerland

    International Nuclear Information System (INIS)

    Tiberini, A.; Brogli, R.; Jermann, M.; Alder, H.P.; Stratton, R.W.; Troyon, F.

    1988-01-01

    Despite the present gloom surrounding the nuclear option for electricity and heat generation, there are still people in Switzerland in industry, research, banking and even politics willing and capable to think in terms of long-range projections. The basis for these projections is the belief that a well-functioning and prosperous society always needs large and reliable sources of acceptably priced energy, which must be generated with a high respect for the necessity of a clean environment. Being aware of the current low acceptance level of the nuclear option, efforts to keep this option open are directed to achieving the following goals: to maintain and improve the country's capabilities to safely operate the four existing nuclear power plants of Beznau (twin units), Muehleberg, Goesgen and Leibstadt; to keep the capability of extending the applications of nuclear energy technology. In practice, this could be in the fields of district heating, fusion, and advanced power reactors

  10. History and current status of nuclear fuel reprocessing technology

    International Nuclear Information System (INIS)

    Funasaka, Hideyuki; Nagai, Toshihisa; Washiya, Tadahiro

    2008-01-01

    History and present state of fast breeder reactor was reviewed in series. As a history and current status of nuclear fuel reprocessing technology, this ninth lecture presented the progress of the FBR fuel reprocessing technology and advanced reprocessing processes. FBR fuel reprocessing technology had been developed to construct the reprocessing equipment test facilities (RETF) based on PUREX process technologies. With economics, reduction of environmental burdens and proliferation resistance taken into consideration, advanced aqueous method for nuclear fuel cycle activities has been promoted as the government's basic policy. Innovative technologies on mechanical disassembly, continuous rotary dissolver, crystallizer, solvent extraction and actinides recovery have been mainly studied. (T. Tanaka)

  11. Advances in medical diagnostic technology

    CERN Document Server

    Lai, Khin Wee; Mohamad Salim, Maheza Irna; Ong, Sang-Bing; Utama, Nugraha Priya; Myint, Yin Mon; Mohd Noor, Norliza; Supriyanto, Eko

    2014-01-01

    This book provides the most recent findings and knowledge in advanced diagnostics technology, covering a wide spectrum including brain activity analysis, breast and lung cancer detection, echocardiography, computer aided skeletal assessment to mitochondrial biology imaging at the cellular level. The authors explored magneto acoustic approaches and tissue elasticity imaging for the purpose of breast cancer detection. Perspectives in fetal echocardiography from an image processing angle are included. Diagnostic imaging in the field of mitochondrial diseases as well as the use of Computer-Aided System (CAD) are also discussed in the book. This book will be useful for students, lecturers or professional researchers in the field of biomedical sciences and image processing.

  12. Nuclear integrated database and design advancement system

    International Nuclear Information System (INIS)

    Ha, Jae Joo; Jeong, Kwang Sub; Kim, Seung Hwan; Choi, Sun Young.

    1997-01-01

    The objective of NuIDEAS is to computerize design processes through an integrated database by eliminating the current work style of delivering hardcopy documents and drawings. The major research contents of NuIDEAS are the advancement of design processes by computerization, the establishment of design database and 3 dimensional visualization of design data. KSNP (Korea Standard Nuclear Power Plant) is the target of legacy database and 3 dimensional model, so that can be utilized in the next plant design. In the first year, the blueprint of NuIDEAS is proposed, and its prototype is developed by applying the rapidly revolutionizing computer technology. The major results of the first year research were to establish the architecture of the integrated database ensuring data consistency, and to build design database of reactor coolant system and heavy components. Also various softwares were developed to search, share and utilize the data through networks, and the detailed 3 dimensional CAD models of nuclear fuel and heavy components were constructed, and walk-through simulation using the models are developed. This report contains the major additions and modifications to the object oriented database and associated program, using methods and Javascript.. (author). 36 refs., 1 tab., 32 figs

  13. Development of Nuclear Fuel Remote Fabrication Technology

    International Nuclear Information System (INIS)

    Lee, Jung Won; Yang, M. S.; Kim, S. S. and others

    2005-04-01

    The aim of this study is to develop the essential technology of dry refabrication using spent fuel materials in a laboratory scale on the basis of proliferation resistance policy. The emphasis is placed on the assessment and the development of the essential technology of dry refabrication using spent fuel materials. In this study, the remote fuel fabrication technology to make a dry refabricated fuel with an enhanced quality was established. And the instrumented fuel pellets and mini-elements were manufactured for the irradiation testing in HANARO. The design and development technology of the remote fabrication equipment and the remote operating and maintenance technology of the equipment in hot cell were also achieved. These achievements will be used in and applied to the future back-end fuel cycle and GEN-IV fuel cycle and be a milestone for Korea to be an advanced nuclear country in the world

  14. NASA's progress in nuclear electric propulsion technology

    International Nuclear Information System (INIS)

    Stone, J.R.; Doherty, M.P.; Peecook, K.M.

    1993-01-01

    The National Aeronautics and Space Administration (NASA) has established a requirement for Nuclear Electric Propulsion (NEP) technology for robotic planetary science mission applications with potential future evolution to systems for piloted Mars vehicles. To advance the readiness of NEP for these challenging missions, a near-term flight demonstration on a meaningful robotic science mission is very desirable. The requirements for both near-term and outer planet science missions are briefly reviewed, and the near-term baseline system established under a recent study jointly conducted by the Lewis Research Center (LeRC) and the Jet Propulsion Laboratory (JPL) is described. Technology issues are identified where work is needed to establish the technology for the baseline system, and technology opportunities which could provide improvement beyond baseline capabilities are discussed. Finally, the plan to develop this promising technology is presented and discussed. 19 refs

  15. New technologies for monitoring nuclear materials

    International Nuclear Information System (INIS)

    Moran, B.W.

    1993-01-01

    This paper describes new technologies for monitoring the continued presence of nuclear materials that are being evaluated in Oak Ridge, Tennessee, to reduce the effort, cost, and employee exposures associated with conducting nuclear material inventories. These technologies also show promise for the international safeguarding of process systems and nuclear materials in storage, including spent fuels. The identified systems are based on innovative technologies that were not developed for safeguards applications. These advanced technologies include passive and active sensor systems based on optical materials, inexpensive solid-state radiation detectors, dimensional surface characterization, and digital color imagery. The passive sensor systems use specialized scintillator materials coupled to optical-fiber technologies that not only are capable of measuring radioactive emissions but also are capable of measuring or monitoring pressure, weight, temperature, and source location. Small, durable solid-state gamma-ray detection devices, whose components are estimated to cost less than $25 per unit, can be implemented in a variety of configurations and can be adapted to enhance existing monitoring systems. Variations in detector design have produced significantly different system capabilities. Dimensional surface characterization and digital color imaging are applications of developed technologies that are capable of motion detection, item surveillance, and unique identification of items

  16. Tournament of Young Professionals: Knowledge Transfer Environment Built on Technology of Crowdsourcing to Advance Young & Best for the Russian Nuclear Industry

    International Nuclear Information System (INIS)

    Karezin, V.; Bronnikova, I.; Terentyeva, T.

    2016-01-01

    Full text: Rosatom being the flagman of the Russian nuclear industry has succession planning as one of the crucial strategic HR objectives. Therefore, it builds different approaches to assure attraction and development of the best and most promising specialists including recent and future graduates. Tournament of young professionals (TEMP) is the corner-stone initiative to select best young professionals in frames of crowdsourcing environment where participants raise the level of professional knowledge, learn to better understand the attitudes of work in the nuclear power industry, compete under the essential tasks of real production value while stakeholders build the culture of knowledge sharing. And the entire scheme rests upon knowledge transfer from the nuclear industry experts to potential hiring pool, applied knowledge accumulation, deep industry involvement and modern Web 2.0 technology capabilities. (author

  17. Nuclear technology and materials science

    International Nuclear Information System (INIS)

    Olander, D.R.

    1992-01-01

    Current and expected problems in the materials of nuclear technology are reviewed. In the fuel elements of LWRs, cladding waterside corrosion, secondary hydriding and pellet-cladding interaction may be significant impediments to extended burnup. In the fuel, fission gas release remains a key issue. Materials issues in the structural alloys of the primary system include stress-corrosion cracking of steel, corrosion of steam generator tubing and pressurized thermal shock of the reactor vessel. Prediction of core behavior in severe accidents requires basic data and models for fuel liquefaction, aerosol formation, fission product transport and core-concrete interaction. Materials questions in nuclear waste management and fusion technology are briefly reviewed. (author)

  18. ADVANCED RECIPROCATING COMPRESSION TECHNOLOGY (ARCT)

    Energy Technology Data Exchange (ETDEWEB)

    Danny M. Deffenbaugh; Klaus Brun; Ralph E. Harris; J. Pete Harrell; Robert J. Mckee; J. Jeffrey Moore; Steven J. Svedeman; Anthony J. Smalley; Eugene L. Broerman; Robert A Hart; Marybeth G. Nored; Ryan S. Gernentz; Shane P. Siebenaler

    2005-12-01

    The U.S. natural gas pipeline industry is facing the twin challenges of increased flexibility and capacity expansion. To meet these challenges, the industry requires improved choices in gas compression to address new construction and enhancement of the currently installed infrastructure. The current fleet of installed reciprocating compression is primarily slow-speed integral machines. Most new reciprocating compression is and will be large, high-speed separable units. The major challenges with the fleet of slow-speed integral machines are: limited flexibility and a large range in performance. In an attempt to increase flexibility, many operators are choosing to single-act cylinders, which are causing reduced reliability and integrity. While the best performing units in the fleet exhibit thermal efficiencies between 90% and 92%, the low performers are running down to 50% with the mean at about 80%. The major cause for this large disparity is due to installation losses in the pulsation control system. In the better performers, the losses are about evenly split between installation losses and valve losses. The major challenges for high-speed machines are: cylinder nozzle pulsations, mechanical vibrations due to cylinder stretch, short valve life, and low thermal performance. To shift nozzle pulsation to higher orders, nozzles are shortened, and to dampen the amplitudes, orifices are added. The shortened nozzles result in mechanical coupling with the cylinder, thereby, causing increased vibration due to the cylinder stretch mode. Valve life is even shorter than for slow speeds and can be on the order of a few months. The thermal efficiency is 10% to 15% lower than slow-speed equipment with the best performance in the 75% to 80% range. The goal of this advanced reciprocating compression program is to develop the technology for both high speed and low speed compression that will expand unit flexibility, increase thermal efficiency, and increase reliability and integrity

  19. Siemens technology transfer and cooperation in the nuclear fuel area

    International Nuclear Information System (INIS)

    Holley, H.-P.; Fuchs, J. H.; Rothenbuecher, R. A.

    1997-01-01

    Siemens is a full-range supplier in the area of nuclear power generation with broad experience and activities in the field of nuclear fuel. Siemens has developed advanced fuel technology for all types fuel assemblies used throughout the world and has significant experience worldwide in technology transfer in the field of nuclear fuel. Technology transfer and cooperation has ranged between the provision of mechanical design advice for a specific fuel design and the erection of complete fabrication plants for commercial operation in 3 countries. In the following the wide range of Siemens' technology transfer activities for both fuel design and fuel fabrication technologies are shown

  20. Proceedings of the second international conference on advances in nuclear materials: abstract booklet and souvenir

    International Nuclear Information System (INIS)

    2011-01-01

    Nuclear materials form special class of materials which either act as fuel for the nuclear reactors or form the structure of the reactors and the allied systems. The topics covered in this conference are: materials challenges for thermal and fast reactors, technological advances in nuclear fuels and components, materials for future reactors, fuel cycles and materials challenges, materials degradation and life management, advanced materials development, modelling and simulation, advanced materials- II, advanced materials for future reactors, development of advanced fuel and structural materials, zirconium alloy developments, irradiation effects and PIE, advanced nuclear fuels, corrosion and materials characterization. Papers relevant to INIS are indexed separately

  1. General survey of Korean advanced technology

    International Nuclear Information System (INIS)

    1984-05-01

    This book includes advanced technology, world trend of advanced technology, technological innovation study for strengthening international competitiveness, patterns of Korea industrialization and its causes, structures of Korea electronic equipment and development direction, middle and long-term prospects of home appliance, the world of computer, current situation and prospect of robot industry, homework for strengthening international competitiveness of machine industry, direction for rationalization of materials industry, current situations of technical textile, future technology of developed countries, and trend of Korea technological activities.

  2. Nuclear technology. All in good hands

    International Nuclear Information System (INIS)

    Mueller, Michaela

    2011-01-01

    Babcock Noell GmbH (BNG) has more than 40 years of practical experience and fundamental know-how in the field of nuclear technology and thus is well equipped to meet future challenges. This applies to building new nuclear power plants, upgrading and decommissioning existing facilities as well as to conditioning and storage of radioactive waste. BNG is a supplier of, among other things, components for machine technology, personnel and materials transfer locks, safety enclosures and pool liners. Outstanding, technically demanding reference projects have demonstrated BNG's capabilities. BNG is a reliable service and assembly partner to the operators of nuclear power plants and nuclear facilities. This sector of activities has as its backbone a separate team of experienced service and assembly personnel. The synergies of engineering and service competence intensively utilized by Babcock Noell GmbH are employed, inter alia, in the development and advanced development, respectively, of nuclear technology products fit for practical use, such as personnel and materials transfer locks. (orig.)

  3. Advanced Research Workshop on Preparedness for Nuclear and Radiological Threats

    CERN Document Server

    Diamond, David; Nuclear Threats and Security Challenges

    2015-01-01

    With the dissolution of the Soviet Union the nuclear threats facing the world are constantly evolving and have grown more complex since the end of the Cold War. The diversion of complete weapon systems or nuclear material to rogue nations and terrorist organizations has increased. The events of the past years have proved the necessity to reevaluate these threats on a level never before considered.  In recognition that no single country possesses all of the answers to the critical scientific, institutional and legal questions associated with combating nuclear and radiological terrorism, the NATO Advanced Research Workshop on “Preparedness for Nuclear and Radiological Threats” and this proceeding was structured to promote wide-ranging, multi-national exploration of critical technology needs and underlying scientific challenges to reducing the threat of nuclear/radiological terrorism; to illustrate through country-specific presentations how resulting technologies were used in national programs; and to outli...

  4. Robot vision for nuclear advanced robot

    International Nuclear Information System (INIS)

    Nakayama, Ryoichi; Okano, Hideharu; Kuno, Yoshinori; Miyazawa, Tatsuo; Shimada, Hideo; Okada, Satoshi; Kawamura, Astuo

    1991-01-01

    This paper describes Robot Vision and Operation System for Nuclear Advanced Robot. This Robot Vision consists of robot position detection, obstacle detection and object recognition. With these vision techniques, a mobile robot can make a path and move autonomously along the planned path. The authors implemented the above robot vision system on the 'Advanced Robot for Nuclear Power Plant' and tested in an environment mocked up as nuclear power plant facilities. Since the operation system for this robot consists of operator's console and a large stereo monitor, this system can be easily operated by one person. Experimental tests were made using the Advanced Robot (nuclear robot). Results indicate that the proposed operation system is very useful, and can be operate by only person. (author)

  5. Advanced Technology and Alternative Fuel Vehicles

    International Nuclear Information System (INIS)

    Tuttle, J.

    2001-01-01

    This fact sheet provides a basic overview of today's alternative fuel choices--including biofuels, biodiesel, electricity, and hydrogen--alternative fuel vehicles, and advanced vehicle technology, such as hybrid electric vehicles, fuel cells and advanced drive trains

  6. Handbook of advanced nuclear hydrogen safety. 1st edition

    International Nuclear Information System (INIS)

    Hino, Ryutaro; Takegami, Hiroaki; Ogawa, Toru

    2017-03-01

    In the aftermath of the Fukushima nuclear accident, safety measures against hydrogen in severe accident has been recognized as a serious technical problem in Japan. Therefore, efforts have begun to form a common knowledge base between nuclear engineers and experts on combustion and explosion, and to secure and improve future nuclear energy safety. As one of such activities, we have prepared the 'Handbook of Advanced Nuclear Hydrogen Safety'. A handbook committee consisting of Japanese experts in the fields of nuclear and combustion-explosion in universities, nuclear companies, electric companies and research institutes was established in 2012. The objective and consents of the handbook were determined, and the outline of the contents was decided. The concepts of the handbook are as follows: to show advanced nuclear hydrogen safety technologies that nuclear engineers should understand, to show hydrogen safety points to make combustion-explosion experts cooperate with nuclear engineers, to expand information on water radiolysis considering the situation from just after the Fukushima accidents and to the waste management necessary for decommissioning after the accident etc. Many experts have participated to manuscript preparation, which was the first step of forming a hydrogen community across the boundaries of fields. The hydrogen community is expected to grow along with its improvement to the knowledge base on nuclear hydrogen safety. (author)

  7. Advanced Training Technologies and Learning Environments

    Science.gov (United States)

    Noor, Ahmed K. (Compiler); Malone, John B. (Compiler)

    1999-01-01

    This document contains the proceedings of the Workshop on Advanced Training Technologies and Learning Environments held at NASA Langley Research Center, Hampton, Virginia, March 9-10, 1999. The workshop was jointly sponsored by the University of Virginia's Center for Advanced Computational Technology and NASA. Workshop attendees were from NASA, other government agencies, industry, and universities. The objective of the workshop was to assess the status and effectiveness of different advanced training technologies and learning environments.

  8. NDE reliability and advanced NDE technology validation

    International Nuclear Information System (INIS)

    Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Hutton, P.H.; Reid, L.D.; Simonen, F.A.; Spanner, J.C.; Vo, T.V.

    1989-01-01

    This paper reports on progress for three programs: (1) evaluation and improvement in nondestructive examination reliability for inservice inspection of light water reactors (LWR) (NDE Reliability Program), (2) field validation acceptance, and training for advanced NDE technology, and (3) evaluation of computer-based NDE techniques and regional support of inspection activities. The NDE Reliability Program objectives are to quantify the reliability of inservice inspection techniques for LWR primary system components through independent research and establish means for obtaining improvements in the reliability of inservice inspections. The areas of significant progress will be described concerning ASME Code activities, re-analysis of the PISC-II data, the equipment interaction matrix study, new inspection criteria, and PISC-III. The objectives of the second program are to develop field procedures for the AE and SAFT-UT techniques, perform field validation testing of these techniques, provide training in the techniques for NRC headquarters and regional staff, and work with the ASME Code for the use of these advanced technologies. The final program's objective is to evaluate the reliability and accuracy of interpretation of results from computer-based ultrasonic inservice inspection systems, and to develop guidelines for NRC staff to monitor and evaluate the effectiveness of inservice inspections conducted on nuclear power reactors. This program started in the last quarter of FY89, and the extent of the program was to prepare a work plan for presentation to and approval from a technical advisory group of NRC staff

  9. Nuclear safeguards technology 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This publication presents the results of the sixth in a series of international symposia on nuclear material safeguards. Development efforts related to safeguards for reprocessing plants constituted over twenty per cent of the programme. Other papers present results of over four years of field testing of near real time material accountancy at a plant in Japan, and results for a lesser period of time at a plant in Scotland. Papers reporting work on destructive and non-destructive measurement procedures or equipment constituted another thirty per cent of the programme, more if measurements in reprocessing and poster presentations are included. In honour of the tenth anniversary of the founding of the Safeguards Analytical Laboratory, two sessions were devoted to a review of destructive analytical measurement procedures. Some subjects received only minor attention during the Symposium. The statistical theory of random sampling, safeguards for uranium enrichment plants, material accountancy systems and several other topics appear only incidentally in the programme, but primarily because there are few remaining problems, not because there is little remaining interest

  10. Nuclear technology terms and definitions

    International Nuclear Information System (INIS)

    1979-02-01

    The terms and definitions in this standard are part of the catalogue of definitions 'Nuclear technology, terms and definitions', in eight parts; they are the latest version of the standards and draft standards of DIN 25 401, part 10 to 19, published at irregular intervals until now. (orig.) [de

  11. Nuclear Reactors and Technology; (USA)

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. (eds.)

    1991-01-01

    Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

  12. Instituto de Asuntos Nucleares: Science and technology for progress

    International Nuclear Information System (INIS)

    Ahumada, J.J.; Zuleta, S.; Lucero, E.; Guzman, O.; Zamora, H.; Briceno de M, C.

    1989-01-01

    On the thirtieth anniversary celebration of the ''Instituto de Asuntos Nucleares'', a historical review of its activities has been made, emphasizing on its politics of development, technological and scientific advances, including the goals and accomplishments attained for the uses and applications of nuclear technology in Colombia. This includes the technical assistance which is being provided by International Organizations. National and international influences are shown for each one of the technical areas: agricultural applications, industrial applications and metallurgy, biochemistry and radiopharmacy, development process, nuclear electronics, solar and non-conventional energies, gamma facility, nuclear physics, hydrology, raw materials, chemistry, health radiophysics, reactor, nuclear documentation and information center and administration

  13. The development of nuclear technology transfer

    International Nuclear Information System (INIS)

    Nack-chung Sung

    1987-01-01

    Korea, as a recipient of nuclear technology transfer, has good experience of progressively building up its indigeneous capability of nuclear technology through three stages of technology transfer, namely: technology transfer under the turnkey approach, component approach, and integrated technology transfer with a local prime contractor. Here, each stage of experience of technology transfer, with Korea as a recipient, is presented. (author)

  14. Nuclear technology and anthroposophic theory

    International Nuclear Information System (INIS)

    Leben, S.

    1982-01-01

    The construction of nuclear power plants as a solution to the current energy, crisis is controversial. That was not so in the beginning of the 'peaceful' utilization of nuclear power; with thousands of millions to promote it given as subsidies by the governments it was developing fast, until citizens' initiatives asked ecologic and moral questions delaying the further extension of this energy production. Both positions can be substantiated. But can a first judgement, too, be given with any degree of safety. And what cognitive aids are provided by the anthroposophic theory. This is demonstrated in some aspects. From the contents: The energy crisis and its apparent way out; of the causes: modern scientific methods; New forces: some facts and phenomena; Destructive powers as viewed by ancient mysteries; Of desirable states of conscience and technical forms; spelling their distortion; Nuclear powers and morality; Untimeliness in historicity; 'What's the stance of anthroposophic theory with regard to nuclear technology'. (orig./HP) [de

  15. Nuclear energy: A female technology

    International Nuclear Information System (INIS)

    Tennenbaum, J.

    1994-01-01

    Amongst the important scientific and technological revolutions of history there is none in which women have played such a substantial and many-sided role as in the development of nuclear energy. The birth of nuclear energy is not only due to Marie Curie and Lise Meitner but also to a large number of courageous 'nuclear women' who decided against all sorts of prejudices and resistances in favour of a life in research. Therefore the revolution of the atom has also become the greatest breakthrough of women in natural sciences. This double revolution is the subject of this book. Here the history of nuclear energy itself is dealt with documented with the original work and personal memories of different persons - mainly women - who have been substantially involved in this development. (orig./HP) [de

  16. Geology behind nuclear fission technology

    International Nuclear Information System (INIS)

    Dhana Raju, R.

    2005-01-01

    Geology appears to have played an important role of a precursor to Nuclear Fission Technology (NFT), in the latter's both birth from the nucleus of an atom of and most important application as nuclear power extracted from Uranium (U), present in its minerals. NFT critically depends upon the availability of its basic raw material, viz., nuclear fuel as U and/ or Th, extracted from U-Th minerals of specific rock types in the earth's crust. Research and Development of the Nuclear Fuel Cycle (NFC) depends heavily on 'Geology'. In this paper, a brief review of the major branches of geology and their contributions during different stages of NFC, in the Indian scenario, is presented so as to demonstrate the important role played by 'Geology' behind the development of NFT, in general, and NFC, in particular. (author)

  17. Export markets for nuclear technology

    International Nuclear Information System (INIS)

    Huettl, A.J.

    1985-01-01

    By late 1984, nuclear power plants were in operation or under construction in 32 countries of the globe. An additional six countries had concrete plans for building nuclear power plants. Of these 38 countries, ten have shown that they posses the necessary know-how and the technical facilities to plan and build nuclear power plants practically on their own. Seven of these ten countries have already acted as exporters of nuclear power plants, albeit with very different degrees of market penetration. In addition, there have been a number of countries for quite some time whose industries have managed to manufacture many important nuclear power plant components. Their high level of technical development and the problems frequently encountered in export financing have made them very attractive partners of the true exporters of nuclear power plants. For the future, it must be expected that some of the countries which have so far limited their efforts to the construction of nuclear power plants at home will also develop into exporters of nuclear technology. The report contains a survey of the range of nuclear products available, a list of reactor vendors, reactor lines, and data on the economics of electricity generation in nuclear plants. It then goes on to offer detailed descriptions of the market and the demand situation. Interesting chapters are devoted to the selection criteria applied by importing countries, to financing problems, and to the influences exerted by the political environment. A realistic forecast is attempted in order to make a quantitative analysis of possible export contracts up until the year 2000. (orig.) [de

  18. ISO standardization in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D [Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia); Cermak, O [Urad pro Normalizaci a Mereni, Prague (Czechoslovakia)

    1984-10-01

    The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

  19. A roadmap for nuclear energy technology

    Science.gov (United States)

    Sofu, Tanju

    2018-01-01

    The prospects for the future use of nuclear energy worldwide can best be understood within the context of global population growth, urbanization, rising energy need and associated pollution concerns. As the world continues to urbanize, sustainable development challenges are expected to be concentrated in cities of the lower-middle-income countries where the pace of urbanization is fastest. As these countries continue their trajectory of economic development, their energy need will also outpace their population growth adding to the increased demand for electricity. OECD IEA's energy system deployment pathway foresees doubling of the current global nuclear capacity by 2050 to reduce the impact of rapid urbanization. The pending "retirement cliff" of the existing U.S. nuclear fleet, representing over 60 percent of the nation's emission-free electricity, also poses a large economic and environmental challenge. To meet the challenge, the U.S. DOE has developed the vision and strategy for development and deployment of advanced reactors. As part of that vision, the U.S. government pursues programs that aim to expand the use of nuclear power by supporting sustainability of the existing nuclear fleet, deploying new water-cooled large and small modular reactors to enable nuclear energy to help meet the energy security and climate change goals, conducting R&D for advanced reactor technologies with alternative coolants, and developing sustainable nuclear fuel cycle strategies. Since the current path relying heavily on water-cooled reactors and "once-through" fuel cycle is not sustainable, next generation nuclear energy systems under consideration aim for significant advances over existing and evolutionary water-cooled reactors. Among the spectrum of advanced reactor options, closed-fuel-cycle systems using reactors with fast-neutron spectrum to meet the sustainability goals offer the most attractive alternatives. However, unless the new public-private partnership models emerge

  20. Advanced robot vision system for nuclear power plants

    International Nuclear Information System (INIS)

    Onoguchi, Kazunori; Kawamura, Atsuro; Nakayama, Ryoichi.

    1991-01-01

    We have developed a robot vision system for advanced robots used in nuclear power plants, under a contract with the Agency of Industrial Science and Technology of the Ministry of International Trade and Industry. This work is part of the large-scale 'advanced robot technology' project. The robot vision system consists of self-location measurement, obstacle detection, and object recognition subsystems, which are activated by a total control subsystem. This paper presents details of these subsystems and the experimental results obtained. (author)

  1. Application of advanced technology to LMR control

    International Nuclear Information System (INIS)

    Lindsay, R.W.

    1989-01-01

    This paper reports that key issues must be resolved to preserve the nuclear option; including new considerations for safety, economics, waste, transportation, diversion, etc. The programs at the Experimental Breeder Reactor II (EBR-II) are now carefully focused to provide answers to the above concerns in connection with the Integral Fast Reactor program at Argonne. Safety features that are inherent in plant design, coupled with automating plant control to help achieve the above objectives are more than just an issue of installing controllers and exotic algorithms, they include the complete integration of plant design, control strategy, and information presentation. Current technology development, both at Argonne and elsewhere includes efforts relating to the use of Artificial Intelligence, sensor/signal validation in many forms, pattern recognition, optimal control technologies, etc. The eBR-II effort is to identify needs, develop and/or adopt promising technologies, and integrate them into an operating power plant for proof of value. After they have proven useful at EBR-II, it is expected that they can be incorporated into advanced designs such as PRISM and/or included in backfit activities as well

  2. 2005 annual nuclear technology conference

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    This year's Annual Nuclear Technology Conference of the Deutsches Atomforum and Kerntechnische Gesellschaft was held in Nuremberg on May 10-12, 2005. More than 1 100 participants from eighteen countries make this specialized event one of the largest international conventions in the field of the peaceful uses of nuclear power, whose attendance has steadily increased over the past few years. The first day of the conference was devoted to plenary lectures traditionally dealing mainly with political and economic problems of the use of nuclear power. The partner country of JK 2005 was Switzerland. Traditionally, the program of the three-day conference was organized in the proven format of plenary sessions on the first day, followed by technical sessions, specialized sessions, poster sessions, and special events on the following days. For the third time, the ''Nuclear Campus'' was organized which successfully made the world of nuclear technology transparent to high school and university students in lectures and an exhibition. The meeting was accompanied by a technical exhibition with meeting points of manufacturers, suppliers, and service industries. (orig.)

  3. Status of advanced nuclear reactor development in Korea

    International Nuclear Information System (INIS)

    Kim, H.R.; Kim, K.K.; Kim, Y.W.; Joo, H.K.

    2014-01-01

    The Korean nuclear industry is facing new challenges to solve the spent fuel storage problem and meet the needs to diversify the application areas of nuclear energy. In order to provide solutions to these challenges, the Korea Atomic Energy Research Institute (KAERI) has been developing advanced nuclear reactors including a Sodium-cooled Fast Reactor, Very High Temperature Gas cooled Reactor (VHTR), and System-integrated Modular Advanced Reactor (SMART) with substantially improved safety, economics, and environment-friendly features. A fast reactor system is one of the most promising options for a reduction of radioactive wastes. The long-term plan for Advanced SFR development in conjunction with the pyro-process was authorized by the Korean Atomic Energy Commission in 2008. The development milestone includes specific design approval of a prototype SFR by 2020, and the construction of a prototype SFR by 2028. KAERI has been carrying out the preliminary design of a 150MWe SFR prototype plant system since 2012. The development of advanced SFR technologies and the basic key technologies necessary for the prototype SFR are also being carried out. By virtue of high-temperature heat, a VHTR has diverse applications including hydrogen production. KAERI launched a nuclear hydrogen project using a VHTR in 2006, which focused on four basic technologies: the development of design tools, very high-temperature experimental technology, TRISO fuel fabrication, and Sulfur-iodine thermo-chemical hydrogen production technology. The technology development project will be continued until 2017. A conceptual reactor design study was started in 2012 as collaboration between industry and government to enhance the early-launching of the nuclear hydrogen development and demonstration (NHDD) project. The goal of the NHDD project is to design and build a nuclear hydrogen demonstration system by 2030. KAERI has developed SMART which is a small-sized advanced integral reactor with a rated

  4. Development of the Advanced Nuclear Safety Information Management (ANSIM) System

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

  5. Physics and Advanced Technologies 2001 Annual Report

    International Nuclear Information System (INIS)

    Jacobs, R

    2002-01-01

    include: (1) Leadership of the Laboratory's Physical Data Research Program that provides fundamental physics information for the Stockpile Stewardship Program. (2) Development of the handheld Microbead Immunoassay Dipstick System that will allow relatively untrained first-responders to run sophisticated onsite diagnostics for pathogens, including those associated with biowarfare agents, by using a simple, one-step measurement. (3) Major advances in target design for inertial fusion energy research using both laser and ion-beam drivers. (4) Development of the Advanced Technology Kill Vehicle concept for use as a high-performance interceptor in a broad range of missile defense programs. Over the course of the past decade, the Laboratory has seen its major program evolve from weapons research, development, and testing, to Stockpile Stewardship. Today, the country's national security priorities are changing rapidly: nuclear security is becoming a broader set of missions, and the Laboratory is being asked to contribute to a range of new mission areas from countering bioterrorism to ensuring information security. As we embark on the twenty-first century, the new PAT Directorate is poised to help lead the Laboratory's response to the country's changing national security needs

  6. A Study on the Nuclear Technology Policy

    International Nuclear Information System (INIS)

    Oh, K. B.; Lee, K. S.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, I.; Lee, J. H.

    2007-02-01

    The objective of the study was to make policy-proposals for enhancing the effectiveness and efficiency of national nuclear technology R and D programs. To do this, environmental changes of international nuclear energy policy and trends of nuclear technology development were surveyed and analyzed. This Study analyzed trends of nuclear technology policies and developed the nuclear energy R and D innovation strategy in a viewpoint of analyzing the changes in the global policy environment associated with nuclear technology development and development of national nuclear R and D strategy

  7. Nuclear technology for the year 2000

    International Nuclear Information System (INIS)

    1987-01-01

    Eighteen papers and abstracts are presented under the following session headings: space nuclear power, health physics and dosimetry, nuclear design and thermal hydraulics, nuclear diagnostics, and fusion technology and plasma physics. The papers were processed separately for the data base

  8. ANSTO: Australian Nuclear Science and Technology Organization

    International Nuclear Information System (INIS)

    1989-01-01

    The Australian Nuclear Science and Technology Organization conducts or is engaged in collaborative research and development in the application of nuclear science and associated technology. Through its Australian radio-isotopes unit, it markets radioisotopes, their products and other services for nuclear medicine industry and research. It also operates national nuclear facilities ( HIFAR and Moata research reactors), promote training, provide advice and disseminates information on nuclear science and technology. The booklet briefly outlines these activities. ills

  9. Nuclear Systems (NS): Technology Demonstration Unit (TDU)

    Data.gov (United States)

    National Aeronautics and Space Administration — The Nuclear Systems Project demonstrates nuclear power technology readiness to support the goals of NASA's Space Technology Mission Directorate. To this end, the...

  10. Fusion of Nuclear and Emerging Technology

    International Nuclear Information System (INIS)

    Nahrul Khaer Alang Rashid

    2005-04-01

    The presentation discussed the following subjects: emerging technology; nuclear technology; fusion emerging and nuclear technology; progressive nature of knowledge; optically stimulated luminescence - application of luminescence technology to sediments; Biosystemics technology -convergence nanotechnology, ecological science, biotechnology, cognitive science and IT - prospective impact on materials science, the management of public system for bio-health, eco and food system integrity and disease mitigation

  11. Advanced Nuclear Fuels Corporation: one year later

    International Nuclear Information System (INIS)

    Bjoernard, T.A.; Sofer, G.A.

    1988-01-01

    About one year ago, after 18 years of business as a wholly owned affiliate of Exxon Corporation, Exxon Nuclear Company was acquired by Siemens/KWU and its name was changed to Advanced Nuclear Fuels Corporation (ANF). This profile describes the status of ANF one year later, principally from the European perspective but with some mention of ANF's worldwide operations to provide a balanced picture. After one year of operation as an affiliate of Siemens/KWU, ANF's role remains as an independent international supplier of nuclear fuel and services to utilities in Europe, the USA and the Far East, but with substantially augmented capabilities resulting from the new affiliation

  12. Nuclear technology databases and information network systems

    International Nuclear Information System (INIS)

    Iwata, Shuichi; Kikuchi, Yasuyuki; Minakuchi, Satoshi

    1993-01-01

    This paper describes the databases related to nuclear (science) technology, and information network. Following contents are collected in this paper: the database developed by JAERI, ENERGY NET, ATOM NET, NUCLEN nuclear information database, INIS, NUclear Code Information Service (NUCLIS), Social Application of Nuclear Technology Accumulation project (SANTA), Nuclear Information Database/Communication System (NICS), reactor materials database, radiation effects database, NucNet European nuclear information database, reactor dismantling database. (J.P.N.)

  13. Interviews concerning topical questions in nuclear technology

    International Nuclear Information System (INIS)

    Segatz, U.; Schatz, A.; Stephany, M.; Michaelis, H.

    1978-01-01

    On the occasion of the Nuclex meeting, October 3-7, 1978, Basle/Switzerland, the editorial department of 'Atom und Strom' questioned some leading scientists in nuclear technology on particularly relevant topics. The following subjects were discussed: - How long can we do without nuclear energy, - Modern technology for nuclear power plants, - Nuclear fuel cycle and environment, - Nuclear energy and European Communities, - Nuclear energy and its risks (reflections on incidents). (orig./UA) [de

  14. Advanced nuclear systems in comparison

    International Nuclear Information System (INIS)

    Brogli, R.; Foskolos, K.; Goetzmann, C.; Kroeger, W.; Stanculescu, A.; Wydler, P.

    1996-09-01

    This study aims at a comparison of future reactor concepts, paying particular attention to aspects of safety, of the fuel cycle, the economics, the experience-base and the state of development. Representative examples of typical development lines, that could possibly be 'of interest' within a time horizon of 50 years were selected for comparison. This can be divided into three phases: - Phase I includes the next 10 years and will be characterised mainly by evolutionary developments of light water reactors (LWR) of large size; representative: EPR, - Phase II: i.e. the time between 2005 and 2020 approximately, encompasses the forecasted doubling of today's world-wide installed nuclear capacity; along with evolutionary reactors, innovative systems like AP600, PIUS, MHTGR, EFR will emerge, - Phase III covers the time between 2020 and 2050 and is characterised by the issue of sufficient fissile material resources; novel fast reactor systems including hybrid systems can, thus, become available; representatives: IFR, EA, ITER (the latter being). The evaluated concepts foresee partly different fuel cycles. Fission reactors can be operated in principle on the basis of either a Uranium-Plutonium-cycle or a Thorium-Uranium-cycle, while combinations of these cycles among them or with other reactor concepts than proposed are possible. With today's nuclear park (comprising mainly LWRs), the world-wide plutonium excess increases annually by about 100 t. Besides strategies based on reprocessing like: - recycling in thermal and fast reactors with mixed oxide fuels, - plutonium 'burning' in reactors with novel fuels without uranium or in 'hybrid' systems, allowing a reduction of this excess, direct disposal of spent fuel elements including their plutonium content ('one-through') is being considered. (author) figs., tabs., 32 refs

  15. Advanced information technology for training and emergency management

    International Nuclear Information System (INIS)

    Wahlstroem, B.

    1989-01-01

    Modern information technology provides many possibilities for improving both the safety and the availability of nuclear installations. A Nordic research programme was started in 1977, in which several organizations in Denmark, Finland, Norway and Sweden has been participating. The work has on a general level been addressing control rooms, human reliability and information technology for nuclear power plants. The research has had impact on the development of the control room solutions and the training simulators in Finland and also in the other Nordic countries. The present phase of the Nordic cooperation is investigating the use of advanced information technology in emergency management. The paper gives a brief introduction to the use of advance information technology for training and emergency management, which is based on the experience from the Nordic projects and other similar application projects in Finland. The paper includes also references to results from several of the projects. (author)

  16. Reexamining the Ethics of Nuclear Technology.

    Science.gov (United States)

    Andrianov, Andrei; Kanke, Victor; Kuptsov, Ilya; Murogov, Viktor

    2015-08-01

    This article analyzes the present status, development trends, and problems in the ethics of nuclear technology in light of a possible revision of its conceptual foundations. First, to better recognize the current state of nuclear technology ethics and related problems, this article focuses on presenting a picture of the evolution of the concepts and recent achievements related to technoethics, based on the ethics of responsibility. The term 'ethics of nuclear technology' describes a multidisciplinary endeavor to examine the problems associated with nuclear technology through ethical frameworks and paradigms. Second, to identify the reasons for the intensification of efforts to develop ethics in relation to nuclear technology, this article presents an analysis of the recent situation and future prospects of nuclear technology deployment. This includes contradictions that have aggravated nuclear dilemmas and debates stimulated by the shortcomings of nuclear technology, as well as the need for the further development of a nuclear culture paradigm that is able to provide a conceptual framework to overcome nuclear challenges. Third, efforts in the field of nuclear technology ethics are presented as a short overview of particular examples, and the major findings regarding obstacles to the development of nuclear technology ethics are also summarized. Finally, a potential methodological course is proposed to overcome inaction in this field; the proposed course provides for the further development of nuclear technology ethics, assuming the axiological multidisciplinary problematization of the main concepts in nuclear engineering through the basic ethical paradigms: analytical, hermeneutical, and poststructuralist.

  17. The impacts of wind technology advancement on future global energy

    International Nuclear Information System (INIS)

    Zhang, Xiaochun; Ma, Chun; Song, Xia; Zhou, Yuyu; Chen, Weiping

    2016-01-01

    Highlights: • Integrated assessment model perform a series of scenarios of technology advances. • Explore the potential roles of wind energy technology advance in global energy. • Technology advance impacts on energy consumption and global low carbon market. • Technology advance influences on global energy security and stability. - Abstract: To avoid additional global warming and environmental damage, energy systems need to rely on the use of low carbon technologies like wind energy. However, supply uncertainties, production costs, and energy security are the main factors considered by the global economies when reshaping their energy systems. Here, we explore the potential roles of wind energy technology advancement in future global electricity generations, costs, and energy security. We use an integrated assessment model performing a series of technology advancement scenarios. The results show that double of the capital cost reduction causes 40% of generation increase and 10% of cost ​decrease on average in the long-term global wind electricity market. Today’s technology advancement could bring us the benefit of increasing electricity production in the future 40–50 years, and decreasing electricity cost in the future 90–100 years. The technology advancement of wind energy can help to keep global energy security and stability. An aggressive development and deployment of wind energy could in the long-term avoid 1/3 of gas and 1/28 of coal burned, and keep 1/2 biomass and 1/20 nuclear fuel saved from the global electricity system. The key is that wind resources are free and carbon-free. The results of this study are useful in broad coverage ranges from innovative technologies and systems of renewable energy to the economic industrial and domestic use of energy with no or minor impact on the environment.

  18. Innovation in nuclear energy technology

    International Nuclear Information System (INIS)

    Dujardin, Th.; Bertel, E.; Kwang Seok, Lee; Foskolos, K.

    2007-01-01

    Innovation has been a driving force for the success of nuclear energy and remains essential for its sustainable future. Many research and development programmes focus on enhancing the performance of power plants in operation, current fuel design and characteristics, and fuel cycle processes used in existing facilities. Generally performed under the leadership of the industry. Some innovation programmes focus on evolutionary reactors and fuel cycles, derived from systems of the current generation. Such programmes aim at achieving significant improvements, in the field of economics or resource management for example, in the medium term. Often, they are undertaken by the industry with some governmental support as they require basic research together with technological development and adaptation. Finally, large programmes, often undertaken in an international, intergovernmental framework are devoted to design and development of a new generation of systems meeting the goals of sustainable development in the long term. Driving forces for nuclear innovation vary depending on the target technology, the national framework and the international context surrounding the research programme. However, all driving factors can be grouped in three categories: market drivers, political drivers and technology drivers. Globally, innovation in the nuclear energy sector is a success story but is a lengthy process that requires careful planning and adequate funding to produce successful outcomes

  19. Advanced research workshop: nuclear materials safety

    International Nuclear Information System (INIS)

    Jardine, L J; Moshkov, M M.

    1999-01-01

    The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of

  20. Annual meeting on nuclear technology 2005. Proceedings

    International Nuclear Information System (INIS)

    2005-03-01

    The proceedings of the annual meeting on nuclear technology 2005 covers the following issues: (1) reactor physics and methods of calculation: design and transients; method development and validation; (2): thermodynamics and fluid dynamics: analytical thermohydraulics for existing reactors; experiments and operational behavior; analytical methods for innovative reactors; (3) Safety of nuclear installations - methods, analysis, results: special problems; PSA and in-vessel phenomena; ex-vessel phenomena; (4) front end and back end of the fuel cycle, radioactive waste, storage: intermediate storage of fuel elements, waste treatment, (5) fuel elements and core components: fuel elements, new methods in the interpretation, manufacturing and service; (6) operation of nuclear installations: experience with the operation of NPPs; management systems, digital instrumentation and control of NPPs revision management; (7) decommissioning of nuclear installations: concepts and strategies for decommissioning and dismantling; experiences with decommissioning projects; (8) fusion technology: fusion facilities; materials and test facility; cryo technique and simulations; (9) research reactors: building new and backfitting of existing research reactors; current development; dismantling of research reactors; (10) advanced reactor concepts, energy systems, energy economics; (11) communication with the public; (12) component materials, fabrication and service behavior: degradation effects of component materials; component behavior; (13): radiation protection: PSA and in-vessel phenomena, ex-vessel phenomena.

  1. China nuclear science and technology reports

    International Nuclear Information System (INIS)

    1987-01-01

    114 abstracts of nuclear science and technology reports, which were published in 1986-1987 in China, are collected. The subjects inclucled are: nuclear physics, nuclear medicine, radiochemistry, isotopes and their applications, reactors and nuclear power plants, radioactive protection, nuclear instruments etc... They are arranged in accordance with the INIS subject categories, and a report number index is annexed

  2. Application of advanced technology to LMR control

    International Nuclear Information System (INIS)

    Lindsay, R.W.

    1989-01-01

    Key issues must be resolved to preserve the nuclear option; including new considerations for safety, economics, waste, transportation, diversion, etc. The programs at the Experimental Breeder Reactor II (EBR-II) are now carefully focused to provide answers to the above concerns in connection with the Integral Fast Reactor program at Argonne. Safety features that are inherent in plant design, coupled with automating plant control to help achieve the above objectives are more than just an issue of installing controllers and exotic algorithms, they include the complete integration of plant design, control strategy, and information presentation. Current technology development, both at Argonne and elsewhere includes efforts relating to the use of Artificial Intelligence, sensor/signal validation in many forms, pattern recognition, optimal develop and/or adopt promising technologies, and integrate them into an operating power plant for proof of value. After they have proven useful at EBR-II, it is expected that they can be incorporated into advanced designs such as PRISM and/or included in backfit activities as well. 6 refs

  3. A project in support of Nuclear Technology Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho (and others)

    2005-12-15

    Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate.

  4. Advances in information technologies for electromagnetics

    CERN Document Server

    Tarricone, Luciano

    2006-01-01

    Talks about the achieved and potentially obtainable advances in electromagnetics with innovative IT technologies. This work contains tutorial chapters, which introduce technologies, such as parallel and distributed computing, object-oriented technologies, grid computing, semantic grids, agent based computing and service-oriented architectures.

  5. Let nuclear technology create new brilliancy for china's sustainable development

    International Nuclear Information System (INIS)

    Du Xiangwan

    2008-01-01

    This paper summarizes the development and application directions of nuclear technology, including five aspects: nuclear technology and energy nuclear technology and medicine, nuclear anclear analysis technology, nuclear radiation technology, astronautics and voyage's nuclear power, etc. The paper discusses the importance of them to sustainable development and generalizes the development trilogy of nuclear science and technology and its prospect. (authors)

  6. 9th Pacific Basin Nuclear Conference. Nuclear energy, science and technology - Pacific partnership. Proceedings Volume 1

    International Nuclear Information System (INIS)

    1994-04-01

    The theme of the 9th Pacific Basin Nuclear conference held in Sydney from 1-6 May 1994, embraced the use of the atom in energy production and in science and technology. The focus was on selected topics of current and ongoing interest to countries around the Pacific Basin. The two-volume proceedings include both invited and contributed papers. They have been indexed separately. This document, Volume 1 covers the following topics: Pacific partnership; perspectives on nuclear energy, science and technology in Pacific Basin countries; nuclear energy and sustainable development; economics of the power reactors; new power reactor projects; power reactor technology; advanced reactors; radioisotope and radiation technology; biomedical applications

  7. National project : advanced robot for nuclear power plant

    International Nuclear Information System (INIS)

    Tsunemi, T.; Takehara, K.; Hayashi, T.; Okano, H.; Sugiyama, S.

    1993-01-01

    The national project 'Advanced Robot' has been promoted by the Agency of Industrial science and Technology, MITI for eight years since 1983. The robot for a nuclear plant is one of the projects, and is a prototype intelligent one that also has a three dimensional vision system to generate an environmental model, a quadrupedal walking mechanism to work on stairs and four fingered manipulators to disassemble a valve with a hand tool. Many basic technologies such as an actuator, a tactile sensor, autonomous control and so on progress to high level. The prototype robot succeeded functionally in official demonstration in 1990. More refining such as downsizing and higher intelligence is necessary to realize a commercial robot, while basic technologies are useful to improve conventional robots and systems. This paper presents application studies on the advanced robot technologies. (author)

  8. Development of inherent core technologies for advanced reactor

    International Nuclear Information System (INIS)

    Kim, Keung Koo; Noh, J.M.; Hwang, D.H.

    1999-03-01

    Recently, the developed countries made their effort on developing the advanced reactor which will result in significantly enhanced safety and economy. However, they will protect the advanced reactor and its design technology with patent and proprietary right. Therefore, it is very important to develop our own key core concepts and inherent core design technologies which can form a foundation of indigenous technologies for development of the domestic advanced reactor in order to keep the superiority in the nuclear plant building market among the developing countries. In order to provide the basic technology for the core design of advanced reactor, this project is for developing the inherent core design concepts with enhanced safety and economy, and associated methodologies and technologies for core analyses. The feasibility study of constructing domestic critical facilities are performed by surveying the status and utilization of foreign facilities and by investigating the demand for domestic facilities. The research results developed in this project, such as core analysis methodologies for hexagonal core, conceptual core design based on hexagonal fuel assemblies and soluble boron core design and control strategies, will provide a technical foundation in developing core design of domestic advanced reactor. Furthermore, they will strengthen the competitiveness of Korean nuclear technology. We also expect that some of the design concepts developed in this project to improve the reactor safety and economy can be applicable to the design of advanced reactor. This will significantly reduce the public anxiety on the nuclear power plant, and will contribute to the economy of construction and operation for the future domestic reactors. Even though the critical facility will not be constructed right now, the investigation of the status and utilization of foreign critical facility will contribute to the future critical facility construction. (author). 150 refs., 34 tabs., 103

  9. Development of inherent core technologies for advanced reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Keung Koo; Noh, J.M.; Hwang, D.H. [and others

    1999-03-01

    Recently, the developed countries made their effort on developing the advanced reactor which will result in significantly enhanced safety and economy. However, they will protect the advanced reactor and its design technology with patent and proprietary right. Therefore, it is very important to develop our own key core concepts and inherent core design technologies which can form a foundation of indigenous technologies for development of the domestic advanced reactor in order to keep the superiority in the nuclear plant building market among the developing countries. In order to provide the basic technology for the core design of advanced reactor, this project is for developing the inherent core design concepts with enhanced safety and economy, and associated methodologies and technologies for core analyses. The feasibility study of constructing domestic critical facilities are performed by surveying the status and utilization of foreign facilities and by investigating the demand for domestic facilities. The research results developed in this project, such as core analysis methodologies for hexagonal core, conceptual core design based on hexagonal fuel assemblies and soluble boron core design and control strategies, will provide a technical foundation in developing core design of domestic advanced reactor. Furthermore, they will strengthen the competitiveness of Korean nuclear technology. We also expect that some of the design concepts developed in this project to improve the reactor safety and economy can be applicable to the design of advanced reactor. This will significantly reduce the public anxiety on the nuclear power plant, and will contribute to the economy of construction and operation for the future domestic reactors. Even though the critical facility will not be constructed right now, the investigation of the status and utilization of foreign critical facility will contribute to the future critical facility construction. (author). 150 refs., 34 tabs., 103

  10. The German competence network on nuclear technology

    International Nuclear Information System (INIS)

    Kuczera, B.; Fritz, P.

    2004-01-01

    Full text: The present German energy policy is based on the phase-out of nuclear electricity generation, which means that the last of the currently operating eighteen German nuclear power plants will run until about 2022. While the plants will be shut down one after the other, decommissioning will start together with interim storage of the radioactive waste. The safe waste disposal in a final repository is planned to start around 2030 and may take another two decades, i.e., in Germany nuclear competence is further needed, at least until the mid of this century. Against this background, a high-ranking commission under the direction of the Federal Ministry of Economy and Technology evaluated the publicly funded nuclear safety related research and development (R and D) activities in Germany. One of the recommendations made by the commission was the foundation of a Competence Network on Nuclear Technology for an optimum coordination of the remaining nuclear activities including aspects of future human resources in this area. This Network was established in March 2000 with the following member institutions: Research Centre Juelich, Research Centre Karlsruhe, Research Centre Rossendorf and the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) in Munich and their neighbouring Technical Universities. The strategic objectives of the Competence Network include: Trend investigations on job development and on university education capacities in the nuclear technology sector; Enhanced cooperation of the Research Centres with universities in the nuclear field and support of international education initiatives (e.g. ENEN, WNU); Coordination and bundling of the activities in publicly funded reactor safety and waste management R and D programmes; Support of qualified young scientists and engineers (pre-doctoral students) - also by third-party funds; Participation in and collaboration with international projects and activities for advancements of international nuclear safety

  11. Material Protection, Accounting, and Control Technologies (MPACT) Advanced Integration Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Durkee, Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Cipiti, Ben [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fallgren, Andrew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jarman, Ken [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Li, Shelly [Argonne National Lab. (ANL), Argonne, IL (United States); Meier, Dave [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Miller, Mike [Argonne National Lab. (ANL), Argonne, IL (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Dasari, Venkateswara Rao [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ticknor, Lawrence O. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-09-30

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling, simulation and integration.

  12. Material Protection, Accounting, and Control Technologies (MPACT) Advanced Integration Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Mike [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cipiti, Ben [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Durkee, Jr., Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fallgren, Andrew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jarman, Ken [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Li, Shelly [Idaho National Lab. (INL), Idaho Falls, ID (United States); Meier, Dave [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Dasari, Venkateswara Rao [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ticknor, Lawrence O. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-30

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling, simulation and integration.

  13. Nuclear technologies for local energy systems

    International Nuclear Information System (INIS)

    McDonnell, F.N.; Lynch, G.F.

    1990-03-01

    If nuclear energy is to realize its full potential as a safe and cost-effective alternative to fossil fuels, applications beyond those that are currently being serviced by large, central nuclear power stations must be identified and appropriate reactors developed. The Canadian program on reactor systems for local energy supply is at the forefront of these developments. This program emphasizes design simplicity, low power density and fuel rating, reliance on natural processes, passive systems, and reduced reliance on operator action. The first product, the SLOWPOKE Energy System, is a 10 MW heat source specifically designed to provide hot water to satisfy the needs of local heating systems for building complexes, institutions and municipal district heating systems. A demonstration heating reactor has been constructed at the Whiteshell Nuclear Research Establishment in Manitoba and has been undergoing an extensive test program since first operation in 1987 July. Based on the knowledge learned from the design, construction, licensing and operational testing of this facility, the design of the 10 MW commercial-size unit is well advanced, and Atomic Energy of Canada Limited is prepared to commit the construction of the first commercial unit. Although the technical demonstration of the concept is important, it is recognized that another crucial element is the public and regulatory acceptance of small nuclear systems in urban areas. The decision by a community to commit the construction of a SLOWPOKE Energy System brings to a sharp focus the current public apprehension about nuclear technologies

  14. Unlocking the atom : the Canadian book on nuclear technology

    International Nuclear Information System (INIS)

    Tammemagi, H.; Jackson, D.

    2002-01-01

    This book describes Canada's role in developing a world-class reactor, medical isotope and food irradiation systems and it's leading role in uranium mining. It gives an introduction to both natural and man-made radiation and covers the spectrum of nuclear technology that includes power reactors, nuclear safety, nuclear waste, medicine, uranium, fusion, industrial and research applications. The second chapter in this book introduces the reader to nuclear fission, the fission reactor, nuclear weapons and the Candu Nuclear Power Reactor. The third chapter familiarizes the reader with different types of natural and man-made radiations. The fourth chapter discusses the biological effects of radiation. Electricity and the different technologies to produce electrical power are the subject of chapter five. The Candu reactor and the various Candu designs and performance are discussed in some detail in chapter six. In chapter seven the authors discuss the different types of reactors that have been constructed worldwide. Nuclear safety and nuclear regulations are the subject of chapter eight. In chapter nine the authors discuss nuclear power and the environment. High-level nuclear waste and nuclear waste disposal are discussed in chapter ten. Diagnostic and therapeutic nuclear medicine is the subject of chapter eleven. The benefits of nuclear technology in industry and science are discussed in chapter twelve. Uranium mining and uranium as the nuclear fuel are discussed in chapter thirteen. Chapter fourteen discusses the future of fission with respect to advanced Candu fuel cycles and advanced Candu reactor designs. Chapter fifteen is a discussion of nuclear fusion and Canada's role in fusion research. Chapter sixteen discusses nuclear science and research and the role of the National nuclear laboratory and the universities

  15. Advanced I and C systems for nuclear power plants feedback of experience

    International Nuclear Information System (INIS)

    Prehler, H.J.

    2001-01-01

    Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS.(author)

  16. Nuclear technology review 2003 update

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-09-01

    Worldwide there were 441 nuclear power plants (NPPs) operating at the end of 2002.These supplied 16% of global electricity generation in 2002, down slightly from 16.2% in 2001.1 Table 1 summarizes world nuclear experience as of the end of 2002. The global energy availability factor for NPPs rose to 83.4% in 2001, from 82.1% in 2000 and 74.2% in 1991. In 2002, upratings calculated from data on the IAEA's Power Reactor Information System (PRIS) totalled approximately 672 MW(e), of which the United States of America accounted for 574 MW(e) and the United Kingdom accounted for 98 MW(e).The United States Nuclear Regulatory Commission (NRC) expects applications for 2270 MW(e) worth of upratings over the next five years. Six new NPPs were connected to the grid in 2000, three in 2001, and six in 2002. There were three retirements in 2000: Chernobyl-3 in Ukraine and two units at Hinkley Point A in the United Kingdom.There were no retirements in 2001 and four in 2002:Kozloduy-1 and -2 in Bulgaria and Bradwell units A and B in the UK. In 2002, construction started on seven new NPPs: six in India and one in the Democratic People's Republic of Korea. This issue covers the following topics: Medium-Term Projections; Sustainable Development; Resources And Fuel; Decommissioning; Advanced Designs; Research Reactors; Waste From Non-Power Applications; Nuclear Knowledge; Matters Of Interest To The IAEA Arising From The World Summit On Sustainable Development; International Project On Innovative Nuclear Reactors And Fuel Cycles (INPRO); Knowledge Management; Key Commitments, Targets And Timetables From The Johannesburg Plan Of Implementation; Management Of The Natural Resource Base.

  17. Nuclear technology review 2003 update

    International Nuclear Information System (INIS)

    2003-09-01

    Worldwide there were 441 nuclear power plants (NPPs) operating at the end of 2002.These supplied 16% of global electricity generation in 2002, down slightly from 16.2% in 2001.1 Table 1 summarizes world nuclear experience as of the end of 2002. The global energy availability factor for NPPs rose to 83.4% in 2001, from 82.1% in 2000 and 74.2% in 1991. In 2002, upratings calculated from data on the IAEA's Power Reactor Information System (PRIS) totalled approximately 672 MW(e), of which the United States of America accounted for 574 MW(e) and the United Kingdom accounted for 98 MW(e).The United States Nuclear Regulatory Commission (NRC) expects applications for 2270 MW(e) worth of upratings over the next five years. Six new NPPs were connected to the grid in 2000, three in 2001, and six in 2002. There were three retirements in 2000: Chernobyl-3 in Ukraine and two units at Hinkley Point A in the United Kingdom.There were no retirements in 2001 and four in 2002:Kozloduy-1 and -2 in Bulgaria and Bradwell units A and B in the UK. In 2002, construction started on seven new NPPs: six in India and one in the Democratic People's Republic of Korea. This issue covers the following topics: Medium-Term Projections; Sustainable Development; Resources And Fuel; Decommissioning; Advanced Designs; Research Reactors; Waste From Non-Power Applications; Nuclear Knowledge; Matters Of Interest To The IAEA Arising From The World Summit On Sustainable Development; International Project On Innovative Nuclear Reactors And Fuel Cycles (INPRO); Knowledge Management; Key Commitments, Targets And Timetables From The Johannesburg Plan Of Implementation; Management Of The Natural Resource Base

  18. Advanced technology for future regional transport aircraft

    Science.gov (United States)

    Williams, L. J.

    1982-01-01

    In connection with a request for a report coming from a U.S. Senate committee, NASA formed a Small Transport Aircraft Technology (STAT) team in 1978. STAT was to obtain information concerning the technical improvements in commuter aircraft that would likely increase their public acceptance. Another area of study was related to questions regarding the help which could be provided by NASA's aeronautical research and development program to commuter aircraft manufacturers with respect to the solution of technical problems. Attention is given to commuter airline growth, current commuter/region aircraft and new aircraft in development, prospects for advanced technology commuter/regional transports, and potential benefits of advanced technology. A list is provided of a number of particular advances appropriate to small transport aircraft, taking into account small gas turbine engine component technology, propeller technology, three-dimensional wing-design technology, airframe aerodynamics/propulsion integration, and composite structure materials.

  19. 2012 annual meeting on nuclear technology. Workshop on 'Preservation of competence in nuclear technology'

    International Nuclear Information System (INIS)

    Steinwarz, Wolfgang

    2012-01-01

    Within the 2-day workshop on 'Preservation of Competence in Nuclear Technology,' 31 young scientists competed for the 'Competence Prize' awarded by Siempelkamp Nukleartechnik for the 14th time. They reported about their papers focusing on nuclear technology, reactor technology, innovative reactor systems, radioactive waste management, radiological protection and energy supply systems. The jury composed of Prof. J. Starflinger (Universitaet Stuttgart, IKE), Prof. M.K. Koch (Ruhr-Universitaet Bochum, LEE), and Dr. W. Steinwarz (Siempelkamp Nukleartechnik) assessed the advance compacts as well as the oral presentations. The winner of the 2012 Competence Prize is Dipl.-Ing.(M.S.) Thomas M. Fesich (University Stuttgart). Dr.-Ing. Oliver Czaikowski (Techn. University Clausthal) and Dipl.-Ing. Mario Kuschewski (Universitaet Stuttgart) won the second and third prizes. (orig.)

  20. Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology part II : Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment

    International Nuclear Information System (INIS)

    Sukarsono, R.; Ganang Suradjijo

    2002-01-01

    Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. This proceedings contains a proposal about basic research in nuclear technology which has environment. This proceedings is the second part of the two parts which published in series. There are 57 articles which have separated index. (PPIN)

  1. The Technology of Nuclear Warfare

    International Nuclear Information System (INIS)

    Broda, E.

    1979-01-01

    The present technical status of the nuclear weapon system and of the systems for their delivery is explained. All these systems have made tremendous progress since the 1960s. Available destructive power now is literally millions of times larger than at the time of Hiroshima. Moreover, technical progress has had, especially through the MIRV principle and the cruise missile, a destabilizing influence and threatens the equilibrium of terror. New strategy doctrines for winning rather than preventing nuclear war are developed. According to the counterforce strategy the retaliation capacity of the opponent is to be destroyed by a surprise attack. Moreover, plans for the tactical first-use of nuclear weapons have been accepted. In a nuclear conflict, the commanders-in-chief are overburdened by the need for ultra-urgent decisions. As a consequence tendencies in the direction of increasing automatization become ever more conspicuous. In the extreme case, decisions may be entirely left to machines, and man would not any more be included in decision-making. The increasing automatization leads to further escalation of insecurity for the whole world. A solution cannot be found on the level of technology, but only on that of practical peace policy. (author)

  2. History of nuclear technology development in Japan

    Science.gov (United States)

    Yamashita, Kiyonobu

    2015-04-01

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  3. History of nuclear technology development in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Kiyonobu, E-mail: yamashita.kiyonobu@jaea.go.jp [Visiting Professor, at the Faculty of Petroleum and Renewable Energy Engineering, University Teknologi Malaysia Johor Bahru 81310 (Malaysia); General Advisor Nuclear HRD Centre, Japan Atomic Energy Agency, TOKAI-mura, NAKA-gun, IBARAKI-ken, 319-1195 (Japan)

    2015-04-29

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

  4. History of nuclear technology development in Japan

    International Nuclear Information System (INIS)

    Yamashita, Kiyonobu

    2015-01-01

    Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident

  5. ISO standardization in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D. (Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia)); Cermak, O. (Urad pro Normalizaci a Mereni, Prague (Czechoslovakia))

    1984-10-01

    The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

  6. Development of nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

    Suzuoki, Akira; Matsumoto, Takashi; Suzuki, Kazumichi; Kawamura, Fumio

    1995-01-01

    In the long term plan for atomic energy that the Atomic Energy Commission decided the other day, the necessity of the technical development for establishing full scale fuel cycle for future was emphasized. Hitachi Ltd. has engaged in technical development and facility construction in the fields of uranium enrichment, MOX fuel fabrication, spent fuel reprocessing and so on. In uranium enrichment, it took part in the development of centrifuge process centering around Power Reactor and Nuclear Fuel Development Corporation (PNC), and took its share in the construction of the Rokkasho uranium enrichment plant of Japan Nuclear Fuel Service Co., Ltd. Also it cooperates with Laser Enrichment Technology Research Association. In Mox fuel fabrication, it took part in the construction of the facilities for Monju plutonium fuel production of PNC, for pellet production, fabrication and assembling processes. In spent fuel reprocessing, it cooperated with the technical development of maintenance and repair of Tokai reprocessing plant of PNC, and the construction of spent fuel stores in Rokkasho reprocessing plant is advanced. The centrifuge process and the atomic laser process of uranium enrichment are explained. The high reliability of spent fuel reprocessing plants and the advancement of spent fuel reprocessing process are reported. Hitachi Ltd. Intends to exert efforts for the technical development to establish nuclear fuel cycle which increases the importance hereafter. (K.I.)

  7. Advancing Binaural Cochlear Implant Technology

    Directory of Open Access Journals (Sweden)

    Mathias Dietz

    2015-12-01

    Full Text Available This special issue contains a collection of 13 papers highlighting the collaborative research and engineering project entitled Advancing Binaural Cochlear Implant Technology—ABCIT—as well as research spin-offs from the project. In this introductory editorial, a brief history of the project is provided, alongside an overview of the studies.

  8. ADVANCED TECHNOLOGIES OF ELECTRONIC EDUCATIONAL SYSTEMS DEVELOPMENT

    Directory of Open Access Journals (Sweden)

    M. Shishkina

    2011-11-01

    Full Text Available Actual problems and contradictions of electronic educational systems development are described: availability of education, quality of educational services; individualization of education; exposures and advantages in using of computer technology; standardization of technologies and resources. Tendencies of their solution in the view of development of new advanced technologies of e-education are specified. The essence and advantages of using the cloud computing technologies as a new platform of distributed learning are specified. Advanced directions of cloud-based data usage in executive system of education are declared: access management, content management, asset management, communications management.

  9. Advanced location-based technologies and services

    CERN Document Server

    Karimi, Hassan A

    2013-01-01

    Due to the rapid increase in the number of mobile device users worldwide, location-based services (LBSs) have become pervasive, and the demand for them will continue to grow. Exploring recent changes in the technology and its uses, Advanced Location-Based Technologies and Services takes an in-depth look at new and existing technologies, techniques, applications, and opportunities. Under the editorial guidance of Hassan Karimi, with contributions from experts in the field, the book examines the breadth and depth of advanced LBS technologies and techniques. The book provides up-to-date informati

  10. LTE-Advanced Relay Technology and Standardization

    CERN Document Server

    Yuan, Yifei

    2013-01-01

    LTE-Advanced Relay Technology and Standardization provides a timely reference work for relay technology with the finalizing of LTE Release 10 specifications. LTE-Advanced is quickly becoming the global standard for 4G cellular communications. The relay technology, as one of the key features in LTE-Advanced, helps not only to improve the system coverage and capacity, but also to save the costs of laying wireline backhaul. As a leading researcher in the field of LTE-Advanced standards, the author provides an in-depth description of LTE-A relay technology, and explains in detail the standard specification and design principles.     Readers from both academic and industrial fields can find sections of interest to them: Sections 2 & 4 could benefit researchers in academia and those who are engaged in exploratory work, while Sections 3 & 4 are more useful to engineers. Dr. Yifei Yuan is the Technical Director at the Standards Department of ZTE Inc.

  11. Ground-based Nuclear Detonation Detection (GNDD) Technology Roadmap

    International Nuclear Information System (INIS)

    Casey, Leslie A.

    2014-01-01

    This GNDD Technology Roadmap is intended to provide guidance to potential researchers and help management define research priorities to achieve technology advancements for ground-based nuclear explosion monitoring science being pursued by the Ground-based Nuclear Detonation Detection (GNDD) Team within the Office of Nuclear Detonation Detection in the National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE). Four science-based elements were selected to encompass the entire scope of nuclear monitoring research and development (R&D) necessary to facilitate breakthrough scientific results, as well as deliver impactful products. Promising future R&D is delineated including dual use associated with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Important research themes as well as associated metrics are identified along with a progression of accomplishments, represented by a selected bibliography, that are precursors to major improvements to nuclear explosion monitoring.

  12. Ground-based Nuclear Detonation Detection (GNDD) Technology Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Casey, Leslie A.

    2014-01-13

    This GNDD Technology Roadmap is intended to provide guidance to potential researchers and help management define research priorities to achieve technology advancements for ground-based nuclear explosion monitoring science being pursued by the Ground-based Nuclear Detonation Detection (GNDD) Team within the Office of Nuclear Detonation Detection in the National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE). Four science-based elements were selected to encompass the entire scope of nuclear monitoring research and development (R&D) necessary to facilitate breakthrough scientific results, as well as deliver impactful products. Promising future R&D is delineated including dual use associated with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Important research themes as well as associated metrics are identified along with a progression of accomplishments, represented by a selected bibliography, that are precursors to major improvements to nuclear explosion monitoring.

  13. Computational Design of Advanced Nuclear Fuels

    International Nuclear Information System (INIS)

    Savrasov, Sergey; Kotliar, Gabriel; Haule, Kristjan

    2014-01-01

    The objective of the project was to develop a method for theoretical understanding of nuclear fuel materials whose physical and thermophysical properties can be predicted from first principles using a novel dynamical mean field method for electronic structure calculations. We concentrated our study on uranium, plutonium, their oxides, nitrides, carbides, as well as some rare earth materials whose 4f eletrons provide a simplified framework for understanding complex behavior of the f electrons. We addressed the issues connected to the electronic structure, lattice instabilities, phonon and magnon dynamics as well as thermal conductivity. This allowed us to evaluate characteristics of advanced nuclear fuel systems using computer based simulations and avoid costly experiments.

  14. Advanced I and C systems for nuclear power plants

    International Nuclear Information System (INIS)

    Bock, H.W.; Graf, A.; Hofmann, H.

    1995-01-01

    Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally, specific requirements coming from the nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are the clear task related architecture with adaptable redundancy, the consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all functions to initiate automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, economical as well as advanced plant automation and man-machine-interfaces can be implemented into Nuclear Plants, assuring the compliance with the relevant international safety standards. (author). 10 figs

  15. Advanced I and C systems for nuclear power plants

    International Nuclear Information System (INIS)

    Bock, H.W.; Graf, A.; Hofmann, H.

    1997-01-01

    Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are a clear task related architecture with adaptable redundancy, a consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all function to initiated automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, advanced and likewise economical plant automation and man-machine-interfaces can be implemented into Nuclear Power Plant, assuring compliance with the relevant international safety standards. (author). 10 figs

  16. Advanced I and C systems for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Bock, H W; Graf, A; Hofmann, H [Siemens AG, Erlangen (Germany)

    1997-07-01

    Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are a clear task related architecture with adaptable redundancy, a consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all function to initiated automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, advanced and likewise economical plant automation and man-machine-interfaces can be implemented into Nuclear Power Plant, assuring compliance with the relevant international safety standards. (author). 10 figs.

  17. Nuclear technology and mineral recovery

    International Nuclear Information System (INIS)

    Stewart, Richard M.; Niermeyer, Karl E.

    1970-01-01

    The particular aspect of nuclear technology most applicable to the mineral field, as has been pointed out by various authors, is nuclear blasting. The prime target for this nuclear blasting has usually been a large disseminated deposit of copper mineralization which, because of large dimensions, employs the nuclear devices most effectively. From the work of the AEC we know that the larger nuclear devices fragment rock for a lower energy cost per unit of ground broken than do smaller nuclear devices or chemical explosives. A mineralized deposit near the surface is usually not amenable to nuclear fragmentation, nor are the more deeply buried thin deposits. Also, one would not anticipate fragmenting a zone of excessively erratic mineralization with nuclear devices. Many of our mineralized areas would be eliminated using the above criteria, so at this point you are well aware that my self-imposed limitation is to nuclear blasting and large disseminated copper deposits. As with most other industries, copper mining faces rising costs and greater demands for its products. One of the rising cost features peculiar to extractive industries is the reliance placed on production from lower grade deposits as the higher grade deposits are depleted. As the grade or metal content of an orebody decreases more material must be handled to produce a given amount of metal. The increased volume of ore which must be handled as the grade declines requires expansion of facilities and higher capital expenditures. Expansion of facilities for mining, milling, and concentrating of the ore increases the per unit capital cost of the end product--copper. Increased copper consumption will aggravate this situation with demand for more metal, much of which will have to be obtained from lower grade deposits. As the higher grade deposits are depleted, future production will come from those deposits which cannot be exploited economically today. Most familiar of the proposed new methods for copper mining

  18. Nuclear technology and mineral recovery

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, Richard M; Niermeyer, Karl E [Anaconda Company, Salt Lake City, UT (United States)

    1970-05-15

    The particular aspect of nuclear technology most applicable to the mineral field, as has been pointed out by various authors, is nuclear blasting. The prime target for this nuclear blasting has usually been a large disseminated deposit of copper mineralization which, because of large dimensions, employs the nuclear devices most effectively. From the work of the AEC we know that the larger nuclear devices fragment rock for a lower energy cost per unit of ground broken than do smaller nuclear devices or chemical explosives. A mineralized deposit near the surface is usually not amenable to nuclear fragmentation, nor are the more deeply buried thin deposits. Also, one would not anticipate fragmenting a zone of excessively erratic mineralization with nuclear devices. Many of our mineralized areas would be eliminated using the above criteria, so at this point you are well aware that my self-imposed limitation is to nuclear blasting and large disseminated copper deposits. As with most other industries, copper mining faces rising costs and greater demands for its products. One of the rising cost features peculiar to extractive industries is the reliance placed on production from lower grade deposits as the higher grade deposits are depleted. As the grade or metal content of an orebody decreases more material must be handled to produce a given amount of metal. The increased volume of ore which must be handled as the grade declines requires expansion of facilities and higher capital expenditures. Expansion of facilities for mining, milling, and concentrating of the ore increases the per unit capital cost of the end product--copper. Increased copper consumption will aggravate this situation with demand for more metal, much of which will have to be obtained from lower grade deposits. As the higher grade deposits are depleted, future production will come from those deposits which cannot be exploited economically today. Most familiar of the proposed new methods for copper mining

  19. National nuclear power planning of China and advanced reactor

    International Nuclear Information System (INIS)

    Qian Jihui

    1990-01-01

    The necessity of investigation on the trends of advanced reactor technology all over the world is elabrated while China is going to set up its long-term national nuclear power programme. In author's opinion, thermal reactor power plants will have a quite long period development in the next century and a new trend of second generation NPPs might emerge in the beginning of next century. These new generation advanced reactors are characterized with new design concepts based on the inherent or passive safety features. Among them, most promising ones are those of AP-600 and MHTGR. Chinese experts are paying special attention to and closely following these two directions

  20. Nuclear science, technology and innovation in Canada - securing the future

    Energy Technology Data Exchange (ETDEWEB)

    Walker, R.S. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    As a Tier 1 Nuclear Nation, Canada has a rich and proud history of achievement in nuclear Science, Technology and Innovation (ST&I) -- from commercializing the CANDU power system around the world, advancing fuel technology and nuclear safety, to protecting human health through nuclear medicine and cancer therapy technology. Today, the nuclear industry in Canada is actively working to secure its promising, long-term place in the world and is embracing the change necessary to fulfill the enormous potential for good of nuclear technology. For its part, the Canadian Government is taking a bold new public policy approach to nuclear ST&I, by restructuring its large, multi-faceted AECL Nuclear Laboratories. Through the restructuring, AECL, as Canada's premier nuclear science and technology organization, will be better positioned for success via an incentivized 'Government-owned-Contractor-operated', private-sector management model. The aim of this new approach is to enhance and grow high-value nuclear innovation for the marketplace, strengthen the competitiveness of Canada's nuclear sector, and reduce costs to the Government of Canada with time. This approach will play a key role in ensuring a bright future for the Canadian Nuclear Industry domestically and globally as it launches its 25-year Vision and Action Plan, where one of the priority action areas is support for a strong, forward-looking, nuclear ST&I agenda. As the new model for the Nuclear Laboratories is moved forward by the Government, with the support of AECL and industry, Canada's nuclear expertise and knowledge continue to be expanded and deepened through the work of the Laboratories' ten Centres of Excellence, where AECL's fundamental approach is guided by the reality that ST&I is needed in all aspects of the nuclear cycle, including decommissioning, waste management and environmental protection. (author)

  1. Public fear of nuclear technology

    International Nuclear Information System (INIS)

    Nealey, S.M.; Radford, L.R.

    1987-01-01

    Excessive fear of nuclear technology (EFONT) is estimated to affect from 35-50 percent of the U.S. public, EFONT is defined as an unpleasant state of fear with components of stress and anxiety, threat to security, and anger. The cognitive aspect of EFONT involves perception of risks, benefits, and values which reinforce and perpetuate the fear. EFONT can be reduced through communications and outreach programs by providing basic information, encouraging participation, and targeting misinformation. Risks need to be put in perspective and benefits made explicit. Safety messages should be combined with other information. Understanding and patience are indispensable in dealing with those who are afraid

  2. Nuclear Science and Technology for Thai Society

    International Nuclear Information System (INIS)

    Thailand Institute of Nuclear Technology, Bangkok

    2009-07-01

    Full text: Full text: The 11th conference on the nuclear science and technology was held on 2-3 July 2009 in Bangkok. This conference contain paper on non-power applications of nuclear technology in medicine, agriculture and industry. These application include irradiation of food for the infestation tram technologies used in diagnosis and therapy and radiation chemistry important to industrial processes. Some technologies which evolved from the development of nuclear power industry are also discussed

  3. Advanced nuclear fuel cycles and radioactive waste management

    International Nuclear Information System (INIS)

    2006-01-01

    This study analyses a range of advanced nuclear fuel cycle options from the perspective of their effect on radioactive waste management policies. It presents various fuel cycle options which illustrate differences between alternative technologies, but does not purport to cover all foreseeable future fuel cycles. The analysis extends the work carried out in previous studies, assesses the fuel cycles as a whole, including all radioactive waste generated at each step of the cycles, and covers high-level waste repository performance for the different fuel cycles considered. The estimates of quantities and types of waste arising from advanced fuel cycles are based on best available data and experts' judgement. The effects of various advanced fuel cycles on the management of radioactive waste are assessed relative to current technologies and options, using tools such as repository performance analysis and cost studies. (author)

  4. Development of the advanced CANDU technology -Development of basic technology for HWR design

    International Nuclear Information System (INIS)

    Seok, Ho Cheon; Seok, Soo Dong; Lee, Sang Yong

    1996-07-01

    It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea. It is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 71 tabs., 147 figs., 143 refs. (Author)

  5. Development of the advanced CANDU technology -Development of basic technology for HWR design-

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR`s that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author).

  6. Development of the advanced CANDU technology -Development of basic technology for HWR design-

    International Nuclear Information System (INIS)

    Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong

    1995-07-01

    It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author)

  7. Nuclear power technology requirements for NASA exploration missions

    International Nuclear Information System (INIS)

    Bloomfield, H.S.

    1990-01-01

    This paper discusses how future exploration of the Moon and Mars will mandate developments in many areas of technology. In particular, major advances will be required in planet surface power systems and space transportation systems. Critical nuclear technology challenges that can enable strategic self-sufficiency, acceptable operational costs and cost-effective space transportation goals for NASA exploration missions have been identified. Critical technologies for surface power systems include stationary and mobile nuclear reactor and radio-isotope heat sources coupled to static and dynamic power conversion devices. These technologies can provide dramatic reductions in mass leading to operational and transportation cost savings. Critical technologies for space transportation systems include nuclear thermal rocket and nuclear electric propulsion options which present compelling concepts for significantly reducing mass, cost or travel time required for Earth-Mars transport

  8. Policy issues inherent in advanced technology development

    Energy Technology Data Exchange (ETDEWEB)

    Baumann, P.D.

    1994-12-31

    In the development of advanced technologies, there are several forces which are involved in the success of the development of those technologies. In the overall development of new technologies, a sufficient number of these forces must be present and working in order to have a successful opportunity at developing, introducing and integrating into the marketplace a new technology. This paper discusses some of these forces and how they enter into the equation for success in advanced technology research, development, demonstration, commercialization and deployment. This paper limits itself to programs which are generally governmental funded, which in essence represent most of the technology development efforts that provide defense, energy and environmental technological products. Along with the identification of these forces are some suggestions as to how changes may be brought about to better ensure success in a long term to attempt to minimize time and financial losses.

  9. Policy issues inherent in advanced technology development

    International Nuclear Information System (INIS)

    Baumann, P.D.

    1994-01-01

    In the development of advanced technologies, there are several forces which are involved in the success of the development of those technologies. In the overall development of new technologies, a sufficient number of these forces must be present and working in order to have a successful opportunity at developing, introducing and integrating into the marketplace a new technology. This paper discusses some of these forces and how they enter into the equation for success in advanced technology research, development, demonstration, commercialization and deployment. This paper limits itself to programs which are generally governmental funded, which in essence represent most of the technology development efforts that provide defense, energy and environmental technological products. Along with the identification of these forces are some suggestions as to how changes may be brought about to better ensure success in a long term to attempt to minimize time and financial losses

  10. Advanced nuclear systems. Review study; Fortgeschrittene Nuklearsysteme. Review Study

    Energy Technology Data Exchange (ETDEWEB)

    Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph [Interdisziplinaere Arbeitsgruppe Naturwissenschaft, Technik und Sicherheit (IANUS), Darmstadt University of Technology, Hochschulstrasse 10, D-64289 Darmstadt (Germany); Baehr, Roland; Hahn, Lothar [Institute for applied ecology (Oeko-Institut), Elisabethenstrasse 55-57, D-64283 Darmstadt (Germany)

    1999-04-01

    The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

  11. Where is high technology taking nuclear medicine

    International Nuclear Information System (INIS)

    Veall, N.

    1985-01-01

    The question is posed as to whether high technology in nuclear medicine might lead to the nuclear medicine practitioner possibly finishing up working for the machine rather than the improvement of health care in its widest sense. A brief examination of some pros and cons of high technology nuclear medicine is given. (U.K.)

  12. Nuclear energy and nuclear technology in Switzerland

    International Nuclear Information System (INIS)

    Graf, P.

    1975-01-01

    The energy crisis, high fuel costs and slow progress in the development of alternative energy sources, e.g. solar energy have given further impetus to nuclear power generation. The Swiss nuclear energy programme is discussed and details are given of nuclear station in operation, under construction, in the project stage and of Swiss participation in foreign nuclear stations. Reference is made to the difficulties, delays and resulting cost increases caused by local and regional opposition to nuclear power stations. The significant contributions made by Swiss industry and Swiss consulting engineers are discussed. (P.G.R.)

  13. Nuclear disarmament and peaceful nuclear technology

    International Nuclear Information System (INIS)

    Taylor, T.B.

    1989-01-01

    According to the author, it remains to be seen whether nuclear disarmament can reduce the risks of nuclear war sufficiently for the residual risks to be acceptable to a majority of the world's population, while at the same time vigorous growth in the world's dependence on nuclear energy for peaceful purposes continues. This paper discusses how use of nuclear materials from dismantled weapons as fuel for peaceful purposes may help progress to be made towards that goal, by stimulating considerable improvements in the effectiveness of arrangements for preventing diversion of the materials from peaceful to military purposes, while at the same time eliminating large numbers of nuclear weapons

  14. Advanced clean coal utilization technologies

    Energy Technology Data Exchange (ETDEWEB)

    Moritomi, Hiroshi [National Inst. for Resources and Environment, Tsukuba, Ibaraki (Japan)

    1993-12-31

    The most important greenhouse gas is CO{sub 2} from coal utilization. Ways of mitigating CO{sub 2} emissions include the use of alternative fuels, using renewable resources and increasing the efficiency of power generation and end use. Adding to such greenhouse gas mitigation technologies, post combustion control by removing CO{sub 2} from power station flue gases and then storing or disposing it will be available. Although the post combustion control have to be evaluated in a systematic manner relating them to whether they are presently available technology, to be available in the near future or long term prospects requiring considerable development, it is considered to be a less promising option owing to the high cost and energy penalty. By contrast, abatement technologies aimed at improving conversion efficiency or reducing energy consumption will reduce emissions while having their own commercial justification.

  15. High technology supporting nuclear power industry in CRIEPI

    International Nuclear Information System (INIS)

    Ueda, Nobuyuki

    2009-01-01

    As a central research institute of electric power industry, Central Research Institute of Electric Power Industry (CRIEPI) has carried out R and D on broad range of topics such as power generation, power transmission, power distribution, power application and energy economics and society, aiming to develop prospective and advanced technologies, fundamental reinforce technologies and next-generation core technologies. To realize low-carbon society to cope with enhancement of global environmental issues, nuclear power is highly recommended as large-scale power with low-carbon emission. At the new start of serial explanation on advanced technologies, R and D on electric power industry was outlined. (T. Tanaka)

  16. Economic benefits of advanced materials in nuclear power systems

    International Nuclear Information System (INIS)

    Busby, J.T.

    2009-01-01

    A key obstacle to the commercial deployment of advanced fast reactors is the capital cost. There is a perception of higher capital cost for fast reactor systems than advanced light water reactors. However, cost estimates come with a large uncertainty since far fewer fast reactors have been built than light water reactor facilities. Furthermore, the large variability of industrial cost estimates complicates accurate comparisons. Reductions in capital cost can result from design simplifications, new technologies that allow reduced capital costs, and simulation techniques that help optimize system design. It is plausible that improved materials will provide opportunities for both simplified design and reduced capital cost. Advanced materials may also allow improved safety and longer component lifetimes. This work examines the potential impact of advanced materials on the capital investment cost of fast nuclear reactors.

  17. Advanced materials and technologies. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Lindroos, V K; Alander, T K.R. [eds.; Helsinki Univ. of Technology, Otaniemi (Finland). Lab. of Physical Metallurgy and Materials Science

    1996-12-31

    The contents of the proceedings consist of three chapters, of which, the first discusses common megatrends, both nationally and globally, in different fields of materials technology. The second chapter is dealing with novel production and processing of base metals and, finally, the third chapter is related with current achievements and future goals of electronic, magnetic, optical and coating materials and their processing

  18. Advancing education by proper technology

    NARCIS (Netherlands)

    Bouwhuis, D.G.; Hoe, van R.R.G.; Bouma, H.; Liao, T.J.

    1996-01-01

    Abstract: The major trends emerging from a review of the first 25 volumes in the NATO Series on Educational Technology are a convergence on Intelligent Tutoring Systems and on microworld simulation tools. In both approaches a radical reform of the entire educational system is generally favored. In

  19. Advanced materials and technologies. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Lindroos, V.K.; Alander, T.K.R. [eds.] [Helsinki Univ. of Technology, Otaniemi (Finland). Lab. of Physical Metallurgy and Materials Science

    1995-12-31

    The contents of the proceedings consist of three chapters, of which, the first discusses common megatrends, both nationally and globally, in different fields of materials technology. The second chapter is dealing with novel production and processing of base metals and, finally, the third chapter is related with current achievements and future goals of electronic, magnetic, optical and coating materials and their processing

  20. Advances in spot curing technology

    International Nuclear Information System (INIS)

    Burga, R.

    1999-01-01

    A brief review of spot curing technology was presented. The process which a spot of energy of a specific wavelength bandwidth and irradiance is used to cause a coating, encapsulant or adhesive to change from a liquid to a solid state

  1. Development of nuclear analytical technology

    International Nuclear Information System (INIS)

    Jee, Kwang Yong; Kim, W. H.; Park, Yeong J.; Park, Yong J.; Sohn, S. C.; Song, B. C.; Jeon, Y. S.; Pyo, H. Y.; Ha, Y. K.

    2004-04-01

    The objectives of this study are to develop the technology for the determination of isotopic ratios of nuclear particles detected from swipe samples and to develop the NIPS system. The R and D contents and results of this study are firstly the production of nuclear micro particle(1 ∼ 20 μm) and standardization, the examination of variation in fission track characteristic according to nuclear particle size and enrichment( 235 U: 1-50%), the construction of database and the application of this technique to swipe samples. If this technique is verified its superiority by various field tests and inter-laboratory comparison program with other institutes in developed countries, it can be possible to join NWAL supervised under IAEA and to export our technology abroad. Secondly, characteristics of alpha track by boron (n, α) nuclear reaction were studied to measure both total boron concentration and 10B enrichment. The correlation of number of alpha tracks and various 10B concentration was studied to evaluate the reliability of this method. Especially, cadmium shielding technique was introduced to reduce the background of alpha tracks by covering the solid track detector and the multi-dot detector plate was developed to increase the reproducibility of measurement by making boron solution dried evenly in the plate. The results of the alpha track method were found to be well agreed with those of mass spectroscopy within less than 10 % deviation. Finally, the NIPS system using 252 Cf neutron source was developed and prompt gamma spectrum and its background were obtained. Monte Carlo method using MCNP-4B code was utilized for the interpretation of neutron and gamma-ray shielding condition as well as the moderation of a fast neutron. Gamma-gamma coincidence was introduced to reduce the prompt gamma background. The counting efficiency of the HPGe detector was calibrated in the energy range from 50 keV to 10 MeV using radio isotope standards and prompt gamma rays of Cl for the

  2. Advanced nuclear reactor public opinion project

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  3. Advanced nuclear reactor public opinion project

    International Nuclear Information System (INIS)

    Benson, B.

    1991-01-01

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions

  4. TASTEX: Tokai Advanced Safeguards Technology Exercise

    International Nuclear Information System (INIS)

    1982-01-01

    During the years 1978 to 1981 the Governments of France, Japan and the United States of America cooperated with the International Atomic Energy Agency in the TASTEX (Tokai Advanced Safeguards Technology Exercise) programme. The aim of this programme was to improve the technology for the application of international safeguards at reprocessing facilities, and the results are presented in the present report

  5. One Micron Laser Technology Advancements at GSFC

    Science.gov (United States)

    Heaps, William S.

    2010-01-01

    This slide presentation reviews the advancements made in one micron laser technology at Goddard Space Flight Center. It includes information about risk factors that are being addressed by GSFC, and overviews of the various programs that GSFC is currently managing that are using 1 micron laser technology.

  6. Advanced conversion technology review panel report

    International Nuclear Information System (INIS)

    Frazier, T.A.

    1998-01-01

    The Department of Energy (DOE), the National Aeronautics and Space Administration (NASA) and the Jet Propulsion Laboratory (JPL) established a DOE lead management team and an Advanced Conversion Technology Review Panel. The panel was tasked with providing the management team with an assessment and ranking of the three advanced conversion technologies. The three advanced conversion technologies were alkali metal thermal to electric converter (AMTEC), Stirling engine converter (SEC), and thermophotovoltaic (TPV). To rate and rank these three technologies, five criteria were developed: (1) Performance, (2) Development and Cost/Production and Cost/Schedule Risk, (3) Spacecraft Interface and Operations, (4) Ability to Scale Conversion, and (5) Safety. Discussed are the relative importance of each of these criteria and the rankings of the three advanced conversion technologies. It was the conclusion of the panel that the technology decision should be based on the risk that DOE and NASA are willing to accept. SEC is the most mature technology and would provide the lowest risk option. However, if more risk is acceptable, AMTEC not only provides benefits in the spacecraft interface but is also predicted to outperform the SEC. It was proposed that if AMTEC were selected, funding should be provided at a reasonable level to support back-up technology to be developed in a parallel fashion until AMTEC has proven its capability. The panel report and conclusion were provided to DOE in February 1997

  7. On the safety performance of the advanced nuclear energy systems

    International Nuclear Information System (INIS)

    Li Shounan

    1999-01-01

    Some features on the safety performances of the Advanced Nuclear Energy Systems are discussed. The advantages and some peculiar problems on the safety of Advanced Nuclear Energy Systems with subcritical nuclear reactor driven by external neutron sources are also pointed out in comparison with conventional nuclear reactors

  8. Physics and Advanced Technologies 2003 Annual Report

    International Nuclear Information System (INIS)

    Hazi, A; Sketchley, J

    2005-01-01

    The Physics and Advanced Technologies (PAT) Directorate overcame significant challenges in 2003 to deliver a wealth of scientific and programmatic milestones, and move toward closer alignment with programs at Lawrence Livermore National Laboratory. We acted aggressively in enabling the PAT Directorate to contribute to future, growing Lawrence Livermore missions in homeland security and at the National Ignition Facility (NIF). We made heavy investments to bring new capabilities to the Laboratory, to initiate collaborations with major Laboratory programs, and to align with future Laboratory directions. Consistent with our mission, we sought to ensure that Livermore programs have access to the best science and technology, today and tomorrow. For example, in a move aimed at revitalizing the Laboratory's expertise in nuclear and radiation detection, we brought the talented Measurement Sciences Group to Livermore from Lawrence Berkeley National Laboratory, after its mission there had diminished. The transfer to our I Division entailed significant investment by PAT in equipment and infrastructure required by the group. In addition, the move occurred at a time when homeland security funding was expected, but not yet available. By the end of the year, though, the group was making crucial contributions to the radiation detection program at Livermore, and nearly every member was fully engaged in programmatic activities. Our V Division made a move of a different sort, relocating en masse from Building 121 to the NIF complex. This move was designed to enhance interaction and collaboration among high-energy-density experimental scientists at the Laboratory, a goal that is essential to the effective use of NIF in the future. Since then, V Division has become increasingly integrated with NIF activities. Division scientists are heavily involved in diagnostic development and fielding and are poised to perform equation-of-state and high-temperature hohlraum experiments in 2004 as

  9. Advanced fuel technologies at General Atomics

    International Nuclear Information System (INIS)

    Back, Christina A.

    2013-01-01

    General Atomics (GA) has made significant contributions since its founding in the 1950's to develop nuclear power for peaceful means. With the conception and construction of the TRIGA reactors and research on TRISO particles, GA has long recognised the importance of 'accident-tolerant' materials. Before the accident at Fukushima Daiichi, GA had already initiated work on silicon carbide (SiC) and SiC-related technologies for application in nuclear reactors. At that time, the work was initiated in support of the GA advanced gas-cooled fast reactor concept called the Energy Multiplier Module, EM2. This work continues, however, the reasons that make SiC materials attractive for fast reactor concepts also make them attractive for advanced light water reactors. These include superior performance over zircaloy for high-temperature strength, especially above 1500 deg. C, and significantly reduced hydrogen production in accident scenarios. The current focus on 'accident-tolerant' components is to develop cladding made of silicon carbide fiber and silicon carbide matrix, SiC-SiC composites. The goal for this work is to produce a cladding that provides strength and impermeability to meet reactor performance and safety requirements. To date, GA has examined the trade-offs between processing time and infiltration uniformity to reduce fabrication time, fabricated cylindrical prototypes, and refined material properties for fracture toughness, impermeability, and thermal conductivity. Generally, the GA programme is developing innovative fuel elements that employ both high density uranium-bearing fuels that enable longer lifetime with higher burn-up, and claddings that are more resistant to neutron damage. In addition to fabrication, significant effort is devoted to measuring the critical parameters, such as thermal conductivity, mechanical strength and component performance at reactor-relevant operational conditions, using a mix of commercial equipment

  10. Nuclear Technologies Secure Food For Future

    International Nuclear Information System (INIS)

    2012-01-01

    use of such techniques to protect plants and animals against disease and pests means many more farmers can produce enough food to feed their own families and to sell on markets. Ultimately, fewer people go hungry. The IAEA collaborates with the United Nations Food and Agriculture Organization (FAO) in providing support through a joint division in Vienna. ''While our profile is modest, the size of our footprint is significant,'' said Qu Liang, Director of the Joint FAO/IAEA Division of Nuclear Techniques. ''We are putting the benefits of tried and tested nuclear technologies into the hands of farmers, particularly small producers in poorer countries, to improve their food security and livelihood.'' ''The assistance is driven by advanced technologies,'' Liang added. ''But what we are delivering has to be appropriate to farmers' needs. That means crops that can flourish in changing and often harsher conditions, pest control without a chemical legacy and protection for livestock.'' The Scientific Forum will be opened by the IAEA Director General and ministers from Indonesia, Kenya and Vietnam. FAO Director General Graziano da Silva will deliver a video address. The Forum will address IAEA activities in the fields of food production, food protection and food safety. Each session features a panel of experts who will present and discuss the benefits of nuclear techniques in food and agriculture. A moderator will guide the discussions. (IAEA)

  11. New nuclear technology; International developments. Review 1995

    International Nuclear Information System (INIS)

    Devell, L.; Aggeryd, I.; Hultgren, Aa.; Lundell, B.; Pedersen, T.

    1995-09-01

    A summary review of the development of new nuclear rector technology is presented in this report. Fuel cycle strategies and waste handling developments are also commented. Different plans for dismantling nuclear weapons are presented. 18 refs

  12. Development of the advanced CANDU technology

    International Nuclear Information System (INIS)

    Suk, Soo Dong; Min, Byung Joo; Na, Y. H.; Lee, S. Y.; Choi, J. H.; Lee, B. C.; Kim, S. N.; Jo, C. H.; Paik, J. S.; On, M. R.; Park, H. S.; Kim, S. R.

    1997-07-01

    The purpose of this study is to develop the advanced design technology to improve safety, operability and economy and to develop and advanced safety evaluation system. More realistic and reasonable methodology and modeling was employed to improve safety margin in containment analysis. Various efforts have been made to verify the CATHENA code which is the major safety analysis code for CANDU PHWR system. Fully computerized prototype ECCS was developed. The feasibility study and conceptual design of the distributed digital control system have been performed as well. The core characteristics of advanced fuel cycle, fuel management and power upgrade have been studied to determine the advanced core. (author). 77 refs., 51 tabs., 108 figs

  13. Development of the advanced CANDU technology

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Soo Dong; Min, Byung Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Na, Y H; Lee, S Y; Choi, J H; Lee, B C; Kim, S N; Jo, C H; Paik, J S; On, M R; Park, H S; Kim, S R [Korea Electric Power Co., Taejon (Korea, Republic of)

    1997-07-01

    The purpose of this study is to develop the advanced design technology to improve safety, operability and economy and to develop and advanced safety evaluation system. More realistic and reasonable methodology and modeling was employed to improve safety margin in containment analysis. Various efforts have been made to verify the CATHENA code which is the major safety analysis code for CANDU PHWR system. Fully computerized prototype ECCS was developed. The feasibility study and conceptual design of the distributed digital control system have been performed as well. The core characteristics of advanced fuel cycle, fuel management and power upgrade have been studied to determine the advanced core. (author). 77 refs., 51 tabs., 108 figs.

  14. Impact of scientific and technological advances.

    Science.gov (United States)

    Dragan, I F; Dalessandri, D; Johnson, L A; Tucker, A; Walmsley, A D

    2018-03-01

    Advancements in research and technology are transforming our world. The dental profession is changing too, in the light of scientific discoveries that are advancing biological technology-from new biomaterials to unravelling the genetic make-up of the human being. As health professionals, we embrace a model of continuous quality improvement and lifelong learning. Our pedagogical approach to incorporating the plethora of scientific-technological advancements calls for us to shift our paradigm from emphasis on skill acquisition to knowledge application. The 2017 ADEE/ADEA workshop provided a forum to explore and discuss strategies to ensure faculty, students and, ultimately, patients are best positioned to exploit the opportunities that arise from integrating new technological advances and research outcomes. Participants discussed methods of incorporating the impact of new technologies and research findings into the education of our dental students. This report serves as a signpost of the way forward and how to promote incorporation of research and technology advances and lifelong learning into the dental education curriculum. © 2018 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

  15. Nuclear power technologies for application in developing countries

    International Nuclear Information System (INIS)

    Zrodnikov, A.V.

    2000-01-01

    The tremendous social and political changes which have occurred during the recent decade in the former USSR made it possible to launch the process of commercialization of defense-related technologies in Russia. The so-called dual-use technologies are meant to be initially developed by the state for defense needs, but having a high commercial potential as well. To date, the process of such technology transfer from the state sector to a private one has been limited primarily by insufficient progress of the national private sector. Essentially, the main economic problem still remains the attraction of private capital for the promotion of dual-use technologies to the point at where they acquire commercially viable. A large number of advanced technologies are waiting to be commercialized. The report presented considers the prospects of civil use of some technologies related to the nuclear power area: space nuclear power systems, nuclear powered submarines and rector-pumped lasers. (author)

  16. Advanced Nuclear Applications in Medicinr at Chiang Mai University

    International Nuclear Information System (INIS)

    Vilasdechanon, Nonglak

    2015-01-01

    The atomic energy applications in Faculty of Medicine, Chiang Mai University (CMU) are mainly performed by department of Radiology that is divided into three dicisions: 1) Diagnostic Radiology Division for the applications of X-rays, ultrasound, and magnetic resonance, 2) Therapeutic Radiology and Oncology Division for cancer treatments by photon accelrator and external radionuclides therapy or brachytherapy, 3) Nuclear Meddicine Division for clinical dignosis by using radionuclide scintigraphy, targeted molecular imaging and internal radionuclide therapy. In the last decade, many advanced medical images for clinical diagnosis included of digital & computed radiology (DR & CR), digital subtraction angiography (DSA) and images (DSI), computed tomography (CT) with dual X-rays energies, manetic resonance imaging (MRI), and hybrid images of SPECT/CT were established in Radiology Department and PET/CT Cyclitron Center Chiang Mai University (PCCMU), respectively. For cancer treatments, the frontier technologies in radiation oncligy therapy such as tomotherapy, IMRT, 3D conformal radiation treatment, stereotactic radiationtherapy (SRT), stereotactic radiation surgery (SRS), and radiation biology laboratory were implemented in the department as well. As far as fast development of nuclear technology in medicine, future implementation of advanced nuclear applications in medicine strongly need an intergrated knoowledge from many specialties e.g. computer softeare in image reconstruction, accuracy and and precision technology, production of specific radiotracers for molecular imaging and therapy, techniques in radionuclide productions, innovation of new wquipment or materials for radiationprotection and safety, etc. However the most important factors of nuclear applications in medicine are the vision, mission and the value statements of the organization on the high cost in radiology investment and human resources development. We have to emphasize that people who are involved

  17. Analysis of nuclear proliferation resistance reprocessing and recycling technologies

    Energy Technology Data Exchange (ETDEWEB)

    Patricia Paviet-Hartmann; Gary Cerefice; Marcela Stacey; Steven Bakhtiar

    2011-05-01

    The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate – and should not be equated -with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with enhanced proliferation resistance. On the other hand, at this moment, there are no proliferation resistance advanced technologies. . Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the US, GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R&D and robust flowsheets. Finally, future generation recycling schemes will handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that are intrinsically more proliferation resistant than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will enhance

  18. Analysis of nuclear proliferation resistance reprocessing and recycling technologies

    International Nuclear Information System (INIS)

    Paviet-Hartmann, Patricia; Cerefice, Gary; Stacey, Marcela; Bakhtiar, Steven

    2011-01-01

    The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate - and should not be equated - with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with enhanced proliferation resistance. On the other hand, at this moment, there are no proliferation resistance advanced technologies. Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the US, GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R and D and robust flowsheets. Finally, future generation recycling schemes will handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that are intrinsically more proliferation resistant than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will enhance

  19. 2010 annual meeting on nuclear technology. Workshop on ''Preservation of competence in nuclear technology''

    International Nuclear Information System (INIS)

    Steinwarz, Wolfgang

    2010-01-01

    Within the two-day workshop on ''Preservation of Competence in Nuclear Technology'', 21 young scientists competed for the ''Competence Prize'' awarded by Siempelkamp Nukleartechnik for the twelfth time. They reported about their term papers, diploma or doctoral theses focusing on reactor technology and reactor safety, the development of innovative reactor systems, and waste management. For the first time, contributions this year were presented also from the field of radiation protection. The jury composed of Prof. T. Schulenberg (Karlsruhe Institute of Technology), Prof. M.K. Koch (Ruhr University, Bochum), and Dr. W. Steinwarz (Siempelkamp Nukleartechnik) assessed the advance compacts as well as the oral presentations. The winner of the 2010 Competence Prize is Heiko Herbell of the Karlsruhe Institute of Technology. Cornelia Heintze of the Dresden-Rossendorf Research Center, and Carola Hartel of the GSI Helmholtz Center for Heavy Ion Research won the second and third prizes. (orig.)

  20. Qualtity assurance in nuclear technology

    International Nuclear Information System (INIS)

    Roesler, U.

    1977-01-01

    The demand for safety in nuclear power plants is rooted in the Atomic Energy Act of the Federal Republic of Germany, under which 'preplanned safety' is a licensing condition. Moreover, the safety of nuclear power plants is outlined in more precise terms in the guidelines of the German Advisory Committee for Reactor Safeguards (Reaktorsicherheitskommission). The usual approach taken in this country, i.e., to establish quality assurance for each specific product, with supplementary quality assurance measures geared to systems requirements being implemented by industry, has proved to work satisfactorily. Product-based quality assurance mainly stems from the classical quality control concept, whereas systems-based quality assurance primarily is to ensure that both manufacturers and systems suppliers take all measures in advance which are needed for the satisfactory processing of an order and to achieve the quality level required. The special features and the advantages of the joint action of manufacturers, systems suppliers and experts, which are characteristic of the German approach, very clearly emerge from a comparison with practices in the United States. In the further refinement of the quality assurance concept as practised in Germany, qhich will have a particularly great impact on costs and schedules because of the manpower requirement involved, it should be carefully weighed where there are exaggerations and unnecessary complications which can no longer be justified by the demand for more safety. (orig.) [de

  1. Ceramic Technology for Advanced Heat Engines Project

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    The Ceramic Technology for Advanced Heat Engines Project was developed by the Department of Energy's Office of Transportation Systems (OTS) in Conservation and Renewable Energy. This project, part of the OTS's Advanced Materials Development Program, was developed to meet the ceramic technology requirements of the OTS's automotive technology programs. Significant accomplishments in fabricating ceramic components for the Department of Energy (DOE), National Aeronautics and Space Administration (NASA), and Department of Defense (DoD) advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. However, these programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially.

  2. Nuclear energy technology transfer: the security barriers

    International Nuclear Information System (INIS)

    Rinne, R.L.

    1975-08-01

    The problems presented by security considerations to the transfer of nuclear energy technology are examined. In the case of fusion, the national security barrier associated with the laser and E-beam approaches is discussed; for fission, the international security requirements, due to the possibility of the theft or diversion of special nuclear materials or sabotage of nuclear facilities, are highlighted. The paper outlines the nuclear fuel cycle and terrorist threat, examples of security barriers, and the current approaches to transferring technology. (auth)

  3. Development of high burnup nuclear fuel technology

    International Nuclear Information System (INIS)

    Suk, Ho Chun; Kang, Young Hwan; Jung, Jin Gone; Hwang, Won; Park, Zoo Hwan; Ryu, Woo Seog; Kim, Bong Goo; Kim, Il Gone

    1987-04-01

    The objectives of the project are mainly to develope both design and manufacturing technologies for 600 MWe-CANDU-PHWR-type high burnup nuclear fuel, and secondly to build up the foundation of PWR high burnup nuclear fuel technology on the basis of KAERI technology localized upon the standard 600 MWe-CANDU- PHWR nuclear fuel. So, as in the first stage, the goal of the program in the last one year was set up mainly to establish the concept of the nuclear fuel pellet design and manufacturing. The economic incentives for high burnup nuclear fuel technology development are improvement of fuel utilization, backend costs plant operation, etc. Forming the most important incentives of fuel cycle costs reduction and improvement of power operation, etc., the development of high burnup nuclear fuel technology and also the research on the incore fuel management and safety and technologies are necessary in this country

  4. Advanced Communication Technology Satellite (ACTS) multibeam antenna technology verification experiments

    Science.gov (United States)

    Acosta, Roberto J.; Larko, Jeffrey M.; Lagin, Alan R.

    1992-01-01

    The Advanced Communication Technology Satellite (ACTS) is a key to reaching NASA's goal of developing high-risk, advanced communications technology using multiple frequency bands to support the nation's future communication needs. Using the multiple, dynamic hopping spot beams, and advanced on board switching and processing systems, ACTS will open a new era in communications satellite technology. One of the key technologies to be validated as part of the ACTS program is the multibeam antenna with rapidly reconfigurable hopping and fixed spot beam to serve users equipped with small-aperature terminals within the coverage areas. The proposed antenna technology experiments are designed to evaluate in-orbit ACTS multibeam antenna performance (radiation pattern, gain, cross pol levels, etc.).

  5. Advanced neutral-beam technology

    International Nuclear Information System (INIS)

    Berkner, K.H.

    1980-09-01

    Extensive development will be required to achieve the 50- to 75-MW, 175- to 200-keV, 5- to 10-sec pulses of deuterium atoms envisioned for ETF and INTOR. Multi-megawatt injector systems are large (and expansive); they consist of large vacuum tanks with many square meters of cryogenic pumping panels, beam dumps capable of dissipating several megawatts of un-neutralized beam, bending magnets, electrical power systems capable of fast turnoff with low (capacity) stored energy, and, of course, the injector modules (ion sources and accelerators). The technology requirements associated with these components are described

  6. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1975-10-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely-activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. A list of measures is given for assessing overall physical protection system performance. (auth)

  7. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1976-01-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major US Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed in this paper. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. Finally, a list of measures is given for assessing overall physical protection system performance. (author)

  8. Evaluation of the use of advanced information technology (expert systems) for data-base system development and emergency management in non-nuclear industries. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Rasmussen, J; Pedersen, O M; Groenberg, C D

    1987-04-01

    During recent years, a number of large industrial accidents have resulted in a widespread concern with organization of emergency services and means for effective support of the distributed organizations involved in emergency management. With the aim of presenting a discussion of the potential of modern information technology for decision support during accidents, the report brings a brief review of approaches to design of decision-support systems and expert systems. From the review it is concluded that models of decision support systems based on a control theoretic point of view, together with a cognitive approach to decision task analysis offer a suitable framework. In addition, it is concluded that Advanced Information-tools for data base design and for communication support in distributed decision-making should be considered for further development. A number of recent Danish industrial accidents are reviewed and key persons interviewed in order to give a preliminary basis for judging the feasibility of the theoretical discussion. The report includes a number of recommendations for further studies to support the development of a distributed data base system for emergency management.

  9. Non-nuclear power application of nuclear technology in Nigeria

    International Nuclear Information System (INIS)

    Funtua, I.I.

    2008-01-01

    Nuclear Technology applications are found in Food and Agriculture, Human Health, Water Resources, Industry, Environment, Education and Research.There are more potentials for the deployment of nuclear technology in more aspects of our life with needed economic development in Nigeria.Nuclear Technology plays and would continue to play vital role in Agriculture, Human health, Water resources and industry in Nigeria.Nuclear technologies have been useful in developmental efforts worldwide and for these to take hold, capacity building programmes must be expanded and the general public must have informed opinions about the benefits and risk associated with the technologies.This presentation gives an overview of nuclear technology applications in Nigeria in the following areas: Food and Agriculture, Human Health, Water Resources, Industry, Education and Research

  10. Advanced fuel technology and performance: Current status and trends

    International Nuclear Information System (INIS)

    1990-11-01

    During the last years the Nuclear Fuel Cycle and Waste Management Division of the IAEA has been giving great attention to the collection, analysis and exchange of information in the field of reactor fuel technology. Most of these activities are being conducted in the framework of the International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT). The purpose of this Advisory Group Meeting on Advanced Fuel Technology and Performance was to update and to continue the previous work, and to review the experience of advanced fuel technology, its performance with regard to all types of reactors and to outline the future trends on the basis of national experience and discussions during the meeting. As a result of the meeting a Summary Report was prepared which reflected the status of the advanced nuclear fuel technology up to 1990. The 10 papers presented by participants of this meeting are also published here. A separate abstract was prepared for each of these papers. Refs, figs and tabs

  11. The recent status of nuclear technology development in Thailand

    International Nuclear Information System (INIS)

    Laoharojanaphand, Sirinart; Cherdchu, Chainarong; Sumitra, Tatchai; Sudprasert, Wanwisa; Chankow, Nares; Tiyapan, Kanokrat; Onjun, Thawatchai; Bhanthumnavin, Duangduen

    2016-01-01

    Thailand has started the peaceful utilization of nuclear program in 1961. The program has developed considerably in various aspects. Laws and regulations were established while applications in medical, agriculture, industry as well as research and education have been accomplished successfully in the country. As for the energy production, Thailand has realized the importance of nuclear power generation several years back. However, the implementation has been delayed. There are four main nuclear organizations namely The Thai Atomic Energy Commission - the country's policy holder, the Office of Atoms for Peace (OAP) - the nuclear regulatory bodies, Thailand Institute of Nuclear Technology (TINT: Public Organization) - the research and services provider in nuclear field and the Nuclear Society of Thailand the non-governmental organization. Major research in nuclear technology is actively carried out at TINT. Filed of research include medical and public health, agricultural, material and industrial, environmental and advanced technology like neutron scattering and nuclear fusion. Nuclear density gauge has been utilized in many industries including petrochemical production and refineries. TINT is also providing services on nuclear radiography to industrial and clients. Additionally, x-ray techniques have been utilized in many manufacturers for quality and process control. Nuclear applications for medical purpose have been utilized in Thailand several years back both for diagnostic and therapeutic purposes. To ensure safe and peaceful use of nuclear technology and for the safety of the general public in Thailand, OAP has launched laws, regulations and ministerial announcements. Thailand has only one multi-purposes nuclear research reactor and no NPP. Yet we have realized the importance of nuclear power generation several years back. (N.T.)

  12. Advanced display concepts in nuclear control rooms

    International Nuclear Information System (INIS)

    Clark, M.T.; Banks, W.W.; Blackman, H.S.; Gertman, D.I.

    1982-01-01

    Precursors necessary for the development of a full-scale predictor display/control system have been under development since the mid 1940's. The predictor display itself has been available for use in manual control systems since 1958. However, the nuclear industry has not yet explored the uses and benefits of predictor systems. The purpose of this paper is to provide information on the application of this technology to the nuclear industry. The possibility of employing a simulation-based control system for nuclear plant systems that currently use conventional auto/manual schemes is discussed. By employing simulation-based systems, a predictor display could be made available to the operator during manual operations, thus facilitating control without outwardly affecting the overall control scheme

  13. New technology in nuclear power plant instrumentation and control

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The primary topic of this book is what can be done to improve nuclear power plant operation safety and the economic benefits that can be gained with the utilization of advance instrumentation and control technology. Other topics discussed are the industry's reluctance to accept new designs determining cost effective improvements, and difficulties in meeting regulatory standards with new technology control. The subjects will be useful when considering the area of instrumentation and control for enhancing plant operation and safety. Contents: Advanced Instrumention, Plant Control and Monitoring, Plant Diagnostics and Failure Detection, Human Factors Considerations in Instrumentation and Control, NRC and Industry Perspective on Advanced Instrumentation and Control

  14. Physics and technology of nuclear materials

    CERN Document Server

    Ursu, Ioan

    2015-01-01

    Physics and Technology of Nuclear Materials presents basic information regarding the structure, properties, processing methods, and response to irradiation of the key materials that fission and fusion nuclear reactors have to rely upon. Organized into 12 chapters, this book begins with selectively several fundamentals of nuclear physics. Subsequent chapters focus on the nuclear materials science; nuclear fuel; structural materials; moderator materials employed to """"slow down"""" fission neutrons; and neutron highly absorbent materials that serve in reactor's power control. Other chapters exp

  15. 78 FR 57839 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2013-09-20

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of public meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT or Committee...

  16. 76 FR 2662 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2011-01-14

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of partially closed meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT...

  17. 78 FR 29704 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2013-05-21

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of Public Meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT or Committee...

  18. 78 FR 292 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2013-01-03

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of Public Meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT or Committee...

  19. 77 FR 3232 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2012-01-23

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of public meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT or Committee...

  20. 76 FR 59659 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2011-09-27

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of public meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT or Committee...

  1. 77 FR 32570 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2012-06-01

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of public meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT or Committee...

  2. 76 FR 29195 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2011-05-20

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of Public Meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT or Committee...

  3. 75 FR 60082 - Visiting Committee on Advanced Technology

    Science.gov (United States)

    2010-09-29

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Visiting Committee on Advanced Technology AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of Public Meeting. SUMMARY: The Visiting Committee on Advanced Technology (VCAT), National...

  4. Advanced Ceramic Materials For Next-Generation Nuclear Applications

    International Nuclear Information System (INIS)

    Marra, J.

    2010-01-01

    proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

  5. Advanced nuclear fuel cycles activities in IAEA

    International Nuclear Information System (INIS)

    Nawada, H.P.; Ganguly, C.

    2007-01-01

    Full text of publication follows. Of late several developments in reprocessing areas along with advances in fuel design and robotics have led to immense interest in partitioning and transmutation (P and T). The R and D efforts in the P and T area are being paid increased attention as potential answers to ever-growing issues threatening sustainability, environmental protection and non-proliferation. Any fuel cycle studies that integrate partitioning and transmutation are also known as ''advanced fuel cycles'' (AFC), that could incinerate plutonium and minor actinide (MA) elements (namely Am, Np, Cm, etc.) which are the main contributors to long-term radiotoxicity. The R and D efforts in developing these innovative fuel cycles as well as reactors are being co-ordinated by international initiatives such as Innovative Nuclear Power Reactors and Fuel Cycles (INPRO), the Generation IV International Forum (GIF) and the Global Nuclear Energy Partnership (GENP). For these advanced nuclear fuel cycle schemes to take shape, the development of liquid-metal-cooled reactor fuel cycles would be the most essential step for implementation of P and T. Some member states are also evaluating other concepts involving the use of thorium fuel cycle or inert-matrix fuel or coated particle fuel. Advanced fuel cycle involving novel partitioning methods such as pyrochemical separation methods to recover the transuranic elements are being developed by some member states which would form a critical stage of P and T. However, methods that can achieve a very high reduction (>99.5%) of MA and long-lived fission products in the waste streams after partitioning must be achieved to realize the goal of an improved protection of the environment. In addition, the development of MA-based fuel is also an essential and crucial step for transmutation of these transuranic elements. The presentation intends to describe progress of the IAEA activities encompassing the following subject-areas: minimization of

  6. CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2005-11-04

    This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

  7. Crosscutting Technology Development at the Center for Advanced Separation Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2006-09-30

    This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

  8. CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2006-05-15

    This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

  9. Advanced power plant materials, design and technology

    Energy Technology Data Exchange (ETDEWEB)

    Roddy, D. (ed.) [Newcastle University (United Kingdom). Sir Joseph Swan Institute

    2010-07-01

    The book is a comprehensive reference on the state of the art of gas-fired and coal-fired power plants, their major components and performance improvement options. Selected chapters are: Integrated gasification combined cycle (IGCC) power plant design and technology by Y. Zhu, and H. C. Frey; Improving thermal cycle efficiency in advanced power plants: water and steam chemistry and materials performance by B. Dooley; Advanced carbon dioxide (CO{sub 2}) gas separation membrane development for power plants by A. Basile, F. Gallucci, and P. Morrone; Advanced flue gas cleaning systems for sulphur oxides (SOx), nitrogen oxides (NOx) and mercury emissions control in power plants by S. Miller and B.G. Miller; Advanced flue gas dedusting systems and filters for ash and particulate emissions control in power plants by B.G. Miller; Advanced sensors for combustion monitoring in power plants: towards smart high-density sensor networks by M. Yu and A.K. Gupta; Advanced monitoring and process control technology for coal-fired power plants by Y. Yan; Low-rank coal properties, upgrading and utilisation for improving the fuel flexibility of advanced power plants by T. Dlouhy; Development and integration of underground coal gasification (UCG) for improving the environmental impact of advanced power plants by M. Green; Development and application of carbon dioxide (CO{sub 2}) storage for improving the environmental impact of advanced power plants by B. McPherson; and Advanced technologies for syngas and hydrogen (H{sub 2}) production from fossil-fuel feedstocks in power plants by P. Chiesa.

  10. Membrane processes in nuclear technologies

    International Nuclear Information System (INIS)

    Zakrzewska-Trznadel, G.

    2006-01-01

    The treatment of radioactive wastes is necessary taking into account the potential hazard of radioactive substances to human health and surrounding environment. The choice of appropriate technology depends on capital and operational costs, wastes amount and their characteristics, appointed targets of the process, e.g. the values of decontamination factors and volume reduction coefficients. The conventional technologies applied for radioactive waste processing, such as precipitation coupled with sedimentation, ion exchange and evaporation have many drawbacks. These include high energy consumption and formation of secondary wastes, e.g. the sludge from sediment tanks, spent ion exchange adsorbents and regeneration solutions. There are also many limitations of such processes, i.e. foaming and drop entrainment in evaporators, loses of solvents and production of secondary wastes in solvent extraction or bed clogging in ion exchange columns. Membrane processes as the newest achievement of the process engineering can successfully supersede many non-effective, out-of-date methods. But in some instances they can also complement these methods whilst improving the parameters of effluents and purification economy. This monograph presents own research data on the application of recent achievements in the area of membrane processes for solving selected problems in nuclear technology. Relatively big space was devoted to the use of membrane processing of low and intermediate radioactive liquid wastes because of numerous applications of these processes in nuclear centres over the world and also because of the interests of the author that was reflected by her recent research projects and activity. This work presents a review on the membrane methods recently introduced into the nuclear technology against the background of the other, commonly applied separation techniques, with indications of the possibilities and prospects for their further developments. Particular attention was paid

  11. Electrochromic Windows: Advanced Processing Technology

    Energy Technology Data Exchange (ETDEWEB)

    SAGE Electrochromics, Inc

    2006-12-13

    This project addresses the development of advanced fabrication capabilities for energy saving electrochromic (EC) windows. SAGE EC windows consist of an inorganic stack of thin films deposited onto a glass substrate. The window tint can be reversibly changed by the application of a low power dc voltage. This property can be used to modulate the amount of light and heat entering buildings (or vehicles) through the glazings. By judicious management of this so-called solar heat gain, it is possible to derive significant energy savings due to reductions in heating lighting, and air conditioning (HVAC). Several areas of SAGE’s production were targeted during this project to allow significant improvements to processing throughput, yield and overall quality of the processing, in an effort to reduce the cost and thereby improve the market penetration. First, the overall thin film process was optimized to allow a more robust set of operating points to be used, thereby maximizing the yield due to the thin film deposition themselves. Other significant efforts aimed at improving yield were relating to implementing new procedures and processes for the manufacturing process, to improve the quality of the substrate preparation, and the quality of the IGU fabrication. Furthermore, methods for reworking defective devices were developed, to enable devices which would otherwise be scrapped to be made into useful product. This involved the in-house development of some customized equipment. Finally, the improvements made during this project were validated to ensure that they did not impact the exceptional durability of the SageGlass® products. Given conservative estimates for cost and market penetration, energy savings due to EC windows in residences in the US are calculated to be of the order 0.026 quad (0.026×1015BTU/yr) by the year 2017.

  12. Overview of space nuclear technologies and the American Nuclear Society

    International Nuclear Information System (INIS)

    Singleterry, R.C. Jr.

    2000-01-01

    The American Nuclear Society (ANS) has seen an aspect of the universe where nuclear technology is the best energy source available for power, transportation, etc. The National Aeronautics and Space Administration (NASA) has been exploiting this aspect of the universe by sending machines and humans into it and exploring, colonizing, industrializing, developing, inhabiting, etc. Space is the final frontier, and nuclear technology is the best suited for today's or the next century's space exploration and development. Many aspects of nuclear technology and its uses in space will be needed. ANS encompasses these and many more aspects of nuclear technology, and all have some role to play in the exploration and development of space. It should be ANS's intent to be an advisory body to NASA on the nuclear aspects of space exploration

  13. The NEA Nuclear Education, Skills and Technology (NEST) Framework

    International Nuclear Information System (INIS)

    Andreeva, Liudmila; Gulliford, Jim

    2016-01-01

    Since the use of nuclear technology for a wide range of purposes is increasing, with many NEA member countries constructing or planning to construct new generation nuclear power plants, the NEA is developing the NEA Nuclear Education, Skills and Technology (NEST) Framework in partnership with its member countries. This initiative will help address important gaps in nuclear skills capacity building, knowledge transfer and technical innovation in an international context. It will also assist countries examining long-term options to manage high-level radioactive waste and spent nuclear fuel, as well as better ways to decommission old facilities. The majority of these countries are likewise facing challenging issues in other fields related to nuclear energy, ranging from medicine to the environment. The need to develop and apply innovative technologies in order to meet these challenges is apparent in all these areas. At the same time, advances in fields such as materials science and instrumentation, linked with the availability of high-performance computing, have opened up new avenues ripe for exploitation, which makes for a combination of exciting new areas of innovation alongside longstanding challenges in the nuclear field. The goal of NEST is to energise advanced students, post-doctoral appointees and young professionals to pursue careers in the nuclear field

  14. Directions for advanced use of nuclear power in century XXI

    International Nuclear Information System (INIS)

    Walter, C.E.

    1999-01-01

    Nuclear power can provide a significant contribution to electricity generation and meet other needs of the world and the US during the next century provided that certain directions are taken to achieve its public acceptance. These directions include formulation of projections of population, energy consumption, and energy resources over a responsible period of time. These projections will allow assessment of cumulative effects on the environment and on fixed resources. Use of fossil energy resources in a century of growing demand for energy must be considered in the context of long-term environmental damage and resource depletion. Although some question the validity of these consequences, they can be mitigated by use of advanced fast reactor technology. It must be demonstrated that nuclear power technology is safe, resistant to material diversion for weapon use, and economical. An unbiased examination of all the issues related to energy use, especially of electricity, is an essential direction to take

  15. Advanced microwave/millimeter-wave imaging technology

    International Nuclear Information System (INIS)

    Shen, Zuowei; Yang, Lu; Luhmann, N.C. Jr.

    2007-01-01

    Millimeter wave technology advances have made possible active and passive millimeter wave imaging for a variety of applications including advanced plasma diagnostics, radio astronomy, atmospheric radiometry, concealed weapon detection, all-weather aircraft landing, contraband goods detection, harbor navigation/surveillance in fog, highway traffic monitoring in fog, helicopter and automotive collision avoidance in fog, and environmental remote sensing data associated with weather, pollution, soil moisture, oil spill detection, and monitoring of forest fires, to name but a few. The primary focus of this paper is on technology advances which have made possible advanced imaging and visualization of magnetohydrodynamic (MHD) fluctuations and microturbulence in fusion plasmas. Topics of particular emphasis include frequency selective surfaces, planar Schottky diode mixer arrays, electronically controlled beam shaping/steering arrays, and high power millimeter wave local oscillator and probe sources. (author)

  16. IEA Energy Technology Essentials: Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-03-15

    The IEA Energy Technology Essentials series offers concise four-page updates on the different technologies for producing, transporting and using energy. Nuclear power is the topic covered in this edition.

  17. Transfer of nuclear technology from Spain

    International Nuclear Information System (INIS)

    Madrid, G.

    1985-01-01

    Technology transfer from Spain is possible in several fields of nuclear technology ranging from the head end of the fuel cycle (ENUSA) to the back end (ENRESA). The advantages of such a transfer are emphasized

  18. Complex program of advance in science and technology

    International Nuclear Information System (INIS)

    Sychev, V.V.

    1986-01-01

    A draft of the complex program of advance in science and technology of the CMEA member-countries is described in brief. The basis of the program includes five priority trends electronics development complex automatization, advanced development of nuclear energy, production of new materials and tecnologies of their production and processing, advanced developmen of biotechnologies. Development of nuclear energy will be based on WWER-440 and WWER-1000 type NPPs. Heat-only nuclear stations and power and heat nuclear stations will receive a large development effort, as well as sodium-cooled fast reactors of the BN type having 800 and 1600 MW capacity, high-temperature gas-cooled breeders of the BGR-300 type, gas-cooled reactors of the VG-400 type for high-temperature heat supply (500-1000 deg C). It is contemplated to design the TOKAMAK-15 research thermonuclear facility and a pilot thermonuclear reactor for power generation and plutonium production. The program also comprises works aimed at improving reliability and safety of the nuclear installations

  19. Melt processed crystalline ceramic waste forms for advanced nuclear fuel cycles: CRP T21027 1813: Processing technologies for high level waste, formulation of matrices and characterization of waste forms, Task 17208: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Amoroso, J. W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Marra, J. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-08-26

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multi-phase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing. This report summarizes results from three years of work on the IAEA Coordinated Research Project on “Processing technologies for high level waste, formulation of matrices and characterization of waste forms” (T21027), and specific task “Melt Processed Crystalline Ceramic Waste Forms for Advanced Nuclear Fuel Cycles” (17208).

  20. Melt processed crystalline ceramic waste forms for advanced nuclear fuel cycles: CRP T21027 1813: Processing technologies for high level waste, formulation of matrices and characterization of waste forms, task 17208: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Amoroso, J. W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Marra, J. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-08-26

    A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multi-phase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing. This report summarizes results from three years of work on the IAEA Coordinated Research Project on “Processing technologies for high level waste, formulation of matrices and characterization of waste forms” (T21027), and specific task “Melt Processed Crystalline Ceramic Waste Forms for Advanced Nuclear Fuel Cycles” (17208).