WorldWideScience

Sample records for base nuclear technology

  1. 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.

  2. Planning of the development of the MMIS core technology based on nuclear-IT convergence

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Kim, Chang Hwoi; Hwang, In Koo [KAERI, Daejeon (Korea, Republic of); and others

    2012-01-15

    - Drive nuclear-IT convergence technologies such as middleware applied new concept nuclear instrumentation and control architecture, automated operation of future nuclear power plant, virtual reality/augmented reality, design and verification technology of a nuclear power plant main control room, software dependability, and cyber security technology - Write state-of-the-art report for the nuclear instrumentation and control based on IT convergence - A prototype which implemented related equipment and software subject to nuclear reactor operator that reside in the main control room (Reactor Operator, RO) order to a on-site operator (Local Operator, LO) and confirm the task performance matches the RO's intention - 'IT Convergence intelligent instrumentation and control technology' project planning for the Fourth Nuclear Power Research and Development in the long-term plan.

  3. Heat and power sources based on nuclear shipbuilding technologies

    Energy Technology Data Exchange (ETDEWEB)

    Veshnyakov, K.; Fadeev, Y.; Panov, Y.; Polunichev, V. [JSC Afrikantov OKBM, Nizhny Novgorod (Russian Federation)

    2009-07-01

    The report gives information on the application of power units with small-power nuclear reactors as advanced energy sources to provide world consumers with electric power, domestic and industrial heat and fresh water. The report describes the technical concept of ABV unified reactor plant (RP) for floating and ground small power plants (SPP) developed in JSC 'Afrikantov OKBM'. The report contains the technical specification of the ABV RP utilizing an integral water-cooled reactor with thermal power of 38 to 45 MW, natural coolant circulation and improved inherent safety, as well as main characteristics of the reactor and core fuel ensuring acceptable mobility of the RP and NPP as a whole. The indicated refueling interval is 10-12 years. The report gives a detailed description of the concept for RP safety provision and compliance with international radiation and nuclear safety requirements, as well as the description of passive and other safety systems securing stability to any low-probability internal events, personnel errors and external impacts. The report provides data on application and technological properties of the floating and ground SPPs with a unified ABV RP; absence of spent fuel and radioactive waste at floating nuclear power plants (FNPP); FNPP transportation to consumers in a ready-to-operate state; arrangement, operation and disposal requirements.

  4. 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.

  5. 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.

  6. Fast 4$\\pi$ track reconstruction in nuclear emulsion detectors based on GPU technology

    CERN Document Server

    Ariga, A

    2013-01-01

    Fast 4$\\pi$ solid angle particle track recognition has been a challenge in particle physics for a long time, especially in using nuclear emulsion detectors. The recent advances in computing technology opened the way for its realization. A fast 4$\\pi$ solid angle particle track reconstruction based on GPU technology combined with a multithread programming is reported here with a detailed comparison between GPU-based and CPU-based programming. A 60 times faster processing of 3D emulsion detector data, corresponding to processing of 15 cm$^2$ emulsion surface scanned per hour, has been achieved by GPUs with an excellent tracking performance.

  7. Industrialization of Nuclear Technology

    Institute of Scientific and Technical Information of China (English)

    2015-01-01

    1 Overview1.1 Income from operating activities Sale income from application of nuclear technology and non-nuclear products totaled 419million Yuan in 2015,an increase of 23.6%over the previous year,exceeding the target income set at the beginning of 2015.Of the total,sale incomes from iridium source,cobalt source,inspection system

  8. Space and nuclear research and technology

    Science.gov (United States)

    1975-01-01

    A fact sheet is presented on the space and nuclear research and technology program consisting of a research and technology base, system studies, system technology programs, entry systems technology, and experimental programs.

  9. Proceedings of the 2011 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Patterson, Eileen F. [Editor; Sandoval, Marisa N. [Editor

    2011-09-13

    These proceedings contain papers prepared for the Monitoring Research Review 2011: Ground-Based Nuclear Explosion Monitoring Technologies, held 13-15 September, 2011 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), National Science Foundation (NSF), and other invited sponsors. The scientific objectives of the research are to improve the United States' capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  10. Proceedings of the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Benson, Jody [Editor; Patterson, Eileen F. [Editor

    2007-09-25

    These proceedings contain papers prepared for the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 25-27 September, 2007 in Denver, Colorado. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  11. Proceedings of the 28th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Benson, Jody [Editor; Patterson, Eileen F. [Editor

    2006-09-19

    These proceedings contain papers prepared for the 28th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 19-21 September, 2006 in Orlando, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  12. Proceedings of the 2010 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A [Editor; Patterson, Eileen F [Editor

    2010-09-21

    These proceedings contain papers prepared for the Monitoring Research Review 2010: Ground-Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2010 in Orlando, Florida,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, National Science Foundation (NSF), Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  13. Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01

    This publication 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 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 the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, 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.

  14. 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.

  15. 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.

  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. New radiological material detection technologies for nuclear forensics: Remote optical imaging and graphene-based sensors.

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, Richard Karl [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Martin, Jeffrey B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wiemann, Dora K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Choi, Junoh [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Howell, Stephen W. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    We developed new detector technologies to identify the presence of radioactive materials for nuclear forensics applications. First, we investigated an optical radiation detection technique based on imaging nitrogen fluorescence excited by ionizing radiation. We demonstrated optical detection in air under indoor and outdoor conditions for alpha particles and gamma radiation at distances up to 75 meters. We also contributed to the development of next generation systems and concepts that could enable remote detection at distances greater than 1 km, and originated a concept that could enable daytime operation of the technique. A second area of research was the development of room-temperature graphene-based sensors for radiation detection and measurement. In this project, we observed tunable optical and charged particle detection, and developed improved devices. With further development, the advancements described in this report could enable new capabilities for nuclear forensics applications.

  18. Proceedings of the 27th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Benson, Jody [Editor; Patterson, Eileen F. [Editor

    2005-09-20

    These proceedings contain papers prepared for the 27th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 20-22 September, 2005 in Rancho Mirage, California. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  19. Proceedings of the 2009 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marv A [Los Alamos National Laboratory; Aguilar - Chang, Julio [Los Alamos National Laboratory; Anderson, Dale [Los Alamos National Laboratory; Arrowsmith, Marie [Los Alamos National Laboratory; Arrowsmith, Stephen [Los Alamos National Laboratory; Baker, Diane [Los Alamos National Laboratory; Begnaud, Michael [Los Alamos National Laboratory; Harste, Hans [Los Alamos National Laboratory; Maceira, Monica [Los Alamos National Laboratory; Patton, Howard [Los Alamos National Laboratory; Phillips, Scott [Los Alamos National Laboratory; Randall, George [Los Alamos National Laboratory; Rowe, Charlotte [Los Alamos National Laboratory; Stead, Richard [Los Alamos National Laboratory; Steck, Lee [Los Alamos National Laboratory; Whitaker, Rod [Los Alamos National Laboratory; Yang, Xiaoning ( David ) [Los Alamos National Laboratory

    2009-09-21

    These proceedings contain papers prepared for the Monitoring Research Review 2009: Ground -Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2009 in Tucson, Arizona,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Test Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States’ capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  20. 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.

  1. Powered by technology or powering technology?---Belief-based decision-making in nuclear power and synthetic fuel

    Science.gov (United States)

    Yang, Chi-Jen

    , indeterminate, and relatively impotent, which explains the hesitancy in the government's synfuel endeavors. In retrospect, it is not difficult to see that many of the pivotal decisions were "belief-based". Due to the long-term nature of energy planning and the inherent unpredictability of the distant future, important energy investment decisions are inevitably based on decision-makers' beliefs. Unfortunately, many generally agreed views about the future turned out to be wrong. Shared beliefs are socially constructed and reflect particular zeitgeists. Another important finding is a recurrent herding phenomenon in the forecasters' community. This phenomenon largely explains the repeated forecasting fallacies. As history reveals itself, shared beliefs about the long-term future have been repeatedly proven wrong. Nevertheless, mistakes caused by misguided beliefs often survive. As culture evolves over the long-term, an old belief system, i.e. a worldview/zeitgeist, may be challenged by a new one. Two competing worldviews underlay the pro- and antinuclear controversies: one embraces modernism while the other is skeptical of it. Long-lived, large-scale capital-intensive energy facilities, such as nuclear power plants, are inevitably encumbered with unique "outlived-zeitgeist" jeopardy. Understanding this peculiar but pervasive characteristic teaches important lessons for today's decision-making about hydrogen and other energy technologies, and the stakes, if anything, are even higher than before.

  2. Development of innovative technological base for large-scale nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Adamov, E.O.; Dedul, A.V.; Orlov, V.V.; Rachkov, V.I.; Slesarev, I.S. [ITC ' ' PRORYV' ' Project, Moscow (Russian Federation)

    2017-04-15

    The problems of the Nuclear Power (NP) further development as well as the ways of their resolution on the basis of innovative fast reactor concepts and the Closed Equilibrium Fuel Cycle (CEFC) are analyzed. The new paradigm of NP and the corresponding NP super task are declared. The corresponding super task could be considered a transition to the vital risk free nuclear power through the guaranteed elimination/suppression of all their vital risks and threats (or their transformation to the category of some ordinary risks and threats) on the base of ''natural safety principle''. The project of Rosatom State Corporation (named ''PRORYV'') is launched within the Federal Target Program ''Nuclear power technologies of new generation for 2010 to 2015 and in perspective till 2020''. It has been planned just for these goals achievement. Super-task solution is quite ''on teeth'' to PRORYV project which is initially focused on the ''natural safety'' realization. This project is aimed, in particular, at construction of the demonstration lead cooled reactor BREST-300-OD and the enterprise for equilibrium fuel cycle closing.

  3. Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Solonin, M.I.; Polyakov, A.S.; Zakharkin, B.S.; Smelov, V.S.; Nenarokomov, E.A.; Mukhin, I.V. [SSC, RF, A.A. Bochvar ALL-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

    2000-07-01

    To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

  4. 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

  5. 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

  6. Development of DUPIC safeguards technology; development of web based nuclear material accounting program

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. T.; Choi, S. H.; Choi, S. J. [Kongju National University, Kongju (Korea)

    2002-04-01

    The purpose of this project is to develop the web-based digital image processing system with the client/server architecture based on TCP/IP to be able to search and manage image data at the remote place. This system provides a nuclear facility with the ability to track the movement of nuclear material and to control and account nuclear material at anywhere and anytime. Also, this system will be helpful to increase the efficiency of safeguards affairs. The developed web-based digital image processing system for tracking the movement of nuclear material and MC and A can be applied to DUPIC facility. The result of this project will eventually contribute to similar nuclear facilities as well as the effective implementation of DUPIC safeguards. In addition, it will be helpful to enhance international confidence build-up in the peaceful use of spent fuel material. 15 refs., 33 figs., 4 tabs. (Author)

  7. Developments of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2003-03-15

    The objective of this research is to develop an efficient evaluation technology and to investigate applicability of newly-developed technology, such as internet-based cyber platform, to operating power plants. Development of efficient evaluation systems for Nuclear Power Plant components, based on structural integrity assessment techniques, are increasingly demanded for safe operation with the increasing operating period of Nuclear Power Plants. The following five topics are covered in this project: development of assessment method for wall-thinned nuclear piping based on pipe test; development of structural integrity program for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for mam components of NPP; development of internet-based cyber platform and integrity program for primary components of NPP; effect of aging on strength of dissimilar welds.

  8. Chinese Nuclear Science Basic Data Base (CNSBDB)

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    A new research project on "Development of the Chinese Nuclear Science Basic Database (CNSBDB)for Fundamental Researches of Nuclear Physics and Interrelated Subjects, and Requirements of NuclearPower and Nuclear Technologies Application" has been commenced. The CNSBDB contains thefollowing eight segments: 1) Information on Nuclear Science (INFO); 2) Nuclear Structure Data Base(NSDB); 3) Nuclear Decay Data Base (NDDB); 4) Nuclear Reaction Data Base (NRDB); 5) Nuclear

  9. Alternative nuclear technologies

    Science.gov (United States)

    Schubert, E.

    1981-10-01

    The lead times required to develop a select group of nuclear fission reactor types and fuel cycles to the point of readiness for full commercialization are compared. Along with lead times, fuel material requirements and comparative costs of producing electric power were estimated. A conservative approach and consistent criteria for all systems were used in estimates of the steps required and the times involved in developing each technology. The impact of the inevitable exhaustion of the low- or reasonable-cost uranium reserves in the United States on the desirability of completing the breeder reactor program, with its favorable long-term result on fission fuel supplies, is discussed. The long times projected to bring the most advanced alternative converter reactor technologies the heavy water reactor and the high-temperature gas-cooled reactor into commercial deployment when compared to the time projected to bring the breeder reactor into equivalent status suggest that the country's best choice is to develop the breeder. The perceived diversion-proliferation problems with the uranium plutonium fuel cycle have workable solutions that can be developed which will enable the use of those materials at substantially reduced levels of diversion risk.

  10. The nuclear materials control technology briefing book

    Energy Technology Data Exchange (ETDEWEB)

    Hartwell, J.K.; Fernandez, S.J.

    1992-03-01

    As national and international interests in nuclear arms control and non-proliferation of nuclear weapons, intensify, it becomes ever more important that contributors be aware of the technologies available for the measurement and control of the nuclear materials important to nuclear weapons development. This briefing book presents concise, nontechnical summaries of various special nuclear material (SNM) and tritium production monitoring technologies applicable to the control of nuclear materials and their production. Since the International Atomic Energy Agency (IAEA) operates a multinational, on-site-inspector-based safeguards program in support of the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), many (but not all) of the technologies reported in this document are in routine use or under development for IAEA safeguards.

  11. Development of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2004-02-15

    The objective of this research is to develop on efficient integrity evaluation technology and to investigate the applicability of the newly-developed technology such as internet-based cyber platform etc. to Nuclear Power Plant(NPP) components. The development of an efficient structural integrity evaluation system is necessary for safe operation of NPP as the increase of operating periods. Moreover, material test data as well as emerging structural integrity assessment technology are also needed for the evaluation of aged components. The following five topics are covered in this project: development of the wall-thinning evaluation program for nuclear piping; development of structural integrity evaluation criteria for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for major components of NPP; ingegration of internet-based cyber platform and integrity evaluation program for primary components of NPP; effects of aging on strength of dissimilar welds.

  12. 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.

  13. Focused technology: Nuclear propulsion

    Science.gov (United States)

    Miller, Thomas J.

    1991-01-01

    The topics presented are covered in viewgraph form and include: nuclear thermal propulsion (NTP), which challenges (1) high temperature fuel and materials, (2) hot hydrogen environment, (3) test facilities, (4) safety, (5) environmental impact compliance, and (6) concept development, and nuclear electric propulsion (NEP), which challenges (1) long operational lifetime, (2) high temperature reactors, turbines, and radiators, (3) high fuel burn-up reactor fuels, and designs, (4) efficient, high temperature power conditioning, (5) high efficiency, and long life thrusters, (6) safety, (7) environmental impact compliance, and (8) concept development.

  14. Recapturing Graphite-Based Fuel Element Technology for Nuclear Thermal Propulsion

    Energy Technology Data Exchange (ETDEWEB)

    Trammell, Michael P [ORNL; Jolly, Brian C [ORNL; Miller, James Henry [ORNL; Qualls, A L [ORNL; Harrison, Thomas J [ORNL

    2013-01-01

    ORNL is currently recapturing graphite based fuel forms for Nuclear Thermal Propulsion (NTP). This effort involves research and development on materials selection, extrusion, and coating processes to produce fuel elements representative of historical ROVER and NERVA fuel. Initially, lab scale specimens were fabricated using surrogate oxides to develop processing parameters that could be applied to full length NTP fuel elements. Progress toward understanding the effect of these processing parameters on surrogate fuel microstructure is presented.

  15. 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)

  16. 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

  17. Development of melt dilute technology for disposition of aluminum based spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Swift, W.F. [Nuclear Material Management Division Westinghouse Savannah River Company, Savannah River Site Building 707-C, Aiken, SC 29808 (United States)

    2002-07-01

    The US Department of Energy (DOE) has for many years had a program for receipt and disposition of spent nuclear fuels of US origin from research reactors around the world. The research reactor spent nuclear fuel that consists of aluminum alloy composition has historically been returned to the Savannah River Site (SRS) and dispositioned via chemical reprocessing. In 1995, the DOE evaluated a number of alternatives to chemical reprocessing. In 2000, the DOE selected the melt-dilute alternative as the primary disposition path and direct disposal as the backup path. The melt-dilute technology has been developed from lab-scale demonstration up through the construction of a pilot-scale facility. The pilot-scale L-Area Experimental Facility (LEF) has been constructed and is ready for operation. The LEF will be used primarily, to confirm laboratory research on zeolite media for off- gas trapping and remote operability. Favorable results from the LEF are expected to lead to final design of the production melt-dilute facility identified as the Treatment and Storage Facility (TSF). This paper will describe the melt-dilute process and provide a status of the program development. (author)

  18. The Governance of Nuclear Technology

    Energy Technology Data Exchange (ETDEWEB)

    Vergino, E S; May, M

    2003-09-22

    Eisenhower's Atoms for Peace speech in 1953 is remembered for engaging the world, and the Soviet Union in particular, in a dialogue about arms control and the formulation of a nuclear regime in which national and international security concerns growing from this unprecedented emerging and frightening new weapons capability would be addressed while tapping the civilian promise of nuclear applications for the good of mankind. Out of it came a series of initiatives, leading fifteen years later to the NPT, intended to allow the growth and spread of the beneficial uses of nuclear know-how while constraining the incentives and capabilities for nuclear weapons. The last 50 years has seen a gradual spread in nations with nuclear weapons, other nations with nuclear knowledge and capabilities, and still others with nuclear weapon intentions. Still most nations of the world have forgone weapon development, most have signed and abided by the NPT, and some that have had programs or even weapons, have turned these capabilities off. Yet despite this experience, and despite a relatively successful record up to a few years ago, there is today a clear and generally recognized crisis in nuclear governance, a crisis that affects the future of all the cross-cutting civilian/security issues we have cited. The crux of this crisis is a lack of consensus among the major powers whose support of international efforts is necessary for effective governance of nuclear activities. The lack of consensus focuses on three challenges: what to do about non-compliance, what to do about non-adherence, and what to do about the possible leakage of nuclear materials and technologies to terrorist groups. Short of regaining consensus on the priority to be given to nuclear material and technology controls, it is unlikely that any international regime to control nuclear materials and technologies, let alone oversee a growth in the nuclear power sector, will be successful in the tough cases where it needs

  19. Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

    Energy Technology Data Exchange (ETDEWEB)

    Hou, Xue Yan; Li, Shu; Li, Qing [China Nuclear Power Operation Technology Co., Wuhan (China)

    2011-08-15

    Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier.

  20. 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.

  1. Spent Nuclear Fuel Alternative Technology Decision Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, C.B.

    1999-11-29

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

  2. 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.

  3. ANSTO: Australian Nuclear Science and Technology Organization

    Science.gov (United States)

    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 the nuclear medicine industry and research. It also operates national nuclear facilities (HIFAR and Moata research reactors), promotes training, provides advice and disseminates information on nuclear science and technology. The booklet briefly outlines these activities.

  4. Spent Nuclear Fuel Alternative Technology Risk Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Perella, V.F.

    1999-11-29

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment.

  5. 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

  6. Development of Nuclear Analytical Technology

    Energy Technology Data Exchange (ETDEWEB)

    Park, Yong Joon; Kim, J. Y.; Sohn, S. C. (and others)

    2007-06-15

    The pre-treatment and handling techniques for the micro-particles in swipe samples were developed for the safeguards purpose. The development of screening technique for the swipe samples has been established using the nuclear fission track method as well as the alpha track method. The laser ablation system to take a nuclear particle present in swipe was designed and constructed for the determination of the enrichment factors for uranium or plutonium, and its performance was tested in atmosphere as well as in vacuum. The optimum conditions for the synthesis of silica based micro-particles were obtained for mass production. The optimum ion exchange resin was selected and the optimum conditions for the uranium adsorption in resin bead technique were established for the development of the enrichment factor for nuclear particles in swipe. The established technique was applied to the swipe taken directly from the nuclear facility and also to the archive samples of IAEA's environmental swipes. The evaluation of dose rate of neutron and secondary gamma-ray for the radiation shields were carried out to design the NIPS system, as well as the evaluation of the thermal neutron concentration effect by the various reflectors. D-D neutron generator was introduced as a neutron source for the NIPS system to have more advantages such as easier control and moderation capability than the {sup 252}Cf source. Simulated samples for explosive and chemical warfare were prepared to construct a prompt gamma-ray database. Based on the constructed database, a computer program for the detection of illicit chemical and nuclear materials was developed using the MATLAB software.

  7. 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.

  8. 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

  9. The broad view of nuclear technology for aerospace

    Energy Technology Data Exchange (ETDEWEB)

    Buden, D. (Center for Nuclear Engineering and Technology, Idaho National Engineering Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415-2516 (US)); Angelo, J.A. Jr. (Science Applications International Corp., 700 South Babcock Street, Suite 300, Melbourne, Florida 32901 (US))

    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.

  10. Nuclear Technology for the Sustainable Development Goals

    Science.gov (United States)

    Darby, Iain

    2017-01-01

    Science, technology and innovation will play a crucial role in helping countries achieve the ambitious Sustainable Development Goals (SDGs). Since the discovery of nuclear fission in the 1930s, the peaceful applications of nuclear technology have helped many countries improve crops, fight pests, advance health, protect the environment and guarantee a stable supply of energy. Highlighting the goals related to health, hunger, energy and the environment, in this presentation I will discuss how nuclear technology contributes to the SDGs and how nuclear technology can further contribute to the well-being of people, help protect the planet and boost prosperity.

  11. Freeze Technology for Nuclear Applications - 13590

    Energy Technology Data Exchange (ETDEWEB)

    Rostmark, Susanne C.; Knutsson, Sven [Lulea University of Technology (Sweden); Lindberg, Maria [Studsvik Nuclear AB, 611 82 Nykoeping (Sweden)

    2013-07-01

    Freezing of soil materials is a complicated process of a number of physical processes: - freezing of pore water in a thermal gradient, - cryogenic suction causing water migration and - ice formation expanding pores inducing frost heave. Structural changes due to increase of effective stress during freezing also take place. The over consolidation gives a powerful dewatering/drying effect and the freeze process causes separation of contaminates. Artificial ground freezing (AGF is a well established technique first practiced in south Wales, as early as 1862. AGF is mostly used to stabilize tunnels and excavations. During the last ten years underwater applications of freeze technologies based on the AGF have been explored in Sweden. The technology can, and has been, used in many different steps in a remediation action. Freeze Sampling where undisturbed samples are removed in both soft and hard sediment/sludge, Freeze Dredging; retrieval of sediment with good precision and minimal redistribution, and Freeze Drying; volume reduction of contaminated sludge/sediment. The application of these technologies in a nuclear or radioactive environment provides several advantages. Sampling by freezing gives for example an advantage of an undisturbed sample taken at a specified depth, salvaging objects by freezing or removal of sludges is other applications of this, for the nuclear industry, novel technology. (authors)

  12. Energy supply technologies. Nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Lauritsen, Bent.; Nonboel, E. [Risoe National Lab. - DTU (Denmark); Vuori, S. [VTT (Finland)

    2007-11-15

    Nuclear power has long been controversial, especially in Europe, with concerns over the safety of nuclear installations, radioactive waste, and proliferation of nuclear weapon materials. Globally, however, renewed interest in nuclear energy has been sparked by concerns for energy security, economic development, and commitment to reduce CO{sub 2} emissions. Nuclear fission is a major source of energy that is free from CO{sub 2} emissions. It provides 15 % of the world's electricity and 7 % of total primary energy consumption. Around 440 nuclear reactors are currently generating power in 31 countries, with largest capacity in Europe, the USA and Southeast Asia. Non-electricity applications are few at present, but include process heat, hydrogen production, ship propulsion, and desalination. Nuclear power is characterised by high construction costs and a relatively long construction period, but low operating and maintenance expenses, including fuel. Most nuclear power plants in the USA and Europe have second-generation light water reactors (LWRs), while the plants now being built in Southeast Asia are of third-generation design. The Evolutionary Power Reactor (EPR) under construction in Finland, and the Pebble Bed Modular Reactor (PBMR) being developed in South Africa, are both of types referred to as Generation III+. From 2020-30 onwards fourth-generation reactors are expected to provide improved fuel utilisation and economics. Nuclear power does not form part of the Danish energy mix and at present there seems to be little political will to change this position. As a result Denmark has relatively little expertise in nuclear power. However, since nuclear power provides a substantial share of Europe's electricity, Denmark should ensure that it has expertise to advise the government and the public on nuclear issues. (BA)

  13. 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

  14. 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

  15. Nuclear vapor thermal reactor propulsion technology

    Science.gov (United States)

    Maya, Isaac; Diaz, Nils J.; Dugan, Edward T.; Watanabe, Yoichi; McClanahan, James A.; Wen-Hsiung Tu, Carman, Robert L.

    1993-01-01

    The conceptual design of a nuclear rocket based on the vapor core reactor is presented. The Nuclear Vapor Thermal Rocket (NVTR) offers the potential for a specific impulse of 1000 to 1200 s at thrust-to-weight ratios of 1 to 2. The design is based on NERVA geometry and systems with the solid fuel replaced by uranium tetrafluoride (UF4) vapor. The closed-loop core does not rely on hydrodynamic confinement of the fuel. The hydrogen propellant is separated from the UF4 fuel gas by graphite structure. The hydrogen is maintained at high pressure (˜100 atm), and exits the core at 3,100 K to 3,500 K. Zirconium carbide and hafnium carbide coatings are used to protect the hot graphite from the hydrogen. The core is surrounded by beryllium oxide reflector. The nuclear reactor core has been integrated into a 75 klb engine design using an expander cycle and dual turbopumps. The NVTR offers the potential for an incremental technology development pathway to high performance gas core reactors. Since the fuel is readily available, it also offers advantages in the initial cost of development, as it will not require major expenditures for fuel development.

  16. ABB Combustion Engineering nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Matzie, R.A.

    1994-12-31

    The activities of ABB Combustion Engineering in the design and construction of nuclear systems and components are briefly reviewed. ABB Construction Engineering continues to improve the design and design process for nuclear generating stations. Potential improvements are evaluated to meet new requirements both of the public and the regulator, so that the designs meet the highest standards worldwide. Advancements necessary to meet market needs and to ensure the highest level of performance in the future will be made.

  17. The social shaping of nuclear energy technology in South Africa

    OpenAIRE

    2016-01-01

    This paper analyses the question why the South African government intends to procure nuclear energy technology, despite affordable and accessible fossil and renewable energy alternatives. We analyse the social shaping of nuclear energy technology based on the statements of political actors in the public media. We combine a discourse network analysis with qualitative analysis to establish the coalitions in support and opposition of the programme. The central arguments in the debate are cost, s...

  18. Atomic nanoscale technology in the nuclear industry

    CERN Document Server

    Woo, Taeho

    2011-01-01

    Developments at the nanoscale are leading to new possibilities and challenges for nuclear applications in areas ranging from medicine to international commerce to atomic power production/waste treatment. Progress in nanotech is helping the nuclear industry slash the cost of energy production. It also continues to improve application reliability and safety measures, which remain a critical concern, especially since the reactor disasters in Japan. Exploring the new wide-ranging landscape of nuclear function, Atomic Nanoscale Technology in the Nuclear Industry details the breakthroughs in nanosca

  19. Prospect of nuclear application in food technology

    Energy Technology Data Exchange (ETDEWEB)

    Maha, M. (National Atomic Energy Agency, Jakarta (Indonesia). Pasar Djumat Research Centre)

    1982-04-01

    Irradiation changes the normal living process of cells and the structure of molecules. It is good for food preservation because it kills off many of the microorganisms in the product and makes the remainder more sensitive to antimicrobial factors prevailing after the radiation treatment. It offers more benefits than conventional preservation in that it increases storage stability and quality of foodstuffs with the minimum use of energy. Good storage quality gives way to wider distribution of food, alleviates the world's food shortage, and improves food supplies. Research proved that irradiation increased the quality of subtropical fruits, spices, fish, and meat. No refrigeration is needed to store meat, poultry and fish preserved by the combination of irradiation and mild heat treatment. Nuclear technology can also be applied to destroy harmful insects, to sterilize food, to inhibit the sprouting of root crops, and to control ripening in stored fruits and vegetables. Based on the above potentials of irradiation, the prospect of nuclear application in food technology is promising.

  20. A study on nuclear technology policy

    Energy Technology Data Exchange (ETDEWEB)

    Yang, M. H.; Kim, H. J.; Chung, W. S.; Yun, S. W.; Kim, H. S

    2001-01-01

    This study was carried out as a part of institutional activities of KAERI. Major research area are as follows; Future directions and effects for national nuclear R and D to be resulted from restructuring of electricity industry are studied. Comparative study was carried out between nuclear energy and other energy sources from the point of views of environmental effects by introducing life cycle assessment(LCA) method. Japanese trends of reestablishment of nuclear policy such as restructuring of nuclear administration system and long-term plan of development and use of nuclear energy are also investigated, and Russian nuclear development program and Germany trends for phase-out of nuclear electricity generation are also investigated. And trends of the demand and supply of energy in eastern asian countries in from the point of view of energy security and tension in the south china sea are analyzed and investigation of policy trends of Vietnam and Egypt for the development and use of nuclear energy for the promotion of nuclear cooperation with these countries are also carried out. Due to the lack of energy resources and high dependence of imported energy, higher priority should be placed on the use of localized energy supply technology such as nuclear power. In this connection, technological development should be strengthened positively in order to improve economy and safety of nuclear energy and proliferation resistance of nuclear fuel cycle and wide ranged use of radiation and radioisotopes and should be reflected in re-establishment of national comprehensive promotion plan of nuclear energy in progress.

  1. U.S. Forward Operating Base Applications of Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, George W. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  2. 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

  3. Basic research for nuclear energy. y Study on the nuclear materials technology

    Energy Technology Data Exchange (ETDEWEB)

    Kuk, I. H.; Lee, H. S.; Jeong, Y. H.; Sung, K. W.; Han, J. H.; Lee, J. T.; Lee, H. K.; Kim, S. J.; Kang, H. S.; An, D. H.; Kim, K. R.; Park, S. D.; Han, C. H.; Jung, M. K.; Oh, Y. J.; Kim, K. H.; Kim, S. H.; Back, J. H.; Kim, C. H.; Lim, K. S.; Kim, Y. Y.; Na, J. W.; Ku, J. H.; Lee, D. H.

    1996-12-01

    A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs.

  4. Current Abstracts Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Bales, J.D.; Hicks, S.C. [eds.

    1993-01-01

    This publication 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 during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international 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 the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, 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.

  5. 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

  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. Proceedings of the 2nd NUCEF international symposium NUCEF`98. Safety research and development of base technology on nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    This volume contains 68 papers presented at the 2nd NUCEF International Symposium NUCEF`98 held on 16-17 November 1998, in Hitachinaka, Japan, following the 1st symposium NUCEF`95 (Proceeding: JAERI-Conf 96-003). The theme of this symposium was `Safety Research and Development of Base Technology on Nuclear Fuel Cycle`. The papers were presented in oral and poster sessions on following research fields: (1) Criticality Safety, (2) Reprocessing and Partitioning, (3) Radioactive Waste Management. The 68 papers are indexed individually. (J.P.N.)

  8. Development of nuclear equipment qualification technology

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

    1999-03-01

    In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

  9. Small Nuclear Technology and Market Entry

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, J S; Schock, R N; Brown, N W; Smith, C F

    2002-05-31

    An overview of energy-system projections into the new century leads to the conclusion that nuclear power will play a significant role. How significant a role will be determined by the marketplace. Within the range of nuclear-power technologies available, small nuclear-power plants of innovative design appear to fit the needs of a number of developing nations and states. Under similar financing options used by the airline industry and others, the capital requirement barrier that puts the nuclear industry at a disadvantage in deregulated markets could be reduced. These plants have the potential advantage of modularity, are proliferation-resistant, incorporate passive safety features, minimize waste, and could be cost-competitive with fossil-fuel plants.

  10. Review of Current Nuclear Vacuum System Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, M.; McCracken, J.; Shope, T.

    2003-02-25

    Nearly all industrial operations generate unwanted dust, particulate matter, and/or liquid wastes. Waste dust and particulates can be readily tracked to other work locations, and airborne particulates can be spread through ventilation systems to all locations within a building, and even vented outside the building - a serious concern for processes involving hazardous, radioactive, or nuclear materials. Several varieties of vacuum systems have been proposed and/or are commercially available for clean up of both solid and liquid hazardous and nuclear materials. A review of current technologies highlights both the advantages and disadvantages of the various systems, and demonstrates the need for a system designed to address issues specific to hazardous and nuclear material cleanup. A review of previous and current hazardous/nuclear material cleanup technologies is presented. From simple conventional vacuums modified for use in industrial operations, to systems specifically engineered for such purposes, the advantages and disadvantages are examined in light of the following criteria: minimal worker exposure; minimal secondary waste generation;reduced equipment maintenance and consumable parts; simplicity of design, yet fully compatible with all waste types; and ease of use. The work effort reviews past, existing and proposed technologies in light of such considerations. Accomplishments of selected systems are presented, including identified areas where technological improvements could be suggested.

  11. Thorium nuclear fuel cycle technology

    Energy Technology Data Exchange (ETDEWEB)

    Eom, Tae Yoon; Do, Jae Bum; Choi, Yoon Dong; Park, Kyoung Kyum; Choi, In Kyu; Lee, Jae Won; Song, Woong Sup; Kim, Heong Woo

    1998-03-01

    Since thorium produces relatively small amount of TRU elements after irradiation in the reactor, it is considered one of possible media to mix with the elements to be transmuted. Both solid and molten-salt thorium fuel cycles were investigated. Transmutation concepts being studied involved fast breeder reactor, accelerator-driven subcritical reactor, and energy amplifier with thorium. Long-lived radionuclides, especially TRU elements, could be separated from spent fuel by a pyrochemical process which is evaluated to be proliferation resistance. Pyrochemical processes of IFR, MSRE and ATW were reviewed and evaluated in detail, regarding technological feasibility, compatibility of thorium with TRU, proliferation resistance, their economy and safety. (author). 26 refs., 22 figs

  12. Preserving competence in nuclear technology. Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Steinwarz, Wolfgang [Siempelkamp Behaeltertechnik GmbH, Krefeld (Germany)

    2015-10-15

    On the 17th workshop Preserving Competence in Nuclear Technology 21 young scientists presented the scientific results from their thesis work for a diploma, mastership or a PhD covering a broad spectrum of technical areas. This demonstrated again the strong engagement of the younger generation as part of the German nuclear society. Prof. Dr.-Ing. Eckart Laurin, Prof. Dr.-Ing. Marco K. Koch and Dr.-Ing. Wolfgang Steinwarz as members of the jury assessed the written compacts and the oral presentations to award the Siempelkamp Competence Price 2015 to Tobias Seidel from Helmholtz-Zentrum Dresden-Rossendorf e.V.

  13. Nuclear Systems (NS): Technology Demonstration Unit (TDU) Project

    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,...

  14. 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

  15. 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

  16. Study on the establishment of nuclear education and training network based on the nuclear knowledge management

    Energy Technology Data Exchange (ETDEWEB)

    Lee, U. J.; Han, K. W.; Jeon, P. I.; Kim, Y. T.; Nam, Y. M.; Won, J. Y.; Kim, H. K. [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    The preservation and succession of nuclear knowledge are essential for the sustainable development of nuclear energy. Nuclear knowledge management is inseparably related with education and training, also should be considered as future oriented activities for the next generation. Nevertheless mankind has enormously benefited worldwide from the use of the nuclear energy over the last half a century, nuclear energy has faced with difficulties from the public. The current nuclear workforce is getting older, less of youth are studying nuclear science and engineering. These issues should be discussed together with the government, research institutes, universities, and industries in terms of the preservation and succession of nuclear knowledge. Therefore, education and training of nuclear technology is requested to develop its role with cooperation of the national level, furthermore of regional and interregional level. This paper provides the methodology of the establishment of a regional network of nuclear education and training based on the nuclear knowledge management.

  17. Development of reliability-based safety enhancement technology; development of organization concept model in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Hyun; Kim, Ju Youl; Kim, Yoon Ik; Yang, Hui Chang; Lee, Yong Sik; Kim, Se Hyung [Seoul National University, Seoul (Korea)

    2002-03-01

    The influences of organizational factors on safety of nuclear power plants are mentioned in the early 1970s and noticed after being focused on in the accident report of TMI in 1979. These needs let us implement this research and the purposes of this research are to assess the organizational influences and to develop the organizational conceptual model to establish the basis of identifying the organizational factors, using this model to contribute to enhance safety and economics in nuclear power plants. Eventually research on the organizational influences is expected to have two effects, which are to improve safety through identifying potential causes of accidents and to elevate economics as a new approach to more efficient operation of nuclear power plants. In this study, recent studies were surveyed on the organizational conceptual model, the identification of organizational factors, assessment of organizational influences and evaluation methods of organizational factors and organizational influences among the overseas and domestic researches. In addition specific characteristics of domestic nuclear power plants were tried to identify through plant visit and an evaluation method of organizational influences on component maintenance and human performance were developed and presented. 71 refs., 40 figs., 18 tabs. (Author)

  18. Analysis of trends in publications and citations of papers on nuclear science and technology field in Korea: Focusing on the Scopus Data Base

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Young Choon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The data on the top 20 journals in the Science Citation Index(Expanded) for 10 years from 2005 to 2014 indicated the first and second positions for Korean papers were occupied by the Korean journals, which implied the need for globalization of target journals to publish Korean papers. Further study is required for comparative analysis of the factors impacting on the number of papers and citations, which is the criteria for quality evaluation of papers, in other area than the Nuclear Energy and Engineering to which this study was limited. As the media for research process and results, papers play an important role in the evaluation of research projects. While the traditional methods for evaluation of research results have been focused on quantity aspects, the implication of quality aspect is increasingly recognized. Most national labs have begun to shift from quantity to quality in their criteria for overall evaluation of research results. It is therefore desired to maximize the quality level of the research papers for which the trends in citation as quality indicator could be analyzed as well as the quantity aspect. This paper looks at the trends in the number of citation and papers as the indicators of quality and quantify, as drawn from Scopus Data Base. It also suggest top 5 Science Citation Index(Expanded) journals in terms of increase rate in both number of papers and citations. The purpose is to compare them with top 20 Science Citation Index(Expanded) journals in which Korea Atomic Energy Research researchers have published their papers in the past 10 years from 2005 to 2014 were submitted. This paper looked at the trends in the number of papers and citations as an indicator of quality of the research papers in the area of Nuclear Energy and Engineering which is in fact a limitation to the key subject area, not covering the whole nuclear science and technology.

  19. Internal Mainland Nuclear Power Liquid Waste Treatment Technology

    Institute of Scientific and Technical Information of China (English)

    YOU; Xin-feng; ZHANG; Zhen-tao; ZHENG; Wen-jun; WANG; Lei; YANG; Lin-yue; HUA; Xiao-hui; ZHENG; Yu; YANG; Yong-gang; WU; Yan

    2013-01-01

    Taohuajiang power station is the first internal mainland nuclear power station,and it adopts AP1000nuclear technology belongs to the Westinghouse Electric Corporation.To ensure the safety of the environment around the station and satisfy the radio liquid waste discharge standards,our team has researched the liquid waste treatment technology for the internal mainland nuclear power plant.According

  20. Current Status of Helium-3 Alternative Technologies for Nuclear Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Henzlova, Daniela [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kouzes, R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); McElroy, R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Peerani, P. [European Commission, Ispra (Italy). Joint Research Centre; Aspinall, M. [Hybrid Instruments Ltd., Birmingham (United Kingdom); Baird, K. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Bakel, A. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Borella, M. [SCK.CEN, Mol (Belgium); Bourne, M. [Univ. of Michigan, Ann Arbor, MI (United States); Bourva, L. [Canberra Ltd., Oxford (United Kingdom); Cave, F. [Hybrid Instruments Ltd., Birmingham (United Kingdom); Chandra, R. [Arktis Radiation Detectors Ltd., Zurich (Sweden); Chernikova, D. [Chalmers Univ. of Technology (Sweden); Croft, S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dermody, G. [Symetrica Inc., Maynard, MA (United States); Dougan, A. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Ely, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fanchini, E. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Finocchiaro, P. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Gavron, Victor [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kureta, M. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Ianakiev, Kiril Dimitrov [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ishiyama, K. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Lee, T. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Martin, Ch. [Symetrica Inc., Maynard, MA (United States); McKinny, K. [GE Reuter-Stokes, Twinsburg, OH (United States); Menlove, Howard Olsen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Orton, Ch. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Pappalardo, A. [Istituto Nazionale di Fisica Nucleare (INFN), Milano (Italy); Pedersen, B. [European Commission, Ispra (Italy). Joint Research Centre; Peranteau, D. [National Nuclear Security Administration (NNSA), Washington, DC (United States); Plenteda, R. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Pozzi, S. [Univ. of Michigan, Ann Arbor, MI (United States); Schear, M. [Symetrica Inc., Maynard, MA (United States); Seya, M. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Siciliano, E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Stave, S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sun, L. [Proportional Technologies Inc., Houston, TX (United States); Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tagziria, H. [European Commission, Ispra (Italy). Joint Research Centre; Vaccaro, S. [DG Energy (Luxembourg); Takamine, J. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Weber, A. -L. [Inst. for Radiological Protection and Nuclear Safety (IRSN), Fontenay-aux-Roses (France); Yamaguchi, T. [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Zhu, H. [National Nuclear Security Administration (NNSA), Washington, DC (United States)

    2015-12-01

    International safeguards inspectorates (e.g., International Atomic Energy Agency {IAEA}, or Euratom) rely heavily on neutron assay techniques, and in particular, on coincidence counters for the verification of declared nuclear materials under safeguards and for monitoring purposes. While 3He was readily available, the reliability, safety, ease of use, gamma-ray insensitivity, and high intrinsic thermal neutron detection efficiency of 3He-based detectors obviated the need for alternative detector technologies. However, the recent decline of the 3He gas supply has triggered international efforts to develop and field neutron detectors that make use of alternative materials. In response to this global effort, the U.S. Department of Energy’s (DOE) National Nuclear Security Administration (NNSA) and Euratom launched a joint effort aimed at bringing together international experts, technology users and developers in the field of nuclear safeguards to discuss and evaluate the proposed 3He alternative materials and technologies. The effort involved a series of two workshops focused on detailed overviews and viability assessments of various 3He alternative technologies for use in nuclear safeguards applications. The key objective was to provide a platform for collaborative discussions and technical presentations organized in a compact, workshop-like format to stimulate interactions among the participants. The meetings culminated in a benchmark exercise providing a unique opportunity for the first inter-comparison of several available alternative technologies. This report provides an overview of the alternative technology efforts presented during the two workshops along with a summary of the benchmarking activities and results. The workshop recommendations and key consensus observations are discussed in the report, and used to outline a proposed path forward and future needs foreseeable in the area of 3

  1. Legal and Regulatroy Obstacles to Nuclear Fission Technology in Space

    Science.gov (United States)

    Force, Melissa K.

    2013-09-01

    In forecasting the prospective use of small nuclear reactors for spacecraft and space-based power stations, the U.S. Air Force describes space as "the ultimate high ground," providing access to every part of the globe. But is it? A report titled "Energy Horizons: United States Air Force Energy Science &Technology Vision 2011-2026," focuses on core Air Force missions in space energy generation, operations and propulsion and recognizes that investments into small modular nuclear fission reactors can be leveraged for space-based systems. However, the report mentions, as an aside, that "potential catastrophic outcomes" are an element to be weighed and provides no insight into the monumental political and legal will required to overcome the mere stigma of nuclear energy, even when referring only to the most benign nuclear power generation systems - RTGs. On the heels of that report, a joint Department of Energy and NASA team published positive results from the demonstration of a uranium- powered fission reactor. The experiment was perhaps most notable for exemplifying just how effective the powerful anti-nuclear lobby has been in the United States: It was the first such demonstration of its kind in nearly fifty years. Space visionaries must anticipate a difficult war, consisting of multiple battles that must be waged in order to obtain a license to fly any but the feeblest of nuclear power sources in space. This paper aims to guide the reader through the obstacles to be overcome before nuclear fission technology can be put to use in space.

  2. Space nuclear power, propulsion, and related technologies.

    Energy Technology Data Exchange (ETDEWEB)

    Berman, Marshall

    1992-01-01

    Sandia National Laboratories (Sandia) is one of the nation's largest research and development (R&D) facilities, with headquarters at Albuquerque, New Mexico; a laboratory at Livermore, California; and a test range near Tonopah, Nevada. Smaller testing facilities are also operated at other locations. Established in 1945, Sandia was operated by the University of California until 1949, when, at the request of President Truman, Sandia Corporation was formed as a subsidiary of Bell Lab's Western Electric Company to operate Sandia as a service to the U.S. Government without profit or fee. Sandia is currently operated for the U.S. Department of Energy (DOE) by AT&T Technologies, Inc., a wholly-owned subsidiary of AT&T. Sandia's responsibility is national security programs in defense and energy with primary emphasis on nuclear weapon research and development (R&D). However, Sandia also supports a wide variety of projects ranging from basic materials research to the design of specialized parachutes. Assets, owned by DOE and valued at more than $1.2 billion, include about 600 major buildings containing about 372,000 square meters (m2) (4 million square feet [ft2]) of floor space, located on land totalling approximately 1460 square kilometers (km2) (562 square miles [mi]). Sandia employs about 8500 people, the majority in Albuquerque, with about 1000 in Livermore. Approximately 60% of Sandia's employees are in technical and scientific positions, and the remainder are in crafts, skilled labor, and administrative positions. As a multiprogram national laboratory, Sandia has much to offer both industrial and government customers in pursuing space nuclear technologies. The purpose of this brochure is to provide the reader with a brief summary of Sandia's technical capabilities, test facilities, and example programs that relate to military and civilian objectives in space. Sandia is interested in forming partnerships with industry and government

  3. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

    2001-03-15

    This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

  4. Nuclear data for fusion technology – the European approach

    Directory of Open Access Journals (Sweden)

    Fischer Ulrich

    2017-01-01

    Full Text Available The European approach for the development of nuclear data for fusion technology applications is presented. Related R&D activities are conducted by the Consortium on Nuclear Data Development and Analysis for Fusion to satisfy the nuclear data needs of the major projects including ITER, the Early Neutron Source (ENS and DEMO. Recent achievements are presented in the area of nuclear data evaluations, benchmarking and validation, nuclear model improvements, and uncertainty assessments.

  5. 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.

  6. Study on international publicity and export strategy establishment of nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ji Bok; Choi, C.O.; Park, K. B.; Chang, M. H.; Kim, K. K.; Yang, M. S.; Jung, I. H.; Kim, K. P.; Wu, J. S.; Jang, C. I.; Han, B. O.; Sim, J. H.; Chung, M.; Chung, J.K

    1999-05-01

    The objective of this study is to devise a proper measure for international publicity and technology export strategy. Analysed and summaries in detail are other countries nuclear policy trend and the current technology development status of Korea Standard Nuclear Plant that we developed on our own technology, design and construction technology for research reactor, System-integrated Modular Advanced Reactor of which design is in progress, Direct use of Spent PWR Fuel in CANDU Reactors, and Radioisotopes. Based on that, the measures are proposed for the export industrialization of nuclear technology and establishment of the export basis. Also the international nuclear cooperation and publicity strategy are suggested to support the technology export basis. By surveying the world nuclear status, the direction for the international cooperation and publicity is settled and the specific publicity strategy is proposed for the cooperation with IAEA and multi-countries and the establishment of the nuclear technology export basis. As part of this project, the panel on major technologies such as Korea Standard Nuclear Plant, HANARO, and System-integrated Modular Advanced Reactor was displayed successfully at the IAEA meeting, which contribute much to the publicity of our nuclear technology to the international nuclear society. (author)

  7. 2nd Symposium on applied nuclear physics and innovative technologies

    CERN Document Server

    2014-01-01

    Symposium on Applied Nuclear Physics and Innovative Technologies will be held for the second time at Collegium Maius, the oldest building of the Jagiellonian University in Cracow, the same building where Nicolaus Copernicus has studied astronomy. Symposium is organized in the framework of the MPD programme carried out by the Foundation for Polish science based on the European Structural Funds. The aim of this conference is to gather together young scientists and experts in the field of applied and fundamental nuclear as well as particle physics. Aiming at interplay of fundamental and applied science the conference will be devoted to the following topics: * Medical imaging and radiotherapy * New materials and technologies in radiation detection * Fission, fusion and spallation processes * High-performance signal processing and data analysis * Tests of foundations of physics and search for a new kind of sub-atomic matter

  8. Comparative Research on Chinese and Foreign Nuclear Power Technology Based on Patents%基于专利的核电技术中外对比研究

    Institute of Scientific and Technical Information of China (English)

    娄岩; 杨培培; 黄鲁成; 苗红

    2016-01-01

    Purpose/Significance] Nuclear energy as an economic and efficient energy for easing the worldˊs energy crisis has many ad-vantages, so it gets more and more attention. Nuclear power generation is a very important application of nuclear energy, the development of nuclear power technology has also caused widespread concern around the world. [ Method/Process] In the study of nuclear power tech-nology it can be divided into patent research and non-patent research, and the patent research on nuclear power technology is few in Chi-na. So this article discusses nuclear power technologyˊs current situation from the perspective of patent and analyses nuclear power technol-ogy from the macro and micro levels, using the patents to find issues in the field of research and development. [ Result/Conclusion] Re-search shows that although the growth rate of patents is increasing in recent years, research of nuclear energy started late, and the number of patents is small, also the exchanges link with research institutions in other countries are less. Finally, concerning the existing problems of the nuclear industry, some suggestions that aim at promoting the development of Chinaˊs nuclear power industry, are given.%[目的/意义]核能作为缓和世界能源危机的一种经济有效的能源有很多优点,因此受到越来越多的关注。核能发电是核能一项很重要的用途,核电技术的发展也受到了世界各国的关注。[方法/过程]对核电技术的研究可以分为专利研究与非专利研究,但国内关于核电技术的专利研究相对较少。从专利的角度来研究核电技术的现状,从宏观和微观两个层面对核电技术进行分析,发现我国该技术领域在研发中存在的问题。[结论/结果]研究表明,尽管我国近年专利增长率不断提高,但是对核电的研究起步较晚,申请专利数量较少,与其他国家的研究机构交流联系较少等问题。最后针对我国核电

  9. Nuclear Technology Series. Course 19: Radiation Shielding.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  10. Nuclear Technology Series. Course 8: Reactor Safety.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutians in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  11. Nuclear Technology Series. Course l: Radiation Physics.

    Science.gov (United States)

    Technical Education Research Center, Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  12. Nuclear Technology Series. Course 28: Welding Inspection.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  13. Nuclear Technology Series. Course 27: Metrology.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  14. Nuclear Technology Series. Course 12: Reactor Physics.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  15. The current state of FPGA technology in the nuclear domain

    Energy Technology Data Exchange (ETDEWEB)

    Ranta, J.

    2012-07-01

    Field programmable gate arrays are a form of programmable electronic device used in various applications including automation systems. In recent years, there has been a growing interest in the use of FPGA-based systems also for safety automation of nuclear power plants. The interest is driven by the need for reliable new alternatives to replace, on one hand, the aging technology currently in use and, on the other hand, microprocessor and software-based systems, which are seen as overly complex from the safety evaluation point of view. This report presents an overview of FPGA technology, including hardware aspects, the application development process, risks and advantages of the technology, and introduces some of the current systems. FPGAs contain an interesting combination of features from software-based and fully hardware-based systems. Application development has a great deal in common with software development, but the final product is a hardware component without the operating system and other platform functions on which software would execute. Currently the number of FPGA-based applications used for safety functions of nuclear power plants is rather limited, but it is growing. So far there is little experience or common solid understanding between different parties on how FPGAs should be evaluated and handled in the licensing process. (orig.)

  16. A Project in Support of Nuclear Technology Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Young Cheol; Kim, Kyoung Pyo; Yi, Ji Ho (and others)

    2007-12-15

    The results and contents of the project are as follows; - 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. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - 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 information and computer software developed in the advanced countries.

  17. Tecnatom virtual reality experience in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Baeza, Guillermo; Cabrera, Esteban; Salve, Ricardo

    2004-07-01

    TECNATOM is a Spanish company focused in providing support to the energy sector. Training, operation engineering and inspection services in nuclear environments are the main business of the company. Emerging applications based on Virtual Reality (VR) are being demanded by the market as a response to the current cost reduction trend and to the new challenges arising in decommissioning of NPP's, human factors analysis and training of personnel in high risk tasks. On this respect, Tecnatom has launched several initiatives to consolidate its internal capabilities in VR and to acquire consulting skills for the Tecnatom market. The results of theses actions will be shown in this paper. (Author)

  18. 8. Innovative Technologies: Two-Phase Heat Transfer in Water-Based Nanofluids for Nuclear Applications Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Buongiorno, Jacopo; Hu, Lin-wen

    2009-07-31

    Nanofluids are colloidal dispersions of nanoparticles in water. Many studies have reported very significant enhancement (up to 200%) of the Critical Heat Flux (CHF) in pool boiling of nanofluids (You et al. 2003, Vassallo et al. 2004, Bang and Chang 2005, Kim et al. 2006, Kim et al. 2007). These observations have generated considerable interest in nanofluids as potential coolants for more compact and efficient thermal management systems. Potential Light Water Reactor applications include the primary coolant, safety systems and severe accident management strategies, as reported in other papers (Buongiorno et al. 2008 and 2009). However, the situation of interest in reactor applications is often flow boiling, for which no nanofluid data have been reported so far. In this project we investigated the potential of nanofluids to enhance CHF in flow boiling. Subcooled flow boiling heat transfer and CHF experiments were performed with low concentrations of alumina, zinc oxide, and diamond nanoparticles in water (≤ 0.1 % by volume) at atmospheric pressure. It was found that for comparable test conditions the values of the nanofluid and water heat transfer coefficient (HTC) are similar (within ±20%). The HTC increased with mass flux and heat flux for water and nanofluids alike, as expected in flow boiling. The CHF tests were conducted at 0.1 MPa and at three different mass fluxes (1500, 2000, 2500 kg/m2s) under subcooled conditions. The maximum CHF enhancement was 53%, 53% and 38% for alumina, zinc oxide and diamond, respectively, always obtained at the highest mass flux. A post-mortem analysis of the boiling surface reveals that its morphology is altered by deposition of the particles during nanofluids boiling. A confocal-microscopy-based examination of the test section revealed that nanoparticles deposition not only changes the number of micro-cavities on the surface, but also the surface wettability. A simple model was used to estimate the ensuing nucleation site

  19. Nuclear Thermal Rocket - An Established Space Propulsion Technology

    Science.gov (United States)

    Klein, Milton

    2004-02-01

    From the late 1950s to the early 1970s a major program successfully developed the capability to conduct space exploration using the advanced technology of nuclear rocket propulsion. The program had two primary elements: pioneering and advanced technology work-Rover-at Los Alamos National Laboratory and its contractors provided the basic reactor design, fuel materials development, and reactor testing capability; and engine development-NERVA-by the industrial team of Aerojet and Westinghouse building on and extending the Los Alamos efforts to flight system development. This presentation describes the NERVA program, the engine system testing that demonstrated the space-practical operation capabilities of nuclear thermal rockets, and the mission studies that point the way to most effectively use the NTR capabilities. Together, the two programs established a technology base that includes proven NTR capabilities of (1) over twice the specific impulse of chemical propulsion systems, (2) thrust capabilities ranging from 44kN to 1112kN, and (3) practical thrust-to-weight ratios for future NASA space exploration missions, both manned payloads to Mars and unmanned payloads to the outer planets. The overall nuclear rocket program had a unique management structure that integrated the efforts of the two government agencies involved-NASA and the then-existing Atomic Energy Commission. The objective of this paper is to summarize and convey the technical and management lessons learned in this program as the nation considers the design of its future space exploration activities.

  20. Annual Report of Institute of Nuclear Chemistry and Technology 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-10-01

    The report is the collection of short communications being the review of the scientific activity of Institute of Nuclear Chemistry and Technology - Warsaw in 1997. The papers are gathered in several branches as follows: radiation chemistry and physics; radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general; radiobiology; nuclear technologies and methods. The annual report of INCT-1997 contains also the general information about INCT as well as the full list of scientific papers being published by the staff in 1997

  1. Mineral-PET Kimberlite sorting by nuclear-medical technology

    CERN Document Server

    Ballestrero, S; Cafferty, L; Caveney, R; Connell, SH; Cook, M; Dalton, M; Gopal, H; Ives, N; Lee, C A; Mampe, W; Phoku, M; Roodt, A; Sibande, W; Sellschop, J P F; Topkin, J; Unwucholaa, D A

    2010-01-01

    A revolutionary new technology for diamond bearing rock sorting which has its roots in medical-nuclear physics has been taken through a substantial part of the R&D phase. This has led to the construction of the technology demonstrator. Experiments using the technology demonstrator and experiments at a hospital have established the scientific and technological viability of the project.

  2. A GRADUATE CERTIFICATE PROGRAM IN NUCLEAR SAFEGUARDS TECHNOLOGY.

    Energy Technology Data Exchange (ETDEWEB)

    FISHBONE, L.; SISKIND, B.; PEPPER, S.

    2005-07-10

    While there are a number of university graduate-education programs that address non-proliferation and safeguards policy issues; there are none in the United States that train students in the specific technical aspects of nuclear safeguards. Formal education of this kind is necessary to sustain the flow of technically trained individuals to diverse programs in safeguards, nonproliferation, and national security. In response to this need, the University of Missouri-Columbia, with assistance from Brookhaven National Laboratory, is initiating a Graduate Certificate Program in Nuclear Safeguards Technology: Students seeking advanced degrees in a variety of technical areas will complete a required sequence of courses in order to receive the certification. Required course work covers topics such as Nuclear Material Control and Accountability (MC&A), Physical Protection (PP); nuclear measurements, and a variety of other relevant subjects. Laboratory-based instruction will be included which will utilize the University of Missouri Research Reactor(MURR). MURR is the largest university-based research reactor and has extensive laboratory resources including a Canberra Aquila MPC&A Operational Monitoring demonstration system.

  3. DUPIC nuclear fuel manufacturing and process technology development at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Yim, Sung Paal; Lee, Jung Won; Kim, Jong Ho; Kim, Soo Sung; Kim, Woong Ki; Yang, Myung Seung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2000-07-01

    DUPIC fuel cycle development project in KAERI of Korea was initiated in 1991 and has advanced in relevant technologies for last 10 years. The project includes five different topics such as nuclear fuel manufacturing, compatibility evaluation, performance evaluation, manufacturing facility management, and safeguards. The contents and results of DUPIC R and D up to now are as follow: - the basic foundation was established for the critically required pelletizing technology and powder treatment technology for DUPIC. - development of DUPIC process line and deployment of 20 each process equipment and examination instruments in DFDF. - powder and pellet characterization study was done at PIEF based on the simfuel study results, and 30 DUPIC pellets were successfully produced. - the manufactured pellets were used for sample fuel rods irradiated in July,2000 in HANARO research reactor in KAERI and has been under post irradiation examination. (Hong, J. S.)

  4. Nuclear Science Technology and Nano Science Technology%核技术与纳米技术

    Institute of Scientific and Technical Information of China (English)

    柴之芳

    2007-01-01

    Nuclear science and technology can play a unique role in nano-science and technology, due to its nuclear characteristics and properties. In many cases nuclear science and technology can acquire intriguing results to help solve some basic scientific problems in nano science and technology, which are often difficult or even impossible for non-nuclear routes. In this review some latest achievements made in this aspect will be selectively introduced with the emphasis on the work done in our laboratory. The work includes (1) nuclear reactions for synthesis of novel nanomaterials; (2) nuclear spectroscopy for characterization of nanomaterials; and (3) nuclear analytical techniques for study of nanosafety and nanotoxicology. Some practical examples to demonstrate the roles of nuclear science and technology will be briefly described.

  5. Atomic Information Technology Safety and Economy of Nuclear Power Plants

    CERN Document Server

    Woo, Taeho

    2012-01-01

    Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

  6. Nuclear propulsion technology development - A joint NASA/Department of Energy project

    Science.gov (United States)

    Clark, John S.

    1992-01-01

    NASA-Lewis has undertaken the conceptual development of spacecraft nuclear propulsion systems with DOE support, in order to establish the bases for Space Exploration Initiative lunar and Mars missions. This conceptual evolution project encompasses nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems. A technology base exists for NTP in the NERVA program files; more fundamental development efforts are entailed in the case of NEP, but this option is noted to offer greater advantages in the long term.

  7. Nuclear propulsion technology development - A joint NASA/Department of Energy project

    Science.gov (United States)

    Clark, John S.

    1992-01-01

    NASA-Lewis has undertaken the conceptual development of spacecraft nuclear propulsion systems with DOE support, in order to establish the bases for Space Exploration Initiative lunar and Mars missions. This conceptual evolution project encompasses nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems. A technology base exists for NTP in the NERVA program files; more fundamental development efforts are entailed in the case of NEP, but this option is noted to offer greater advantages in the long term.

  8. A Unique Master's Program in Combined Nuclear Technology and Nuclear Chemistry at Chalmers University of Technology, Sweden

    Science.gov (United States)

    Skarnemark, Gunnar; Allard, Stefan; Ekberg, Christian; Nordlund, Anders

    2009-08-01

    The need for engineers and scientists who can ensure safe and secure use of nuclear energy is large in Sweden and internationally. Chalmers University of Technology is therefore launching a new 2-year master's program in Nuclear Engineering, with start from the autumn of 2009. The program is open to Swedish and foreign students. The program starts with compulsory courses dealing with the basics of nuclear chemistry and physics, radiation protection, nuclear power and reactors, nuclear fuel supply, nuclear waste management and nuclear safety and security. There are also compulsory courses in nuclear industry applications and sustainable energy futures. The subsequent elective courses can be chosen freely but there is also a possibility to choose informal tracks that concentrate on nuclear chemistry or reactor technology and physics. The nuclear chemistry track comprises courses in e.g. chemistry of lanthanides, actinides and transactinides, solvent extraction, radioecology and radioanalytical chemistry and radiopharmaceuticals. The program is finished with a one semester thesis project. This is probably a unique master program in the sense of its combination of deep courses in both nuclear technology and nuclear chemistry.

  9. Configuration and technology implications of potential nuclear hydrogen system applications.

    Energy Technology Data Exchange (ETDEWEB)

    Conzelmann, G.; Petri, M.; Forsberg, C.; Yildiz, B.; ORNL

    2005-11-05

    Nuclear technologies have important distinctions and potential advantages for large-scale generation of hydrogen for U.S. energy services. Nuclear hydrogen requires no imported fossil fuels, results in lower greenhouse-gas emissions and other pollutants, lends itself to large-scale production, and is sustainable. The technical uncertainties in nuclear hydrogen processes and the reactor technologies needed to enable these processes, as well waste, proliferation, and economic issues must be successfully addressed before nuclear energy can be a major contributor to the nation's energy future. In order to address technical issues in the time frame needed to provide optimized hydrogen production choices, the Nuclear Hydrogen Initiative (NHI) must examine a wide range of new technologies, make the best use of research funding, and make early decisions on which technology options to pursue. For these reasons, it is important that system integration studies be performed to help guide the decisions made in the NHI. In framing the scope of system integration analyses, there is a hierarchy of questions that should be addressed: What hydrogen markets will exist and what are their characteristics? Which markets are most consistent with nuclear hydrogen? What nuclear power and production process configurations are optimal? What requirements are placed on the nuclear hydrogen system? The intent of the NHI system studies is to gain a better understanding of nuclear power's potential role in a hydrogen economy and what hydrogen production technologies show the most promise. This work couples with system studies sponsored by DOE-EE and other agencies that provide a basis for evaluating and selecting future hydrogen production technologies. This assessment includes identifying commercial hydrogen applications and their requirements, comparing the characteristics of nuclear hydrogen systems to those market requirements, evaluating nuclear hydrogen configuration options

  10. The Nuclear Education and Staffing Challenge: Rebuilding Critical Skills in Nuclear Science and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Wogman, Ned A.; Bond, Leonard J.; Waltar, Alan E.; Leber, R E.

    2005-01-01

    The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory were 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of Nuclear Legacies, Global Security, Nonproliferation, Homeland Security and National Defense, Radiobiology and Nuclear Energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. This paper presents the current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs.

  11. The Nuclear Education and Staffing Challenge: Rebuilding Critical Skills in Nuclear Science and Technology.

    Energy Technology Data Exchange (ETDEWEB)

    Wogman, Ned A.; Bond, Leonard J.; Waltar, Alan E.; Leber, R. E.

    2005-01-01

    The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory where 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of Nuclear Legacies, Global Security, Nonproliferation, Homeland Security and National Defense, Radiobiology and Nuclear Energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. This paper presents the current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs.

  12. 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.

  13. 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).

  14. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

    2006-10-02

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector

  15. Development of Fabrication Technology for Ceramic Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. S.; Lee, Y. W.; Na, S. H.; Kim, Y. G.; Jung, C. Y.; Kim, S. H.; Lee, S. C.; Son, D. S

    2006-04-15

    Purpose and Necessity Research purposes for the 3rd stage were to reaffirm the MOX fabrication processes and to establish the process database, based on the fabrication technology developed during the previous stage. This project was also proceeded to improve the fuel performance and to accomplish the inherent MOX technology for PWR. The fabrication processes should be proceeded in the glove boxes because the raw powders of MOX fuel is very toxic. Therefore, some special technology were needed to develop besides the fuel fabrication technology. Both core technology and steadiness of fabrication process are important to obtain homogeneity and thermo-physical properties of MOX fuel pellet. By developing these technology in fashion unique to ourselves, we can take the initiative in the nuclear fuel for next generation. The uranium price has been increasing along with the oil price recently. We have to secure the MOX fabrication technology which serves the effective use of uranium resource. Improvement of pellet characteristics along with the MOX irradiation analysis: Collection and monitoring of the MOX irradiation data, Establishment of the improvement methods of pellet characteristics Establishment of the MOX pellet fabrication process by the unique technology, Establishment of database with the MOX fabrication parameters and characteristics, Analysis of co-relation and re-appearance of the pellet characteristics affected by each process parameter, Construction of feedback system between database and process, Application of the unique fabrication technology to the industrial spot. Applicability of the unique fabrication processes to the glove box technology, Installment of process equipment in the glove box and development of operation skill, Methods for modifying, handling, maintaining and fixing of glove box and subsidiary, Construction of transport channel for the connection between glove boxes - MOX fabrication by the unique technology in the glove box. Research

  16. Systematization of nuclear fuel facility decommissioning technology

    Energy Technology Data Exchange (ETDEWEB)

    Sugitsue, Noritake [Japan Nuclear Cycle Development Inst., Ningyo Toge Environmental Engineering Center, Kamisaibara, Okayama (Japan)

    2001-09-01

    In the Ningyo-Toge Environmental Engineering Center, the nature of all decommissioning works is clarified and, as an information base for planning the promotion of efficiency of a work, the Decommissioning Engineering System is being developed. The Decommissioning Engineering System consists of a function for performing work support for a decommissioning, a function for gathering information results of the decommissioning technology and a general evaluation function for the decommissioning plan on the basis of facilities information collected by three-dimensional CAD. (author)

  17. Nuclear Medicine Technology: A Suggested Postsecondary Curriculum.

    Science.gov (United States)

    Technical Education Research Center, Cambridge, MA.

    The purpose of this curriculum guide is to assist administrators and instructors in establishing nuclear medicine technician programs that will meet the accreditation standards of the American Medical Association (AMA) Council on Medical Education. The guide has been developed to prepare nuclear medicine technicians (NMT's) in two-year…

  18. A study on the nuclear technology policy

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Maeng Ho; Ham, C. H.; Kim, H. J.; Chung, W. S.; Lee, T. J.; Lee, B. O.; Yun, S. W.; Choi, Y. M.; Eom, T. Y

    1998-01-01

    This study analyzed the major issues as the research activities for the support of establishment and implementation of national policy. The analyses were focused on the recommendations of the responsive direction of national policy in positive and effective manners in accordance with the changes of international nuclear affairs. This study also analyzed the creation of environmental foundation for effective implementation of the national policy and national R and D investment such as securing national consensus and openings of policy information to the public. The major results of the role and position of nuclear policy, trends of nuclear policy and nuclear R and D activities of USA, France, Japan, Asian developing countries etc. and international trends of small- and medium-sized reactor as well as spin-offs of nuclear R and D activities, were analyzed. (author). 66 refs., 27 tabs., 15 figs

  19. Measuring Public Acceptance of Nuclear Technology with Big data

    Energy Technology Data Exchange (ETDEWEB)

    Roh, Seugkook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Surveys can be conducted only on people in specific region and time interval, and it may be misleading to generalize the results to represent the attitude of the public. For example, opinions of a person living in metropolitan area, far from the dangers of nuclear reactors and enjoying cheap electricity produced by the reactors, and a person living in proximity of nuclear power plants, subject to tremendous damage should nuclear meltdown occur, certainly differs for the topic of nuclear generation. To conclude, big data is a useful tool to measure the public acceptance of nuclear technology efficiently (i.e., saves cost, time, and effort of measurement and analysis) and this research was able to provide a case for using big data to analyze public acceptance of nuclear technology. Finally, the analysis identified opinion leaders, which allows target-marketing when policy is executed.

  20. Investigation of gaseous nuclear rocket technology

    Science.gov (United States)

    Kendall, J. S.

    1972-01-01

    The experimental and theoretical investigations conducted during the period from September 1969 through September 1972 are reported which were directed toward obtaining information necessary to determine the feasibility of the full-scale nuclear light bulb engine, and of small-scale nuclear tests involving fissioning uranium plasmas in a unit cell installed in a driver reactor, such as the Nuclear Furnace. Emphasis was placed on development of RF simulations of conditions expected in nuclear tests in the Nuclear Furnace. The work included investigations of the following: (1) the fluid mechanics and containment characteristics of one-component and two-component vortex flows, both unheated and RF-induction heated; (2) heating of particle-seeded streams by thermal radiation from a dc arc to simulate propellant heating; (3) condensation and separation phenomena for metal-vapor/heated-gas mixtures to provide information for conceptual designs of components of fuel exhaust and recycle systems; (4) the characteristics of the radiant energy spectrum emitted from the fuel region, with emphasis on definition of fuel and buffer-gas region seed systems to reduce the ultraviolet radiation emitted from the nuclear fuel; and (5) the effects of nuclear radiation on the optical transmission characteristics of transparent materials.

  1. Education and communication to increase public understanding of nuclear technology peaceful uses

    Energy Technology Data Exchange (ETDEWEB)

    Levy, Denise S.; Passos, Igor S., E-mail: denise@omiccron.com.br [Omiccron Programacao Grafica, Atibaia, SP (Brazil)

    2014-07-01

    Nuclear technology helps to improve the quality of our everyday life. Nevertheless, there is still great misinformation and the issue divides public opinion. Several surveys were conducted over the past years to study public acceptance of Nuclear Technology in Brazil and worldwide. GlobeScan (2005), for the International Atomic Energy Agency (IAEA), and Eurobarometers (2010), published by the Nuclear Energy Agency (NEA) and the Organization for Economic Co-operation and development (OECD), report similar socio-demographic trends: the higher the education level, the more favorable is public opinion towards nuclear power. Taking into account education and communication are crucial to increase public knowledge and understanding of the benefits of Nuclear Technology and that Internet access has increased strongly all over the country, this educational project aims to take advantage of the potential of Information and Communication Technology (ICT) to disseminate the peaceful use of nuclear technology and its benefits, informing children and teenagers, as well as parents and teachers, who are most often unaware of the matter. Whereas Internet access has increased strongly for both public and private schools all over the country, this web-based educational project, entitled Radioatividades (Radioactivities), provides short courses, curiosities and interactive activities covering topics related to Nuclear Technology and its beneficial applications in several areas, such as medicine, agriculture, industry, art and electric power generation. The project uses the combination of multiple technologies and last generation internet resources. Our target is the dissemination of information, promoting the benefits of Nuclear Technology for new generations, contributing to public acceptance of Nuclear Technology, combating misinformation in our society, omission of the media and knowledge fragmentation. Education transforms old prejudices and inspires new thoughts, stimulating

  2. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    Science.gov (United States)

    Chadwick, M. B.; Obložinský, P.; Herman, M.; Greene, N. M.; McKnight, R. D.; Smith, D. L.; Young, P. G.; MacFarlane, R. E.; Hale, G. M.; Frankle, S. C.; Kahler, A. C.; Kawano, T.; Little, R. C.; Madland, D. G.; Moller, P.; Mosteller, R. D.; Page, P. R.; Talou, P.; Trellue, H.; White, M. C.; Wilson, W. B.; Arcilla, R.; Dunford, C. L.; Mughabghab, S. F.; Pritychenko, B.; Rochman, D.; Sonzogni, A. A.; Lubitz, C. R.; Trumbull, T. H.; Weinman, J. P.; Brown, D. A.; Cullen, D. E.; Heinrichs, D. P.; McNabb, D. P.; Derrien, H.; Dunn, M. E.; Larson, N. M.; Leal, L. C.; Carlson, A. D.; Block, R. C.; Briggs, J. B.; Cheng, E. T.; Huria, H. C.; Zerkle, M. L.; Kozier, K. S.; Courcelle, A.; Pronyaev, V.; van der Marck, S. C.

    2006-12-01

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes, based on experimental data and theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, 6Li, 10B, Au and for 235,238U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced evaluations up to 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; (10) New methods for uncertainties and covariances, together with covariance evaluations for some sample cases; and (11) New actinide fission energy deposition. The paper provides an overview of this library, consisting of 14 sublibraries in the same ENDF-6 format as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched uranium thermal assemblies is removed; (b) The 238U and 208Pb reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good

  3. Defining the "proven technology" technical criterion in the reactor technology assessment for Malaysia's nuclear power program

    Science.gov (United States)

    Anuar, Nuraslinda; Kahar, Wan Shakirah Wan Abdul; Manan, Jamal Abdul Nasir Abd

    2015-04-01

    Developing countries that are considering the deployment of nuclear power plants (NPPs) in the near future need to perform reactor technology assessment (RTA) in order to select the most suitable reactor design. The International Atomic Energy Agency (IAEA) reported in the Common User Considerations (CUC) document that "proven technology" is one of the most important technical criteria for newcomer countries in performing the RTA. The qualitative description of five desired features for "proven technology" is relatively broad and only provides a general guideline to its characterization. This paper proposes a methodology to define the "proven technology" term according to a specific country's requirements using a three-stage evaluation process. The first evaluation stage screens the available technologies in the market against a predefined minimum Technology Readiness Level (TRL) derived as a condition based on national needs and policy objectives. The result is a list of technology options, which are then assessed in the second evaluation stage against quantitative definitions of CUC desired features for proven technology. The potential technology candidates produced from this evaluation is further narrowed down to obtain a list of proven technology candidates by assessing them against selected risk criteria and the established maximum allowable total score using a scoring matrix. The outcome of this methodology is the proven technology candidates selected using an accurate definition of "proven technology" that fulfills the policy objectives, national needs and risk, and country-specific CUC desired features of the country that performs this assessment. A simplified assessment for Malaysia is carried out to demonstrate and suggest the use of the proposed methodology. In this exercise, ABWR, AP1000, APR1400 and EPR designs assumed the top-ranks of proven technology candidates according to Malaysia's definition of "proven technology".

  4. Nuclear Symbiosis - A Means to Achieve Sustainable Nuclear Growth while Limiting the Spread of Sensititive Nuclear Technology

    Energy Technology Data Exchange (ETDEWEB)

    David Shropshire

    2009-09-01

    Global growth of nuclear energy in the 21st century is creating new challenges to limit the spread of nuclear technology without hindering adoption in countries now considering nuclear power. Independent nuclear states desire autonomy over energy choices and seek energy independence. However, this independence comes with high costs for development of new indigenous fuel cycle capabilities. Nuclear supplier states and expert groups have proposed fuel supply assurance mechanisms such as fuel take-back services, international enrichment services and fuel banks in exchange for recipient state concessions on the development of sensitive technologies. Nuclear states are slow to accept any concessions to their rights under the Non-Proliferation Treaty. To date, decisions not to develop indigenous fuel cycle capabilities have been driven primarily by economics. However, additional incentives may be required to offset a nuclear state’s perceived loss of energy independence. This paper proposes alternative economic development incentives that could help countries decide to forgo development of sensitive nuclear technologies. The incentives are created through a nuclear-centered industrial complex with “symbiotic” links to indigenous economic opportunities. This paper also describes a practical tool called the “Nuclear Materials Exchange” for identifying these opportunities.

  5. Nuclear technologies in a sustainable energy system

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, G.S.; Mc Donald, A.

    1983-01-01

    This book presents papers on nuclear and thermonuclear reactors. Topics considered include energy strategies and nuclear power, self-sustaining systems of reactors, sustainable minireactors, small reactors, fast breeders and fusion-fission hybrids, the tokamak as a candidate for a D-T fusion reactor, the fusion breeder, hydrogen production through fusion, hydrogen production by means of electrolysis, the dense plasma focus, and radioactive waste management.

  6. A study on future nuclear reactor technology and development strategy

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. Y.; Kim, S. H.; Sohn, D. S.; Suk, S. D.; Zee, S. K.; Yang, M. H.; Kim, H. J.; Park, W. S

    2000-12-01

    Development of nuclear reactor and fuel cycle technology for future is essential to meet the current issues such as enhancement of nuclear power reactor safety, economically competitive with gas turbine power generation, less production of radioactive waste, proliferation resistant fuel cycle, and public acceptance in consideration of lack of energy resources in the nuclear countries worldwide as well as in Korea. This report deals with as follows, 1) Review the world energy demand and supply perspective and analyse nature of energy and sustainable development to set-up nuclear policy in Korea 2) Recaptitulate the current long term nuclear R and D activities 3) Review nuclear R and D activities and programs of USA, Japan, France, Russia, international organizations such as IAEA, OECD/NEA 4) Recommend development directions of nuclear reactors and fuels.

  7. DUPIC nuclear fuel manufacturing and process technology development

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Myung Seung; Park, J. J.; Lee, J. W. [and others

    2000-05-01

    In this study, DUPIC fuel fabrication technology and the active fuel laboratory were developed for the study of spent nuclear fuel. A new nuclear fuel using highly radioactive nuclear materials can be studied at the active fuel laboratory. Detailed DUPIC fuel fabrication process flow was developed considering the manufacturing flow, quality control process and material accountability. The equipment layout of about twenty DUPIC equipment at IMEF M6 hot cell was established for the minimization of the contamination during DUPIC processes. The characteristics of the SIMFUEL powder and pellets was studied in terms of milling conditions. The characteristics of DUPIC powder and pellet was studied by using 1 kg of spent PWR fuel at PIEF nr.9405 hot cell. The results were used as reference process conditions for following DUPIC fuel fabrication at IMEF M6. Based on the reference fabrication process conditions, the main DUPIC pellet fabrication campaign has been started at IMEF M6 using 2 kg of spent PWR fuel since 2000 January. As of March 2000, about thirty DUPIC pellets were successfully fabricated.

  8. Template identification technology of nuclear warheads and components

    Institute of Scientific and Technical Information of China (English)

    Liu Su-Ping; Gong Jian; Hao Fan-Hua; Hu Guang-Chun

    2008-01-01

    Template identification technology (TIT) is designed for the scenarios where a batch of disarmed nuclear weapons or components would be dismantled to observe a nuclear disarmament treaty.The core function played by the TIT is to make a judgment on whether the verified item belongs to a certain kind of nuclear weapons or component (NW/NC) or to which kind the verified item belongs.This paper analyses the functions played by the TIT in the process of NW/NC dismantlement,and proposes that two phases would be followed when applying the TIT:firstly to establish NW/NC templates with a sample of size n drawn from a certain kind of disarmament NW;secondly to authenticate NW/NC by means of the TIT.This paper also expatiates some terms related to the concept of the TIT and investigates on the development status of NW/NC TIT based on radiation signatures.The study concludes that the design of template structure is crucial to the establishment of an effective TIT and that starting from different research angles and aiming at the same goal of classification different template structures and corresponding template identification methods can be built up to meet specific identification requirements.

  9. 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.

  10. Institute of Nuclear Chemistry and Technology annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology (INCT), Warsaw, in 1995. The papers are gathered in several branches as follows: radiation chemistry and physics (15); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (23); radiobiology (7); nuclear technologies and methods (21); nucleonic control systems (5). The Annual Report of INCT - 1995 contains also a general information about the staff and organization of the Institute, the full list of scientific publications and patents, conferences organized by INCT, thesis and list of projects granted by Polish and international organizations.

  11. Survey of advanced nuclear technologies for potential applications of sonoprocessing.

    Science.gov (United States)

    Rubio, Floren; Blandford, Edward D; Bond, Leonard J

    2016-09-01

    Ultrasonics has been used in many industrial applications for both sensing at low power and processing at higher power. Generally, the high power applications fall within the categories of liquid stream degassing, impurity separation, and sonochemical enhancement of chemical processes. Examples of such industrial applications include metal production, food processing, chemical production, and pharmaceutical production. There are many nuclear process streams that have similar physical and chemical processes to those applications listed above. These nuclear processes could potentially benefit from the use of high-power ultrasonics. There are also potential benefits to applying these techniques in advanced nuclear fuel cycle processes, and these benefits have not been fully investigated. Currently the dominant use of ultrasonic technology in the nuclear industry has been using low power ultrasonics for non-destructive testing/evaluation (NDT/NDE), where it is primarily used for inspections and for characterizing material degradation. Because there has been very little consideration given to how sonoprocessing can potentially improve efficiency and add value to important process streams throughout the nuclear fuel cycle, there are numerous opportunities for improvement in current and future nuclear technologies. In this paper, the relevant fundamental theory underlying sonoprocessing is highlighted, and some potential applications to advanced nuclear technologies throughout the nuclear fuel cycle are discussed.

  12. ABB Combustion Engineering`s nuclear experience and technologies

    Energy Technology Data Exchange (ETDEWEB)

    Matzie, R.A.

    1994-12-31

    ABB Combustion Engineering`s nuclear experience and technologies are outlined. The following topics are discussed: evolutionary approach using proven technology, substantial improvement to plant safety, utility perspective up front in developing design, integrated design, competitive plant cost, operability and maintainability, standardization, and completion of US NRC technical review.

  13. Cost estimate guidelines for advanced nuclear power technologies

    Energy Technology Data Exchange (ETDEWEB)

    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.

  14. Cost estimate guidelines for advanced nuclear power technologies

    Energy Technology Data Exchange (ETDEWEB)

    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.

  15. Cost estimate guidelines for advanced nuclear power technologies

    Energy Technology Data Exchange (ETDEWEB)

    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.

  16. A decade of 3C technologies: insights into nuclear organization

    NARCIS (Netherlands)

    de Wit, E.; de Laat, W.

    2012-01-01

    Over the past 10 years, the development of chromosome conformation capture (3C) technology and the subsequent genomic variants thereof have enabled the analysis of nuclear organization at an unprecedented resolution and throughput. The technology relies on the original and, in hindsight, remarkably

  17. The sustainable nuclear energy technology platform. A vision report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    Nuclear fission energy can deliver safe, sustainable, competitive and practically carbon-free energy to Europe's citizens and industries. Within the framework of the Strategic Energy Technology Plan (SET Plan), the European Commission's stakeholders in this field have formulated a collective vision of the contributions this energy could make towards Europe's transition to a low-carbon energy mix by 2050, with the aim of integrating and expanding R and D capabilities in order to further this objective. The groundwork has been prepared by the stakeholders listed in Annex II, within the framework of two EURATOM FP6 (Sixth Framework Programme) Coordination Actions, namely SNF-TP (Sustainable Nuclear Fission Technology Platform) and PATEROS (Partitioning and Transmutation European Road-map for Sustainable Nuclear Energy), with contributions from Europe's technical safety organisations. This vision report prepares the launch of the European Technology Platform on Sustainable Nuclear Energy (SNE-TP). It proposes a vision for the short-, medium- and long-term development of nuclear fission energy technologies, with the aim of achieving a sustainable production of nuclear energy, a significant progress in economic performance, and a continuous improvement of safety levels as well as resistance to proliferation. In particular, this document proposes road-maps for the development and deployment of potentially sustainable nuclear technologies, as well as actions to harmonize Europe's training and education, whilst renewing its research infrastructures. Public acceptance is also an important issue for the development of nuclear energy. Therefore, research in the fields of nuclear installation safety, protection of workers and populations against radiation, management of all types of waste, and governance methodologies with public participation will be promoted. The proposed road-maps provide the backbone for a strategic research agenda (SRA) to maintain

  18. Communicating with the public: space of nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Maffei, Patricia Martinez; Aquino, Afonso Rodrigues; Gordon, Ana Maria Pinho Leite; Oliveira, Rosana Lagua de; Padua, Rafael Vicente de; Vieira, Martha Marques Ferreira; Vicente, Roberto, E-mail: pmaffei@ipen.br, E-mail: araquino@usp.br, E-mail: amgordon@ipen.br, E-mail: rloliveira@ipen.br, E-mail: rpadua@ipen.br, E-mail: mmvieira@ipen.br, E-mail: rvicente@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    For two decades the Nuclear and Energy Research Institute (IPEN) has been developing activities for popularization of its R and D activities in the nuclear field. Some of the initiatives already undertaken by IPEN are lectures at schools, guided visits to IPEN facilities, printed informative material, FAQ page in the Web, and displays in annual meetings and technology fairs highlighting its achievements. In order to consolidate these initiatives, IPEN is planning to have a permanent Space of Nuclear Technology (SNT), aiming at introducing students, teachers and the general public to the current applications of nuclear technology in medicine, industry, research, electric power generation, etc. It is intended as an open room to the public and will have a permanent exhibit with historical, scientific, technical and cultural developments of nuclear technology and will also feature temporary exhibitions about specific themes. The space will display scientific material in different forms to allow conducting experiments to demonstrate some of the concepts associated with the properties of nuclear energy, hands-on programs and activities that can be customized to the students' grade level and curriculum. (author)

  19. Global Nuclear Energy Partnership Technology Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    David J. Hill

    2007-07-01

    This plan describes the GNEP Technology Demonstration Program (GNEP-TDP). It has been prepared to guide the development of integrated plans and budgets for realizing the domestic portion of the GNEP vision as well as providing the basis for developing international cooperation. Beginning with the GNEP overall goals, it describes the basic technical objectives for each element of the program, summarizes the technology status and identifies the areas of greatest technical risk. On this basis a proposed technology demonstration program is described that can deliver the required information for a Secretarial decision in the summer of 2008 and support construction of facilities.

  20. Nuclear physics detector technology applied to plant biology research

    Energy Technology Data Exchange (ETDEWEB)

    Weisenberger, Andrew G. [JLAB; Kross, Brian J. [JLAB; Lee, Seung Joo [JLAB; McKisson, John E. [JLAB; Xi, Wenze [JLAB; Zorn, Carl J. [JLAB; Howell, Calvin [DUKE; Crowell, A.S. [DUKE; Reid, C.D. [DUKE; Smith, Mark [MARYLAND U.

    2013-08-01

    The ability to detect the emissions of radioactive isotopes through radioactive decay (e.g. beta particles, x-rays and gamma-rays) has been used for over 80 years as a tracer method for studying natural phenomena. More recently a positron emitting radioisotope of carbon: {sup 11}C has been utilized as a {sup 11}CO{sub 2} tracer for plant ecophysiology research. Because of its ease of incorporation into the plant via photosynthesis, the {sup 11}CO{sub 2} radiotracer is a powerful tool for use in plant biology research. Positron emission tomography (PET) imaging has been used to study carbon transport in live plants using {sup 11}CO{sub 2}. Presently there are several groups developing and using new PET instrumentation for plant based studies. Thomas Jefferson National Accelerator Facility (Jefferson Lab) in collaboration with the Duke University Phytotron and the Triangle Universities Nuclear Laboratory (TUNL) is involved in PET detector development for plant imaging utilizing technologies developed for nuclear physics research. The latest developments of the use of a LYSO scintillator based PET detector system for {sup 11}CO{sub 2} tracer studies in plants will be briefly outlined.

  1. Advanced maintenance, inspection & repair technology for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hinton, B.M.

    1994-12-31

    Maintenance, inspection, and repair technology for nuclear power plants is outlined. The following topics are discussed: technology for reactor systems, reactor refueling bridge, fuel inspection system, fuel shuffling software, fuel reconstitution, CEA/RCCA/CRA inspection, vessel inspection capabilities, CRDM inspection and repair, reactor internals inspection and repair, stud tensioning system, stud/nut cleaning system, EDM machining technology, MI Cable systems, core exit T/C nozzle assemblies, technology for steam generators, genesis manipulator systems, ECT, UT penetrant inspections, steam generator repair and cleaning systems, technology for balance of plant, heat exchangers, piping and weld inspections, and turbogenerators.

  2. Current Development of Nuclear Thermal Propulsion technologies at the Center for Space Nuclear Research

    Energy Technology Data Exchange (ETDEWEB)

    Robert C. O' Brien; Steven K. Cook; Nathan D. Jerred; Steven D. Howe; Ronald Samborsky; Daniel Brasuell

    2012-09-01

    Nuclear power and propulsion has been considered for space applications since the 1950s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors / rocket engines in the Rover/NERVA programs1. The Aerojet Corporation was the prime contractor for the NERVA program. Modern changes in environmental laws present challenges for the redevelopment of the nuclear rocket. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel composition that is significantly different from those of the NERVA project can be engineered; this may be needed to ensure public support and compliance with safety requirements. The Center for Space Nuclear Research (CSNR) is pursuing a number of technologies, modeling and testing processes to further the development of safe, practical and affordable nuclear thermal propulsion systems.

  3. Annual meeting on nuclear technology 2013. Pt. 2. Section reports

    Energy Technology Data Exchange (ETDEWEB)

    Rohde, U.; Hoehne, Thomas [Forschungszentrum Dresden-Rossendorf (FZD) e.V., Dresden (Germany); Seidl, Marcus [E.ON Kernkraft GmbH, Hannover (Germany); Rossbach, Detlev [AREVA GmbH, Erlangen (Germany); Skrzyppek, Juergen [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany); Klute, Stefan [Siempelkamp Nukleartechnik GmbH, Heidelberg (Germany); Willmann, Frank [Toshiba International Europe Ltd., Uxbridge (United Kingdom)

    2013-10-15

    Summary report on 4 out of 12 sessions of the Annual Conference on Nuclear Technology held in Berlin, 14 to 16 May 2013: - Reactor physics and methods of calculation (Section 1), - Thermodynamics and fluid dynamics (Section 2), - Radioactive waste management, Storage (Section 5), and - Decommissioning of nuclear installations (Section 8). The Session Education, Expert knowledge, Know-how-transfer (Section 12) was covered in atw 8/9 (2013). The other sessions (Safety of nuclear installations - methods, analysis, Front end of the fuel cycle, fuel elements and core components, Operation of nuclear installations, Fusion technology, New build and innovations, Energy industry and Economics, and Radiation protection) will be covered in further issues of atw. (orig.)

  4. Annual meeting on nuclear technology 2013. Section report. Pt. 6

    Energy Technology Data Exchange (ETDEWEB)

    Buettner, Klaus [NUKEM Technologies GmbH, Alzenau (Germany). Dept. Process Engineering; Reimann, Peter [AREVA GmbH, Erlangen (Germany). Fuel Germany F-G; Vallentin, Roger [WTI GmbH, Juelich (Germany)

    2014-02-15

    Summary report on 2 out of 12 sessions of the Annual Conference on Nuclear Technology held in Berlin, 14 to 16 May 2013: - Radioactive waste management, Storage (Section 5), and - Decommissioning of nuclear installations (Section 8). The Sessions Reactor physics and methods of calculation (Section 1), Thermodynamics and fluid dynamics (Section 2), Safety of nuclear installations - methods, analysis, results (Section 3), Front End of the Fuel Cycle, Fuel Elements and Core Components (Section 4), Operation of nuclear installations (Section 6), New build and innovations (Section 7), and Education, Fusion technology (Section 9), Radiation protection (Section 11), and Expert knowledge, Know-how-transfer (Section 12) have been covered in atw 8/9 to 12 (2013) and 1 (2014). The other sessions (Front end of the fuel cycle, fuel elements and core components; and Energy industry and Economics) will be covered in further issues of atw. (orig.)

  5. Institute of Nuclear Chemistry and Technology annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This annual report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology, Warsaw, Poland in 1994. The papers are gathered into several branches as follows: radiation chemistry and physics (16 papers); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (17 papers); radiobiology (6 papers); nuclear technologies and methods (30 papers). The annual report of INCT-1994 contains also a general information about the Institute, the full list of papers published in 1994, information about Nukleonika - the International Journal of Nuclear Research being edited in INCT, the list of patent granted and patent applications in 1994, information about conferences organized by the Institute, the list of Ph.D. and D.Sc. finished in 1994 as well as the list of research projects and contracts being realized in INCT during 1994.

  6. NRV web knowledge base on low-energy nuclear physics

    Science.gov (United States)

    Karpov, A. V.; Denikin, A. S.; Naumenko, M. A.; Alekseev, A. P.; Rachkov, V. A.; Samarin, V. V.; Saiko, V. V.; Zagrebaev, V. I.

    2017-07-01

    The paper describes the principles of organization and operation of the NRV web knowledge base on low-energy nuclear physics (http://nrv.jinr.ru/) which integrates a large amount of digitized experimental data on the properties of nuclei and nuclear reaction cross sections with a wide range of computational programs for modeling of nuclear properties and various processes of nuclear dynamics which work directly in the browser of a remote user. The paper also gives an overview of the current situation in the field of application of network information technologies in nuclear physics. The features of the NRV knowledge base are illustrated in detail on the example of the analysis of nucleon transfer reactions within the distorted wave Born approximation.

  7. A Project in Support of Nuclear Technology Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Deok Ku; Kim, Kyoung Pyo; Ko, Young Chel (and others)

    2006-12-15

    Establish strategies of international cooperation in an effect 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. Using the INIS output data, it has provided domestic users with searching. Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing.

  8. Development of Curricula for Nuclear Radiation Protection, Nuclear Instrumentation, and Nuclear Materials Processing Technologies. Final Report.

    Science.gov (United States)

    Hull, Daniel M.

    A study was conducted to assist two-year postsecondary educational institutions in providing technical specialty courses for preparing nuclear technicians. As a result of project activities, curricula have been developed for five categories of nuclear technicians and operators: (1) radiation protection technician, (2) nuclear instrumentation and…

  9. Annual report of Institute of Nuclear Chemistry and Technology 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    The report is a collection of short communications being a review of the scientific activities of the Institute of Nuclear Chemistry and Technology, Warsaw in 1996. The papers are gathered in several branches as follows: radiation chemistry and physics (17); Radiochemistry, stable isotopes, nuclear analytical methods,chemistry in general (20); radiobiology (9); nuclear technologies and methods (28).The last and biggest chapter has been divided in four smaller groups; process engineering; material engineering,structural studies,diagnostics; radiation technologies; nucleonic control systems. The annual report of INCT-1996 contains also a general information of Institute, the full list of scientific publications and patents, conferences organized by INCT, Ph.D. and D.Sc. thesis, a list of projects granted by Polish Committee of Scientific Research and other organizations.

  10. 秦山核电基地放射性废物减容技术研究%Research on Radioactive Waste Volume Reduction Technology in Qinshan Nuclear Power Base

    Institute of Scientific and Technical Information of China (English)

    康云鼎

    2012-01-01

    分析秦山核电基地放射性废物的现状及其处理与贮存方式,主要研究针对蒸残液固化物、可压缩废物和废树脂3类产生量较大的固体废物的减容技术.研究表明秦山核电基地的放射性废物还有很大的减容空间,并提出增加秦山核电基地固体废物贮存时间5a以上的减容方案,可有效缓解废物贮存库容的压力.%The paper analyzes the present situation of radioactive wastes in Qinshan nuclear power base and its processing and storage, and focuses on the volume reduction technology for large number of solid wastes including steamed residual liquid condensates, compressible waste and waste resin. Research shows that there is great potential for volume reduction of radioactive wastes in Qinshan nuclear power base, and the volume reduction scheme is provided. With the proposed scheme, the storage capacity for solid wastes in Qinshan nuclear power base can be increased by more than 5 years, which will effectively relieve the pressure for waste storage capacity.

  11. Technology based Education System

    DEFF Research Database (Denmark)

    Kant Hiran, Kamal; Doshi, Ruchi; Henten, Anders

    2016-01-01

    Abstract - Education plays a very important role for the development of the country. Education has multiple dimensions from schooling to higher education and research. In all these domains, there is invariably a need for technology based teaching and learning tools are highly demanded in the acad...

  12. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    Science.gov (United States)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  13. Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors

    Science.gov (United States)

    Radulescu, Laura; Pavelescu, Margarit

    2010-01-01

    The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors. Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat. The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

  14. A methodology for evaluating ``new`` technologies in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Clark, R.L.; Holcomb, D.E.

    1994-06-01

    As obsolescence and spare parts issues drive nuclear power plants to upgrade with new technology (such as optical fiber communication systems), the ability of the new technology to withstand stressors present where it is installed needs to be determined. In particular, new standards may be required to address qualification criteria and their application to the nuclear power plants of tomorrow. This paper discusses the failure modes and age-related degradation mechanisms of fiber optic communication systems, and suggests a methodology for identifying when accelerated aging should be performed during qualification testing.

  15. Nuclear transfer technology in mammalian cloning.

    Science.gov (United States)

    Wolf, D P; Mitalipov, S; Norgren, R B

    2001-01-01

    The past several years have witnessed remarkable progress in mammalian cloning using nuclear transfer (NT). Until 1997 and the announcement of the successful cloning of sheep from adult mammary gland or fetal fibroblast cells, our working assumption was that cloning by NT could only be accomplished with relatively undifferentiated embryonic cells. Indeed, live offspring were first produced by NT over 15 years ago from totipotent, embryonic blastomeres derived from early cleavage-stage embryos. However, once begun, the progression to somatic cell cloning or NT employing differentiated cells as the source of donor nuclei was meteoric, initially involving differentiated embryonic cell cultures in sheep in 1996 and quickly thereafter, fetal or adult somatic cells in sheep, cow, mouse, goat, and pig. Several recent reviews provide a background for and discussion of these successes. Here we will focus on the potential uses of reproductive cloning along with recent activities in the field and a discussion concerning current interests in human reproductive and therapeutic cloning.

  16. Technology Teachers' Attitudes toward Nuclear Energy and Their Implications for Technology Education

    Science.gov (United States)

    Lee, Lung-Sheng; Yang, Hsiu-Chuan

    2013-01-01

    The purpose of this paper was to explore high-school (grades 10-12) technology teachers' attitudes toward nuclear energy and their implications to technology education. A questionnaire was developed to solicit 323 high-school technology teachers' responses in June 2013 and 132 (or 41%) valid questionnaires returned. Consequently, the following…

  17. Application study of nuclear technologies for dual use

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jae Gon; Chung, W. S.; Park, W. S.; Lee, K. W.; Cha, H. K.; Han, M. H.; Yoon, J. S.; Honh, D. H.; Park, J. Y.; Lee, C. H.; Yeo, J. W.; Jung, M.; Ra, G. H

    2000-02-01

    The projects for the joint development of technology common to the civilian and military sectors are being carried out at national level to maximize the utilization of limited resources. The technologies have been identified through a process which considered whether they are duplicates of the present military technology, whether they are necessary, and whether their realization is feasible. In addition, the problems surfaced during the identification process have been analyzed and suggestions to vitalize the military application of civilian nuclear technology are presented in the contexts of personal channel, institutional networking, R and D information exchange, and budgetary support. (author)

  18. NRV web knowledge base on low-energy nuclear physics

    Science.gov (United States)

    Karpov, V.; Denikin, A. S.; Alekseev, A. P.; Zagrebaev, V. I.; Rachkov, V. A.; Naumenko, M. A.; Saiko, V. V.

    2016-09-01

    Principles underlying the organization and operation of the NRV web knowledge base on low-energy nuclear physics (http://nrv.jinr.ru) are described. This base includes a vast body of digitized experimental data on the properties of nuclei and on cross sections for nuclear reactions that is combined with a wide set of interconnected computer programs for simulating complex nuclear dynamics, which work directly in the browser of a remote user. Also, the current situation in the realms of application of network information technologies in nuclear physics is surveyed. The potential of the NRV knowledge base is illustrated in detail by applying it to the example of an analysis of the fusion of nuclei that is followed by the decay of the excited compound nucleus formed.

  19. Chemistry of nuclear resources, technology, and waste

    Energy Technology Data Exchange (ETDEWEB)

    Keller, O.L. Jr.

    1978-01-01

    Chemistry is being called on today to obtain useful results in areas that have been found very difficult for it in the past, but new instrumentation and new theories are allowing much progress. The area of hydrolytic phenomena and colloid chemistry, as exemplified by the plutonium polymer problem, is clearly entering a new phase in which it can be studied in a much more controlled and understandable manner. The same is true of the little studied interfacial regions, where so much important chemistry occurs in solvent extraction and other systems. The studies of the adsorption phenomena on clays are an illustration of the new and useful modeling of geochemical phenomena that is now possible. And finally, the chemist is called upon to participate in the developement and evaluation of models for nuclear waste isolation requiring extrapolations of hundreds to hundreds of thousands of years into the future. It is shown that chemistry may be useful in keeping the extrapolations in the shorter time spans, and also in selecting the best materials for containment. 36 figures.

  20. Application of Telepresence Technologies to Nuclear Material Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Wright, M.C.; Rome, J.A.

    1999-09-20

    Implementation of remote monitoring systems has become a priority area for the International Atomic Energy Agency and other international inspection regimes. For the past three years, DOE2000 has been the US Department of Energy's (DOE's) initiative to develop innovative applications to exploit the capabilities of broadband networks and media integration. The aim is to enhance scientific collaboration by merging computing and communications technologies. These Internet-based telepresence technologies could be easily extended to provide remote monitoring and control for confidence building and transparency systems at nuclear facilities around the world. One of the original DOE2000 projects, the Materials Microcharacterization Collaboratory is an interactive virtual laboratory, linking seven DOE user facilities located across the US. At these facilities, external collaborators have access to scientists, data, and instrumentation, all of which are available to varying degrees using the Internet. Remote operation of the instruments varies between passive (observational) to active (direct control), in many cases requiring no software at the remote site beyond a Web browser. Live video streams are continuously available on the Web so that participants can see what is happening at a particular location. An X.509 certificate system provides strong authentication, The hardware and software are commercially available and are easily adaptable to safeguards applications.

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

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.; Brown, W. (Brookhaven National Lab., Upton, NY (United States)); Granda, T.; Baker, C. (Carlow Associates, Inc., Fairfax, VA (United States))

    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.

  2. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim, Yun Jae; Choi, Jae Boong [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2002-03-15

    This project focuses on developing reliable life evaluation technology for nuclear power plant components, and is divided into two parts, development of a life evaluation system for nuclear pressure vessels and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered in this project: defect assessment method for steam generator tubes, development of fatigue monitoring system, assessment of corroded pipes, domestic round robin analysis for constructing P-T limit curve for RPV, development of probabilistic integrity assessment technique, effect of aging on strength of dissimilar welds, applicability of LBB to cast stainless steel, and development of probabilistic piping fracture mechanics.

  3. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

  4. Nuclear fission technology in Spain: History and social concerns.

    Science.gov (United States)

    Aliende Urtasun, Ana; Luquin, Asunción; Garrido, Julián J

    2016-07-19

    This research examines the evolution of nuclear technology in Spain from the early years of the Franco dictatorship to the global financial crisis and technology's influence on Spanish culture. To this end, we take a sociological perspective, with science culture and social perceptions of risk in knowledge societies serving as the two elements of focus in this work. In this sense, this article analyses the transformation of social relationships in light of technological changes. We propose technology as a strategic place to observe the institutional and organisational dynamics of technologic-scientific risks, the expert role and Spain's science culture. In addition, more specifically, within the language of co-production, we 'follow the actor' and favour new forms of citizen participation that promote ethics to discuss technological issues.

  5. Science and technology as strategic way for nuclear activities; A C e T como fator estrategico para as atividades nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Paiano, Silvestre

    2000-07-01

    The article brings few instructive examples on the interaction between nuclear energy and other areas of science and technology, Microelectronics, computer technology, and new materials are among the many technologies which are crucial for developing nuclear energy technology. On the other way round, nuclear energy presents also a wide range of new demands and opportunities for several areas of science and technology. The problem is that such a relationship is not well understood by the society, and to a large extent it brings about the very process of legitimating the use of nuclear energy (author)

  6. A Study on the Beta Voltaic Micro -nuclear Battery Based on the Planar Technology Silicon Detector%基于平面工艺硅探测器的β伏打微核能电池

    Institute of Scientific and Technical Information of China (English)

    张凯; 何高魁; 黄小健; 刘洋; 孟欣; 郝晓勇

    2011-01-01

    It describes briefly the beta voltaic micro - nuclear battery based on the planar technology silicon detector and radioisotope. Different sensitive area of silicon detectors are used to cooperate with Ni source to buildup of beta voltaic micro - nuclear batteries. The experimental data show that the larger sensitive area the silicon detector has, the higher open circuit voltage it produces, and the open circuit voltage of single cell has reached an excellent result from 0. 15 V to 0. 30V. It is possible to get high output power by series or parallel connecting the beta voltaic micro - nuclear batteries.%简要叙述了利用平面工艺硅探测器和放射性同位素构成的β伏打微核能电池的原理,比较了不同灵敏面积硅探测器对β伏打微核能电池开路电压的影响.实验证明,单个β伏打微核能电池的开路电压可达到0.15V~0.3V,采用串、并联方式可以获得较大的输出功率.

  7. Lifetime Management in Non-US-Technology Nuclear Power Plants using US Regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cornelius Steenkamp, J.; Encabo Espartero, J.; Garcia Iglesias, R.

    2013-07-01

    In July 2009 the Spanish Nuclear Regulator (CSN) issued a Safety Instruction (IS-22) for the development of Lifetime Management in the Nuclear Power Plants within Spain. The context of this Safety Instruction is based on the American Regulations 10CFR54, NUREG1800/1801 and the technical guide NEI95-10. All these regulations are aimed at US-Technology Nuclear Power Plants. Lifetime Management of Nuclear Power Plants with a plant design different from US technologies can most certainly be developed with the mentioned US regulations. The successful development of Lifetime Management in these cases depends on the adaptation of the different requirements of the regulations. Challenges resulting from the adaptation process can be resolved by taking into consideration the plant design of the plant in question.

  8. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). About cores, coal and cash

    Energy Technology Data Exchange (ETDEWEB)

    Podivinsky, Tomas Jan

    2016-07-15

    Rationality and - especially with regard to reducing emissions - technological neutrality are two commitments for nuclear fission. The Czech Republic, where conditions are not suitable for economical large-scale operation of facilities based on renewables, there is no alternative in environmental or business policy to the reasonable use of nuclear energy. The aim of the updated Czech energy strategy is to increase the proportion of nuclear energy from 35 % to approx. 50 % of power generation and to cover the rest - together with ultra-high efficiency coal fired power plants - with energy from renewable sources and gas fired power plants.

  9. Advantage of nuclear knowledge for the new technologies; Aprovechamiento del conocimiento nuclear a las nuevas tecnologias

    Energy Technology Data Exchange (ETDEWEB)

    Legaz, R.

    2002-07-01

    Gathered experiences by several companies related with the nuclear sector, have let us to face up with reliability and optimism, the challenge to undertake other energy experiences with new technologies. As a result of this combined strategy, we have succeeded to keep up the existence and companies development that compete and stand out from a more divers and globalized energetic world. (Author)

  10. PREFACE: EPS Euroconference XIX Nuclear Physics Divisional Conference: New Trends in Nuclear Physics Applications and Technology

    Science.gov (United States)

    2006-06-01

    It was with great pleasure that the Department of Nuclear and Theoretical Physics of the University of Pavia and the INFN (Istituto Nazionale di Fisica Nucleare) Structure of Pavia organised the XIX Nuclear Physics Divisional Conference of the European Physical Society, which was held in the historical buildings of the University of Pavia from 5-9 September 2005. The Conference was devoted to the discussion of the most recent experimental and theoretical achievements in the field of Nuclear Physics applications, as well as of the latest developments in technological tools related to Nuclear Physics research. The University of Pavia has a long tradition in Physics and in Applied Physics, being the site where Alessandro Volta developed his "pila", the precursor of the modern battery. This is the place where the first experiments with electricity were conducted and where the term "capacitance" used for capacitors was invented. Today the University hosts a Triga Mark II nuclear reactor, which is used by the Departments of the University of Pavia and by other Universities and private companies as well. Moreover, Pavia is the site selected for the construction of the CNAO complex "Centro Nazionale di Adroterapia Oncologica" (National Centre for Oncological Hadrontherapy), planned for 2005-2008 which represents a unique facility in Italy and will be among the first complexes of this type in Europe. The Conference has gathered together experts in various fields from different countries and has been the occasion to review the present status and to discuss the new emerging trends in Nuclear Physics and its applications to multidisciplinary researches and the development of new technologies. The following topics were treated: Nuclear Techniques in Medicine and Life Sciences (Cancer Therapy, new Imaging and Diagnostics Tools, Radioisotope production, Radiation Protection and Dosimetry). Applications of Nuclear Techniques in Art, Archaeometry and other Interdisciplinary fields

  11. FY04 Engineering Technology Reports Technology Base

    Energy Technology Data Exchange (ETDEWEB)

    Sharpe, R M

    2005-01-27

    Lawrence Livermore National Laboratory's Engineering Directorate has two primary discretionary avenues for its investment in technologies: the Laboratory Directed Research and Development (LDRD) program and the ''Tech Base'' program. This volume summarizes progress on the projects funded for technology-base efforts in FY2004. The Engineering Technical Reports exemplify Engineering's more than 50-year history of researching and developing (LDRD), and reducing to practice (technology-base) the engineering technologies needed to support the Laboratory's missions. Engineering has been a partner in every major program and project at the Laboratory throughout its existence, and has prepared for this role with a skilled workforce and technical resources. This accomplishment is well summarized by Engineering's mission: ''Enable program success today and ensure the Laboratory's vitality tomorrow''. LDRD is the vehicle for creating those technologies and competencies that are cutting edge. These require a significant level of research or contain some unknown that needs to be fully understood. Tech Base is used to apply those technologies, or adapt them to a Laboratory need. The term commonly used for Tech Base projects is ''reduction to practice''. Tech Base projects effect the natural transition to reduction-to-practice of scientific or engineering methods that are well understood and established. They represent discipline-oriented, core competency activities that are multi-programmatic in application, nature, and scope. The objectives of technology-base funding include: (1) the development and enhancement of tools and processes to provide Engineering support capability, such as code maintenance and improved fabrication methods; (2) support of Engineering science and technology infrastructure, such as the installation or integration of a new capability; (3) support for technical and

  12. Nuclear Technology Programs semiannual progress report, October 1988--March 1989

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. [ed.

    1990-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. 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 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 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. 127 refs., 76 figs., 103 tabs.

  13. Nuclear Technology Programs semiannual progress report, April-- September 1990

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. (ed.)

    1992-06-01

    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 1990. 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 in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  14. Nuclear Technology Programs semiannual progress report, April-- September 1990

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. [ed.

    1992-06-01

    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 1990. 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 in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  15. Nuclear technology programs. Semiannual progress report, April--September 1991

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. 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 in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  16. Nuclear technology programs; Semiannual progress report, October 1989--March 1990

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. [ed.

    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&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.

  17. Nuclear Technology Programs semiannual progress report, October 1990--March 1991

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. 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 transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  18. Instructional Technologies in the Workforce: Case Studies from the Nuclear Industry.

    Science.gov (United States)

    Widen, William C.; Roth, Gene L.

    1992-01-01

    Describes six types of instructional technology used in the nuclear industry: Study Pacs, computerized test banks, computer-based training, interactive videodisc, artificial intelligence, and full-scope simulation. Each description presents the need, training device, outcomes, and limitations or constraints on use. (SK)

  19. Refractory alloy technology for space nuclear power applications

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, R.H. Jr.; Hoffman, E.E. (eds.)

    1984-01-01

    Purpose of this symposium is twofold: (1) to review and document the status of refractory alloy technology for structural and fuel-cladding applications in space nuclear power systems, and (2) to identify and document the refractory alloy research and development needs for the SP-100 Program in both the short and the long term. In this symposium, an effort was made to recapture the space reactor refractory alloy technology that was cut off in midstream around 1973 when the national space nuclear reactor program began in the early 1960s, was terminated. The six technical areas covered in the program are compatibility, processing and production, welding and component fabrication, mechanical and physical properties, effects of irradiation, and machinability. The refractory alloys considered are niobium, molybdenum, tantalum, and tungsten. Thirteen of the 14 pages have been abstracted separately. The remaining paper summarizes key needs for further R and D on refractory alloys. (DLC)

  20. Nuclear fission: the interplay of science and technology.

    Science.gov (United States)

    Stoneham, A M

    2010-07-28

    When the UK's Calder Hall nuclear power station was connected to the grid in 1956, the programmes that made this possible involved a powerful combination of basic and applied research. Both the science and the engineering were novel, addressing new and challenging problems. That the last Calder Hall reactor was shut down only in 2003 attests to the success of the work. The strengths of bringing basic science to bear on applications continued to be recognized until the 1980s, when government and management fashions changed. This paper identifies a few of the technology challenges, and shows how novel basic science emerged from them and proved essential in their resolution. Today, as the threat of climate change becomes accepted, it has become clear that there is no credible solution without nuclear energy. The design and construction of new fission reactors will need continuing innovation, with the interplay between the science and technology being a crucial component.

  1. A State-of-the-Art Report on Cutting Technologies for Decommissioning Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Kyun; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-10-15

    This report provides the status of the cryogenic cutting technology as a new dismantling technology for dismantling radioactive nuclear facilities and also presents the direction of study to apply it to a radioactive nuclear facility research aim of its nuclear. This report consists of four chapter : - 1. Background and objectives of dismantling technology for dismantling a radioactive nuclear facility. - 2. Analysis of the status of conventional cutting technologies - 3. Analysis of the status of cryogenic cutting technology - 4. Discussion, conclusion, and future work on state-of-the-art technology of dismantling for nuclear facilities.

  2. 核四极共振技术在黑火药探测中的研究%Research in the detection of black powder based on nuclear quadrupole resonance technology

    Institute of Scientific and Technical Information of China (English)

    李康宁; 俞硕; 李兴; 张向阳

    2011-01-01

    In order to increase types of explosives detection based on nuclear quadrupole resonance (NQR), the detection method on black powder is researched in this paper. The results include NQR frequencies and some important detection parameters. Practical test shows this method is precise, so it is very useful to expand the application about NQR technology in the near future.%为增加基于核四极共振(NQR)技术探测爆炸物的种类,对黑火药的NQR特性进行了研究.介绍了探测方案的设计与实现,掌握了黑火药NQR共振频率等参数及试验方法.实际测试表明,探测结果准确,从而也为今后NQR技术的扩展应用打下了基础.

  3. Sub-Critical Nuclear Reactor Based on FFAG-Accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hee Seok; Kang, Hung Sik; Lee, Tae Yeon [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)

    2011-10-15

    After the East-Japan earthquake and the subsequent nuclear disaster, the anti-nuclear mood has been wide spread. It is very unfortunate both for nuclear science community and for the future of mankind, which is threatened by two serious challenges, the global warming caused by the greenhouse effect and the shortage of energy cause by the petroleum exhaustion. While the nuclear energy seemed to be the only solution to these problems, it is clear that it has its own problems, one of which broke out so strikingly in Japan. There are also other problems such as the radiotoxic nuclear wastes that survive up to even tens of thousands years and the limited reserves of Uranium. To solve these problems of nuclear fission energy, accelerator-based sub-critical nuclear reactor was once proposed. (Its details will be explained below.) First of all, it is safe in a disaster such as an earthquake, because the deriving accelerator stops immediately by the earthquake. It also minimizes the nuclear waste problem by reducing the amount of the toxic waste and shortening their half lifetime to only a few hundred years. Finally, it solves the Uranium reserve problem because it can use Thorium as its fuel. The Thorium reserve is much larger than that of Uranium. Although the idea of the accelerator-driven nuclear reactor was proposed long time ago, it has not been utilized yet first by technical difficulty and economical reasons. The accelerator-based system needs 1 GeV, 10 MW power proton accelerator. A conventional linear accelerator would need several hundred m length, which is highly costly particularly in Korea because of the high land cost. However, recent technologies make it possible to realize that scale accelerator by a reasonable size. That is the fixed-field alternating gradient (FFAG) accelerator that is described in this article

  4. A comparative study on the effective safety of nuclear technology in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Soh, Young Jin [Daegu University, Daegu (Korea); Kim, Young Pyoung [Korea University, Seoul (Korea); Jung, Yoon Soo [Myoungji University, Seoul (Korea); Chung, Ik Jae; Choi, Byung Sun [Seoul National University, Seoul (Korea)

    2001-12-01

    The main purpose of this research is to analyze Korean perception of nuclear risk in comparison with other technological risks. In order to understand the characteristics of risk perception, the concept of 'effective safety' is clarified and defined. This research also covers such issues as relative riskiness of major risks, risk attitude, risk attribution, behavioral pattern for risky situation, and risk knowledge. A nation-wide survey was conducted for this study with a sample size of 1870. It was based on the purposive quota sampling to compare nuclear risk and other technological risks selected are 6 groups of risk; nuclear risk, environmental risk, traffic risk, chemical materials, industrial safety, and other recent risks. Accross these groups, a total of 25 risks are examined. 52 refs., 14 figs., 125 tabs. (Author)

  5. The development of VR technology for nuclear industry applications

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Bum; Cho, Jai Wan; Lee, Nam Ho; Choi, Young Soo; Park, Soon Yong

    1998-01-01

    By searching the present condition of virtual reality technology of which researches were carried out not only abroad but also the country in nuclear power industry, we confirm the possibility of practical usage of VR in it. And as a fundamental research for applications of VR in nuclear power industry, gesture recognition for remote working and VR training system for severe working were performed. 1. A study on gesture recognition for remote working : The hand gesture recognition technology using visual signal and tactile magnetic sensor as a basic study for the introduction of task command and communication were performed. 2. A study on an construction of the virtual environment training system for the task in a severe condition: A construction of virtual reality training system for the tasks in a severe working condition was implemented. This system was intended to enhance the efficiency of actual tasks through advanced practicing the motion procedures those should be performed in a severe working condition where it is difficult to access for personnel. The motion information which is came from the sensors attached on trainers body was used for construction of the virtual environment through the computer graphic procedures. The VR training system has many merits relative to the conservative training method that was performed with mock-up which was made as the same size and shape as real component in nuclear power plant. (author). 27 refs., 21 tabs., 51 figs

  6. CONTRIBUTION OF HANARO IRRADIATION TECHNOLOGIES TO NATIONAL NUCLEAR R&D

    Directory of Open Access Journals (Sweden)

    KEE NAM CHOO

    2014-08-01

    Full Text Available HANARO is a multipurpose research reactor located at the Korea Atomic Energy Research Institute (KAERI. Since the commencement of its operation in 1995, various neutron irradiation facilities, such as rabbit irradiation facilities, fuel test loop (FTL facilities, capsule irradiation facilities, and neutron transmutation doping (NTD facilities, have been developed and actively utilized for various nuclear material irradiation tests requested by users from research institutes, universities, and industries. Most irradiation tests have been related to national R&D relevant to present nuclear power reactors such as the ageing management and safety evaluation of the components. Based on the accumulated experience as well as the sophisticated requirements of users, HANARO has recently supported national R&D projects relevant to new nuclear systems including the System-integrated Modular Advanced Reactor (SMART, research reactors, and future nuclear systems. This paper documents the current state and utilization of irradiation facilities in HANARO, and summarizes ongoing research efforts to deploy advanced irradiation technology.

  7. Development of Noncontact Imaging Technology for the Detection of Internal Defects of a Nuclear Fuel Plate

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Baik, S. H.; Lee, Y. S.; Cheong, Y. M.

    2012-01-15

    The object of the research is to develop a new imaging inspection technology for the quality testing of plate-type nuclear fuel whose demanding is currently increasing in nuclear research reactors. A new noncontact imaging inspection technique is developed for the detection of internal defects in plate-type nuclear fuel. To develop the imaging inspection technique, a hardware system based on active optical interference is configured. An operating software for the developed nondestructive inspection system is developed after designing an advanced signal processing algorithm to improve the detection capability of the system. The developed system is optimized through experiments and optimal heating condition is studied. The performance of a lock-in thermography is also evaluated to see the possibility of the plate-type nuclear fuel application.

  8. 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.

  9. Technology development of nuclear material safeguards for DUPIC fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Kim, Ho Dong; Kang, Hee Young; Lee, Young Gil; Byeon, Kee Ho; Park, Young Soo; Cha, Hong Ryul; Park, Ho Joon; Lee, Byung Doo; Chung, Sang Tae; Choi, Hyung Rae; Park, Hyun Soo

    1997-07-01

    During the second phase of research and development program conducted from 1993 to 1996, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. By securing in advance a optimized safeguards system with domestically developed hardware and software, it will contribute not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author). 27 refs., 13 tabs., 89 figs.

  10. Nuclear technology aspects of ITER vessel-mounted diagnostics

    Science.gov (United States)

    Vayakis, George; Bertalot, Luciano; Encheva, Anna; Walker, Chris; Brichard, Benoît; Cheon, M. S.; Chitarin, G.; Hodgson, Eric; Ingesson, Christian; Ishikawa, M.; Kondoh, T.; Meister, Hans; Moreau, Philippe; Peruzzo, Simone; Pak, S.; Pérez-Pichel, Germán; Reichle, Roger; Testa, Duccio; Toussaint, Matthieu; Vermeeren, Ludo; Vershkov, Vladimir

    2011-10-01

    ITER has diagnostics with machine protection, basic and advanced control, and physics roles. Several are distributed on the inner and outer periphery of the vacuum vessel. They have reduced maintainability compared to diagnostics in ports. They also endure some of the highest nuclear and EM loads of any diagnostic for the longest time. They include: Inductive sensors for time-integrated and raw inductive measurements; Steady-state magnetic sensors to correct drifts of the inductive sensors; Bolometer cameras to provide electromagnetic radiation tomography; Microfission chambers and neutron activation stations to provide fusion power and fluence; MM-wave reflectometry to measure the plasma density profile and the plasma-wall distance and; Wiring to service magnetics, bolometry, and in-vessel instrumentation. This paper summarises the key technological issues these diagnostics arising from the nuclear environment, recent progress and outstanding R&D for each system.

  11. Technology development for nuclear power generation for space application

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Lamartine N.F.; Ribeiro, Guilherme B.; Braz Filho, Francisco A.; Nascimento, Jamil A.; Placco, Guilherme M., E-mail: guimarae@ieav.cta.br, E-mail: lamartine.guimaraes@pq.cnpq.br [Instituto de Estudos Avancados (IEAv), Sao Jose dos Campos, SP (Brazil). Divisao de Energia Nuclear; Faria, Saulo M. de [Instituto Tecnologico de Aeronautica (ITA), Sao Jose dos Campos, SP (Brazil)

    2015-07-01

    For a few years now, the TERRA project is developing several technology pieces to foster nuclear space applications. In this way, a nuclear reactor concept has been developed as a first proposal. Together, the problem of heat to electricity conversion has been addressed. A closed Brayton cycle is being built and a Stirling machine is being worked out and perfected. In addition, two types of heat pipes are being look at. One related with high temperature made of Mo13Re, an especial alloy. And a second one made of copper, which mainly could be used as a passive heat rejection. In this way, all major areas of interest in a micro station to be used in space has been addressed. A new passive technology has been inferred and is related with Tesla turbine or its evolution, known as multi fluid passive turbine. This technology has the potential to either: improve the Brayton cycle or its efficiency. In this paper, some details are discussed and some will be shown during the presentation, as the work evolve. (author)

  12. Fabrication of CeO2 by sol-gel process based on microfluidic technology as an analog preparation of ceramic nuclear fuel microspheres

    CERN Document Server

    Ye, Bin; Li, Jiaolong; Zhao, Zichen; Chang, Zhenqi; Serra, Christophe A

    2012-01-01

    Microfluidics integrated with sol-gel processes is introduced in preparing monodispersed MOX nuclear fuel microspheres using nonactive cerium as a surrogate for uranium or plutonium. The detailed information about microfluidic devices and sol-gel processes are provided. The effects of viscosity and flow rate of continuous and dispersed phase on size and size distribution of CeO2 microspheres have been investigated. A comprehensive characterization of the CeO2 microspheres has been conducted, including XRD pattern, SEM, density, size and size distribution. The size of prepared monodisperse particles can be controlled precisely in range of 10{\\mu}m to 1000{\\mu}m and the particle CV is below 3%.

  13. Overview of materials technologies for space nuclear power and propulsion

    Science.gov (United States)

    Zinkle, S. J.; Ott, L. J.; Ingersoll, D. T.; Ellis, R. J.; Grossbeck, M. L.

    2002-01-01

    A wide range of different space nuclear systems are currently being evaluated as part of the DOE Special Purpose Fission Technology program. The near-term subset of systems scheduled to be evaluated range from 50 kWe gas-, pumped liquid metal-, or liquid metal heat pipe-cooled reactors for space propulsion to 3 kWe heat pipe or pumped liquid metal systems for Mars surface power applications. The current status of the materials technologies required for the successful development of near-term space nuclear power and propulsion systems is reviewed. Materials examined in this overview include fuels (UN, UO2, UZrH), cladding and structural materials (stainless steel, superalloys, refractory alloys), neutron reflector materials (Be, BeO), and neutron shield materials (B4C,LiH). The materials technologies issues are considerably less demanding for the 3 kWe reactor systems due to lower operating temperatures, lower fuel burnup, and lower radiation damage levels. A few reactor subcomponents in the 3 kWe reactors under evaluation are being used near or above their engineering limits, which may adversely affect the 5 to 10 year lifetime design goal. It appears that most of these issues for the 3 kWe reactor systems can be accommodated by incorporating a few engineering design changes. Design limits (temperature, burnup, stress, radiation levels) for the various materials proposed for space nuclear reactors will be summarized. For example, the temperature and stress limits for Type 316 stainless steel in the 3 kWe Na-cooled heat pipe reactor (Stirling engine) concept will be controlled by thermal creep and CO2 corrosion considerations rather than radiation damage issues. Conversely, the lower operating temperature limit for the LiH shield material will likely be defined by ionizing radiation damage (radiolysis)-induced swelling, even for the relatively low radiation doses associated with the 3 kWe reactor. .

  14. Proceedings of the Nuclear Criticality Technology Safety Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Rene G. Sanchez

    1998-04-01

    This document contains summaries of most of the papers presented at the 1995 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 16 and 17 at San Diego, Ca. The meeting was broken up into seven sessions, which covered the following topics: (1) Criticality Safety of Project Sapphire; (2) Relevant Experiments For Criticality Safety; (3) Interactions with the Former Soviet Union; (4) Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses; (5) Monte Carlo Vulnerabilities of Execution and Interpretation; (6) Monte Carlo Vulnerabilities of Representation; and (7) Benchmark Comparisons.

  15. 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)

  16. 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)

  17. Status and prospect of NDT technology for nuclear energy industry in Korea

    Science.gov (United States)

    Lee, Joon Hyun

    2016-02-01

    Innovative energy technology is considered to be one of the key solutions for meeting the challenges of climate change and energy security, which is why global leaders are focusing on enhancing energy technology R&D. In accordance with the global movements to accelerate energy R&D, the Korean government has made significant investments in a broad spectrum of energy R&D programs, including energy efficiency, resources, CCS, new and renewable energy, power generation and electricity delivery, nuclear power and nuclear waste management. In order to manage government sponsored energy R&D programs in an efficient and effective way, the government established the Korea Institute of Energy technology Evaluation and Planning (KETEP) in 2009. Main activities of KETEP include developing energy technology roadmaps, planning, evaluating, and managing R&D programs, fostering experts in the field of energy, promoting international cooperation programs, gathering and analyzing energy statistics, and supporting infrastructure and commercialization. KETEP assists the Ministry of Trade, Industry and Energy in developing national R&D strategies while also working with researchers, universities, national institutes and the private sector for their successful energy technology and deployment. This presentation consists of three parts. First, I will introduce the characteristics of energy trends and mix in Korea. Then, I'll speak about the related national R&D strategies of energy technology. Finally, I'll finish up with the status and prospect of NDT technology for nuclear energy industry in Korea. The development of the on-line structural integrity monitoring systems and the related techniques in Korean nuclear power plant for the purpose of condition based maintenance is introduced. The needs of NDT techniques for inspection and condition monitoring for GEN IV including SFR, small module reactor etc., are also discussed.

  18. Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts

    Energy Technology Data Exchange (ETDEWEB)

    S. Bays; S. Piet; N. Soelberg; M. Lineberry; B. Dixon

    2010-09-01

    The following report provides a rich resource of information for exploring fuel cycle characteristics. The most noteworthy trends can be traced back to the utilization efficiency of natural uranium resources. By definition, complete uranium utilization occurs only when all of the natural uranium resource can be introduced into the nuclear reactor long enough for all of it to undergo fission. Achieving near complete uranium utilization requires technologies that can achieve full recycle or at least nearly full recycle of the initial natural uranium consumed from the Earth. Greater than 99% of all natural uranium is fertile, and thus is not conducive to fission. This fact requires the fuel cycle to convert large quantities of non-fissile material into fissile transuranics. Step increases in waste benefits are closely related to the step increase in uranium utilization going from non-breeding fuel cycles to breeding fuel cycles. The amount of mass requiring a disposal path is tightly coupled to the quantity of actinides in the waste stream. Complete uranium utilization by definition means that zero (practically, near zero) actinide mass is present in the waste stream. Therefore, fuel cycles with complete (uranium and transuranic) recycle discharge predominately fission products with some actinide process losses. Fuel cycles without complete recycle discharge a much more massive waste stream because only a fraction of the initial actinide mass is burned prior to disposal. In a nuclear growth scenario, the relevant acceptable frequency for core damage events in nuclear reactors is inversely proportional to the number of reactors deployed in a fuel cycle. For ten times the reactors in a fleet, it should be expected that the fleet-average core damage frequency be decreased by a factor of ten. The relevant proliferation resistance of a fuel cycle system is enhanced with: decreasing reliance on domestic fuel cycle services, decreasing adaptability for technology misuse

  19. Cryogenic Fluid Management Technology and Nuclear Thermal Propulsion

    Science.gov (United States)

    Taylor, Brian D.; Caffrey, Jarvis; Hedayat, Ali; Stephens, Jonathan; Polsgrove, Robert

    2016-01-01

    Cryogenic fluid management (CFM) is critical to the success of future nuclear thermal propulsion powered vehicles. While this is an issue for any propulsion system utilizing cryogenic propellants, this is made more challenging by the radiation flux produced by the reactor in a nuclear thermal rocket (NTR). Managing the cryogenic fuel to prevent propellant loss to boil off and leakage is needed to limit the required quantity of propellant to a reasonable level. Analysis shows deposition of energy into liquid hydrogen fuel tanks in the vicinity of the nuclear thermal engine. This is on top of ambient environment sources of heat. Investments in cryogenic/thermal management systems (some of which are ongoing at various organizations) are needed in parallel to nuclear thermal engine development in order to one day see the successful operation of an entire stage. High durability, low thermal conductivity insulation is one developmental need. Light weight cryocoolers capable of removing heat from large fluid volumes at temperatures as low as approx. 20 K are needed to remove heat leak from the propellant of an NTR. Valve leakage is an additional CFM issue of great importance. Leakage rates of state of the art, launch vehicle size valves (which is approximately the size valves needed for a Mars transfer vehicle) are quite high and would result in large quantities of lost propellant over a long duration mission. Additionally, the liquid acquisition system inside the propellant tank must deliver properly conditioned propellant to the feed line for successful engine operation and avoid intake of warm or gaseous propellant. Analysis of the thermal environment and the CFM technology development are discussed in the accompanying presentation.

  20. Developments and needs in nuclear analysis of fusion technology

    Energy Technology Data Exchange (ETDEWEB)

    Pampin, R., E-mail: raul.pampin@f4e.europa.eu [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Davis, A. [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Izquierdo, J. [F4E Fusion For Energy, Josep Pla 2, Torres Diagonal Litoral B3, Barcelona 08019 (Spain); Leichtle, D. [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz Platz 1, D-76344 Karlsruhe (Germany); Loughlin, M.J. [ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance (France); Sanz, J. [UNED, Departamento de Ingenieria Energetica, Juan del Rosal 12, 28040 Madrid (Spain); Turner, A. [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Villari, R. [Associazione EURATOM-ENEA sulla Fusione, Via Enrico Fermi 45, 00044 Frascati, Rome (Italy); Wilson, P.P.H. [University of Wisconsin, Nuclear Engineering Department, Madison, WI (United States)

    2013-10-15

    Highlights: • Complex fusion nuclear analyses require detailed models, sophisticated acceleration and coupling of cumbersome tools. • Progress on development of tools and methods to meet specific needs of fusion nuclear analysis reported. • Advances in production of reference models and in preparation and QA of acceleration and coupling algorithms shown. • Evaluation and adaptation studies of alternative transport codes presented. • Discussion made of the importance of efforts in these and other areas, considering some of the more pressing needs. -- Abstract: Nuclear analyses provide essential input to the conceptual design, optimisation, engineering and safety case of fusion technology in current experiments, ITER, next-step devices and power plant studies. Calculations are intricate and computer-intensive, typically requiring detailed geometry models, sophisticated acceleration algorithms, high-performance parallel computations, and coupling of large and complex transport and activation codes and databases. This paper reports progress on some key areas in the development of tools and methods to meet the specific needs of fusion nuclear analyses. In particular, advances in the production and modernisation of reference models, in the preparation and quality assurance of acceleration algorithms and coupling schemes, and in the evaluation and adaptation of alternative transport codes are presented. Emphasis is given to ITER-relevant activities, which are the main driver of advances in the field. Discussion is made of the importance of efforts in these and other areas, considering some of the more pressing needs and requirements. In some cases, they call for a more efficient and coordinated use of the scarce resources available.

  1. Construction of APR1000 nuclear power information management system based on international standards

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Seung Hwan [Korea Electric Power Research Institute, Daejeon (Korea, Republic of); Song, Deok Yong; Han, Byung Sub [Enesys Co., Daejeon (Korea, Republic of); An, Kyung Ik; Hwang, Jin Sang [PartDB Co., Daejeon (Korea, Republic of)

    2010-10-15

    In recent years, due to speedy rise of international oil prices, orders of nuclear power plant construction have been in progress by many countries to solve the stable supply of power. Our country has continued to perform nuclear power construction. As only a few developed countries like Japan and European countries have its own nuclear power construction technology, competition among them is keen. Our country has awarded the contract of UAE nuclear power plants based on the accumulated nuclear power plant construction technologies so far. In this regard, KEPCO has recognized the needs of information management system to manage nuclear power information and proceeded the implementation of nuclear power information management system for export-model

  2. New nuclear technology; International developments. Review 1995; Ny kaernteknik; Utvecklingsinsatser internationellt. Sammanfattning och oeversikt 1995

    Energy Technology Data Exchange (ETDEWEB)

    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.

  3. Energy conservation technologies based on thermodynamic principles

    Energy Technology Data Exchange (ETDEWEB)

    Hirata, Masaru [Shibaura Institute of Technology of Technology, Tokyo (Japan)

    1996-12-31

    In order to reduce CO{sub 2} emission to prevent global warming, the most promising way for electric generation in the Northeast Asia is to introduce cogeneration and {open_quotes}repowering{close_quotes} technologies based on high temperature gas turbines fueled by natural gas. Especially the old type coal burning boiler-steam turbine plants should be retrofit by introducing gas turbines to become highly efficient combined cycle. Same technologies should be applied to the old garbage incineration plants and/or even to the nuclear power plants. The exhaust heat or steam should become much increased and it should be utilized as the process heat for industries or heat supply as the distinct heating or cooling for residential area. This paper introduces a brief survey of these new technologies.

  4. High Energy Nuclear Database: A Testbed for Nuclear Data Information Technology

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D A; Vogt, R; Beck, B; Pruet, J

    2007-04-18

    We describe the development of an on-line high-energy heavy-ion experimental database. When completed, the database will be searchable and cross-indexed with relevant publications, including published detector descriptions. While this effort is relatively new, it will eventually contain all published data from older heavy-ion programs as well as published data from current and future facilities. These data include all measured observables in proton-proton, proton-nucleus and nucleus-nucleus collisions. Once in general use, this database will have tremendous scientific payoff as it makes systematic studies easier and allows simpler benchmarking of theoretical models for a broad range of experiments. Furthermore, there is a growing need for compilations of high-energy nuclear data for applications including stockpile stewardship, technology development for inertial confinement fusion, target and source development for upcoming facilities such as the International Linear Collider and homeland security. This database is part of a larger proposal that includes the production of periodic data evaluations and topical reviews. These reviews would provide an alternative and impartial mechanism to resolve discrepancies between published data from rival experiments and between theory and experiment. Since this database will be a community resource, it requires the high-energy nuclear physics community's financial and manpower support. This project serves as a testbed for the further development of an object-oriented nuclear data format and database system. By using ''off-the-shelf'' software tools and techniques, the system is simple, robust, and extensible. Eventually we envision a ''Grand Unified Nuclear Format'' encapsulating data types used in the ENSDF, ENDF/B, EXFOR, NSR and other formats, including processed data formats.

  5. Planning nuclear energy centers under technological and demand uncertainty

    Energy Technology Data Exchange (ETDEWEB)

    Meier, P.M.; Palmedo, P.F.

    1976-01-01

    The question considered is whether new nuclear power plants should be located in nuclear energy centers, or ''power parks'' with co-located fabrication and reprocessing facilities. That issue has been addressed in a recent study by the Nuclear Regulatory Commission and remains under investigation at Brookhaven and elsewhere. So far, however, the advisability of this policy has been analyzed primarily within the framework of a single view of the future. Suggestions of the types of questions that should be asked regarding this policy if it is properly to be viewed as an example of decision making under uncertainty are made. It is concluded that ''A consideration of the various uncertainties involved in the question of dispersed vs. remote siting of energy facilities introduces a number of new elements into the analysis. On balance those considerations provide somewhat greater support for the clustered concept. The NEC approach seems to provide somewhat greater flexibility in accomodating possible future electricity generating technologies. Increased regulatory and construction efficiencies possible in an NEC reduces the impact of demand uncertainty as does the lower costs associated with construction acceleration or deceleration.'' It is also noted that, in the final analysis, ''it is the public's perception of the relative costs and benefits of a measure that determine the acceptability or unacceptability of a particular innovation,'' not the engineer's cost/benefit analysis. It is further noted that if the analysis can identify limits on analytical methods and models, it will not make the job of energy decision-making any easier, but it may make the process more responsive to its impact on society. (MCW)

  6. Proceedings of the nuclear criticality technology safety project

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  7. Science and technology with nuclear tracks in solids

    CERN Document Server

    Buford-Price, P

    2005-01-01

    Fission track dating has greatly expanded its usefulness to geology over the last 40 years. It is central to thermochronology—the use of shortened fission tracks to decipher the thermal history, movement, and provenance of rocks. When combined with other indicators, such as zircon color and (U–Th)/He, a range of temperatures from C to C can be studied. Combining fission track analysis with cosmogenic nuclide decay rates, one can study landscape development and denudation of passive margins. Technological applications have expanded from biological filters, radon mapping, and dosimetry to the use of ion track microtechnology in microlithography, micromachining by ion track etching, microscopic field emission tips, magnetic nanowires as magnetoresistive sensors, microfluidic devices, physiology of ion channels in single cells, and so on. In nuclear and particle physics, relatively insensitive glass detectors have been almost single-handedly responsible for our knowledge of cluster radioactivity, and plastic ...

  8. Atomistic molecular point of view for liquid lead and lithium in Nuclear Fusion technology

    Energy Technology Data Exchange (ETDEWEB)

    Fraile, A. [Instituto de Fusión Nuclear, ETSI Industriales, Universidad Politécnica de Madrid, José Gutierrez Abascal, 2, 28006 Madrid (Spain); Cuesta-López, S., E-mail: scuesta@ubu.es [Universidad de Burgos, Parque Científico I-D-I, Plaza Misael Bañuelos s/n, 09001 Burgos (Spain); Iglesias, R. [Universidad de Oviedo, Departamento de Física, Calvo Sotelo s/n, 33007 Oviedo (Spain); Caro, A. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Perlado, J.M. [Instituto de Fusión Nuclear, ETSI Industriales, Universidad Politécnica de Madrid, José Gutierrez Abascal, 2, 28006 Madrid (Spain)

    2013-09-15

    Understanding the behavior and properties of liquid metals is a crucial milestone in different current Nuclear Technology developments. Extracting both structural and dynamical properties of liquid metals via Molecular Dynamics simulations, represents a strong pillar for multiscale modeling efforts aiming to understand the suitability of these compounds. Here we present first results on the validation of two semi-empirical potentials for Li and Pb in liquid phase. Our results establish a solid base as a previous, but crucial step, to implement a LiPb cross potential. Structural and thermodynamical analyses confirm that the analyzed potentials for Li and Pb are sufficiently accurate to simulate both elements in the liquid phase, and in conditions of interest for Nuclear Technology.

  9. Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Staiger, Merle Daniel; M. C. Swenson

    2005-01-01

    This report documents an inventory of calcined waste produced at the Idaho Nuclear Technology and Engineering Center during the period from December 1963 to May 2000. The report was prepared based on calciner runs, operation of the calcined solids storage facilities, and miscellaneous operational information that establishes the range of chemical compositions of calcined waste stored at Idaho Nuclear Technology and Engineering Center. The report will be used to support obtaining permits for the calcined solids storage facilities, possible treatment of the calcined waste at the Idaho National Engineering and Environmental Laboratory, and to ship the waste to an off-site facility including a geologic repository. The information in this report was compiled from calciner operating data, waste solution analyses and volumes calcined, calciner operating schedules, calcine temperature monitoring records, and facility design of the calcined solids storage facilities. A compact disk copy of this report is provided to facilitate future data manipulations and analysis.

  10. Study on the Promotion in the Citation of the Nuclear Engineering and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Young Choon; Yoo, J. B.; Yi, J. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    The Korean journal published in English, Nuclear Engineering and Technology (here under NET) has been enlisted in the global citation database SCI E(Science Citation Index Expanded) of Thomson Reuters (past ISI), beginning with NET vol.39 No.1 (Feb. 2007). As of July 2009, the citation index of NET as reported by JCR (Journal Citation Report) based on the cumulative data from ISI (Institute for Scientific Information) reached to 0.991. This index ranks on 12{sup th} among the 33 journals in the area of nuclear science and technology in the science and technology covered by JCR, meaning fairly high impact factor. The following year 2010, however, witnessed the JCR figure dropping down to 0.465. The reason behind such drastic fall would be the decreased citation and in a lesser extent self-citation in 2010, in comparison with 2009, despite the increased number of paper publication. This study attempts to give an analysis as of the end of 2011 on the NET citation frequency in SCI Source Journal and the citation frequency by KAERI authors, together with the nationalities of NET authors and SCI journals that refer to NET most. Based on the analysis, the paper suggests some ways to promoting the position of NET as a journal in the international nuclear sector

  11. Molecular–Genetic Imaging: A Nuclear Medicine–Based Perspective

    Directory of Open Access Journals (Sweden)

    Ronald G. Blasberg

    2002-07-01

    Full Text Available Molecular imaging is a relatively new discipline, which developed over the past decade, initially driven by in situ reporter imaging technology. Noninvasive in vivo molecular–genetic imaging developed more recently and is based on nuclear (positron emission tomography [PET], gamma camera, autoradiography imaging as well as magnetic resonance (MR and in vivo optical imaging. Molecular–genetic imaging has its roots in both molecular biology and cell biology, as well as in new imaging technologies. The focus of this presentation will be nuclear-based molecular–genetic imaging, but it will comment on the value and utility of combining different imaging modalities. Nuclear-based molecular imaging can be viewed in terms of three different imaging strategies: (1 “indirect” reporter gene imaging; (2 “direct” imaging of endogenous molecules; or (3 “surrogate” or “bio-marker” imaging. Examples of each imaging strategy will be presented and discussed. The rapid growth of in vivo molecular imaging is due to the established base of in vivo imaging technologies, the established programs in molecular and cell biology, and the convergence of these disciplines. The development of versatile and sensitive assays that do not require tissue samples will be of considerable value for monitoring molecular–genetic and cellular processes in animal models of human disease, as well as for studies in human subjects in the future. Noninvasive imaging of molecular–genetic and cellular processes will complement established ex vivo molecular–biological assays that require tissue sampling, and will provide a spatial as well as a temporal dimension to our understanding of various diseases and disease processes.

  12. Nuclear Technology Series. Course 20: Radiation Monitoring Techniques (Radiochemical).

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  13. Nuclear Technology Series. Course 2: Radiation Protection I.

    Science.gov (United States)

    Technical Education Research Center, Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  14. Nuclear Technology Series. Course 13: Power Plant Chemistry.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  15. Nuclear Technology Series. Course 17: Radiation Protection II.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  16. Nuclear Technology Series. Course 11: Radiation Detection and Measurement.

    Science.gov (United States)

    Technical Education Research Center, Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  17. Nuclear Technology Series. Course 15: Metallurgy and Metals Properties.

    Science.gov (United States)

    Technical Education Research Center, Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  18. Nuclear Technology Series. Course 21: Radioactive Materials Disposal and Management.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  19. Nuclear Technology Series. Course 25: Radioactive Material Handling Techniques.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  20. Home-based Healthcare Technology

    DEFF Research Database (Denmark)

    Verdezoto, Nervo

    of these systems target a specific treatment or condition and might not be sufficient to support the care management work at home. Based on a case study approach, my research investigates home-based healthcare practices and how they can inform future design of home-based healthcare technology that better account...

  1. Intelligent control and automation technology for nuclear application

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hee; Eom, Heung Sub; Kim, Ko Ryu; Lee, Jae Cheol; Choi, You Rak; Lee, Soo Cheol [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    Using recent technologies on a mobile robot and computer science, we developed an automatic inspection system for weld lines of the reactor pressure vessel. The ultrasonic inspection of the reactor pressure vessel is currently performed by commercialized robot manipulators. Since, however, the conventional fixed type robot manipulator is very huge, heavy and expensive, it needs long inspection time and is hard to handle and maintain. In order to resolve these problems, we developed a new inspection automation system using a small mobile robot crawling on the vertical wall. According to the conceptual design studied in the first year, we developed the inspection automation system including an underwater inspection robot, a laser position control subsystem and a main control subsystem. And we carried out underwater experiments on the reactor vessel mockup. After finishing this project successfully, we have a plan to commercialize our inspection system. Using this system, we can expect much reduction of the inspection time, performance enhancement, automatic management of inspection history, etc. In the economic point of view, we can also expect import substitution more than 5 million dollars. The established essential technologies for intelligent control and automation are expected to be synthetically applied to the automation of similar systems in nuclear power plants. 4 tabs., 37 figs., 6 refs. (Author).

  2. Cooperation of nuclear manpower development between Viet Nam and Korea in order to enhance establishment of infrastructure in exporting nuclear technology to Viet Nam

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Park, J. K.; Kim, Y. T.; Nam, Y. M.; Jang, Y. H.; Yang, M. H

    2003-08-15

    Through this project, KAERI provided OJT Programme to 3 nuclear experts of Viet Nam at the KAERI for 3 months as a cooperation of human resource development in the field of nuclear policy, nuclear safety analysis and thermo hydraulic. We could have publicity activities of S/W and H/W then achieve an advantage position of economical and technical in exporting nuclear technology to Viet Nam. Also we have provided a training course and seminar for a high-level delegation of nuclear policy decision makers, which is consisted of 5 deputy ministers and general directors of Viet Nam in Korea. Thus we could have Vietnamese who are favoring Korea. The KAERI will also prepare a data base of trained Vietnamese in Korea for the maximum utilization of them in cooperating with Viet Nam. We accomplished the cooperation of human resource development and providing program and curriculum of the nuclear education and training in Viet Nam. Furthermore, it is expected that the enhancement of nuclear technical cooperation between Viet Nam and Korea and the nuclear human resource development.

  3. Application of Radiation Chemistry to Some Selected Technological Issues Related to the Development of Nuclear Energy.

    Science.gov (United States)

    Bobrowski, Krzysztof; Skotnicki, Konrad; Szreder, Tomasz

    2016-10-01

    The most important contributions of radiation chemistry to some selected technological issues related to water-cooled reactors, reprocessing of spent nuclear fuel and high-level radioactive wastes, and fuel evolution during final radioactive waste disposal are highlighted. Chemical reactions occurring at the operating temperatures and pressures of reactors and involving primary transients and stable products from water radiolysis are presented and discussed in terms of the kinetic parameters and radiation chemical yields. The knowledge of these parameters is essential since they serve as input data to the models of water radiolysis in the primary loop of light water reactors and super critical water reactors. Selected features of water radiolysis in heterogeneous systems, such as aqueous nanoparticle suspensions and slurries, ceramic oxides surfaces, nanoporous, and cement-based materials, are discussed. They are of particular concern in the primary cooling loops in nuclear reactors and long-term storage of nuclear waste in geological repositories. This also includes radiation-induced processes related to corrosion of cladding materials and copper-coated iron canisters, dissolution of spent nuclear fuel, and changes of bentonite clays properties. Radiation-induced processes affecting stability of solvents and solvent extraction ligands as well oxidation states of actinide metal ions during recycling of the spent nuclear fuel are also briefly summarized.

  4. Nuclear technology in secondary school in the city of Sao Paulo

    Energy Technology Data Exchange (ETDEWEB)

    Benites, Daniela B.; Gordon, Ana Maria P.L. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: dbenites@ipen.br, e-mail: amgordon@ipen.br

    2009-07-01

    Nowadays, much has been said about nuclear technology development in Brazil. The importance of introducing the nuclear energy in the Brazilian energetic matrix has been now recognized by the society. There is a highly accepted assertion about the role developed by the energy offer for the country development, although it is wellknown that this is a necessary condition, but not enough. Another major issue is the environment preservation, so that future generations may live in adequate climatic and environmental conditions. Industrial activities and mining are some of the issues debated in the world scenario. Therefore the option to introduce nuclear energy in the country energetic matrix is a decision that should be supported by its knowledge. Nevertheless, do the youth know what nuclear energy is? What this kind of technology applications and implications are? To answer these questions, this project aims to analyze to what extent secondary schools are aware of nuclear technology and its applications, to verify whether there are the minimal necessary conditions for their interpretation and comprehension of related phenomena, as well as to analyze whether these students are able to critically opine on this subject. The methodology consists in using, as a data collection tool, a questionnaire applied to the students. For this purpose, the research field is constituted of the third year secondary school students, from public state schools, in the city of Sao Paulo. The data survey was restricted to schools belonging to three levels of classification, in the National Examination of Secondary Schools 2007. The questions proposed in the questionnaire were elaborated in considering what students, according to their age, were supposed to know concerning nuclear technology having as reference the 'Leis de Diretrizes e Bases da Educacao Nacional' (National Education Guidance Law), the 'Parametros Curriculares Nacionais' (National Curricula Parameters) and

  5. An Overview of Comprehensive Inspection Technologies Under Investigation at Legacy Underground Nuclear Test Sites

    Science.gov (United States)

    Chipman, V.; Emer, D. F.; Townsend, M.; Drellack, S.

    2013-12-01

    Comprehensive Inspection Technologies (CIT) under investigation include methods that might be of use in detecting a clandestine underground nuclear test. These include techniques for detecting noble gases, visual observation methods, hyperspectral imaging, controlled- and passive-source seismic surveys, and other geophysical methods. Noble gas detection studies include a series of experiments called the Noble Gas Migration (NGM) experiments, that explore the fundamental parameters that determine the capability to detect radioxenon isotopes and 37Ar produced in underground nuclear tests. These isotopes are of interest to both the International Monitoring System (IMS) global monitoring and On-Site Inspection (OSI) regimes. Through a unique combination of field experiments, sampling of radioactive noble gas from a legacy underground nuclear test, large-scale hydrogeologic computer simulations, and a regimen involving carefully designed field-sampling techniques, the experiments are providing information about the production, release, and sampling challenges that determine the ability to detect these two important noble gases. Other CIT experiments explore and validate geophysical (controlled-source and passive-source seismic, gravity, electrical, magnetic, etc.) and optical techniques (both visual and instrument-based) that greatly enhance the understanding of the efficiency of these techniques for OSI, including how to better integrate the various technologies with each other and individually at different physical scales. This work was done by National Security Technologies, LLC, under Contract No. DE-AC52-06NA25946 with the U.S. Department of Energy. DOE/NV/25936--1840.

  6. Measurements of nuclear data and possibility to construct the nuclear data production facility based on electron linac

    Energy Technology Data Exchange (ETDEWEB)

    Namkung, Won; Ko, In Soo; Cho, Moo Hyun; Kim, Gui Nyun; Lee, Young Seok; Kang, Heung Sik [Pohang University of Science and Technology, Pohang(Korea)

    2001-04-01

    In order to construct an infrastructure to produce nuclear data, we studied three main items; (1) Study on the possibility to construct a facility for nuclear data production, (2) Production of nuclear data for nuclear power plant, and (3) Pulsed neutron source based on a 100-MeV electron linac at Pohang Accelerator Laboratory (PAL). We confirmed the possibility to build a nuclear data production facility utilizing a 100-MeV electron linac at PAL and manpower who wanted to participate the nuclear data production experiments. In order to measure the nuclear data for nuclear power plant, we used several nuclear data production facilities in abroad. We measured total cross sections and neutron caprure cross sections for {sup nat}Dy and {sup nat}Hf using the pulsed neutron facility in the Research Reactor Institute, Kyoto University (KURRI). The neutron capture cross sections for {sup 161,162,163,164}Dy were measured at KURRI in the neutron energy region between 0.001 eV and several tens keV, and at the fast neutron facility in Tokyo Institute of Technology in the neutron energy region between 10 keV and 100 keV. We also measured the neutron capture cross sections and gamma multiplicity of {sup 232}Th at the IBR30 in Dubna, Russia. We have construct a pulsed neutron source using a 100-MeV electron linac at PAL. We measured neutron time-of-flight (TOF) spectra in order to check the characteristics of the pulsed neutron source. We also measured a neutron total cross sections of W and Cu. The pulsed neutron facility can be utilized in the education facility for nuclear data production and the test facility for the R and D purpose of the nuclear data production facility. 29 refs., 57 figs., 22 tabs. (Author)

  7. Technology of remote monitoring for nuclear activity monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Kwack, Ehn Ho; Kim, Jong Soo; Yoon, Wan Ki; Park, Sung Sik; Na, Won Woo; An, Jin Soo; Cha, Hong Ryul; Kim, Jung Soo

    2000-05-01

    In a view of safeguards monitoring at nuclear facilities, the monitoring is changing to remote method so that this report is described to remote monitoring(RM) applying on commercial NPP in Korea. To enhance IAEA safeguards efficiency and effectiveness, IAEA is taking into account of remote monitoring system(RMS) and testing as a field trial. IRMP(International Remote Monitoring Project) in participating many nations for development of RMS is proceeding their project such as technical exchange and research etc. In case of our country are carrying out the research relevant RM since acceptance RMS at 7th ROK-IAEA safeguards implementation review meeting. With a view to enhancement the RMS, installation location and element technology of the RM equipment are evaluated in a view of safeguards in Korea LWRs, and proposed a procedure for national inspection application through remote data evaluation from Younggwang-3 NPP. These results are large valuable to use of national inspection at time point extending installation to all Korea PWR NPP. In case of CANDU, neutron, gamma measurement and basic concept of network using optical fiber scintillating detector as remote verification method for dry storage canister are described. Also RM basic design of spent fuel transfer campaign is described that unattended RM without inspector instead of performing in participating together with IAEA and national inspector. The transfer campaign means the spent fuel storage pond to dry storage canister for about two months every year. Therefore, positively participation of IAEA strength safeguards project will be increased transparency for our nuclear activity as well as contributed to national relevant industry.

  8. Design Features and Technology Uncertainties for the Next Generation Nuclear Plant

    Energy Technology Data Exchange (ETDEWEB)

    John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

    2004-06-01

    This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

  9. 科学家与公众对核能技术接受度的比较分析——以日本福岛核泄露事故为例%Comparative Analysis on the Acceptances of Nuclear Technology between Scientists and the Public:Based on the Case of Fukushima Nuclear Leak

    Institute of Scientific and Technical Information of China (English)

    郭跃; 汝鹏; 苏竣

    2012-01-01

    There is an ongoing debate about the use of nuclear energy all over the world.In March 2011,the Fukushima Nuclear leak made the international society reconsider the security and extensibility of nuclear technology.The extents to which scientists and the public accept nuclear technology differs distinctly.This paper deeply analyzes the acceptances of nuclear energy technology after Fukushima nuclear leak between scientists and the public and their difference.Then the reasons for this difference are discussed from the perspective of determinants.Finally,this paper proposes several policy suggestions about the strategy for the future nuclear energy development in China.%核能技术的应用历来在各国存在广泛争议。2011年3月的福岛核泄漏事故再度引发国际社会对核能技术安全性与可推广性的关注,并争论不休。在福岛核泄漏事故中,科学家与公众对核能技术的接受度表现出明显的差异。分析了福岛核泄漏事故中科学家与公众对核能技术的接受度,从决定因素的角度探讨了造成科学家与公众对核能技术的接受度差异的原因,并对我国未来的核能发展战略提出政策建议。

  10. Sustainable and safe nuclear fission energy technology and safety of fast and thermal nuclear reactors

    CERN Document Server

    Kessler, Günter

    2012-01-01

    Unlike existing books of nuclear reactor physics, nuclear engineering and nuclear chemical engineering this book covers a complete description and evaluation of nuclear fission power generation. It covers the whole nuclear fuel cycle, from the extraction of natural uranium from ore mines, uranium conversion and enrichment up to the fabrication of fuel elements for the cores of various types of fission reactors. This is followed by the description of the different fuel cycle options and the final storage in nuclear waste repositories. In addition the release of radioactivity under normal and possible accidental conditions is given for all parts of the nuclear fuel cycle and especially for the different fission reactor types.

  11. Nuclear facilities: repair and replacement technologies; Installations nucleaires: technologies de reparation et de remplacement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The oldest operating reactors are more than 35 years old and are now facing major maintenance operations. The first replacement of a pressurizer took place in autumn 2005 at the St-Lucie plant (Usa) while steam generators have been currently replaced since 1983. Nuclear industry has to adapt to this new market by proposing innovative technological solutions in the reactor maintenance field. This document gathers the 9 papers presented at the conference. The main improvements concern repair works on internal components of PWR-type reactors, the replacement of major components of the primary coolant circuit and surface treatments to limit the propagation of damages. The first paper shows that adequate design and feedback experience are good assets to manage the ageing of a nuclear unit. Another paper shows that a new repair method of a relief valve can avoid its replacement. (A.C.)

  12. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    Generally speaking, robotic technologies are anticipated to be very useful for hazardous works in nuclear facilities because robotic systems are relatively immune to radiation exposure. But the application of robotic systems for such environments has not been increasing during past 20 years. Applying highly reliable and conservative 'defense in depth' concepts in the design and construction of NPPs, there is very little probability of accidents occurring or radioactive materials being released into the environments. As a precaution, however NPPs are prepared with emergency response procedures and routinely conduct exercises for post accident circumstances based on these procedures. The last year's accident at the Fukushima Daiichi nuclear power plant promotes the needs for remote response technologies based on mobile robotic system to recognize the internal status and mitigate the unanticipated events of nuclear power plants in emergency situations. For initial observation of reactor buildings two robots named 'PackBot' were used because the internal conditions were unknown so as to allow human workers for entrance into the reactor building. But there were severe limitations for the robots to perform the given tasks from various obstacles and poor visibility inside though they provided crucial information such as views of internal structures, dose level and temperature that supported the decision for human worker's entrance. The application of robots for emergency response tasks for post accidents in nuclear facilities is not a new concept. Robots were sent to recover the damaged reactor at Chernobyl where human workers could have received a lifetime dose of radiation in minutes. Based on NRC's TMI 2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. A robot was used for several years

  13. Design and Test Plans for a Non-Nuclear Fission Power System Technology Demonstration Unit

    Science.gov (United States)

    Mason, Lee; Palac, Donald; Gibson, Marc; Houts, Michael; Warren, John; Werner, James; Poston, David; Qualls, Arthur Lou; Radel, Ross; Harlow, Scott

    2012-01-01

    A joint National Aeronautics and Space Administration (NASA) and Department of Energy (DOE) team is developing concepts and technologies for affordable nuclear Fission Power Systems (FPSs) to support future exploration missions. A key deliverable is the Technology Demonstration Unit (TDU). The TDU will assemble the major elements of a notional FPS with a non-nuclear reactor simulator (Rx Sim) and demonstrate system-level performance in thermal vacuum. The Rx Sim includes an electrical resistance heat source and a liquid metal heat transport loop that simulates the reactor thermal interface and expected dynamic response. A power conversion unit (PCU) generates electric power utilizing the liquid metal heat source and rejects waste heat to a heat rejection system (HRS). The HRS includes a pumped water heat removal loop coupled to radiator panels suspended in the thermal-vacuum facility. The basic test plan is to subject the system to realistic operating conditions and gather data to evaluate performance sensitivity, control stability, and response characteristics. Upon completion of the testing, the technology is expected to satisfy the requirements for Technology Readiness Level 6 (System Demonstration in an Operational and Relevant Environment) based on the use of high-fidelity hardware and prototypic software tested under realistic conditions and correlated with analytical predictions.

  14. Biophysics at the intersection of health science and nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Marquardt, D. [Brock Univ., Dept. of Physics, St. Catharines, Ontario (Canada); Alsop, R.J.; Rheinstadter, M.C. [McMaster Univ., Dept. of Physics and Astronomy, Hamilton, Ontario (Canada); Harroun, T.A. [Brock Univ., Dept. of Physics, St. Catharines, Ontario (Canada)

    2014-12-15

    We're all on a quest for improved heart health, but what do we really know about it? A daily regimen of aspirin can help some people with heart disease. We need to lower our cholesterol, and increase our intake of omega fatty acids. There is simply no health benefit to taking extra vitamin E, and it's not known why. Apart from cardiac tests with radiopharmaceuticals, what role does nuclear technology play in this story? It turns out that cold and thermal neutrons are important tools for the biophysicists studying these topics. We will review some recently published studies that are advancing our understanding of how cholesterol, vitamin E, and aspirin all work at the molecular level, inside the membrane of our cells. These insights could not have been learned without access to research reactor neutron beams such as those at the Canadian Neutron Beam Centre, and how this new knowledge has really engaged the broader health science community into new ways of thinking about these molecules. (author)

  15. Biophysics at the intersection of health science and nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Marquardt, D., E-mail: thad.harroun@brocku.ca [Brock Univ., Dept. of Physics, St. Catherines, Ontario (Canada); Alsop, R.J.; Rheinstadter, M.C. [McMaster Univ., Dept. of Physics and Astronomy, Hamilton, Ontario (Canada); Harroun, T.A. [Brock University, Dept. of Physics, St. Catherines, Ontario (Canada)

    2014-07-01

    We're all on a quest for improved heart health, but what do we really know about it? A daily regimen of aspirin can help some people with heart disease. We need to lower our cholesterol, and increase our intake of omega fatty acids. There is simply no health bene t to taking extra vitamin E, and it's not known why. Apart from cardiac tests with radiopharmaceuticals, what role does nuclear technology play in this story? It turns out that cold and thermal neutrons are important tools for the biophysicists studying these topics. We will review some recently published studies that are advancing our understanding of how cholesterol, vitamin E, and aspirin all work at the molecular level, inside the membrane of our cells. These insights could not have been learned without access to research reactor neutron beams such as those at the Canadian Neutron Beam Centre, and how this new knowledge has really engaged the broader health science community into new ways of thinking about these molecules. (author)

  16. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Song, Sung Jin; Kim, Young Hwan; Shin, Hyun Jae [Sungkwunkwan Univ., Seoul (Korea, Republic of); Lee, Hyang Beom [Soongsil Univ., Seoul (Korea, Republic of); Shin, Young Kil [Kunsan National Univ., Gunsan (Korea, Republic of); Chung, Hyun Jo [Wonkwang Univ., Iksan (Korea, Republic of); Park, Ik Keun; Park, Eun Soo [Seoul National University of Technology, Seoul (Korea, Republic of)

    2001-03-15

    Retaining reliabilities of nondestructive testing is essential for the life-time maintenance of nuclear power plant. In order to Improve reliabilities of ultrasonic testing and eddy current testing, the following five subjects were carried out in this study: development of BEM analysis technique for ECT of SG tube, development of neural network technique for the intelligent analysis of ECT flaw signals of SG tubes, development of RFECT technology for the inspection of SG tube, FEM analysis of ultrasonic scattering field and evaluation of statistical reliability of PD-RR test of ultrasonic testing. As results, BEM analysis of eddy current signal, intelligent analysis of eddy current signal using neural network, and FEM analysis of remote field eddy current testing have been developed for the inspection of SG tubes. FEM analysis of ultrasonic waves in 2-dimensional media and evaluation of statistical reliability of ultrasonic testing with PD-RR test also have been carried out for the inspection of weldments. Those results can be used to Improve reliability of nondestructive testing.

  17. Technology base for microgravity horticulture

    Science.gov (United States)

    Sauer, R. L.; Magnuson, J. W.; Scruby, R. R.; Scheld, H. W.

    1987-01-01

    Advanced microgravity plant biology research and life support system development for the spacecraft environment are critically hampered by the lack of a technology base. This inadequacy stems primarily from the fact that microgravity results in a lack of convective currents and phase separation as compared to the one gravity environment. A program plan is being initiated to develop this technology base. This program will provide an iterative flight development effort that will be closely integrated with both basic science investigations and advanced life support system development efforts incorporating biological processes. The critical considerations include optimum illumination methods, root aeration, root and shoot support, and heat rejection and gas exchange in the plant canopy.

  18. International academic program in technologies of light-water nuclear reactors. Phases of development and implementation

    Science.gov (United States)

    Geraskin, N. I.; Glebov, V. B.

    2017-01-01

    The results of implementation of European educational projects CORONA and CORONA II dedicated to preserving and further developing nuclear knowledge and competencies in the area of technologies of light-water nuclear reactors are analyzed. Present article addresses issues of design and implementation of the program for specialized training in the branch of technologies of light-water nuclear reactors. The systematic approach has been used to construct the program for students of nuclear specialties, which corresponding to IAEA standards and commonly accepted nuclear principles recognized in the European Union. Possibilities of further development of the international cooperation between countries and educational institutions are analyzed. Special attention is paid to e-learning/distance training, nuclear knowledge preservation and interaction with European Nuclear Education Network.

  19. Nuclear Safety in A Post-Fukushima ERDA: Moving Forward with smart Mobile Technology

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J. H. [PHILOSOPHIA, Seoul (Korea, Republic of); Suh, K. Y. [Seoul National Univ., Seoul (Korea, Republic of)

    2012-03-15

    . Experienced workers can support remote learners. One can obtain the various LOCAity information with the GNPs technology. One can glimpse the electric cable or piping behind the wall through handy cameras and gain mechanical specification or manual for them. High performance mobile devices can show high resolution, three-dimensional (3D) virtual reality (VR) contents. The NPP operators can train themselves with full 3D VR emergency program installed in their smart mobile device. The NPP smart device system makes it possible for operators to gate information about the real time distribution of the radioactivity so that they can manage the source term by accessing to the main control system. Also, complex calculational simulation such as severe accident and thermohydraulic analyses can be made on the smart mobile devices. As such, the smart mobile technology possesses unlimited potential to improve nuclear power industry combining various functional ideas. This technology should inexorably speed up the development of nuclear power industry and enhance market competitiveness. All these innovative wonders should, however, be supported by the security policy for information network. This technology is based on the strong network technology. These has recently been a NPP hacking accident in the U. S. The same kind of accident is deemed possible in Korea by North Korean hackers. The Republic of Korea ought first to be equipped with powerful technology and policies for network security so as to safely move forward with the smart mobile technology with immeasurable potential.

  20. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Opening address

    Energy Technology Data Exchange (ETDEWEB)

    Gueldner, Ralf [Deutsches Atomforum e.V. (DAtF), Berlin (Germany)

    2016-06-15

    The 47{sup th} Annual Meeting on Nuclear Technology (AMNT 2016) was an excellent opportunity for a comprehensive outlook on nuclear technology, fostering international exchange in industry, research, politics and administration. Ralf Gueldner, President of the German Atomic Forum (DAtF) talked about important decisions in nuclear energy in Germany in 2016. Finally, Gueldner noticed that even with a phase out, Germany needs nuclear expertise and competent people for the upcoming challenges and international cooperation. In this context, also publicly-financed education and research are indispensable.

  1. Nuclear technology in research and everyday life; Kerntechnik in Forschung und Alltag

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-12-15

    The paper.. discusses the impact of nuclear technology in research and everyday life covering the following issues: miniaturization of memory devices, neutron radiography in material science, nuclear reactions in the universe, sterilization of food, medical applies, cosmetics and packaging materials using beta and gamma radiation, neutron imaging for radioactive waste analysis, microbial transformation of uranium (geobacter uraniireducens), nuclear technology knowledge preservation, spacecrafts voyager 1 and 2, future fusion power plants, prompt gamma activation analysis in archeology, radiation protection and radioecology and nuclear medicine (radiotherapy).

  2. Current Status of World Nuclear Fuel Cycle Technology (I): Canada and Latin America

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hang Bok; Ko, Won Il

    2007-05-15

    Canada produces about one third of the world's uranium mine output, most of it from two new mines. After 2007 Canadian production is expected to increase further as more new mines come into production. About 15% of Canada's electricity comes from nuclear power, using indigenous technology, and 18 reactors provide over 12,500 MWe of power. Mexico has two nuclear reactors generating almost 5% of its electricity. Its first commercial nuclear power reactor began operating in 1989. There is some government support for expanding nuclear energy to reduce reliance on natural gas. Argentina has two nuclear reactors generating nearly one tenth of its electricity. Its first commercial nuclear power reactor began operating in 1974. Brazil has two nuclear reactors generating 4% of its electricity. Its first commercial nuclear power reactor began operating in 1982.

  3. A review on the status of development in thorium-based nuclear fuels

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Woo; Na, S. H.; Lee, Y. W.; Kim, H. S.; Kim, S. H.; Joung, C.Y

    2000-02-01

    Thorium as an alternative nuclear energy source had been widely investigated in the 1950s-1960s because it is more abundant than uranium, but the studies of thorium nuclear fuel cycle were discontinued by political and economic reasons in the 1970s. Recently, however, renewed interest was vested in thorium-based nuclear fuel cycle because it may generate less long-lived minor actinides and has a lower radiotoxicity of high level wastes after reprocessing compared with the thorium fuel cycle. In this state-of the art report, thorium-based nuclear cycle. In this state-of the art report, thorium-based nuclear fuel cycle and fuel fabrication processes developed so far with different reactor types are reviewed and analyzed to establish basic technologies of thorium fuel fabrication which could meet our situation. (author)

  4. 全球核科学和核技术发展现状及趋势%Progress and Developing Trend of Global Nuclear Science and Technology

    Institute of Scientific and Technical Information of China (English)

    沈欣媛

    2015-01-01

    国际原子能机构(International Atomic Energy Agency, IAEA)认为,2014年全球核技术发展主要集中在动力应用、原子数据和核数据、加速器和研究堆应用以及非动力应用这四大领域.本文从上述四个方面,对2014年以来全球在核科学与技术方面所取得的主要进展进行概括与阐述.认为全球核能发展暂时仍未能脱离调整阶段,我国科技界和管理部门可重点关注核技术的非动力应用.%Nuclear technology refers to a modern high technology, based on nuclear properties, nuclear reactions, nuclear effects and nuclear spectroscopy, using reactors, accelerators, radiation and nuclear radiation detectors as tools. As a clean energy source, nuclear energy has many advantages such as low-emission, high fuel energy density, and low cost etc. Many countries regarded nuclear power as an effective way to meet electricity demand growth, energy security, as well as to deal with climate change. On the other hand, as another major application ifeld of nuclear technology, non-power applications of nuclear technology is also very active in the ifelds of isotope hydrology, cancer prevention and control, climate change, and marine environment. International Atomic Energy Agency(IAEA) indicates that since 2014, the major developments of the world's nuclear technology focused on the areas of power applications, atomic and nuclear data, accelerator and research reactor, and non-power applications. This paper elaborates the world's major progress in nuclear science and technology from the four aspects mentioned above.

  5. Cooperative technological innovation and competitiveness in the nuclear arena; Innovacion tecnologica cooperativa y competitividad en el ambito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Castro Galvan, A.; Marco Pelegrin, M.; Salve Galiana, R.; Vallejo Haya, J.; Tagle Gonzalez, J. A.

    2000-07-01

    R and D and, more recently, technological innovation and its relationship with competitivity are more and more part of conferences, books, articles and political speeches and very often are the central part of them. Innovation has become fashionable and many initiatives have come out in connection with it. However, the relationship between technological innovation and competitivity are not always obvious. The current article intends to illustrate some mechanisms that link these two concepts through a specific case, DTN, that is already providing results for the Spanish nuclear industry and whose example can be extrapolated to other industrial sectors. The importance given by the nuclear to the innovation, the research and the technological development it is not new either exclusively belong to any specific organisation but makes evident the coherence between its traditional approach and the current idea of modernizing the country promoting the national technological capacity. (Author)

  6. Detection of Nuclear Weapons and Materials: Science, Technologies, Observations

    Science.gov (United States)

    2010-06-04

    between Z=57 (lanthanum) and Z=72 ( hafnium ), inclusive, are very rare in commerce, making 72 a reasonable boundary between high Z and lower Z elements...materials used in nuclear weapons of other nations (e.g., for alloys ) for purposes of nuclear forensics. (2) Another task is to develop the algorithms

  7. Nuclear power program and technology development in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung-Oke

    1994-12-31

    KEPCO has successfully implemented the construction and operation of nuclear power plants since the early 1970s, and will continue to build safer and more efficient nuclear plants in the future in accordance with the nuclear power development plan previously established. KEPCO will also make every effort to enhance nuclear safety and obtain the public`s acceptance for nuclear power. We are, however, facing the same difficulties, as United States and other countries have, in strengthened regulatory requirements, public acceptance, radwaste disposal, and acquisition of new plant sites despite an active nuclear power program. Story of Ted Turner, CNN; {open_quotes}It ain`t as easy as it looks.{close_quotes} Yes! It is difficult. But we will cope with these issues so that we can promote the nuclear power development and continue to supply a highly economical and clean energy to the world. In this regard, it is my sincere wish that each organization participating in the nuclear industry, especially Korea and United States strengthen their ties and help each other so that we together can successfully accomplish our goals.

  8. Study on Seal Technology for Nuclear Material Control

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    The seals have important application in nuclear safeguards, and are designed to record unauthorizedaccess or entry to inspected material and equipment. They can provide assurance for the continuity andintegrity of nuclear material accountancy. It is very useful to improve the inspection efficiency by means

  9. 1st International Nuclear Science and Technology Conference 2014 (INST2014)

    Science.gov (United States)

    2015-04-01

    Nuclear technology has played an important role in many aspects of our lives, including agriculture, energy, materials, medicine, environment, forensics, healthcare, and frontier research. 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. INST has evolved from a series of national conferences in Thailand called Nuclear Science and Technology (NST) Conference, which has been held for 11 times, the first being in 1986. INST2014 was held in August 2014 and hosted by Thailand Institute of Nuclear Technology (TINT). The theme was "Driving the future with nuclear technology". The conference working language was English. The proceedings were peer reviewed and considered for publication. The topics covered in the conference were: • Agricultural and food applications [AGR] • Environmental applications [ENV] • Radiation processing and industrial applications [IND] • Medical and nutritional applications [MED] • Nuclear physics and engineering [PHY] • Nuclear and radiation safety [SAF] • Other related topics [OTH] • Device and instrument presentation [DEV] Awards for outstanding oral and poster presentations will be given to qualified students who present their work during the conference.

  10. Analysis of Pending Problems for a Technology Demand of Domestic Operational Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Dae Seo; Park, Won Seok; Wi, Myung Hwan; Ha, Jae Joo

    2008-01-15

    Eleven technology fields were chosen, which have a relation with the solution of the pending problems of domestic operational nuclear power plants to manage an efficient operation and safe regulation for domestic nuclear power plants. The progressive background, requirements, and performance on the pending problems, 34, of an operation and regulation for domestic nuclear power plants were analyzed with regard to a risk information application, severe accident, PSR of structural materials, underwater monitoring, operation inspection and a fire protection, an instrument aging, metal integrity and steam generator, human technology and a digital I and C, quality assurance, secondary system and a user reliance and mass communications. KAERI's role is to provide a solution to these pending problems of domestic nuclear power plants. KAERI's technology is to be applicable to the pending problems for domestic nuclear power plants to raise an operational efficiency and an application frequency of nuclear power plants. In the future, a technology treaty between KAERI and KHNP is to be established to solve the pending problems for domestic nuclear power plants. Operation rate of nuclear power plants will also be raised and contribute to the supply of national energy due to this technology treaty.

  11. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  12. ARMS CONTROL: U.S. Efforts to Control the Transfer of Nuclear-Capable Missile Technology

    Science.gov (United States)

    2015-12-11

    risk of diversion is an important part of its analysis, Commerce focuses its reviews on certain countries that are developing nuclear-capable missiles...ogy to countries developing nuclear-capable missile systems. Our work was conducted in the United States at the Departments of State, Commerce , and...the MTCR in halting the transfer of MTCR-related systems and technology to countries developing nuclear-capable missile systems. The objectives, scope

  13. 2011 annual meeting on nuclear technology. Topical sessions. Pt. 5; Jahrestagung Kerntechnik 2011. Fachsitzungsberichte. T. 5

    Energy Technology Data Exchange (ETDEWEB)

    Fazio, Concetta [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany). Nuclear Safety Research Programme

    2011-12-15

    Summary report on the Topical Session of the Annual Conference on Nuclear Technology held in Berlin, 17 to 19 May 2011: - Sodium Cooled Fast Reactors. The reports on the Topical Sessions: - CFD-Simulations for Safety Relevant Tasks, - Final Disposal: From Scientific Basis to Application, - Characteristics of a High Reliability Organization (HRO) Considering Experience Gained from Events at Nuclear Power Stations, and - Nuclear Competence in Germany and Europe have been covered in atw 7, 8/9, 10 and 11 (2011). (orig.)

  14. Nuclear and clean coal technology options for sustainable development in India

    Energy Technology Data Exchange (ETDEWEB)

    Mallah, Subhash; Bansal, N.K. [Shri Mata Vaishno Devi University, Katra -182320, Jammu and Kashmir (India)

    2010-07-15

    Due to the growing energy needs along with increasing concerns towards control of greenhouse gas emissions, most developing countries are under pressure to find alternative methods for energy conversion and policies to make these technologies economically viable. Most of the energy is produced from fossil fuel in India which is not a sustainable source of energy. In this paper Indian power sector has been examined by using MARKAL model for introduction of clean coal and advanced nuclear technologies with implementation of energy conservation potential. The result shows that application of clean technologies gives energy security but not significant reduction in carbon dioxide emissions. When clean technologies apply with energy conservation a huge amount of CO{sub 2} can be reduced and also economically viable. Three scenarios including base case scenario have been developed to estimate the resource allocations and CO{sub 2} mitigation. The clean technologies with maximum savings potential shows 70% CO{sub 2} reduction in the year 2045. (author)

  15. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    John Collins

    2009-01-01

    This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

  16. Nuclear Technology Series. Radiation Protection Technician. A Suggested Program Planning Guide. Revised June 80.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This program planning guide for a two-year postsecondary radiation protection technician program is designed for use with courses 17-22 of thirty-five included in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians, and operators; and to assist planners,…

  17. Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    M. D. Staiger

    2007-06-01

    This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

  18. Nuclear Energy Enabling Technologies (NEET) Reactor Materials: News for the Reactor Materials Crosscut, May 2016

    Energy Technology Data Exchange (ETDEWEB)

    Maloy, Stuart Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Materials Science in Radiation and Dynamics Extremes

    2016-09-26

    In this newsletter for Nuclear Energy Enabling Technologies (NEET) Reactor Materials, pages 1-3 cover highlights from the DOE-NE (Nuclear Energy) programs, pages 4-6 cover determining the stress-strain response of ion-irradiated metallic materials via spherical nanoindentation, and pages 7-8 cover theoretical approaches to understanding long-term materials behavior in light water reactors.

  19. DUPIC nuclear fuel manufacturing and process technology development

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-05-01

    In this study, the DUPIC fuel fabrication technology for DUPIC pellet and element satisfying the standard specification was verified through (1) the improvement of fabrication technology and equipment, (2) remote operation of fuel manufacturing and inspection equipment installed at DFDF and (3) the study on the material properties of DUPIC fuel. The blending process was newly developed for making DUPIC powder composition homogeneous, and mixing process was added to the DUPIC process flow for fabricating crack-free pellets. A series of fabrication experiments were carried out in terms of various process conditions. Based on these experimental results, the optimal process flow and conditions for DUPIC fuel fabrication were established. 6 DUPIC elements and 6 mini-elements for irradiation test in HANARO was successfully fabricated using 7.4 kg of spent PWR fuel in 2000. The process qualification tests has been performed using 10 kg of spent PWR fuel since May 2001. The optimal DUPIC fuel fabrication process meeting AECL's quality requirements has been established and qualified. Quality assurance system for DUPIC fuel fabrication was also established in cooperation of AECL.

  20. New reactor technology: safety improvements in nuclear power systems.

    Science.gov (United States)

    Corradini, M L

    2007-11-01

    Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

  1. 2008 annual meeting on nuclear technology. Pt. 1. Section reports; JAHRESTAGUNG KERNTECHNIK 2008. T. 1. Sektionsberichte

    Energy Technology Data Exchange (ETDEWEB)

    Dagan, Ron; Sanchez Espinoza, Victor Hugo [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Reaktorsicherheit; Rohde, U.; Kliem, Soeren [Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany); Faber, Wolfgang; Berlepsch, Thilo v.; Spann, Holger [E.ON Kernkraft GmbH, Hannover (Germany); Schaffrath, Andreas [TUEV Nord SysTec GmbH und Co. KG, Hamburg (Germany); Schubert, Bernd [Vattenfall Europe Nuclear Energy GmbH, Hamburg (Germany); Rieger, Udo [Vattenfall Nuclear Energy GmbH, Hamburg (Germany); Christ,, Bernhard G. [NUKEM Technologies GmbH, Alzenau (Germany); Gulden, Werner [Fusion for Energy, Barcelona (Spain); Bogusch, Edgar [AREVA NP GmbH, Erlangen (Germany)

    2008-08-15

    Summary report on these 5 - out of 11 - Sections of the Annual Conference on Nuclear Technology held in Hamburg on May 27-29, 2008: - Reactor Physics and Methods of Calculation - Thermodynamics and Fluid Dynamics - Safety of Nuclear Installations - Methods, Analysis, Results - Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage - Fusion Technology. Other Sections will be covered in reports in further issues of atw. (orig.)

  2. Nuclear technology and knowledge management in radioprotection; Tecnologia nuclear y gestion del conocimiento en Radioproteccion

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, A.

    2007-07-01

    The cycle of life of nuclear power plant expands along seven well defined phases lasting about a century and therefore employing three successive generations. Each one of such phases is in need of specific knowledge on radiation protection matters. The nuclear moratorium introduced in Spain in 1983 suspended all those activities related to site selection, design and construction of new units and their commissioning. As it does not seem to be prudent to renounce to nuclear energy on a permanent basis, nuclear utilities, engineering and service companies, academic, research and state organizations agencies should establish programmes to recuperate the radiological knowledge and experience, among other subjects, acquired in the interrupted activities. Likewise, those responsible for the operation of nuclear power plants and the follow up activities should also establish knowledge management activities on radiation protection and other subject matters in line with the IAEA recommendations. (Author) 19 refs.

  3. Artificial intelligence and nuclear power. Report by the Technology Transfer Artificial Intelligence Task Team

    Energy Technology Data Exchange (ETDEWEB)

    1985-06-01

    The Artificial Intelligence Task Team was organized to review the status of Artificial Intelligence (AI) technology, identify guidelines for AI work, and to identify work required to allow the nuclear industry to realize maximum benefit from this technology. The state of the nuclear industry was analyzed to determine where the application of AI technology could be of greatest benefit. Guidelines and criteria were established to focus on those particular problem areas where AI could provide the highest possible payoff to the industry. Information was collected from government, academic, and private organizations. Very little AI work is now being done to specifically support the nuclear industry. The AI Task Team determined that the establishment of a Strategic Automation Initiative (SAI) and the expansion of the DOE Technology Transfer program would ensure that AI technology could be used to develop software for the nuclear industry that would have substantial financial payoff to the industry. The SAI includes both long and short term phases. The short-term phase includes projects which would demonstrate that AI can be applied to the nuclear industry safely, and with substantial financial benefit. The long term phase includes projects which would develop AI technologies with specific applicability to the nuclear industry that would not be developed by people working in any other industry.

  4. Development of Operation of Nuclear Technology Education Program for Mutual Technical Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H. Y.; Han, K. W.; Lee, E. J. (and others)

    2004-12-15

    The objective of this project is to provide training opportunities to key personnel from developing countries in the field of nuclear technologies through which it would be possible to expand our nation's role as a technology donor and as a leading country in the international nuclear society. In addition, it is expected that this training course would be useful for building a foundation to enter the international markets of nuclear technology and related products. Through this project, it was possible to obtain the current status of the nuclear industries in the countries with which potential cooperation would be expected in the future. Inviting key manager groups from countries which are interested in technology transfer from other countries could provide them with an opportunity to experience our nation's nuclear industries and technologies. Specifically, this project could open with a seminar in Kazakhstan which has abundant natural resources including uranium. Through this visit, it was possible to enhance the cooperation between the two countries in nuclear technology, and it opened a way to cooperate in the support of the Kazakhstan medical radioisotope center and human resources development.

  5. Capacitor-based detection of nuclear magnetization: nuclear quadrupole resonance of surfaces.

    Science.gov (United States)

    Gregorovič, Alan; Apih, Tomaž; Kvasić, Ivan; Lužnik, Janko; Pirnat, Janez; Trontelj, Zvonko; Strle, Drago; Muševič, Igor

    2011-03-01

    We demonstrate excitation and detection of nuclear magnetization in a nuclear quadrupole resonance (NQR) experiment with a parallel plate capacitor, where the sample is located between the two capacitor plates and not in a coil as usually. While the sensitivity of this capacitor-based detection is found lower compared to an optimal coil-based detection of the same amount of sample, it becomes comparable in the case of very thin samples and even advantageous in the proximity of conducting bodies. This capacitor-based setup may find its application in acquisition of NQR signals from the surface layers on conducting bodies or in a portable tightly integrated nuclear magnetic resonance sensor.

  6. Recent Canadian advances in nuclear-based hydrogen production and the thermochemical Cu-Cl cycle

    Energy Technology Data Exchange (ETDEWEB)

    Naterer, G. [Canada Research Chair Professor, University of Ontario Institute of Technology (UOIT), 2000 Simcoe Street, Oshawa, Ontario L1H 7K4 (Canada); Suppiah, S. [Manager, Hydrogen Isotopes Technology Branch, AECL, Chalk River, Ontario K0J 1J0 (Canada); Lewis, M. [Chemist, Chemical Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, Illinois 60439 (United States); Gabriel, K. [Associate Provost, Research, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Dincer, I.; Rosen, M.A. [Professor of Mechanical Engineering, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Fowler, M. [Assistant Professor of Chemical Engineering, University of Waterloo, 200 University Avenue, Waterloo, Ontario N2L 3G1 (Canada); Rizvi, G. [Assistant Professor of Mechanical Engineering, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Easton, E.B. [Assistant Professor of Chemistry, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Ikeda, B.M.; Pioro, I. [Associate Professor, Faculty of Energy Systems and Nuclear Science, UOIT, 2000 Simcoe St., Oshawa, ON L1H 7K4 (Canada); Kaye, M.H.; Lu, L. [Assistant Professor, Faculty of Energy Systems and Nuclear Science, UOIT, 2000 Simcoe Street, Oshawa, Ontario L1H 7K4 (Canada); Spekkens, P. [Vice President of Science and Technology Development, Ontario Power Generation, 889 Brock Road, Pickering, Ontario (Canada); Tremaine, P. [Professor of Chemistry, University of Guelph, 50 Stone Road East, Guelph, Ontario N1G 2W1 (Canada); Mostaghimi, J. [Canada Research Chair Professor, Mechanical Engineering, University of Toronto, Toronto, Ontario M5S 3E5 (Canada); Avsec, J. [Assistant Professor, Faculty of Energy Technology, Univ. of Maribor, Hocevarjev trg 1, 8270 Krsko (Slovenia); Jiang, J. [Professor and NSERC/UNENE Senior Industrial Research Chair, Electrical and Computer Engineering, Univ. of Western Ontario, London, Ontario N6A 5B9 (Canada)

    2009-04-15

    This paper presents recent Canadian advances in nuclear-based production of hydrogen by electrolysis and the thermochemical copper-chlorine (Cu-Cl) cycle. This includes individual process and reactor developments within the Cu-Cl cycle, thermochemical properties, advanced materials, controls, safety, reliability, economic analysis of electrolysis at off-peak hours, and integrating hydrogen plants with Canada's nuclear power plants. These enabling technologies are being developed by a Canadian consortium, as part of the Generation IV International Forum (GIF) for hydrogen production from the next generation of nuclear reactors. (author)

  7. Dynamic Analysis of Nuclear Waste Generation Based on Nuclear Fuel Cycle Transition Scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, S. R. [University of Science and Technology, Daejeon (Korea, Republic of); Ko, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    According to the recommendations submitted by the Public Engagement Commission on Spent Nuclear Fuel Management (PECOS), the government was advised to pick the site for an underground laboratory and interim storage facilities before the end of 2020 followed by the related research for permanent and underground disposal of spent fuel after 10 years. In the middle of the main issues, the factors of environmentally friendly and safe way to handle nuclear waste are inextricable from nuclear power generating nation to ensure the sustainability of nuclear power. For this purposes, the closed nuclear fuel cycle has been developed regarding deep geological disposal, pyroprocessing, and burner type sodium-cooled fast reactors (SFRs) in Korea. Among two methods of an equilibrium model and a dynamic model generally used for screening nuclear fuel cycle system, the dynamic model is more appropriate to envisage country-specific environment with the transition phase in the long term and significant to estimate meaningful impacts based on the timedependent behavior of harmful wastes. This study aims at analyzing the spent nuclear fuel generation based on the long-term nuclear fuel cycle transition scenarios considered at up-to-date country specific conditions and comparing long term advantages of the developed nuclear fuel cycle option between once-through cycle and Pyro-SFR cycle. In this study, a dynamic analysis was carried out to estimate the long-term projection of nuclear electricity generation, installed capacity, spent nuclear fuel arising in different fuel cycle scenarios based on the up-to-date national energy plans.

  8. Nuclear medicine technology. Review questions for the board examinations. 3. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Ramer, Karen [CNMT, Marianka (Slovakia); Alavi, Abass [Pennsylvania Univ., Philadelphia, PA (United States). Hospital

    2008-07-01

    This book prepares students and technologists for registry examinations in nuclear medicine technology by providing practice questions and answers with detailed explanations, as well as a mock registry exam. The questions are designed to test the basic knowledge required of nuclear medicine technologists, as well as the practical application of that knowledge. The topics covered closely follow the content specifications for the exam given by the American Registry of Radiologic Technologist and the components of preparedness published by the Nuclear Medicine Technology Certification Board. This third edition includes a new chapter on positron emission tomography. (orig.)

  9. Operation technology of air treatment system in nuclear facilities

    CERN Document Server

    Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

    2001-01-01

    Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

  10. The Technology Trend of Japanese Patent for the Nuclear Fuel Assembly Inspection

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jai Wan; Choi, Young Soo; Lee, Nam Ho; Jeong, Kyung Min; Suh, Yong Chil; Kim, Chang Hoi; Shin, Jung Cheol

    2008-06-15

    Japanese technology patents for the nuclear fuel assembly inspection unit, from the year 1993 to the year 2006, were investigated. The fuel rods which contain fissile material are grouped together in a closely-spaced array within the fuel assembly. Various kinds of reactor including the PWR reactor are being operated in Japan. There are many kinds of nuclear fuel assemblies in Japan, and the shape and the size of these nuclear fuel assemblies are various also. As the structure of these various fuel assemblies is a regular square as the same as the Korean one, the inspection method described in Japanese technology patent can be applied to the inspection of the nuclear fuel assembly of the Korea. This report focuses on advances in VIT(visual inspection test) of nuclear fuel assembly using the state-of-the-art CCD camera system.

  11. Nuclear Technology, Global Warming, and the Politicization of Science

    Science.gov (United States)

    Weart, Spencer

    2016-03-01

    Since the mid 20th century physical scientists have engaged in two fierce public debates on issues that posed existential risks to modern society: nuclear weapons and global warming. The two overlapped with a third major debate over the deployment of nuclear power reactors. Each controversy included technical disagreements raised by a minority among the scientists themselves. Despite efforts to deal with the issues objectively, the scientists became entangled in left vs. right political polarization. All these debates, but particularly the one over climate change, resulted in a deterioration of public faith in the objectivity and integrity of scientists.

  12. Nuclear Thermal Rocket (Ntr) Propulsion: A Proven Game-Changing Technology for Future Human Exploration Missions

    Science.gov (United States)

    Borowski, Stanley K.; McCurdy, David R.; Packard, Thomas W.

    2012-01-01

    The NTR represents the next evolutionary step in high performance rocket propulsion. It generates high thrust and has a specific impulse (Isp) of approx.900 seconds (s) or more V twice that of today s best chemical rockets. The technology is also proven. During the previous Rover and NERVA (Nuclear Engine for Rocket Vehicle Applications) nuclear rocket programs, 20 rocket reactors were designed, built and ground tested. These tests demonstrated: (1) a wide range of thrust; (2) high temperature carbide-based nuclear fuel; (3) sustained engine operation; (4) accumulated lifetime; and (5) restart capability V all the requirements needed for a human mission to Mars. Ceramic metal cermet fuel was also pursued, as a backup option. The NTR also has significant growth and evolution potential. Configured as a bimodal system, it can generate electrical power for the spacecraft. Adding an oxygen afterburner nozzle introduces a variable thrust and Isp capability and allows bipropellant operation. In NASA s recent Mars Design Reference Architecture (DRA) 5.0 study, the NTR was selected as the preferred propulsion option because of its proven technology, higher performance, lower launch mass, simple assembly and mission operations. In contrast to other advanced propulsion options, NTP requires no large technology scale-ups. In fact, the smallest engine tested during the Rover program V the 25,000 lbf (25 klbf) Pewee engine is sufficient for human Mars missions when used in a clustered engine arrangement. The Copernicus crewed spacecraft design developed in DRA 5.0 has significant capability and a human exploration strategy is outlined here that uses Copernicus and its key components for precursor near Earth asteroid (NEA) and Mars orbital missions prior to a Mars landing mission. Initially, the basic Copernicus vehicle can enable reusable 1-year round trip human missions to candidate NEAs like 1991 JW and Apophis in the late 2020 s to check out vehicle systems. Afterwards, the

  13. Nuclear Medicine Technology: A Suggested Two-Year Curriculum Manual.

    Science.gov (United States)

    Hunter, David

    This curriculum guide prescribes an educational program for training nuclear medicine technologists. Following a brief section on program development, the curriculum is both outlined and presented in detail. For each of the 44 courses, the following information is given: (1) sequential placement of the course in the curriculum; (2) course…

  14. Technology diffusion of a different nature: Applications of nuclear safeguards technology to the chemical weapons verification regime

    Energy Technology Data Exchange (ETDEWEB)

    Kadner, S.P. [Aquila Technologies Group, Inc., Albuquerque, NM (United States); Reisman, A. [Brookhaven National Lab., Upton, NY (United States); Turpen, E. [Aquila Technologies Group, Inc., Cambridge, MA (United States)

    1996-10-01

    The following discussion focuses on the issue of arms control implementation from the standpoint of technology and technical assistance. Not only are the procedures and techniques for safeguarding nuclear materials undergoing substantial changes, but the implementation of the Chemical Weapons Convention (CWC) and the Biological Weapons Convention (BWC) will give rise to technical difficulties unprecedented in the implementation of arms control verification. Although these regimes present new challenges, an analysis of the similarities between the nuclear and chemical weapons non-proliferation verification regimes illustrates the overlap in technological solutions. Just as cost-effective and efficient technologies can solve the problems faced by the nuclear safeguards community, these same technologies offer solutions for the CWC safeguards regime. With this in mind, experts at the Organization for the Prohibition of Chemical Weapons (OPCW), who are responsible for verification implementation, need to devise a CWC verification protocol that considers the technology already available. The functional similarity of IAEA and the OPCW, in conjunction with the technical necessities of both verification regimes, should receive attention with respect to the establishment of a technical assistance program. Lastly, the advanced status of the nuclear and chemical regime vis-a-vis the biological non-proliferation regime can inform our approach to implementation of confidence building measures for biological weapons.

  15. Use of comparative assessment framework for comparison of geological nuclear waste and CO2 disposal technologies

    Energy Technology Data Exchange (ETDEWEB)

    Streimikiene, Dalia

    2010-09-15

    Comparative assessment of few future energy and climate change mitigation options for Lithuania in 2020 performed indicated that nuclear and combined cycle gas turbine technologies are very similar energy options in terms of costs taking into account GHG emission reduction costs. Comparative assessment of these energy options requires evaluation of the potentials and costs for geological CO2 and nuclear waste storage as the main uncertainties in comparative assessment of electricity generation technologies are related with these back-end technologies. The paper analyses the main characteristics of possible geological storage of CO2 and NW options in Lithuania.

  16. Developing countries' motivation to use nuclear technology. Motivation von Drittweltlaendern zur Nutzung der Kernenergie

    Energy Technology Data Exchange (ETDEWEB)

    Ratsch, U. (FEST, Heidelberg (Germany))

    1990-08-01

    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).

  17. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topic / Outstanding know-how and sustainable excellence. Workshop: Preserving competence in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Steinwarz, Wolfgang

    2016-10-15

    On the 18{sup th} workshop Preserving Competence in Nuclear Technology 24 young scientists presented the scientific results from their work covering a broad spectrum of technical areas. This demonstrated again the strong engagement of the younger generation as part of the German nuclear society. Prof.Dr.-Ing. Eckart Laurin, Prof.Dr.-Ing. Marco K. Koch, Dr. Katharina Stummeyer, and Dr.-Ing. Wolfgang Steinwarz as members of the jury assessed the written compacts and the oral presentations to award the Siempelkamp Competence Price 2016 to Andreas Wanninger from Technische Universitaet Muenchen.

  18. Sensors and nuclear power. Report by the Technology Transfer Sensors Task Team

    Energy Technology Data Exchange (ETDEWEB)

    1985-06-01

    The existing sensor systems for the basic process parameters in nuclear power plant operation have limitations with respect to accuracy, ease of maintenance and signal processing. These limitations comprise the economy of nuclear power generation. To reduce the costs and improve performance of nuclear power plant fabrication, operation, maintenance and repair we need to advance the sensor technology being applied in the nuclear industry. The economic viability and public acceptance of nuclear power will depend on how well we direct and apply technological advances to the industry. This report was prepared by a team with members representing a wide range of the nuclear industry embracing the university programs, national laboratories, architect engineers and reactor manufacturers. An intensive effort was made to survey current sensor technology, evaluate future trends and determine development needs. This included literature surveys, visits with utilities, universities, laboratories and organizations outside the nuclear industry. Several conferences were attended to take advantage of the access to experts in selected topics and to obtain opinions. Numerous telephone contacts and exchanges by mail supplemented the above efforts. Finally, the broad technical depth of the team members provided the basis for the stimulating working sessions during which this report was organized and drafted.

  19. Novel fabrication of silicon carbide based ceramics for nuclear applications

    Science.gov (United States)

    Singh, Abhishek Kumar

    Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These materials include refractory alloys based on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as SiC--SiCf; carbon--carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor components is necessary for improved efficiency. Improving thermal conductivity of the fuel can lower the center-line temperature and, thereby, enhance power production capabilities and reduce the risk of premature fuel pellet failure. Crystalline silicon carbide has superior characteristics as a structural material from the viewpoint of its thermal and mechanical properties, thermal shock resistance, chemical stability, and low radioactivation. Therefore, there have been many efforts to develop SiC based composites in various forms for use in advanced energy systems. In recent years, with the development of high yield preceramic precursors, the polymer infiltration and pyrolysis (PIP) method has aroused interest for the fabrication of ceramic based materials, for various applications ranging from disc brakes to nuclear reactor fuels. The pyrolysis of preceramic polymers allow new types of ceramic materials to be processed at relatively low temperatures. The raw materials are element-organic polymers whose composition and architecture can be tailored and varied. The primary focus of this study is to use a pyrolysis based process to fabricate a host of novel silicon carbide-metal carbide or oxide composites, and to synthesize new materials based on mixed-metal silicocarbides that cannot be processed using conventional techniques. Allylhydridopolycarbosilane (AHPCS), which is an organometal polymer, was used as the precursor for silicon carbide. Inert gas pyrolysis of AHPCS produces near-stoichiometric amorphous

  20. Technology development for nuclear material measurement and accountability

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Lee, Byung Doo; Cha, Hong Ryul; Lee, Yong Duk; Choi, Hyung Nae; Nah, Won Woo; Park, Hoh Joon; Lee, Yung Kil [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    The measurement techniques for Pu samples and spent fuel assembly were developed in support of the implementation of national inspection responsibility under the Atomic Energy Act promulgated in 1994 and a computer program was also developed to assess the total nuclear material balance by facility declared records. The results of plutonium isotopic determination by gamma-ray spectrometry with high resolution germanium detector with peak analysis codes (FRAM and MGA codes) were approached to within 1% {approx} 2% of error from chemical analysis values by mass spectrometry. A gamma-ray measurement system for underwater spent nuclear fuels was developed and tested successfully. The falsification of facility and state records can be traced with the help of the developed computer code against declared reports submitted by the concerned state. This activity eventually resulted in finding the discrepancy of accountability records. 18 figs, 20 tabs, 27 refs. (Author).

  1. Study on the high-precision laser welding technology of nuclear fuel elements processing

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Soo Sung; Yang, M. S.; Kim, W. K.; Lee, D. Y

    2001-01-01

    The proper welding method for appendage of bearing pads and spacers of PHWR nuclear fuel elements is considered important in respect to the soundness of weldments and the improvement of the performance of nuclear fuels during the operation in reactor. The probability of welding defects of the appendage parts is mostly apt to occur and it is connected directly with the safty and life prediction of the nuclear reactor in operation. Recently there has been studied all over the world to develope welding technology by laser in nuclear fuel processing, and the appendage of bearing pads and spacers of PHWR nuclear fuel elements. Therefore, the purpose of this study is to investigate the characteristics of the laser welded specimens and make some samples for the appendage of bearing pads of PHWR nuclear fuel elements. This study will be also provide the basic data for the fabrications of the appendage of bearing pads and spacers. Especially the laser welding is supposed to be used in the practical application such as precise materials manufacturing fields. In this respect this technology is not only a basic advanced technology with wide applications but also likely to be used for the development of directly applicable technologies for industries, with high potential benefits derived in the view point of economy and industry.

  2. Status of Fuel Development and Manufacturing for Space Nuclear Reactors at BWX Technologies

    Science.gov (United States)

    Carmack, W. J.; Husser, D. L.; Mohr, T. C.; Richardson, W. C.

    2004-02-01

    New advanced nuclear space propulsion systems will soon seek a high temperature, stable fuel form. BWX Technologies Inc (BWXT) has a long history of fuel manufacturing. UO2, UCO, and UCx have been fabricated at BWXT for various US and international programs. Recent efforts at BWXT have focused on establishing the manufacturing techniques and analysis capabilities needed to provide a high quality, high power, compact nuclear reactor for use in space nuclear powered missions. To support the production of a space nuclear reactor, uranium nitride has recently been manufactured by BWXT. In addition, analytical chemistry and analysis techniques have been developed to provide verification and qualification of the uranium nitride production process. The fabrication of a space nuclear reactor will require the ability to place an unclad fuel form into a clad structure for assembly into a reactor core configuration. To this end, BWX Technologies has reestablished its capability for machining, GTA welding, and EB welding of refractory metals. Specifically, BWX Technologies has demonstrated GTA welding of niobium flat plate and EB welding of niobium and Nb-1Zr tubing. In performing these demonstration activities, BWX Technologies has established the necessary infrastructure to manufacture UO2, UCx, or UNx fuel, components, and complete reactor assemblies in support of space nuclear programs.

  3. Gas Turbine Energy Conversion Systems for Nuclear Power Plants Applicable to LiFTR Liquid Fluoride Thorium Reactor Technology

    Science.gov (United States)

    Juhasz, Albert J.

    2014-01-01

    This panel plans to cover thermal energy and electric power production issues facing our nation and the world over the next decades, with relevant technologies ranging from near term to mid-and far term.Although the main focus will be on ground based plants to provide baseload electric power, energy conversion systems (ECS) for space are also included, with solar- or nuclear energy sources for output power levels ranging tens of Watts to kilo-Watts for unmanned spacecraft, and eventual mega-Watts for lunar outposts and planetary surface colonies. Implications of these technologies on future terrestrial energy systems, combined with advanced fracking, are touched upon.Thorium based reactors, and nuclear fusion along with suitable gas turbine energy conversion systems (ECS) will also be considered by the panelists. The characteristics of the above mentioned ECS will be described, both in terms of their overall energy utilization effectiveness and also with regard to climactic effects due to exhaust emissions.

  4. A Discrepancy-Based Methodology for Nuclear Training Program Evaluation.

    Science.gov (United States)

    Cantor, Jeffrey A.

    1991-01-01

    A three-phase comprehensive process for commercial nuclear power training program evaluation is presented. The discrepancy-based methodology was developed after the Three Mile Island nuclear reactor accident. It facilitates analysis of program components to identify discrepancies among program specifications, actual outcomes, and industry…

  5. Thoria-based nuclear fuels thermophysical and thermodynamic properties, fabrication, reprocessing, and waste management

    CERN Document Server

    Bharadwaj, S R

    2013-01-01

    This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. With the help of key databases, many of which were created by the authors, information is presented in the form of tables, figures, schematic diagrams and flow sheets, and photographs. This information will be useful for scientists and engineers working in the nuclear field, particularly for design and simulation, and for establishing the technology. One special feature is the inclusion of the latest information on thoria-based fuels, especially on the use of thorium in power generation, as it has less proliferation potential for nuclear weapons. Given its natural abundance, thorium offers a future alternative to uranium fuels in nuc...

  6. Evaluation of thorium based nuclear fuel. Extended summary

    Energy Technology Data Exchange (ETDEWEB)

    Franken, W.M.P.; Bultman, J.H.; Konings, R.J.M.; Wichers, V.A.

    1995-04-01

    Application of thorium based nuclear fuels has been evaluated with emphasis on possible reduction of the actinide waste. As a result three ECN-reports are published, discussing in detail: - The reactor physics aspects, by comparing the operation characteristics of the cores of Pressurized Water Reactors and Heavy Water Reactors with different fuel types, including equilibrium thorium/uranium free, once-through uranium fuel and equilibrium uranium/plutonium fuel, - the chemical aspects of thorium based fuel cycles with emphasis on fuel (re)fabrication and fuel reprocessing, - the possible reduction in actinide waste as analysed for Heavy Water Reactors with various types of thorium based fuels in once-through operation and with reprocessing. These results are summarized in this report together with a short discussion on non-proliferation and uranium resource utilization. It has been concluded that a substantial reduction of actinide radiotoxicity of the disposed waste may be achieved by using thorium based fuels, if very efficient partitioning and multiple recycling of uranium and thorium can be realized. This will, however, require large efforts to develop the technology to the necessary industrial scale of operation. (orig.).

  7. Technology Status of Thermionic Fuel Elements for Space Nuclear Power

    Science.gov (United States)

    Holland, J. W.; Yang, L.

    1984-01-01

    Thermionic reactor power systems are discussed with respect to their suitability for space missions. The technology status of thermionic emitters and sheath insulator assemblies is described along with testing of the thermionic fuel elements.

  8. DISRUPTIVE TECHNOLOGIES FOR POWER AND PROPULSION (DIPOP) FISSION NUCLEAR OPTIONS

    OpenAIRE

    2013-01-01

    The Disruptive Technologies for Power and Propulsion (DiPoP) Study reviewed advanced space technologies for large interplanetary missions of interest to Europe taking account of European industry capabilities. These included surface power generation, high power instruments, large robotic missions to outer planets, asteroid de ection missions and longer term interplanetary manned missions. The propulsion applications involve high speed increments, generally beyond the capability...

  9. Fermilab Project X nuclear energy application: Accelerator, spallation target and transmutation technology demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Yousry; /Argonne; Johnson, David; Johnson, Todd; Mishra, Shekhar; /Fermilab

    2011-04-01

    The recent paper 'Accelerator and Target Technology for Accelerator Driven Transmutation and Energy Production' and report 'Accelerators for America's Future' have endorsed the idea that the next generation particle accelerators would enable technological breakthrough needed for nuclear energy applications, including transmutation of waste. In the Fall of 2009 Fermilab sponsored a workshop on Application of High Intensity Proton Accelerators to explore in detail the use of the Superconducting Radio Frequency (SRF) accelerator technology for Nuclear Energy Applications. High intensity Continuous Wave (CW) beam from the Superconducting Radio Frequency (SRF) Linac (Project-X) at beam energy between 1-2 GeV will provide an unprecedented experimental and demonstration facility in the United States for much needed nuclear energy Research and Development. We propose to carry out an experimental program to demonstrate the reliability of the accelerator technology, Lead-Bismuth spallation target technology and a transmutation experiment of spent nuclear fuel. We also suggest that this facility could be used for other Nuclear Energy applications.

  10. MOX - TDB : Nuclear Thermodynamic DataBase

    OpenAIRE

    Cheynet, Bertrand

    2006-01-01

    37 pages; A thermodynamic database collecting critical assessments made for nuclear applications has been built since 2003 for the MOX fuel. MOX-TDB is a thermodynamic database for in-vessel applications coontaining : Ba-Fe-La-O-Pu-Ru-Sr-U-Zr + Ar-H. This database covers the entire field from metal to oxide domains.

  11. High Efficiency Nuclear Power Plants Using Liquid Fluoride Thorium Reactor Technology

    Science.gov (United States)

    Juhasz, Albert J.; Rarick, Richard A.; Rangarajan, Rajmohan

    2009-01-01

    An overall system analysis approach is used to propose potential conceptual designs of advanced terrestrial nuclear power plants based on Oak Ridge National Laboratory (ORNL) Molten Salt Reactor (MSR) experience and utilizing Closed Cycle Gas Turbine (CCGT) thermal-to-electric energy conversion technology. In particular conceptual designs for an advanced 1 GWe power plant with turbine reheat and compressor intercooling at a 950 K turbine inlet temperature (TIT), as well as near term 100 MWe demonstration plants with TITs of 950 and 1200 K are presented. Power plant performance data were obtained for TITs ranging from 650 to 1300 K by use of a Closed Brayton Cycle (CBC) systems code which considered the interaction between major sub-systems, including the Liquid Fluoride Thorium Reactor (LFTR), heat source and heat sink heat exchangers, turbo-generator machinery, and an electric power generation and transmission system. Optional off-shore submarine installation of the power plant is a major consideration.

  12. Development of accident management technology and computer codes -A study for nuclear safety improvement-

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chang Kyu; Jae, Moo Sung; Jo, Young Gyun; Park, Rae Jun; Kim, Jae Hwan; Ha, Jae Ju; Kang, Dae Il; Choi, Sun Young; Kim, Si Hwan [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1994-07-01

    We have surveyed new technologies and research results for the accident management of nuclear power plants. And, based on the concept of using the existing plant capabilities for accident management, both in-vessel and ex-vessel strategies were identified and analyzed. When assessing accident management strategies, their effectiveness, adverse effects, and their feasibility must be considered. We have developed a framework for assessing the strategies with these factors in mind. We have applied the developed framework to assessing the strategies, including the likelihood that the operator correctly diagnoses the situation and successfully implements the strategies. Finally, the cavity flooding strategy was assessed by applying it to the station blackout sequence, which have been identified as one of the major contributors to risk at the reference plant. The thermohydraulic analyses with sensitivity calculations have been performed using MAAP 4 computer code. (Author).

  13. Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    M. D. Staiger

    1999-06-01

    A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

  14. Electrochemical processing of spent nuclear fuels: An overview of oxide reduction in pyroprocessing technology

    Directory of Open Access Journals (Sweden)

    Eun-Young Choi

    2015-12-01

    Full Text Available The electrochemical reduction process has been used to reduce spent oxide fuel to a metallic form using pyroprocessing technology for a closed fuel cycle in combination with a metal-fuel fast reactor. In the electrochemical reduction process, oxides fuels are loaded at the cathode basket in molten Li2O–LiCl salt and electrochemically reduced to the metal form. Various approaches based on thermodynamic calculations and experimental studies have been used to understand the electrode reaction and efficiently treat spent fuels. The factors that affect the speed of the electrochemical reduction have been determined to optimize the process and scale-up the electrolysis cell. In addition, demonstrations of the integrated series of processes (electrorefining and salt distillation with the electrochemical reduction have been conducted to realize the oxide fuel cycle. This overview provides insight into the current status of and issues related to the electrochemical processing of spent nuclear fuels.

  15. Designing a nuclear data base prototype using Oracle and Prolog

    Energy Technology Data Exchange (ETDEWEB)

    Paviotti-Corcuera, R.; Ford, C.E.; Perez, R.B.

    1988-11-01

    An ever-increasing demand exists for easily accessible nuclear data base systems. The purpose of this work is to analyze the feasibility of using artificial intelligence methods as tools to provide the necessary functionality to extract information from nuclear data files in a user-friendly manner. For the prototype of this work, a sample of data that can be later enlarged to a complete, evaluated nuclear data base has been used. To implement this prototype, two approaches have been followed: a conventional approach using the commercially available Oracle relational data base management system; and an artificial intelligence approach using the Prolog programming language. This prototypic work shows the feasibility of applying artificial intelligence methods to data bases, and represents a first step toward development of intelligent nuclear data base systems. The characteristics of the query language from both approaches make the second one preferable from a user's point of view. 23 refs., 7 tabs.

  16. The 2011 nuclear medicine technology job analysis project of the American Registry of Radiologic Technologists.

    Science.gov (United States)

    Anderson, Dan; Hubble, William; Press, Bret A; Hall, Scott K; Michels, Ann D; Koenen, Roxanne; Vespie, Alan W

    2010-12-01

    The American Registry of Radiologic Technologists (ARRT) conducts periodic job analysis projects to update the content and eligibility requirements for all certification examinations. In 2009, the ARRT conducted a comprehensive job analysis project to update the content specifications and clinical competency requirements for the nuclear medicine technology examination. ARRT staff and a committee of volunteer nuclear medicine technologists designed a job analysis survey that was sent to a random sample of 1,000 entry-level staff nuclear medicine technologists. Through analysis of the survey data and judgments of the committee, the project resulted in changes to the nuclear medicine technology examination task list, content specifications, and clinical competency requirements. The primary changes inspired by the project were the introduction of CT content to the examination and the expansion of the content covering cardiac procedures.

  17. Australian Nuclear Science and Technology Organisation (ANSTO) Annual Report 1997-1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This is the 46th Annual Report of ANSTO or its predecessor, AAEC outlining the quality services being delivered and the development of knowledge in areas where ANSTO`s nuclear science and technology and related capabilities are of strategic and technical benefit. ANSTO is reporting against established performance indicators within the the five core scientific business areas: International strategic relevance of Nuclear Science; Core nuclear facilities operation and development; Applications of Nuclear Science and Technology to the understanding of natural processes; Treatment and management of man-made and naturally occurring radioactive substances; and Competitiveness and ecological sustainability of industry. Also presented are the objectives, outcomes and activities which supports the core scientific areas by providing best practice corporate support, safety management, information and human resource management for ANSTO staff

  18. 2009 annual meeting on nuclear technology. Pt. 1. Section reports; JAHRESTAGUNG KERNTECHNIK 2009. T. 1. Sektionsberichte

    Energy Technology Data Exchange (ETDEWEB)

    Schaffrath, Andreas [TUeV NORD SysTec GmbH und Co. KG, Hamburg (Germany); Hartmann, Miks; Hoffmann, Petra Britt [Areva NP GmbH, Erlangen (Germany); Stieglitz, Robert [Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen (Germany); Hoehne, Thomas [Forschungszentrum Dresden-Rossendorf, Dresden (Germany); Weiss, Frank-Peter [Forschungszentrum Dresden-Rossendorf, Inst. fuer Sicherheitsforschung, Dresden (Germany); Hollands, Thorsten [Ruhr-Univ. Bochum (RUB), Energy Systems and Energy Economics (LEE), Bochum (Germany); Sanchez Espinoza, Victor Hugo [Forschungszentrum Karlsruhe, Inst. fuer Reaktorsicherheit, Eggenstein-Leopoldshafen (Germany); Tietsch, Wolfgang [Westinghouse Electric Germany GmbH, Mannheim (Germany); Sonnenburg, H.G. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Muenchen (Germany)

    2009-08-15

    Summary report on these 3 - out of 13 - Sessions of the Annual Conference on Nuclear Technology held in Dresden on May 12 to 14, 2009: Thermodynamics and Fluid Dynamics (Session 2), Safety of Nuclear Installations - Methods, Analysis, Results (Session 3), and, Front End of the Fuel Cycle, Fuel Elements and Core Components (Session 4). The other Sessions Reactor Physics and Methods of Calculation (Session 1), Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage (Session 5), Operation of Nuclear Installations (Session 6), Decommissioning of Nuclear Installations (Session 7), Fusion Technology (Session 8), Research Reactors, Neutron Sources (Session 9), Energy Industry and Economics (Session 10), Radiation Protection (Session 11), New Build and Innovations (Session 12), and Education, Expert Knowledge, Know How Transfer (Session 13) have be covered in reports in further issues of atw. (orig.)

  19. Project-Based Learning in the Masters degree in Nuclear Engineering at BarcelonaTECH. Experience gained in the area of Management of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Reventos, F.; Vives, E.; Brunet, A.; Sabate, R.; Calvino, F.; Batet, L.

    2014-07-01

    From its first edition, that took place in 2011-2012, the Masters degree in Nuclear Engineering from BarcelonaTECH has been using techniques of Project-Based Learning to fulfill the purpose of training nuclear engineers with a profile suitable for positions in the industry. The Master is sponsored by ENDESA and relies on the collaboration with institutions and companies. The Master is embedded in EMINE, the European Master in Innovation in Nuclear Energy, supported by KIC-InnoEnergy and the European Institute of Technology. (Author)

  20. An American Vital Interest: Preserving the Nuclear Enterprise Supplier Base

    Science.gov (United States)

    2012-02-15

    machined parts, and printed wire boards (PWBs). Honeywell maintains the nuclear enterprise’s Master Approved Supplier List containing all qualified...and technologies that have experienced significant decline include aerospace, semiconductors, PWBs, machine tools, and advanced materials (e.g...re-energized their relationship with Brush Wellman on Beryllium Supply, and undertaken energetic materials development with Roxcel. It is

  1. FY02 Engineering Technology Reports Volume 1: Technology Base

    Energy Technology Data Exchange (ETDEWEB)

    Minichino, C; Meeker, D

    2003-01-28

    Engineering has touched on every challenge, every accomplishment, and every endeavor of Lawrence Livermore National Laboratory during its fifty-year history. In this time of transition to new leadership, Engineering continues to be central to the mission of the Laboratory, returning to the tradition and core values of E. O. Lawrence: science-based engineering--turning scientific concepts into reality. This volume of Engineering Technical Reports summarizes progress on the projects funded for technology-base efforts. Technology-base projects effect the natural transition to reduction-to-practice of scientific or engineering methods that are well understood and established. They represent discipline-oriented, core competency activities that are multi-programmatic in application, nature, and scope. Objectives of technology-base funding include: (1) the development and enhancement of tools and processes to provide Engineering support capability, such as code maintenance and improved fabrication methods; (2) the support of Engineering science and technology infrastructure, such as the installation or integration of a new capability; (3) support for technical and administrative leadership through our technology Centers; and (4) the initial scoping and exploration of selected technology areas with high strategic potential, such as assessment of university, laboratory, and industrial partnerships. Five Centers focus and guide longer-term investments within Engineering. The Centers attract and retain top staff, develop and maintain critical core technologies, and enable programs. Through their technology-base projects, they oversee the application of known engineering approaches and techniques to scientific and technical problems.

  2. Development of dry storage technology of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Maruoka, Kunio [Mitsubishi Heavy Industries Ltd., Yokohama (Japan). Nuclear Energy Systems Engineering Center; Murakami, Kazuo; Yokoyama, Takeshi; Natsume, Tomohiro; Irino, Mitsuhiro

    1998-07-01

    The increasing demand for storage of spent fuel assemblies generated by commercial nuclear power plants is the urgent subject to solve. The dry storage system is as economically more advantageous than the pool storage system, and so, Mitsubishi Heavy Industries, Ltd. has developed the metal storage cask suited to small and medium storage capacity under 2000MTU - 3000MTU. For large scale capacity, the new `Mitsubishi Vault Storage System` has been developed, and it provides a safe and economical solution. Technical study concerning cooling ability was performed. (author)

  3. Z-Pinch fusion-based nuclear propulsion

    Science.gov (United States)

    Miernik, J.; Statham, G.; Fabisinski, L.; Maples, C. D.; Adams, R.; Polsgrove, T.; Fincher, S.; Cassibry, J.; Cortez, R.; Turner, M.; Percy, T.

    2013-02-01

    Fusion-based nuclear propulsion has the potential to enable fast interplanetary transportation. Due to the great distances between the planets of our solar system and the harmful radiation environment of interplanetary space, high specific impulse (Isp) propulsion in vehicles with high payload mass fractions must be developed to provide practical and safe vehicles for human space flight missions. The Z-Pinch dense plasma focus method is a Magneto-Inertial Fusion (MIF) approach that may potentially lead to a small, low cost fusion reactor/engine assembly [1]. Recent advancements in experimental and theoretical understanding of this concept suggest favorable scaling of fusion power output yield [2]. The magnetic field resulting from the large current compresses the plasma to fusion conditions, and this process can be pulsed over short timescales (10-6 s). This type of plasma formation is widely used in the field of Nuclear Weapons Effects testing in the defense industry, as well as in fusion energy research. A Z-Pinch propulsion concept was designed for a vehicle based on a previous fusion vehicle study called "Human Outer Planet Exploration" (HOPE), which used Magnetized Target Fusion (MTF) [3] propulsion. The reference mission is the transport of crew and cargo to Mars and back, with a reusable vehicle. The analysis of the Z-Pinch MIF propulsion system concludes that a 40-fold increase of Isp over chemical propulsion is predicted. An Isp of 19,436 s and thrust of 3812 N s/pulse, along with nearly doubling the predicted payload mass fraction, warrants further development of enabling technologies.

  4. 2011 annual meeting on nuclear technology. Pt. 4. Topical sessions; Jahrestagung Kerntechnik 2011. T. 4. Fachsitzungsberichte

    Energy Technology Data Exchange (ETDEWEB)

    Schoenfelder, Christian; Dams, Wolfgang [AREVA NP GmbH, Offenbach (Germany)

    2011-11-15

    Summary report on the Topical Session of the Annual Conference on Nuclear Technology held in Berlin, 17 to 19 May 2011: - Nuclear Competence in Germany and Europe. The Topical Session: - Sodium Cooled Fast Reactors -- will be covered in a report in a further issue of atw. The reports on the Topical Sessions: - CFD-Simulations for Safety Relevant Tasks; and - Final Disposal: From Scientific Basis to Application; - Characteristics of a High Reliability Organization (HRO) Considering Experience Gained from Events at Nuclear Power Stations -- have been covered in atw 7, 8/9, and 10 (2011). (orig.)

  5. 2009 Annual meeting on nuclear technology. Pt. 2. Topical sessions; Jahrestagung Kerntechnik 2009. T.2. Fachsitzungsberichte

    Energy Technology Data Exchange (ETDEWEB)

    Fazio, Concetta [Forschungszentrum Karlsruhe/KIT, Eggenstein-Leopoldshafen (Germany); Delpech, Marc [Centre CEA de Saclay (Essonne), Gif-sur-Yvette (France); Schaffrath, Andreas [TUeV NORD SysTec GmbH und Co. KG, Abt. Sicherheitsanalyse und Systemtechnik (ETB), Hamburg (Germany)

    2009-10-15

    Summary report on the Topical Sessions of the Annual Conference on Nuclear Technology held in Dresden, May 12 to 14, 2009: Flexible Concept for Sustainable Use of Nuclear Energy and Waste Minimization; Thermohydraulic Experiments for Reactors of the Second and Third Generation. The reports on the Topical Sessions: Advances in the Development of Integrated Management Systems for the Optimisation of Safety and Operational Availability of Nuclear Power Stations (Dr. Markus Nie and Dipl.-Ing. Karl Ramler), and; Fuel Elements: Zero Failure - Road to the Target (Dipl.-Ing. Andreas Huettmann) have been covered in atw 8/9 (2009). (orig.)

  6. Nuclear Thermal Propulsion (NTP): A Proven Growth Technology for Human NEO/Mars Exploration Missions

    Science.gov (United States)

    Borowski, Stanley K.; McCurdy, David R.; Packard, Thomas W.

    2012-01-01

    The nuclear thermal rocket (NTR) represents the next "evolutionary step" in high performance rocket propulsion. Unlike conventional chemical rockets that produce their energy through combustion, the NTR derives its energy from fission of Uranium-235 atoms contained within fuel elements that comprise the engine s reactor core. Using an "expander" cycle for turbopump drive power, hydrogen propellant is raised to a high pressure and pumped through coolant channels in the fuel elements where it is superheated then expanded out a supersonic nozzle to generate high thrust. By using hydrogen for both the reactor coolant and propellant, the NTR can achieve specific impulse (Isp) values of 900 seconds (s) or more - twice that of today s best chemical rockets. From 1955 - 1972, twenty rocket reactors were designed, built and ground tested in the Rover and NERVA (Nuclear Engine for Rocket Vehicle Applications) programs. These programs demonstrated: (1) high temperature carbide-based nuclear fuels; (2) a wide range of thrust levels; (3) sustained engine operation; (4) accumulated lifetime at full power; and (5) restart capability - all the requirements needed for a human Mars mission. Ceramic metal "cermet" fuel was pursued as well, as a backup option. The NTR also has significant "evolution and growth" capability. Configured as a "bimodal" system, it can generate its own electrical power to support spacecraft operational needs. Adding an oxygen "afterburner" nozzle introduces a variable thrust and Isp capability and allows bipropellant operation. In NASA s recent Mars Design Reference Architecture (DRA) 5.0 study, the NTR was selected as the preferred propulsion option because of its proven technology, higher performance, lower launch mass, versatile vehicle design, simple assembly, and growth potential. In contrast to other advanced propulsion options, no large technology scale-ups are required for NTP either. In fact, the smallest engine tested during the Rover program

  7. Nuclear Safety Design Base for License Application

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-09-29

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111(b) [DIRS 173273] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113(b) and (c) [DIRS 173273] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period.

  8. Long term panorama of the nuclear technology; Panorama a largo plazo de la tecnologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Velez, C. [Electricite de France, Comite Cientifico Asesor, 22-30 avenue de Wagram, 75382 Paris (France)

    2009-07-01

    The concern for the security of the hydrocarbons supply, essentials for the transport and every time more important in the electricity production, it is one of the rebirth causes of interest for the nuclear energy. On the other hand, it is the increase of the hydrocarbons price. In some countries, included Mexico, the price of gas is subject to strong seasonal fluctuations, aggravating by the congestion of the ducts. It is certain that great part of the prices rise of petroleum that we are experiencing is due to speculation, for what it is necessary to look for objective elements that allow to venture in the difficult topic of the future price of crude. One finishes reason of the resurgence of interest for the nuclear energy, is the growing perception that with the gases emission of greenhouse effect we are exposing our planet to an uncontrollable experiment with consequences potentially catastrophic. This perception is translated in a pressure of the public opinion for to use renewable energy sources that do not contribute to the greenhouse effect. In this work a general panorama is exposed on the advances that exist at the present time, like nuclear reactors with the purpose of solving the current problem that the world is crossing. (Author)

  9. Public acceptance of the utilization of nuclear technology. Necessity of using the system which is similar to that of the ISO14001

    Energy Technology Data Exchange (ETDEWEB)

    Kurata, Kenji; Kanda, Keiji [Graduate School of Energy Science, Kyoto University, Kyoto (Japan)

    2001-05-01

    Safety itself is a key factor in enhancing public acceptance of the utilization of nuclear technology. At the same time, it is indispensable for businesses using nuclear technology to foster public trust by being regarded as 'companies which are making serious efforts to attain higher level of safety'. However, recent nuclear accidents related to the MONJU plant and JCO have seriously hampered this trust. Based on the above understanding, this paper uses the ISO14001 framework to consider a possible solution to recover public trust. An examination of the ISO14001 shows that it is seen as a framework to prove to the outside world that the party in question is reliable in terms of behaving in an environmentally sound manner. Accordingly, their must be a possibility for businesses using a nuclear technology to be able to use the ideas of the framework in terms of safety instead of the environment. (author)

  10. Quantum Computing Using Pulse-Based Electron-Nuclear Double Resonance (endor):. Molecular Spin-Qubits

    Science.gov (United States)

    Sato, Kazuo; Nakazawa, Shigeki; Rahimi, Robabeh D.; Nishida, Shinsuke; Ise, Tomoaki; Shimoi, Daisuke; Toyota, Kazuo; Morita, Yasushi; Kitagawa, Masahiro; Carl, Parick; Höfner, Peter; Takui, Takeji

    2009-06-01

    Electrons with the spin quantum number 1/2, as physical qubits, have naturally been anticipated for implementing quantum computing and information processing (QC/QIP). Recently, electron spin-qubit systems in organic molecular frames have emerged as a hybrid spin-qubit system along with a nuclear spin-1/2 qubit. Among promising candidates for QC/QIP from the materials science side, the reasons for why electron spin-qubits such as molecular spin systems, i.e., unpaired electron spins in molecular frames, have potentialities for serving for QC/QIP will be given in the lecture (Chapter), emphasizing what their advantages or disadvantages are entertained and what technical and intrinsic issues should be dealt with for the implementation of molecular-spin quantum computers in terms of currently available spin manipulation technology such as pulse-based electron-nuclear double resonance (pulsed or pulse ENDOR) devoted to QC/QIP. Firstly, a general introduction and introductory remarks to pulsed ENDOR spectroscopy as electron-nuclear spin manipulation technology is given. Super dense coding (SDC) experiments by the use of pulsed ENDOR are also introduced to understand differentiating QC ENDOR from QC NMR based on modern nuclear spin technology. Direct observation of the spinor inherent in an electron spin, detected for the first time, will be shown in connection with the entanglement of an electron-nuclear hybrid system. Novel microwave spin manipulation technology enabling us to deal with genuine electron-electron spin-qubit systems in the molecular frame will be introduced, illustrating, from the synthetic strategy of matter spin-qubits, a key-role of the molecular design of g-tensor/hyperfine-(A-)tensor molecular engineering for QC/QIP. Finally, important technological achievements of recently-emerging CD ELDOR (Coherent-Dual ELectron-electron DOuble Resonance) spin technology enabling us to manipulate electron spin-qubits are described.

  11. Building tomorrow's nuclear power plants with 4{sup +}D VR technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Il S.; Yoon, Sang H.; Shim, Kyu W.; Yu, Yong H.; Suh, Kune Y. [PhiloSOPhIA, Inc., Seoul (Korea, Republic of)

    2002-04-15

    There continues to be an increasing demand of electricity around the globe to fuel the industrial growth and to promote the human welfare. The economic activities have brought about richness in our material and cultural lives, in which process the electric power has been at the heart of the versatile energy sources. In order to timely and competitively respond to rapidly changing energy environment in the twenty-first century there is a growing need to build the advanced nuclear power plants in the unlimited workspace of virtual reality (VR) prior to commissioning. One can then realistically evaluate their construction time and cost per varying methods and options available from the leading-edge technology. In particular a great deal of efforts have yet to be made for time- and cost-dependent plant simulation and dynamically coupled database construction in the VR space. The operator training and personnel education may also benefit from the VR technology. The present work is being proposed in the three-dimensional space and time plus cost coordinates, i. e. four plus dimensional (4{sup +}D) coordinates. The 4{sup +}D VR application will enable the nuclear industry to narrow the technological gap from the other leading industries that have long since been employing the VR engineering. The 4{sup +}D technology will help nurture public understanding of the special discipline of nuclear power plants. The technology will also facilitate public access to the knowledge on the nuclear science and engineering which has so far been monopolized by the academia, national laboratories and the heavy industry. The 4{sup +}D virtual design and construction will open up the new horizon for revitalization of the nuclear industry over the globe in the foreseeable future. Considering the long construction and operation time for the nuclear power plants, the preliminary VR simulation capability for the plants will supply the vital information not only for the actual design and

  12. Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications

    Energy Technology Data Exchange (ETDEWEB)

    Coble, Jamie B.; Ramuhalli, Pradeep; Bond, Leonard J.; Hines, Wes; Upadhyaya, Belle

    2012-07-17

    This report reviews the current state of the art of prognostics and health management (PHM) for nuclear power systems and related technology currently applied in field or under development in other technological application areas, as well as key research needs and technical gaps for increased use of PHM in nuclear power systems. The historical approach to monitoring and maintenance in nuclear power plants (NPPs), including the Maintenance Rule for active components and Aging Management Plans for passive components, are reviewed. An outline is given for the technical and economic challenges that make PHM attractive for both legacy plants through Light Water Reactor Sustainability (LWRS) and new plant designs. There is a general introduction to PHM systems for monitoring, fault detection and diagnostics, and prognostics in other, non-nuclear fields. The state of the art for health monitoring in nuclear power systems is reviewed. A discussion of related technologies that support the application of PHM systems in NPPs, including digital instrumentation and control systems, wired and wireless sensor technology, and PHM software architectures is provided. Appropriate codes and standards for PHM are discussed, along with a description of the ongoing work in developing additional necessary standards. Finally, an outline of key research needs and opportunities that must be addressed in order to support the application of PHM in legacy and new NPPs is presented.

  13. Applications of the gas chromatography in the nuclear science and technology; Aplicaciones de la cromatografia de gases a la ciencia y tecnologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gasco Sanchez, L.

    1972-07-01

    This paper is a review on the applications of the gas chromatography in the nuclear science and technology published up to December 1971. Its contents has been classified under the following heads; I) Radiogaschromatography, II) Isotope separation, III) Preparation of labelled molecules, IV) Nuclear fuel cycle, V) Nuclear reactor technology, VI) Irradiation chemistry, VIl) Separation of me tal compounds in gas phase, VIII) Applications of the gas chromatography carried out at the Junta de Energia Nuclear, Spain. Arapter VIII only includes the investigations carried out from January 1969 to December 1971. Previous investigations in this field has been published elsewhere. (Author)

  14. Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers

    Energy Technology Data Exchange (ETDEWEB)

    Heather D. Medema; Ronald K. Farris

    2012-09-01

    This report is a guidance document prepared for the benefit of commercial nuclear power plants’ (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel. This information is not intended to replace basic project management practices or reiterate these processes, but is to support decision-making, planning, and preparation of a business case.

  15. Nuclear medicine technology. Review questions for the board examinations. 2. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Ramer, K. [CNMT, Marianka (Slovakia); Alavi, A. [Pennsylvania Univ. Hospital, Philadelphia, PA (United States)

    2005-07-01

    This book prepares students and technologists for registry examinations in nuclear medicine technology by providing practice questions and answers and a mock registry exam. The questions test both subject comprehension of material and practical applications. The topics covered closely follow the content specifications for the exam given by the American Registry of Radiologic Technologist and the components of preparedness published by the Nuclear Medicine Technology Certification Board. Figure-related questions, similar to those on current registry examinations, are provided. Also included are up-to-date questions and answers regarding NRC regulations. (orig.)

  16. Risks perception and the public acceptance of nuclear technology; Percepcao de riscos e a aceitacao publica da tecnologica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Walter Mendes [Instituto de Radioprotecao e Dosimetria, Rio de Janeiro, RJ (Brazil)]. E-mail: wmendes@ird.gov.br; Gavazza, Sergio; Estrada, Julio J.S. [Instituto Militar de Engenharia, Rio de Janeiro, RJ (Brazil)

    2000-07-01

    This work establishes a methodology to evaluate the public acceptance of nuclear technology taking into consideration several risk concepts. Basic concepts of the nuclear science were transmitted, in form of lectures and courses, to the 13,439 Goiania residents, after the closing of the decontamination works, caused by the violation of the source of {sup 137}Cs, of a teletherapy machine, in 1987. The results of the indicators shown that public's individuals perceive radiation risks and develop behaviors according to a constructive outline. The public does not know technical terms, being quite influenced by media, from where gets information of interest. The public orders the risks, relating them to accidents according to subjective criteria and models them as unknown, new and not observed at short period, establishing destruction, environmental catastrophe and diseases images. (author)

  17. The virtual digital nuclear power plant: A modern tool for supporting the lifecycle of VVER-based nuclear power units

    Science.gov (United States)

    Arkadov, G. V.; Zhukavin, A. P.; Kroshilin, A. E.; Parshikov, I. A.; Solov'ev, S. L.; Shishov, A. V.

    2014-10-01

    The article describes the "Virtual Digital VVER-Based Nuclear Power Plant" computerized system comprising a totality of verified initial data (sets of input data for a model intended for describing the behavior of nuclear power plant (NPP) systems in design and emergency modes of their operation) and a unified system of new-generation computation codes intended for carrying out coordinated computation of the variety of physical processes in the reactor core and NPP equipment. Experiments with the demonstration version of the "Virtual Digital VVER-Based NPP" computerized system has shown that it is in principle possible to set up a unified system of computation codes in a common software environment for carrying out interconnected calculations of various physical phenomena at NPPs constructed according to the standard AES-2006 project. With the full-scale version of the "Virtual Digital VVER-Based NPP" computerized system put in operation, the concerned engineering, design, construction, and operating organizations will have access to all necessary information relating to the NPP power unit project throughout its entire lifecycle. The domestically developed commercial-grade software product set to operate as an independently operating application to the project will bring about additional competitive advantages in the modern market of nuclear power technologies.

  18. Robotics and tele-operation technology for applications in nuclear fields

    Energy Technology Data Exchange (ETDEWEB)

    Kosuge, Kazuhiro; Hirata, Yasuhisa; Takeo, Koji [Tohoku Univ., Department of Machine Intelligence and Systems Engineering, Sendai, Miyagi (Japan)

    2002-01-01

    In this article, we introduce available robotics and tele-operation technology for applications in Nuclear Fields. First, robotics technology for manipulation of a large object is introduced which has been experimentally applied to ITER Maintenance Robot. Then, transportation technology of a large object by multiple mobile robots is reviewed. At last, recent tele-operation technologies and a prototype tele-operation system, referred to as VISIT (Visual Interface System for Interactive Task-execution), is introduced. Several experimental results are also introduced. (author)

  19. Assessment of decision making models in sensitive technology: the nuclear energy case; Avaliacao de modelos decisorios em tecnologia sensivel: o caso da energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Eduardo Ramos Ferreira da [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: erfsilva@ipen.br

    2007-07-01

    In this paper a bibliographic review is proceeded on the decision making processes approaching the sensitive technologies (the military and civilian uses as well), and the nuclear technology herself. It is made a correlation among the development of the nuclear technology and the decision making processes, showing that from 70 decade on, such processes are connected to the national security doctrines influenced by the Brazilian War College. So, every time that the national security is altered, so is the master line of the decision making process altered. In the Brazil case, the alteration appeared from the World War II up to the new proposals coming out from the Ministry of Defense are shown related to the nuclear technology. The existent models are analysed with a conclusion that such models are unveiling at the present situation of the moment, concerning to the nuclear technology.

  20. On the future of civilian plutonium: An assessment of technological impediments to nuclear terrorism and proliferation

    Science.gov (United States)

    Avedon, Roger Edmond

    This dissertation addresses the value of developing diversion- and theft-resistant nuclear power technology, given uncertain future demand for nuclear power, and uncertain risks of nuclear terrorism and of proliferation from the reprocessing of civilian plutonium. The methodology comprises four elements: Economics. An economic growth model coupled with market penetration effects for plutonium and for the hypothetical new technology provides a range of estimates for future nuclear demand. A flow model accounts for the longevity of capital assets (nuclear plants) over time. Terrorism. The commercial nuclear fuel cycle may provide a source of fissile material for terrorists seeking to construct a crude nuclear device. An option value model is used to estimate the effects of the hypothetical new technology on reducing the probability of theft. A game theoretic model is used to explore the deterrence value of physical security and then to draw conclusions about how learning on the part of terrorists or security forces might affect the theft estimate. The principal uncertainties in the theft model can be updated using Bayesian techniques as new data emerge. Proliferation. Access to fissile material is the principal technical impediment to a state's acquisition of nuclear weapons. A game theoretic model is used to determine the circumstances under which a state may proliferate via diversion. The model shows that the hypothetical new technology will have little value for counter-proliferation if diversion is not a preferred proliferation method. A technology policy analysis of the choice of proliferation method establishes that diversion is unlikely to be used because it has no constituency among the important parties to the decision, namely the political leadership, the scientific establishment, and the military. Value. The decision whether to develop a diversion- and theft-resistant fuel cycle depends on the perceived value of avoiding nuclear terrorism and proliferation

  1. Development and Enhancement of Web-based Nuclear Education System and It's Enhancement

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Sipyo; Lee, K. B.; Nam, Y. M; Kim, H. K.; Hwang, I. A.; Yang, S. W.; Nam, J. S.; Yoo, H. W.

    2012-02-15

    To deliver rapidly changing technologies effectively and economically, E-learning in the field of nuclear technology is being done gradually. In the first year of this project, 'Development and Enhancement of Web-based Nuclear Education System; we had established a server system, fitting-up several home pages in NTC(Nuclear Training and Education Center in KAERI) and newly developed LMS(Learning Management System). We had selected a MOODLE for it is one of popular open source in LMS field, and connected to the ANENT(Asian Nuclear in Education for Nuclear Technology) web portal, which is co-operating with IAEA/NKM. We had produced e-learning content mainly composed of the video clip that was taken by making a film of the lecturing in the course of training and education in NTC. The running time of the content is 100 hours totally. This e-learning content is going to reinforce by adding quiz and Q and A. Another activity is web-conferencing between NWU in South Africa and KAERI, which executed 4 times successfully. We are going to make a pre-course for the foreigners who will take part in our training and education course.

  2. The Need for a Strong Science and Technology Program in the Nuclear Weapons Complex for the 21st Century

    Energy Technology Data Exchange (ETDEWEB)

    Garaizar, Xabier [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2009-07-02

    In this paper I argue for the need for a strong Science and Technology program in the Nuclear Weapons Complex as the basis for maintaining a credible deterrence capability. The current Nuclear Posture Review establishes a New Triad as the basis for the United States deterrence strategy in a changing security environment. A predictive science capability is at the core of a credible National Nuclear Weapons program in the 21st Century. In absence of nuclear testing, the certification of our current Nuclear Weapons relies on predictive simulations and quantification of the associated simulation uncertainties. In addition, a robust nuclear infrastructure needs an active research and development program that considers all the required nuclear scenarios, including new configurations for which there is no nuclear test data. This paper also considers alternative positions to the need for a Science and Technology program in the Nuclear Weapons complex.

  3. Summary and recommendations on nuclear electric propulsion technology for the space exploration initiative

    Science.gov (United States)

    Doherty, Michael P.; Holcomb, Robert S.

    1993-01-01

    A project in Nuclear Electric Propulsion (NEP) technology is being established to develop the NEP technologies needed for advanced propulsion systems. A paced approach has been suggested which calls for progressive development of NEP component and subsystem level technologies. This approach will lead to major facility testing to achieve TRL-5 for megawatt NEP for SEI mission applications. This approach is designed to validate NEP power and propulsion technologies from kilowatt class to megawatt class ratings. Such a paced approach would have the benefit of achieving the development, testing, and flight of NEP systems in an evolutionary manner. This approach may also have the additional benefit of synergistic application with SEI extraterrestrial surface nuclear power applications.

  4. Space Exploration Initiative Fuels, Materials and Related Nuclear Propulsion Technologies Panel

    Science.gov (United States)

    Bhattacharyya, S. K.; Olsen, C.; Cooper, R.; Matthews, R. B.; Walter, C.; Titran, R. J.

    1993-01-01

    This report was prepared by members of the Fuels, Materials and Related Technologies Panel, with assistance from a number of industry observers as well as laboratory colleagues of the panel members. It represents a consensus view of the panel members. This report was not subjected to a thorough review by DOE, NASA or DoD, and the opinions expressed should not be construed to represent the official position of these organizations, individually or jointly. Topics addressed include: requirement for fuels and materials development for nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP); overview of proposed concepts; fuels technology development plan; materials technology development plan; other reactor technology development; and fuels and materials requirements for advanced propulsion concepts.

  5. 2009 Mississippi Curriculum Framework: Postsecondary Nuclear Medicine Technology. (Program CIP: 51.0905 - Nuclear Medical Technology/Technologist)

    Science.gov (United States)

    Boney, Linda; Lee, Joanne; Pyles, Alice; Whitfield, Stacy

    2009-01-01

    As the world economy continues to evolve, businesses and industries must adopt new practices and processes in order to survive. Quality and cost control, work teams and participatory management, and an infusion of technology are transforming the way people work and do business. Employees are now expected to read, write, and communicate…

  6. Supporting project on international education and training in cooperated program for Radiation Technology with World Nuclear University

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Byung Duk; Nam, Y. M.; Noh, S. P.; Shin, J. Y. [KAERI, Daejeon (Korea, Republic of)

    2010-08-15

    The objective is promote national status and potential of Nuclear radiation industry, and take a world-wide leading role in radiation industry, by developing and hosting the first WNU Radiation Technology School. RI School (World Nuclear University Radioisotope School) is the three-week program designed to develop and inspire future international leaders in the field of radioisotope for the first time. The project would enable promote abilities of radioactive isotopes professions, and to build the human network with future leaders in the world-wide nuclear and radiation field. Especially by offering opportunity to construct human networks between worldwide radiation field leaders of next generation, intangible assets and pro-Korean human networks are secured among international radiation industry personnel. This might enhance the power and the status of Korean radiation industries, and establish the fundamental base for exporting of radiation technology and its products. We developed the performance measurement method for the school. This shows that 2010 WNU RI School was the first training program focusing on the radioisotope and very useful program for the participants in view of knowledge management and strengthening personal abilities. Especially, the experiences and a human network with world-wide future-leaders in radiation field are most valuable asset. It is expected that the participants could this experience and network developed in the program as a stepping stone toward the development of Korea's nuclear and radiation industry.

  7. Review of LIBS application in nuclear fusion technology

    Science.gov (United States)

    Li, Cong; Feng, Chun-Lei; Oderji, Hassan Yousefi; Luo, Guang-Nan; Ding, Hong-Bin

    2016-12-01

    Nuclear fusion has enormous potential to greatly affect global energy production. The next-generation tokamak ITER, which is aimed at demonstrating the feasibility of energy production from fusion on a commercial scale, is under construction. Wall erosion, material transport, and fuel retention are known factors that shorten the lifetime of ITER during tokamak operation and give rise to safety issues. These factors, which must be understood and solved early in the process of fusion reactor design and development, are among the most important concerns for the community of plasma-wall interaction researchers. To date, laser techniques are among the most promising methods that can solve these open ITER issues, and laser-induced breakdown spectroscopy (LIBS) is an ideal candidate for online monitoring of the walls of current and next-generation (such as ITER) fusion devices. LIBS is a widely used technique for various applications. It has been considered recently as a promising tool for analyzing plasma-facing components in fusion devices in situ. This article reviews the experiments that have been performed by many research groups to assess the feasibility of LIBS for this purpose.

  8. Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

  9. The Fukushima nuclear disaster and its effects on media framing of fission and fusion energy technologies

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, Luisa; Horta, Ana; Pereira, Sergio; Delicado, Ana [Institute of Social Sciences of the University of Lisbon, Av. Prof. Anibal de Bettencourt, 9 1600-189 Lisbon (Portugal)

    2015-07-01

    This paper presents results of a comparison of media coverage of fusion and fission energy technologies in three countries (Germany, Spain and Portugal) and in the English language international print media addressing transnational elite, from 2008 to 2012. The analysis showed that the accident in Fukushima in March 2010 did not have significant impact on media framing of nuclear fusion in the major part of print media under investigation. In fact, fusion is clearly dissociated from traditional nuclear (fission) energy and from nuclear accidents. It tends to be portrayed as a safe, clean and unlimited source of energy, although less credited when confronted with research costs, technological feasibility and the possibility to be achieved in a reasonable period of time. On the contrary, fission is portrayed as a hazardous source of energy, expensive when compared to research costs of renewables, hardly a long-term energy option, susceptible to contribute to the proliferation of nuclear weapons or rogue military use. Fukushima accident was consistently discussed in the context of safety problems of nuclear power plants and in many cases appeared not as an isolated event but rather as a reminder of previous nuclear disasters such as Three Miles Island and Chernobyl. (authors)

  10. Proceedings of the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear Test-Ban Treaty

    Energy Technology Data Exchange (ETDEWEB)

    Warren, N. Jill [Editor

    1999-09-21

    These proceedings contain papers prepared for the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear-Test-Ban Treaty, held 21-24 September 1999 in Las Vegas, Nevada. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Technical Applications Center (AFTAC), Department of Defense (DoD), the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  11. Towards possible opportunities in nuclear materials science and technology at an X-ray free electron laser research facility

    Science.gov (United States)

    Froideval, A.; Badillo, A.; Bertsch, J.; Churakov, S.; Dähn, R.; Degueldre, C.; Lind, T.; Paladino, D.; Patterson, B. D.

    2011-09-01

    Spectroscopy and imaging of condensed matter have benefited greatly from the availability of intense X-ray beams from synchrotron sources, both in terms of spatial resolution and of elemental specificity. The advent of the X-ray free electron laser (X-ray FEL) provides the additional features of ultra-short pulses and high transverse coherence, which greatly expand possibilities to study dynamic processes and to image non-crystalline materials. The proposed SwissFEL facility at the Paul Scherrer Institute is one of at present four X-ray FEL projects worldwide and is scheduled to go into operation in the year 2017. This article describes a selection of problems in nuclear materials science and technology that would directly benefit from this and similar X-ray FEL sources. X-ray FEL-based experiments are proposed to be conducted on nuclear energy-related materials using single-shot X-ray spectroscopy, coherent X-ray scattering and/or X-ray photon correlation spectroscopy in order to address relevant scientific questions such as the evolution in time of the irradiation-induced damage processes, the deformation processes in nuclear materials, the ion diffusion processes in the barrier systems of geological repositories, the boiling heat transfer in nuclear reactors, as well as the structural characterization of graphite dust in advanced nuclear reactors and clay colloid aggregates in the groundwater near a radioactive waste repository.

  12. CEIDEN: Technological platform of R+D on fission technology; CEIDEN: La plataforma tecnologica de I+D de tecnologia nuclear de fision

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, J. M.; Carmena, P.; Gonzalez, E. M.; Leon, P. t.; Marchena, P.; Ortega, P.

    2007-07-01

    Technological platform CEIDEN is an organism to coordinate the R and D needs and efforts in the field of fission nuclear technology. Its objective is to develop joint projects that affect different entities with similar problems and to present a single position to the international proposals or compromises. In the CEIDEN Platform all the sectors related to the Spanish nuclear R and D are represented and its aim includes both nuclear power plants currently in opration and design of future reactors. (Author)

  13. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.

    1984-10-01

    The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage. (MOW)

  14. Robotics and nuclear power. Report by the Technology Transfer Robotics Task Team

    Energy Technology Data Exchange (ETDEWEB)

    1985-06-01

    A task team was formed at the request of the Department of Energy to evaluate and assess technology development needed for advanced robotics in the nuclear industry. The mission of these technologies is to provide the nuclear industry with the support for the application of advanced robotics to reduce nuclear power generating costs and enhance the safety of the personnel in the industry. The investigation included robotic and teleoperated systems. A robotic system is defined as a reprogrammable, multifunctional manipulator designed to move materials, parts, tools, or specialized devices through variable programmed motions for the performance of a variety of tasks. A teleoperated system includes an operator who remotely controls the system by direct viewing or through a vision system.

  15. Opening speech annual meeting on nuclear technology 2013, 14 to 16 May 2013, Berlin, Germany

    Energy Technology Data Exchange (ETDEWEB)

    Gueldner, Ralf [Deutsches Atomforum e.V. (DAtF), Berlin (Germany)

    2013-07-15

    Germany is an important location for nuclear technology also in the face of the 'Energiewende'. Our industry is not merely the object of political decisions, but it also continues to make its reliable and safe contribution to supplying energy and to this country's prosperity. The 9 nuclear power plants connected to the grid are a pillar of the energy supply especially for baseload generation, with an installed power of 12,700 MW at an average availability of over 90 %. With almost 100 billion kilowatt hours generated annually, they contributed 1/6 of the electricity generated in Germany in 2012 and made Germany the second largest nuclear power producer in the European Union. The nuclear power plants ensure, as do the other large power plants, the regional voltage and frequency stability and with their good controllability and the large standard service volume make an important contribution to integrating the production of electricity from renewables which is very high by international comparison. Nuclear technology in Germany is not restricted to the dismantling, final storage and remaining operations of plants, but rather it is made up of a vigorous, competitive nuclear industry that is among the best in the world. That does not merely show in the ranking of the nuclear power plants with the highest output rates, which placed 4 German plants in the top ten in the world also in 2012. It also becomes apparent when nuclear technology Made in Germany is sought after all over the world, in particular where the level of safety is concerned, e.g. worldwide in improving the safety of plants after the accident at Fukushima. Quite a number of safety components that are just being ordered elsewhere have been tried and tested for years already in Germany, and are supplied, installed and serviced by German suppliers and service providers. The broad range of the nuclear industry in Germany and its backing in a diverse research landscape means that the products

  16. Engineering Technology Reports, Volume 2: Technology Base FY01

    Energy Technology Data Exchange (ETDEWEB)

    Minichino, C; Meeker, D

    2002-07-01

    Engineering has touched on every challenge, every accomplishment, and every endeavor of Lawrence Livermore National Laboratory during its fifty-year history. In this time of transition to new leadership, Engineering continues to be central to the mission of the Laboratory, returning to the tradition and core values of E.O. Lawrence: science-based engineering--turning scientific concepts into reality. This volume of Engineering Technical Reports summarizes progress on the projects funded for technology-base efforts. Technology-base projects effect the natural transition to reduction-to-practice of scientific or engineering methods that are well understood and established. They represent discipline-oriented, core competency activities that are multi-programmatic in application, nature, and scope. Objectives of technology-base funding include: (1) the development and enhancement of tools and processes to provide Engineering support capability, such as code maintenance and improved fabrication methods; (2) the support of Engineering science and technology infrastructure, such as the installation or integration of a new capability; (3) support for technical and administrative leadership through our technology Centers; (4) the initial scoping and exploration of selected technology areas with high strategic potential, such as assessment of university, laboratory, and industrial partnerships.

  17. SCINTILLA A European project for the development of scintillation detectors and new technologies for nuclear security

    CERN Document Server

    Alemberti, A; Botta, E; De Vita, R; Fanchini, E; Firpo, G

    2014-01-01

    Europe monitors transits using radiation detectors to prevent illicit trafficking of nuclear materials. The SCINTILLA project aims to develop a toolbox of innovative technologies designed to address different usage cases. This article will review the scope, approach, results of the first benchmark campaign and future plans of the SCINTILLA project.

  18. 37 CFR 5.20 - Export of technical data relating to sensitive nuclear technology.

    Science.gov (United States)

    2010-07-01

    ... 37 Patents, Trademarks, and Copyrights 1 2010-07-01 2010-07-01 false Export of technical data... LICENSES TO EXPORT AND FILE APPLICATIONS IN FOREIGN COUNTRIES Licenses for Foreign Exporting and Filing § 5.20 Export of technical data relating to sensitive nuclear technology. Under regulations (10 CFR...

  19. 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.

  20. The detection of bulk explosives using nuclear-based techniques

    Energy Technology Data Exchange (ETDEWEB)

    Morgado, R.E.; Gozani, T.; Seher, C.C.

    1988-01-01

    In 1986 we presented a rationale for the detection of bulk explosives based on nuclear techniques that addressed the requirements of civil aviation security in the airport environment. Since then, efforts have intensified to implement a system based on thermal neutron activation (TNA), with new work developing in fast neutron and energetic photon reactions. In this paper we will describe these techniques and present new results from laboratory and airport testing. Based on preliminary results, we contended in our earlier paper that nuclear-based techniques did provide sufficiently penetrating probes and distinguishable detectable reaction products to achieve the FAA operational goals; new data have supported this contention. The status of nuclear-based techniques for the detection of bulk explosives presently under investigation by the US Federal Aviation Administration (FAA) is reviewed. These include thermal neutron activation (TNA), fast neutron activation (FNA), the associated particle technique, nuclear resonance absorption, and photoneutron activation. The results of comprehensive airport testing of the TNA system performed during 1987-88 are summarized. From a technical point of view, nuclear-based techniques now represent the most comprehensive and feasible approach for meeting the operational criteria of detection, false alarms, and throughput. 9 refs., 5 figs., 2 tabs.

  1. The state of the art on the dry decontamination technologies applicable to highly radioactive contaminants and their needs for the national nuclear fuel cycle developent

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Lee, K.W.; Won, H.J.; Jung, C.H.; Chol, W.K.; Kim, G.N.; Moon, J.K

    2000-12-01

    This report is intended to establish their needs to support the dry decontamination activities applicable to highly radioactive contaminants based on the requirement of technologies development suggested from the national nuclear fuel cycle projects, such as DUPIC, advanced spent fuel management and long-lived radionuclides conversion. The technology needs associated with decontamination addressed the requirements associated with the efficiency of decontamination technology, the reduction of secondary wastes, applicabilities and the remote operation. And also, Characterization and decontamination technologies for various contaminants are reviewed and analysed. Based on the assessment, Unit dry decontamination processes are selected and the schematic flow diagram for decontamination of highly radioactive contaminants.

  2. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, Alan Keith; Mc Cray, John Alan; Rogers, Adam Zachary; Simmons, R. F.; Palethorpe, S. J.

    1999-03-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  3. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program, FY-98 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.; Rogers, A.Z.; McCray, J.A.; Simmons, R.F.; Palethorpe, S.J.

    1999-03-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  4. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Hinckley, Steve Harold

    1999-10-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

  5. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    A. K. Herbst; J. A. McCray; R. J. Kirkham; J. Pao; S. H. Hinckley

    1999-09-30

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

  6. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Argyle, Mark Don; Lauerhass, Lance; Bendixsen, Carl Lee; Hinckley, Steve Harold

    2000-11-01

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  7. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.; McCray, J.A.; Kirkham, R.J.; Pao, J.; Argyle, M.D.; Lauerhass, L.; Bendixsen, C.L.; Hinckley, S.H.

    2000-10-31

    The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

  8. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program, FY-98 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.; Rogers, A.Z.; McCray, J.A.; Simmons, R.F.; Palethorpe, S.J.

    1999-03-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  9. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.; McCray, J.A.; Rogers, A.Z.; Simmons, R.F.; Palethrope, S.J.

    1999-03-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  10. JANIS: NEA JAva-based Nuclear Data Information System

    Directory of Open Access Journals (Sweden)

    Soppera Nicolas

    2017-01-01

    Full Text Available JANIS (JAva-based Nuclear Data Information System software is developed by the OECD Nuclear Energy Agency (NEA Data Bank to facilitate the visualization and manipulation of nuclear data, giving access to evaluated nuclear data libraries, such as ENDF, JEFF, JENDL, TENDL etc., and also to experimental nuclear data (EXFOR and bibliographical references (CINDA. It is available as a standalone Java program, downloadable and distributed on DVD and also a web application available on the NEA website. One of the main new features in JANIS is the scripting capability via command line, which notably automatizes plots generation and permits automatically extracting data from the JANIS database. Recent NEA software developments rely on these JANIS features to access nuclear data, for example the Nuclear Data Sensitivity Tool (NDaST makes use of covariance data in BOXER and COVERX formats, which are retrieved from the JANIS database. New features added in this version of the JANIS software are described along this paper with some examples.

  11. 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).

  12. Communication Technologies Preferred by School Based Administrators

    Science.gov (United States)

    Weir, Paul

    2012-01-01

    The purpose of this study was to determine the communication technologies preferred by school based administrators. This study surveyed and interviewed 96 school based administrators in a mid-sized suburban school system. The data show that individual emails, email lists, and cell phone technologies had the highest percentage effectiveness ratings…

  13. Cutting Technology for Decommissioning of the Reactor Pressure Vessels in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kim, Geun Ho; Moon, Jei Kwon; Choi, Byung Seon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Lots of nuclear power plants have been decommissioned during the last 2 decades. An essential part of this work is the dismantling of the Reactor Pressure Vessel and its Internals. For this purpose a wide variety of different cutting technologies have been developed, adapted and applied. A detailed introduction to Plasma Arc cutting, Contact Arc Metal cutting and Abrasive Water Suspension Jet cutting is given, as it turned out that these cutting technologies are particularly suitable for these type of segmentation work. A comparison of these technologies including gaseous emissions, cutting power, manipulator requirements as well as selected design approaches are given. Process limits as well as actual limits of application are presented

  14. 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)

  15. 我国核电技术创新及模式分析%Analysis on the Main Innovation Model of China's Nuclear Power Technology

    Institute of Scientific and Technical Information of China (English)

    黄栋; 刘雪姣

    2014-01-01

    从中国的能源状况以及节能减排需求来看,中国必须发展核电产业。核电发展的重点是进行核电技术创新。我国核电技术创新模式主要分为自主创新模式和模仿创新模式。基于政府和企业的角度分析我国核电技术创新的影响因素以及不同核电技术创新模式的实现路径。%From the point of view of China's energy situation and the demand for energy conservation,China must develop its nuclear power industry. The key point of nuclear power development is carrying out nuclear power technology innovation.China's nuclear power technology innovation modes are divided into independent innovation model and imitated innovation model. This article analyzed the factors influencing China’ s nuclear technology innovation based on the perspective of the government and enterprises. It also analyzed different paths to achieve nuclear technology innovation model.

  16. High Temperature Electrolysis for Hydrogen Production from Nuclear Energy – TechnologySummary

    Energy Technology Data Exchange (ETDEWEB)

    J. E. O' Brien; C. M. Stoots; J. S. Herring; M. G. McKellar; E. A. Harvego; M. S. Sohal; K. G. Condie

    2010-02-01

    The Department of Energy, Office of Nuclear Energy, has requested that a Hydrogen Technology Down-Selection be performed to identify the hydrogen production technology that has the best potential for timely commercial demonstration and for ultimate deployment with the Next Generation Nuclear Plant (NGNP). An Independent Review Team has been assembled to execute the down-selection. This report has been prepared to provide the members of the Independent Review Team with detailed background information on the High Temperature Electrolysis (HTE) process, hardware, and state of the art. The Idaho National Laboratory has been serving as the lead lab for HTE research and development under the Nuclear Hydrogen Initiative. The INL HTE program has included small-scale experiments, detailed computational modeling, system modeling, and technology demonstration. Aspects of all of these activities are included in this report. In terms of technology demonstration, the INL successfully completed a 1000-hour test of the HTE Integrated Laboratory Scale (ILS) technology demonstration experiment during the fall of 2008. The HTE ILS achieved a hydrogen production rate in excess of 5.7 Nm3/hr, with a power consumption of 18 kW. This hydrogen production rate is far larger than has been demonstrated by any of the thermochemical or hybrid processes to date.

  17. 64 International conference "NUCLEUS-2014" Fundamental problems of nuclear physics, atomic power engineering and nuclear technologies

    OpenAIRE

    Vlasnikov, A. K.

    2014-01-01

    Тезисы 64 международной конференции «ЯДРО-2014» (Фундаментальные проблемы ядерной физики, атомной энергетики и ядерных технологий), БГУ, Минск, 1 – 4 июля 2014 года. The scientific program of the conference covers almost all problems in nuclear physics and its applications such as: neutron-rich nuclei, nuclei far from stability valley, giant resonances, many-phonon and many-quasiparticle states in nuclei, high-spin and super-deformed states in nuclei, synthesis of super-heavy elements, ...

  18. Evaluation of thorium based nuclear fuel. Chemical aspects

    Energy Technology Data Exchange (ETDEWEB)

    Konings, R.J.M.; Blankenvoorde, P.J.A.M.; Cordfunke, E.H.P.; Bakker, K.

    1995-07-01

    This report describes the chemical aspects of a thorium-based fuel cycle. It is part of a series devoted to the study of thorium-based fuel as a means to achieve a considerable reduction of the radiotoxicity of the waste from nuclear power production. Therefore special emphasis is placed on fuel (re-)fabrication and fuel reprocessing in the present work. (orig.).

  19. 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.

  20. Irradiation characteristics examination technology development of irradiated nuclear material and high burn-up fuels

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Kwon Pyo; Choo, Y. S.; Oh, Y. W. [and others

    2002-12-01

    The research and development for the first year of the project are performed through specialization of researchers, information from aborad and international cooperation, securement of advanced nuclear technology, development and installation of test equipment, application of external man-power, establishment of advanced test techniques, and certified test method. 1. Absolute efficiency measurement examination technology development of gamma scanning system 2. Sample preparation technology development of SEM and EPMA for micro-structural observation and chemical composition analysis 3. Irradiated high burn-up nuclear fuel transportation and test for PWR 4. Development of hot cell examination techniques and equipment 5. Acquirement of KOLAS system. In addition to the project, the following activities are carried out as follows; - PIE of Hanaro fuel(KH99H-001) - PIE of U-Mo advanced nuclear fuel irradiated at Hanaro - PIE of Hi-MET advanced nuclear fuel irradiated at Hanaro - PIE of DUPIC project - Hot cell examination of Hanaro irradiated capsule - Leaching test of PWR fuels - Surveillance test of PWR vessels - Mechanical test of CANDU pressure tubes.

  1. 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

  2. Hydrogen Gas Production from Nuclear Power Plant in Relation to Hydrogen Fuel Cell Technologies Nowadays

    Science.gov (United States)

    Yusibani, Elin; Kamil, Insan; Suud, Zaki

    2010-06-01

    Recently, world has been confused by issues of energy resourcing, including fossil fuel use, global warming, and sustainable energy generation. Hydrogen may become the choice for future fuel of combustion engine. Hydrogen is an environmentally clean source of energy to end-users, particularly in transportation applications because without release of pollutants at the point of end use. Hydrogen may be produced from water using the process of electrolysis. One of the GEN-IV reactors nuclear projects (HTGRs, HTR, VHTR) is also can produce hydrogen from the process. In the present study, hydrogen gas production from nuclear power plant is reviewed in relation to commercialization of hydrogen fuel cell technologies nowadays.

  3. A review of nuclear data needs and their status for fusion reactor technology with some suggestions on a strategy to satisfy the requirements

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.L. [Argonne National Lab., IL (United States); Cheng, E.T. [TSI Research, Inc., Solana Beach, CA (United States)

    1991-09-01

    A review was performed on the needs and status of nuclear data for fusion-reactor technology. Generally, the status of nuclear data for fusion has been improved during the past two decades due to the dedicated effort of the nuclear data developers. However, there are still deficiencies in the nuclear data base, particularly in the areas of activation and neutron scattering cross sections. Activation cross sections were found to be unsatisfactory in 83 of the 153 reactions reviewed. The scattering cross sections for fluorine and boron will need to be improved at energies above 1 MeV. Suggestions concerning a strategy to address the specific fusion nuclear data needs for dosimetry and activation are also provided.

  4. The bungling giant : Atomic Energy Canada Limited and next-generation nuclear technology, 1980-1994

    Energy Technology Data Exchange (ETDEWEB)

    Slater, I.J

    2003-07-01

    From 1980-1994 Atomic Energy Canada Limited (AECL), the Crown Corporation responsible for the development of nuclear technology in Canada, ventured into the market for small-scale, decentralized power systems with the Slowpoke Energy System (SES), a 10MW nuclear reactor for space heating in urban and remote areas. The SES was designed to be 'passively' or 'inherently' safe, such that even the most catastrophic failure of the system would not result in a serious accident (e.g. a meltdown or an explosion). This Canadian initiative, a beneficiary of the National Energy Program, was the first and by far the most successful attempt at a passively safe, decentralized nuclear power system anywhere in the world. Part one uses archival documentation and interviews with project leaders to reconstruct the history of the SES. The standard explanations for the failure of the project, cheap oil, public resistance to the technology, and lack of commercial expertise, are rejected. Part two presents an alternative explanation for the failure of AECL to commercialize the SES. In short, technological momentum towards large-scale nuclear designs led to structural restrictions for the SES project. These restrictions manifested themselves internally to the company (e.g., marginalization of the SES) and externally to the company (e.g., licensing). In part three, the historical lessons of the SES are used to refine one of the central tenets of Popper's political philosophy, 'piecemeal social engineering.' Popper's presentation of the idea is lacking in detail; the analysis of the SES provides some empirical grounding for the concept. I argue that the institutions surrounding traditional nuclear power represent a form utopian social engineering, leading to consequences such as the suspension of civil liberties to guarantee security of the technology. The SES project was an example of a move from the utopian social engineering of large

  5. Contributions of the SCK.CEN Academy to education and training in nuclear science and technology

    Energy Technology Data Exchange (ETDEWEB)

    Coeck, Michele [SCK.CEN Academy, Boeretang 200, BE-2400 Mol (Belgium)

    2015-07-01

    Thanks to its thorough experience in the field of nuclear science and technology, its innovative research and the availability of large and unique nuclear installations, SCK.CEN is not only a renowned nuclear research institution, but also an important partner for nuclear education and training in Belgium as well as at international level. Within the SCK.CEN Academy, more than 60 years of nuclear expertise and experience gained from our different research projects is collected and transferred. In the interest of maintaining a competent workforce in industry, Healthcare, research, and policy, and of transferring nuclear knowledge and skills to the next generations, the SCK.CEN Academy takes it as its mission to: - provide guidance for students and early-stage researchers; - organize academic courses and customized training for professionals; - offer policy support with regard to education and training matters; - care for critical-intellectual capacities for society. Specifically in the domain of nuclear instrumentation the SCK.CEN Academy provides an opportunity to students at Bachelor, Master and PhD level to make use of the SCK.CEN infrastructure to support their thesis research or to perform an internship with the aim to improve and extend their knowledge and skills in a specific research or technical domain. Further, they can contribute to new findings in the field of nuclear instrumentation. The students are guided by our scientists, engineers and technicians who have years of experience in the relevant field. In addition, the SCK.CEN Academy contributes to traditional university education programs and delivers courses in several nuclear topics such as dosimetry. We also coordinate the Belgian Nuclear higher Engineering Network (BNEN), a one year (60 ECTS) master-after-master specialization in nuclear engineering in which 6 Belgian universities and SCK.CEN are involved. Beyond the contributions to academic education, we also provide several customized training

  6. Towards many-body based nuclear reaction modelling

    Science.gov (United States)

    Hilaire, Stéphane; Goriely, Stéphane

    2016-06-01

    The increasing need for cross sections far from the valley of stability poses a challenge for nuclear reaction models. So far, predictions of cross sections have relied on more or less phenomenological approaches, depending on parameters adjusted to available experimental data or deduced from systematic expressions. While such predictions are expected to be reliable for nuclei not too far from the experimentally known regions, it is clearly preferable to use more fundamental approaches, based on sound physical principles, when dealing with very exotic nuclei. Thanks to the high computer power available today, all the ingredients required to model a nuclear reaction can now be (and have been) microscopically (or semi-microscopically) determined starting from the information provided by a nucleon-nucleon effective interaction. This concerns nuclear masses, optical model potential, nuclear level densities, photon strength functions, as well as fission barriers. All these nuclear model ingredients, traditionally given by phenomenological expressions, now have a microscopic counterpart implemented in the TALYS nuclear reaction code. We are thus now able to perform fully microscopic cross section calculations. The quality of these ingredients and the impact of using them instead of the usually adopted phenomenological parameters will be discussed. Perspectives for the coming years will be drawn on the improvements one can expect.

  7. Technology for Bayton-cycle powerplants using solar and nuclear energy

    Science.gov (United States)

    English, R. E.

    1986-01-01

    Brayton cycle gas turbines have the potential to use either solar heat or nuclear reactors for generating from tens of kilowatts to tens of megawatts of power in space, all this from a single technology for the power generating system. Their development for solar energy dynamic power generation for the space station could be the first step in an evolution of such powerplants for a very wide range of applications. At the low power level of only 10 kWe, a power generating system has already demonstrated overall efficiency of 0.29 and operated 38 000 hr. Tests of improved components show that these components would raise that efficiency to 0.32, a value twice that demonstrated by any alternate concept. Because of this high efficiency, solar Brayton cycle power generators offer the potential to increase power per unit of solar collector area to levels exceeding four times that from photovoltaic powerplants using present technology for silicon solar cells. The technologies for solar mirrors and heat receivers are reviewed and assessed. This Brayton technology for solar powerplants is equally suitable for use with the nuclear reactors. The available long time creep data on the tantalum alloy ASTAR-811C show that such Brayton cycles can evolve to cycle peak temperatures of 1500 K (2240 F). And this same technology can be extended to generate 10 to 100 MW in space by exploiting existing technology for terrestrial gas turbines in the fields of both aircraft propulsion and stationary power generation.

  8. Cognitive neurorehabilitation based on interactive video technology

    OpenAIRE

    Martinez Moreno, Jose Maria; Solana Sánchez, Javier; R. Sánchez; González Palmero, S.; Sánchez González, Patricia; Gómez Pérez, C.; Morell Vilaseca, Marc; Cáceres Taladriz, César; Roig Rovira, Teresa; Tormos Muñoz, Josep M.; Gómez Aguilera, Enrique J.

    2013-01-01

    Cognitive impairment is the main cause of disability in developed societies. New interactive technologies help therapists in neurorehabilitation in order to increase patients’ autonomy and quality of life. This work proposes Interactive Video (IV) as a technology to develop cognitive rehabilitation tasks based on Activities of Daily Living (ADL). ADL cognitive task has been developed and integrated with eye-tracking technology for task interaction and patients’ performance monitoring....

  9. Neutronic simulation calculations to assess the proliferation resistance of nuclear technologies; Neutronenphysikalische Simulationsrechnungen zur Proliferationsresistenz nuklearer Technologien

    Energy Technology Data Exchange (ETDEWEB)

    Englert, Matthias

    2009-07-13

    This thesis investigates the proliferation resistance of nuclear technologies on the basis of three case studies. After a brief description of the concept of proliferation resistance the utilized computer codes and methods are presented. The first case study investigates the potential of monolithic fuel for the conversion of one-fuel-element high-flux research reactors from highly enriched to low enriched uranium using the example of the german research reactor FRM-II. The second case study assesses the proliferation potential of future tokamak based fusion reactors by using neutronic simulations of a possible plutonium production. The third example investigates the proliferation potential of spallation neutron sources to produce nuclear weapon relevant material and the proliferation resistance of such facilities. (orig.)

  10. New computer simulation technology of WSPEEDI for local and regional environmental assessment during nuclear emergency

    Energy Technology Data Exchange (ETDEWEB)

    Chino, Masamichi; Furuno, Akiko; Terada, Hiroaki; Kitabata, Hideyuki [Japan Atomic Energy Research Institute, Ibaraki-Ken (Japan)

    2002-07-01

    The increase of nuclear power plants in the Asian region necessitates the capability to predict long-range atmospheric dispersions of radionuclides and radiological impacts due to a nuclear accident. For this purpose, we have developed a computer-based emergency response system WSPEEDI. This paper aims to expanding the capability of WSPEEDI so that it can be applied to simultaneous multi-scale predictions of local and regional scales in the Asian region.

  11. Ship-Based Nuclear Energy Systems for Accelerating Developing World Socioeconomic Advance

    Science.gov (United States)

    Petroski, Robert; Wood, Lowell

    2014-07-01

    Technological, economic, and policy aspects of supplying energy to newly industrializing and developing countries using ship-deployed nuclear energy systems are described. The approach analyzed comprises nuclear installations of up to gigawatt scale deployed within currently mass-produced large ship hulls which are capable of flexibly supplying energy for electricity, water desalination and district heating-&-cooling with low latencies and minimized shoreside capital expenditures. Nuclear energy is uniquely suited for mobile deployment due to its combination of extraordinary energy density and high power density, which enable enormous supplies of energy to be deployed at extremely low marginal costs. Nuclear installations on ships also confer technological advantages by essentially eliminating risk from earthquakes, tsunamis, and floods; taking advantage of assured access to an effectively unlimited amount of cooling water, and involving minimal onshore preparations and commitments. Instances of floating nuclear power stations that have been proposed in the past, some of which are currently being pursued, have generally been based on conventional LWR technology, moreover without flexibility or completeness of power output options. We consider nuclear technology options for their applicability to the unique opportunities and challenges of a marine environment, with special attention given to low-pressure, high thermal margin systems with continuous and assured afterheat dissipation into the ambient seawater. Such systems appear promising for offering an exceptionally high degree of safety while using a maximally simple set of components. We furthermore consider systems tailored to Developing World contexts, which satisfy societal requirements beyond electrification, e.g., flexible sourcing of potable water and HVAC services, servicing time-varying user requirements, and compatibility with the full spectrum of local renewable energy supplies, specifically including

  12. Nuclear medicine technology. Review questions for the board examinations. 4. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Ramer, Karen [Ochotnicky Partners s.r.o., Marianka (Slovakia); Mantel, Eleanor [Pennsylvania Univ., Hammonton, NJ (United States). Nuclear Medicine/Molecular Imaging; Reddin, Janet S.; Alavi, Abass [Pennsylvania Univ., Philadelphia, PA (United States). Radiology/Nuclear Medicine; Cheng, Gang [Philadelphia VA Medical Center, PA (United States). Radiology

    2013-07-01

    The only comprehensive exam preparation guide on the market. Includes a mock registry exam. Provides expanded coverage of positron emission tomography and other new procedures and practices. This book prepares students and technologists for registry examinations in nuclear medicine technology by providing practice questions and answers with detailed explanations, as well as a mock registry exam. The questions are designed to test the basic knowledge required of nuclear medicine technologists, as well as the practical application of that knowledge. The topics covered closely follow the content specifications and the components of preparedness as published by the certification boards. This 4th edition includes expanded coverage of positron emission tomography and other new procedures and practices in the field of nuclear medicine and molecular imaging.

  13. Space nuclear power: technology, policy, and risk considerations in human missions to Mars.

    Science.gov (United States)

    Friedensen, V P

    1998-01-01

    There is a large discrepancy between potential needs for nuclear propulsion and power systems for the human exploration of Mars and the current status of R&D funding, public opinion, and governmental support for these technologies. Mission planners and spacecraft designers, energized by the recent claims of possible discovery of life on Mars and responding to increased public interest in the human exploration of Mars, frequently propose nuclear reactors and radioisotope thermoelectric generators (RTGs) for interplanetary spacecraft propulsion and for power supply on the surface of Mars. These plans and designs typically assume that reactors will be available "on-the-shelf," and do not take the extensive R&D costs required to develop such reactors into consideration. However, it is likely that current U.S. policies, if unchanged, will prohibit the launch of nuclear reactors and large RTGs in response to a perceived risk by the public.

  14. Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

    Energy Technology Data Exchange (ETDEWEB)

    Joung, Chang Young; Ahn, Sung Ho; Heo, Sung Ho; Hong, Jin Tae; Kim, Ka Hye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses.

  15. Supporting Technology for Chain of Custody of Nuclear Weapons and Materials throughout the Dismantlement and Disposition Processes

    Energy Technology Data Exchange (ETDEWEB)

    Bunch, Kyle J.; Jones, Anthony M.; Ramuhalli, Pradeep; Benz, Jacob M.; Denlinger, Laura S.

    2014-05-04

    The ratification and ongoing implementation of the New START Treaty have been widely regarded as noteworthy global security achievements for both the Obama Administration and the Putin (formerly Medvedev) regime. But deeper cuts that move beyond the United States and Russia to engage the P-5 and other nuclear weapons possessor states are envisioned under future arms control regimes, and are indeed required for the P-5 in accordance with their Article VI disarmament obligations in the Nuclear Non-Proliferation Treaty. Future verification needs will include monitoring the cessation of production of new fissile material for weapons, monitoring storage of warhead components and fissile materials and verifying dismantlement of warheads, pits, secondary stages, and other materials. A fundamental challenge to implementing a nuclear disarmament regime is the ability to thwart unauthorized material diversion throughout the dismantlement and disposition process through strong chain of custody implementation. Verifying the declared presence, or absence, of nuclear materials and weapons components throughout the dismantlement and disposition lifecycle is a critical aspect of the disarmament process. From both the diplomatic and technical perspectives, verification under these future arms control regimes will require new solutions. Since any acceptable verification technology must protect sensitive design information and attributes to prevent the release of classified or other proliferation-sensitive information, non-nuclear non-sensitive modalities may provide significant new verification tools which do not require the use of additional information barriers. Alternative verification technologies based upon electromagnetic and acoustics could potentially play an important role in fulfilling the challenging requirements of future verification regimes. For example, researchers at the Pacific Northwest National Laboratory (PNNL) have demonstrated that low frequency electromagnetic

  16. Broken Arrows: Radiological hazards from nuclear warhead accidents (the Minot USAF base nuclear weapons incident)

    CERN Document Server

    Liolios, Theodore

    2009-01-01

    According to numerous press reports, in 2007 at Minot US Air Force Base six AGM-129 Advanced Cruise Missiles mistakenly armed with W80-1 thermonuclear warheads were loaded on a B-52H heavy bomber in place of six unarmed AGM-129 missiles that were awaiting transport to Barksdale US Air Force Base for disposal. The live nuclear missiles were not reported missing, and stood unsecured and unguarded while mounted to the aircraft for a period of 36 hours. The present work investigates the radiological hazards associated with a worst-case postulated accident that would disperse the nuclear material of the six warheads in large metropolitan cities. Using computer simulations approximate estimates are derived for the ensuing cancer mortality and land contamination after the accident. Health, decontamination and evacuation costs are also estimated in the framework of the linear risk model.

  17. High frame rate imaging systems developed in Northwest Institute of Nuclear Technology

    Science.gov (United States)

    Li, Binkang; Wang, Kuilu; Guo, Mingan; Ruan, Linbo; Zhang, Haibing; Yang, Shaohua; Feng, Bing; Sun, Fengrong; Chen, Yanli

    2007-01-01

    This paper presents high frame rate imaging systems developed in Northwest Institute of Nuclear Technology in recent years. Three types of imaging systems are included. The first type of system utilizes EG&G RETICON Photodiode Array (PDA) RA100A as the image sensor, which can work at up to 1000 frame per second (fps). Besides working continuously, the PDA system is also designed to switch to capture flash light event working mode. A specific time sequence is designed to satisfy this request. The camera image data can be transmitted to remote area by coaxial or optic fiber cable and then be stored. The second type of imaging system utilizes PHOTOBIT Complementary Metal Oxygen Semiconductor (CMOS) PB-MV13 as the image sensor, which has a high resolution of 1280 (H) ×1024 (V) pixels per frame. The CMOS system can operate at up to 500fps in full frame and 4000fps partially. The prototype scheme of the system is presented. The third type of imaging systems adopts charge coupled device (CCD) as the imagers. MINTRON MTV-1881EX, DALSA CA-D1 and CA-D6 camera head are used in the systems development. The features comparison of the RA100A, PB-MV13, and CA-D6 based systems are given in the end.

  18. Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Staiger, M. Daniel, Swenson, Michael C.

    2011-09-01

    This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

  19. Dissemination of medical applications of nuclear energy with virtual reality technology

    Energy Technology Data Exchange (ETDEWEB)

    Botelho, Felipe M.; Oliveira, Beatriz A.R. [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro, RJ (Brazil). Escola de Belas Artes]. E-mail: felipemurybotelho@yahoo.com.br; Jorge, Carlos A.F.; Mol, Antonio C.A.; Lapa, Celso M.F. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: lapa@ien.gov.br

    2007-07-01

    This work makes use of Virtual Reality technology to disseminate medical applications of nuclear energy, with educational purposes. Virtual Reality is an effective learning tool, since navigation and interaction in virtual worlds can improve motivation in the learning process. With this technology, learning can be achieved in a clearer, joyful and more objective way. Among the existing medical applications of nuclear energy, this work focuses on the use of radiopharmaceuticals. The goal is to simulate this application in a virtual environment, for educational purposes, and to show the absorption of a radiopharmaceutical by the human body, during a diagnostics or treatment procedure. An example has been chosen, for Iodine radiopharmaceutical, which has affinity with the thyroid, and then concentrates in this organ. During the simulation, the concentration of the radioactive Iodine in the thyroid can be emphasized, and in the sequence, the virtual patient can be shown during the imaging procedure. (author)

  20. Technology development on the assessment of structural integrity of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jeong Moon; Choun, Y. S.; Choi, I. K. and others

    1999-04-01

    Nuclear power plants in Korea show drop off in their performance and safety margin as the age of plants increase. The reevaluation of Kori-1 Unit on its performance and safety for life extension is expected in the near future. However, technologies and information related are insufficient to quantitatively estimate them. The final goal of this study is to develop the basic testing and evaluation techniques related with structural integrity of important nuclear equipment and structures. A part of the study includes development of equipment qualification technique. To ensure the structural integrity of structures, systems, and equipment in nuclear power plants, the following 5 research tasks were performed in the first year. - Analysis of dynamic characteristics of reactor internals - Analysis of engineering characteristics of instrumental earthquakes recorded in Korea - Analysis of ultimate pressure capacity and failure mode of containments building - Development of advanced NDE techniques using ultrasonic resonance scattering - Development of equipment qualification technique against vibration aging. These technologies developed in this study can be used to ensure the structural safety of operational nuclear power plants, and for the long-term life management. (author)

  1. Technology development on the assessment of structural integrity of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jeong Moon; Choun, Y. S.; Choi, I. K. and others

    1999-04-01

    Nuclear power plants in Korea show drop off in their performance and safety margin as the age of plants increase. The reevaluation of Kori-1 Unit on its performance and safety for life extension is expected in the near future. However, technologies and information related are insufficient to quantitatively estimate them. The final goal of this study is to develop the basic testing and evaluation techniques related with structural integrity of important nuclear equipment and structures. A part of the study includes development of equipment qualification technique. To ensure the structural integrity of structures, systems, and equipment in nuclear power plants, the following 5 research tasks were performed in the first year. - Analysis of dynamic characteristics of reactor internals - Analysis of engineering characteristics of instrumental earthquakes recorded in Korea - Analysis of ultimate pressure capacity and failure mode of containments building - Development of advanced NDE techniques using ultrasonic resonance scattering - Development of equipment qualification technique against vibration aging. These technologies developed in this study can be used to ensure the structural safety of operational nuclear power plants, and for the long-term life management. (author)

  2. Proceedings of the 30th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marv A [Los Alamos National Laboratory; Aguilar-chang, Julio [Los Alamos National Laboratory; Arrowsmith, Marie [Los Alamos National Laboratory; Arrowsmith, Stephen [Los Alamos National Laboratory; Baker, Diane [Los Alamos National Laboratory; Begnaud, Michael [Los Alamos National Laboratory; Harste, Hans [Los Alamos National Laboratory; Maceira, Monica [Los Alamos National Laboratory; Patton, Howard [Los Alamos National Laboratory; Phillips, Scott [Los Alamos National Laboratory; Randall, George [Los Alamos National Laboratory; Revelle, Douglas [Los Alamos National Laboratory; Rowe, Charlotte [Los Alamos National Laboratory; Stead, Richard [Los Alamos National Laboratory; Steck, Lee [Los Alamos National Laboratory; Whitaker, Rod [Los Alamos National Laboratory; Yang, Xiaoning [Los Alamos National Laboratory

    2008-09-23

    These proceedings contain papers prepared for the 30th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 23-25 September, 2008 in Portsmouth, Virginia. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States’ capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  3. Enabling Technologies for Ultra-Safe and Secure Modular Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    Mendez Cruz, Carmen Margarita [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rochau, Gary E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Middleton, Bobby [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rodriguez, Salvador B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rodriguez, Carmelo [General Atomics, San Diego, CA (United States); Schleicher, Robert [General Atomics, San Diego, CA (United States)

    2016-06-01

    Sandia National Laboratories and General Atomics are pleased to respond to the Advanced Research Projects Agency-Energy (ARPA-e)’s request for information on innovative developments that may overcome various current reactor-technology limitations. The RFI is particularly interested in innovations that enable ultra-safe and secure modular nuclear energy systems. Our response addresses the specific features for reactor designs called out in the RFI, including a brief assessment of the current state of the technologies that would enable each feature and the methods by which they could be best incorporated into a reactor design.

  4. Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

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

    Energy Technology Data Exchange (ETDEWEB)

    Hashemian, H.M. [Analysis and Measurement Services Corporation, Knoxville, TN (United States)

    1996-03-01

    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&C) systems for the next generation of reactors and in older plants which are retrofitted with new I&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.

  6. Evaluation of Non-Nuclear Techniques for Well Logging: Technology Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Leonard J.; Denslow, Kayte M.; Griffin, Jeffrey W.; Dale, Gregory E.; Harris, Robert V.; Moran, Traci L.; Sheen, David M.; Schenkel, Thomas

    2010-11-01

    This report presents an initial review of the state-of-the-art nuclear and non-nuclear well logging methods and seeks to understand the technical and economic issues if AmBe, and potentially other isotope sources, are reduced or even eliminated in the oil-field services industry. Prior to considering alternative logging technologies, there is a definite need to open up discussions with industry regarding the feasibility and acceptability of source replacement. Industry views appear to range from those who see AmBe as vital and irreplaceable to those who believe that, with research and investment, it may be possible to transition to electronic neutron sources and employ combinations of non-nuclear technologies to acquire the desired petro-physical parameters. In one sense, the simple answer to the question as to whether petro-physical parameters can be sensed with technologies other than AmBe is probably "Yes". The challenges come when attention turns to record interpretation. The many decades of existing records form a very valuable proprietary resource, and the interpretation of subtle features contained in these records are of significant value to the oil-gas exploration community to correctly characterize a well. The demonstration of equivalence and correspondence/correlation between established and any new sensing modality, and correlations with historic records is critical to ensuring accurate data interpretation. Establishing the technical basis for such a demonstration represents a significant effort.

  7. Defining the “proven technology” technical criterion in the reactor technology assessment for Malaysia’s nuclear power program

    Energy Technology Data Exchange (ETDEWEB)

    Anuar, Nuraslinda, E-mail: nuraslinda@uniten.edu.my [College of Engineering, Universiti Tenaga Nasional, Jalan IKRAM-UNITEN, 43000 Kajang, Selangor (Malaysia); Kahar, Wan Shakirah Wan Abdul, E-mail: shakirah@tnb.com.my; Manan, Jamal Abdul Nasir Abd [Nuclear Energy Department, Regulatory Economics and Planning Division, Tenaga Nasional Berhad, No. 8 Jalan Tun Sambanthan, Brickfields, 50470 Kuala Lumpur (Malaysia)

    2015-04-29

    Developing countries that are considering the deployment of nuclear power plants (NPPs) in the near future need to perform reactor technology assessment (RTA) in order to select the most suitable reactor design. The International Atomic Energy Agency (IAEA) reported in the Common User Considerations (CUC) document that “proven technology” is one of the most important technical criteria for newcomer countries in performing the RTA. The qualitative description of five desired features for “proven technology” is relatively broad and only provides a general guideline to its characterization. This paper proposes a methodology to define the “proven technology” term according to a specific country’s requirements using a three-stage evaluation process. The first evaluation stage screens the available technologies in the market against a predefined minimum Technology Readiness Level (TRL) derived as a condition based on national needs and policy objectives. The result is a list of technology options, which are then assessed in the second evaluation stage against quantitative definitions of CUC desired features for proven technology. The potential technology candidates produced from this evaluation is further narrowed down to obtain a list of proven technology candidates by assessing them against selected risk criteria and the established maximum allowable total score using a scoring matrix. The outcome of this methodology is the proven technology candidates selected using an accurate definition of “proven technology” that fulfills the policy objectives, national needs and risk, and country-specific CUC desired features of the country that performs this assessment. A simplified assessment for Malaysia is carried out to demonstrate and suggest the use of the proposed methodology. In this exercise, ABWR, AP1000, APR1400 and EPR designs assumed the top-ranks of proven technology candidates according to Malaysia’s definition of “proven technology”.

  8. Evaluation methodology for seismic base isolation of nuclear equipments

    Energy Technology Data Exchange (ETDEWEB)

    Ebisawa, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)); Uga, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))

    1993-08-01

    An evaluation methodology for seismic base isolated nuclear equipments is proposed. The evaluation can be classified into two steps. In the first step, the seismic functional failure probability during the lifetime of equipment without base isolation devices is quantified in order to decide the applicability of the base isolated structure. The second step is comparative and calculates the ratio of the seismic failure frequency of the equipment without base isolation devices to that with them in order to evaluate the effectiveness of the base isolated structure. The sample evaluation considers the case of high voltage type emergency transformer with ceramic tubes. (orig.)

  9. Prevention and Thinking of the Risk of Nuclear Technology%核技术风险的防范与思考

    Institute of Scientific and Technical Information of China (English)

    高盼

    2012-01-01

    核技术是当今高技术的重要组成部分.核技术在给人类造福的同时,也带来一些值得人们关注的风险.当下能源危机愈演愈烈,核技术带来的新型能源是解决目前能源短缺的重要手段.然而,人们在使用核技术的过程中要采取必要的防范措施来使这一技术更好的造福于人类.%Nuclear technology is an important part of today's high-tech. Nuclear technology brings the benefit for mankind, it also brings the risk at the same time. With the energy crisis, the new energy based on nuclear technology is an important means to solve the current energy shortage. However, we have to take the necessary precautions to make this technology better bring the benefit for mankind in the use of nuclear technology.

  10. Nonproliferation impacts assessment for the management of the Savannah River Site aluminum-based spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    On May 13, 1996, the US established a new, 10-year policy to accept and manage foreign research reactor spent nuclear fuel containing uranium enriched in the US. The goal of this policy is to reduce civilian commerce in weapons-usable highly enriched uranium (HEU), thereby reducing the risk of nuclear weapons proliferation. Two key disposition options under consideration for managing this fuel include conventional reprocessing and new treatment and packaging technologies. The Record of Decision specified that, while evaluating the reprocessing option, ``DOE will commission or conduct an independent study of the nonproliferation and other (e.g., cost and timing) implications of chemical separation of spent nuclear fuel from foreign research reactors.`` DOE`s Office of Arms Control and Nonproliferation conducted this study consistent with the aforementioned Record of Decision. This report addresses the nonproliferation implications of the technologies under consideration for managing aluminum-based spent nuclear fuel at the Savannah River Site. Because the same technology options are being considered for the foreign research reactor and the other aluminum-based spent nuclear fuels discussed in Section ES.1, this report addresses the nonproliferation implications of managing all the Savannah River Site aluminum-based spent nuclear fuel, not just the foreign research reactor spent nuclear fuel. The combination of the environmental impact information contained in the draft EIS, public comment in response to the draft EIS, and the nonproliferation information contained in this report will enable the Department to make a sound decision regarding how to manage all aluminum-based spent nuclear fuel at the Savannah River Site.

  11. Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

    1995-10-20

    The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

  12. Developing competence based qualification system in the nuclear energy sector

    Energy Technology Data Exchange (ETDEWEB)

    Ceclan, Mihail [European Commission, Petten (Netherlands). Inst. for Energy and Transport

    2016-04-15

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  13. Evaluation of High Energy Nuclear Data of Importance for Use in Accelerator and Space Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Ouk

    2005-10-15

    New evaluation were performed for neutron- and proton-induced reactions for energies up to 250 400 MeV on C-12, N-14, O-16, Al-27, Si-28, Ca-40, Ar-40, Fe-54,58, Ni-64, Cu-63,65, Zr-90, Pb-208, Th-232, U-233,234,236, and Cm-243246. The evaluated results are then applied to the accelerator and space technology. A set of optical model parameters were optimized by searching a number of adjustable coefficients with the Simulated Annealing(SA) method for the spherical nuclei. A parameterization of the empirical formula was proposed to describe the proton-nucleus non-elastic cross sections of high-priority elements for space shielding purpose for proton energies from reaction threshold up to 400 MeV, which was then implemented into the fast scoping space shielding code CHARGE, based on the results of the optical model analysis utilizing up-to-date measurements. For proton energies up to 400 MeV covering most of the incident spectrum for trapped protons and solar energetic particle events, energy-angle spectra of secondary neutrons produced from the proton-induced neutron production reaction were prepared. The evaluated cross section set was applied to the thick target yield (TTY) and promp radiation benchmarks for the accelerator shielding. As for the assessment of the radiological impact of the accelerator to the environment, relevant nuclear reaction cross sections for the activation of the air were recommended among the author's evaluations and existing library based on the available measurements.

  14. CAD-based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC

    Science.gov (United States)

    Wu, Yican; Song, Jing; Zheng, Huaqing; Sun, Guangyao; Hao, Lijuan; Long, Pengcheng; Hu, Liqin

    2014-06-01

    Monte Carlo (MC) method has distinct advantages to simulate complicated nuclear systems and is envisioned as routine method for nuclear design and analysis in the future. High fidelity simulation with MC method coupled with multi-physical phenomenon simulation has significant impact on safety, economy and sustainability of nuclear systems. However, great challenges to current MC methods and codes prevent its application in real engineering project. SuperMC is a CAD-based Monte Carlo program for integrated simulation of nuclear system developed by FDS Team, China, making use of hybrid MC-deterministic method and advanced computer technologies. The design aim, architecture and main methodology of SuperMC were presented in this paper. SuperMC2.1, the latest version for neutron, photon and coupled neutron and photon transport calculation, has been developed and validated by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model. SuperMC is still in its evolution process toward a general and routine tool for nuclear system. Warning, no authors found for 2014snam.conf06023.

  15. Micro technology based sun sensor

    DEFF Research Database (Denmark)

    Hales, Jan Harry; Pedersen, Martin; Fléron, René

    2003-01-01

    There is increasing interest among universities in the scientific and educational possibilities of picosatellites base on the CubeSat 5 concept. Due to sever mass and dimension constraints place on this type of satellites, new approaches and ideas regarding different systems arises to accommodate...... DTUsat sun sensors are needed along with a magnetometer to obtain unambiguous attitude determination for the ACDS and the payloads - an electrodynamic tether and a camera. The accuracy needed was not obtainable by employing conventional attitude sensors. Hence a linear slit sensor was designed...

  16. Space-Based Observation Technology

    Science.gov (United States)

    2007-11-02

    jusqu’ici par des systèmes aéroportés, par des systèmes spatiaux. Les capteurs spatiaux sont des capteurs radar et optiques . Les capteurs optiques ...de l’observation de la terre à partir de capteurs spatiaux offre de nombreux avantages par rapport à l’observation à partir de capteurs terrestres...résolution optique . Le SAR a également d’autres fonctionnalités telles que la classification basée sur les techniques Doppler ou la polarimétrie, la

  17. The Science of Nuclear Materials: A Modular, Laboratory-based Curriculum

    Energy Technology Data Exchange (ETDEWEB)

    Cahill, C.L., E-mail: cahill@gwu.edu [Department of Chemistry and Elliott School of International Affairs, The George Washington University, Washington, DC 20052 (United States); Feldman, G.; Briscoe, W.J. [Department of Physics, The George Washington University, Washington, DC 20052 (United States)

    2014-06-15

    The development of a curriculum for nuclear materials courses targeting students pursuing Master of Arts degrees at The George Washington University is described. The courses include basic concepts such as radiation and radioactivity as well as more complex topics such the nuclear fuel cycle, nuclear weapons, radiation detection and technological aspects of non-proliferation.

  18. Gap analysis survey: an aid in transitioning to standardized curricula for nuclear medicine technology.

    Science.gov (United States)

    Bires, Angela Macci; Mason, Donna L; Gilmore, David; Pietrzyk, Carly

    2012-09-01

    This article discusses the process by which the Society of Nuclear Medicine Technology Section (SNMTS) is assisting educators as they transition to comply with the fourth edition of the Curriculum Guide for Educational Programs in Nuclear Medicine Technology. An electronic survey was sent to a list of nuclear medicine technology programs compiled by the educational division of the SNMTS. The collected data included committee member demographics, goals and objectives, conference call minutes, consultation discussions, transition examples, 4- and 2-y program curricula, and certificate program curricula. There were 56 responses to the survey. All respondents were program directors, with 3 respondents having more than one type of program, for a total of 59 programs. Of these, 19 (33.93%) were baccalaureate, 19 (28.57%) associate, and 21 (37.5%) certificate. Forty-eight respondents (85.71%) had accreditation through the Joint Review Commission on Educational Programs in Nuclear Medicine Technology, 6 (10.71%) had regional accreditation, and 2 (3.57%) were accredited through other entities. Thirteen categories of required general education courses were identified, and the existing program curricula of 9 (69.2%) courses were more than 50% compliant with the fourth edition Curriculum Guide. The fact that no measurable gap could be found within the didactic professional content across programs was due to the lack of a degree requirement and content standardization within the profession. The data indicated that the participating programs offer a minimum of 1-15 contact hours in emerging technology modalities. The required clinical hours ranged from 765 to 1,920 for degree or certificate completion. The average number of clinical hours required for all programs was 1,331.69. Standardization of the number and types of courses is needed both for current baccalaureate programs and for clinical education. This standardization will guide programs in transitioning from a

  19. Proceedings of seventh symposium on sharing of computer programs and technology in nuclear medicine, computer assisted data processing

    Energy Technology Data Exchange (ETDEWEB)

    Howard, B.Y.; McClain, W.J.; Landay, M. (comps.)

    1977-01-01

    The Council on Computers (CC) of the Society of Nuclear Medicine (SNM) annually publishes the Proceedings of its Symposium on the Sharing of Computer Programs and Technology in Nuclear Medicine. This is the seventh such volume and has been organized by topic, with the exception of the invited papers and the discussion following them. An index arranged by author and by subject is included.

  20. A novel fiber-based adsorbent technology

    Energy Technology Data Exchange (ETDEWEB)

    Reynolds, T.A. [Chemica Technologies, Inc., Bend, OR (United States)

    1997-10-01

    In this Phase I Small Business Innovation Research program, Chemica Technologies, Inc. is developing an economical, robust, fiber-based adsorbent technology for removal of heavy metals from contaminated water. The key innovation is the development of regenerable adsorbent fibers and adsorbent fiber cloths that have high capacity and selectivity for heavy metals and are chemically robust. The process has the potential for widespread use at DOE facilities, mining operations, and the chemical process industry.

  1. Implicit attitudes toward nuclear power and mobile phone base stations: support for the affect heuristic.

    Science.gov (United States)

    Siegrist, Michael; Keller, Carmen; Cousin, Marie-Eve

    2006-08-01

    The implicit association test (IAT) measures automatic associations. In the present research, the IAT was adapted to measure implicit attitudes toward technological hazards. In Study 1, implicit and explicit attitudes toward nuclear power were examined. Implicit measures (i.e., the IAT) revealed negative attitudes toward nuclear power that were not detected by explicit measures (i.e., a questionnaire). In Study 2, implicit attitudes toward EMF (electro-magnetic field) hazards were examined. Results showed that cell phone base stations and power lines are judged to be similarly risky and, further, that base stations are more closely related to risk concepts than home appliances are. No differences between experts and lay people were observed. Results of the present studies are in line with the affect heuristic proposed by Slovic and colleagues. Affect seems to be an important factor in risk perception.

  2. Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Hui Zhang; Raman P. Singh

    2008-11-30

    Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys base on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiCf-SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor componets is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.

  3. Recent progress in EDF-based methods applied to nuclear properties

    Directory of Open Access Journals (Sweden)

    Khan E.

    2014-03-01

    Full Text Available Recent results obtained with energy density functional (EDF based methods are presented, focused on the nuclear phenomenology. EDF approaches aim for an universal description of the nuclear phenomena over the nuclear chart. Achievements from large to small nuclear systems are depicted: equation of state of nuclear matter, heavy and light nuclei. Dynamical aspects such as nuclear excitations, decay and reactions are also presented. EDF methods are progressing towards an unified and systematic description of the rich variety of the nuclear phenomena such as quantum liquid and cluster states, or nuclear structure and reactions.

  4. Polarized nuclear target based on parahydrogen induced polarization

    Energy Technology Data Exchange (ETDEWEB)

    Budker, D., E-mail: dbudker@gmail.com [Department of Physics, University of California at Berkeley, Berkeley, CA 94720-7300 (United States); Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Ledbetter, M.P. [Department of Physics, University of California at Berkeley, Berkeley, CA 94720-7300 (United States); Appelt, S. [Central Institute for Electronics, Research Center Juelich, D-52425 Juelich (Germany); Bouchard, L.S. [Department of Chemistry and Biochemistry, California NanoSystems Institute, Biomedical Engineering IDP, Jonsson Comprehensive Cancer Center, University of California, Los Angeles, CA 90095 (United States); Wojtsekhowski, B. [Thomas Jefferson National Accelerator Facility, Newport News, VA 23606 (United States)

    2012-12-01

    We discuss a novel concept of a polarized nuclear target for accelerator fixed-target scattering experiments, which is based on parahydrogen induced polarization (PHIP). One may be able to reach a 33% free-proton polarization in the ethane molecule. The potential advantages of such a target include operation at zero magnetic field, fast ({approx}100Hz) polarization oscillation (akin to polarization reversal), and operation with large intensity of an electron beam. -- Highlights: Black-Right-Pointing-Pointer Novel concept for polarized nuclear targets. Black-Right-Pointing-Pointer The target features fast reversal and operates at near-zero magnetic field. Black-Right-Pointing-Pointer Based on the technique of parahydrogen induced polarization that is revolutionizing NMR and enables NMR/MRI without magnets. Black-Right-Pointing-Pointer Competitive figure-of-merit for polarized targets.

  5. Nuclear technology and chronic diseases: an exploratory study evolving the clinical physician perception; Doencas cronicas e tecnologia nuclear: estudo exploratorio envolvendo a percepcao de medicos clinicos

    Energy Technology Data Exchange (ETDEWEB)

    Sato, Renato Cesar

    2010-07-01

    This research is an exploratory cross-sectional study about the relationship of chronic disease and the use of nuclear technology. There is a concern over the increase of the prevalence of chronic disease in developing countries and it should hence be carefully evaluated in the context of societies, organizations and individuals. The technological advances experienced in the last decades especially in the nuclear technology area have created expectations to deal more efficiently with the challenge of chronic diseases. However little has been explored in this area under the point-of-view of medical doctors as agents who make this system of relations between disease and technology. The necessity for public and private planning to deal with this set of problems can benefit through an initial evaluation about the forthcoming theme, but should incorporate the agenda of health and technology planning for the following years. Using mixed methodology, made up of qualitative and quantitative approach, this research sought to reveal and configure important dimensions around the theme of this study. The field research was made up of interviews analyzed using techniques of fundamental theory and also of questionnaires sent by web analyzed statistically using exploratory factor analysis. These ventures allowed dimensions to be revealed that make up the perception of chronic disease and the use of nuclear technology. These dimensions presented in a form of a theoretical construct that were then discussed under the point of view of social theory and technological innovation. (author)

  6. Polarized nuclear target based on parahydrogen induced polarization

    Energy Technology Data Exchange (ETDEWEB)

    D. Budker, M.P. Ledbetter, S. Appelt, L.S. Bouchard, B. Wojtsekhowski

    2012-12-01

    We discuss a novel concept of a polarized nuclear target for accelerator fixed-target scattering experiments, which is based on parahydrogen induced polarization (PHIP). One may be able to reach a 33% free-proton polarization in the ethane molecule. The potential advantages of such a target include operation at zero magnetic field, fast ({approx}100 HZ) polarization oscillation (akin to polarization reversal), and operation with large intensity of an electron beam.

  7. Australian Nuclear Science and Technology Organization. Annual Report 1995-1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    The report provides an overview of the outcomes achieved and the current activities of ANSTO related to its core business activities. The core business of ANSTO were identified as follows: international strategic relevance of nuclear science; core facilities operation and development; applications of nuclear science and technology to the understanding of natural processes; treatment and management of man-made and naturally occurring radioactive substances; competitiveness and ecological sustainability of industry and organizational development and support. The report also include specific reporting against those performance indicators that were negotiated with the Government as part of the Triennium Funding Agreement and are regarded as appropriate for science agencies or for ANSTO specifically. Contains a glossary and an detailed index. tables., figures.

  8. 4{sup +}D Technology{sup TM} for nuclear systems soft solutions

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Kune Y., E-mail: kysuh@philosophia.co.k [Philosophia, Inc., Seoul National University, 599 Gwanak-Ro, Gwanak-Gu, 151-744 Seoul (Korea, Republic of)

    2010-10-15

    The signature in the proposal lies with the NSSS (Nuclear Systems Soft Solutions). NSSS proposed in the 3-dimensional space and time plus cost coordinates, i.e. 4{sup +} dimensional technology, is the backbone of digital engineering in the nuclear system design and management. The NSSS is empowered by Janus (Junctional Analysis Neo dynamic Unit Soft Power), NOTUS (Neo systemic Optimization Technical Unit Soft Power), Venus (Virtual Engineering Neo cybernetic Unit Soft Power), EURUS (Engineering Utilities Research Unit Soft Power) and INUUS (Informative Neo graphic Utilities Unit Soft Power). Janus extracts the geometric data directly from the computer-aided design CAD files to import to multidimensional computational fluid and structural dynamics codes. Janus uses the joint-CAD analysis methods to eliminate the necessity of any pre- and post- processors. Starting from the 3-dimensional CAD, NOTUS contributes to reducing the construction cost of the nuclear power plants by optimizing the component manufacturing procedure and the plant construction process. Planning and scheduling construction projects can thus benefit greatly by integrating traditional management techniques with digital process simulation visualization. The 3-dimensional visualization of construction processes and resulting products intrinsically afford most of the advantages realized by the 4{sup +}D technology. Problems with equipment positioning and manpower congestion in certain areas can readily be visualized prior to the actual operation, thus preventing accidents and safety problems such as collision between two machines and losses in productivity. Venus applied the virtual reality technology in nuclear industry. Virtual reality provides an interactive real time motion with sound and tactile and other forms of feedback. The management and workers can thus comprehend the work process crystal clear by visualizing precisely how activities relate to one another, whereby reducing conflicting

  9. 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)

  10. Non-Nuclear Testing of Compact Reactor Technologies at NASA MSFC

    Science.gov (United States)

    Houts, Michael G.; Pearson, J. Boise; Godfroy, Thomas J.

    2011-01-01

    Safe, reliable, compact, autonomous, long-life fission systems have numerous potential applications, both terrestrially and in space. Technologies and facilities developed in support of these systems could be useful to a variety of concepts. At moderate power levels, fission systems can be designed to operate for decades without the need for refueling. In addition, fast neutron damage to cladding and structural materials can be maintained at an acceptable level. Nuclear design codes have advanced to the stage where high confidence in the behavior and performance of a system can be achieved prior to initial testing. To help ensure reactor affordability, an optimal strategy must be devised for development and qualification. That strategy typically involves a combination of non-nuclear and nuclear testing. Non-nuclear testing is particularly useful for concepts in which nuclear operating characteristics are well understood and nuclear effects such as burnup and radiation damage are not likely to be significant. To be mass efficient, a SFPS must operate at higher coolant temperatures and use different types of power conversion than typical terrestrial reactors. The primary reason is the difficulty in rejecting excess heat to space. Although many options exist, NASA s current reference SFPS uses a fast spectrum, pumped-NaK cooled reactor coupled to a Stirling power conversion subsystem. The reference system uses technology with significant terrestrial heritage while still providing excellent performance. In addition, technologies from the SFPS system could be applicable to compact terrestrial systems. Recent non-nuclear testing at NASA s Early Flight Fission Test Facility (EFF-TF) has helped assess the viability of the reference SFPS and evaluate methods for system integration. In July, 2011 an Annular Linear Induction Pump (ALIP) provided by Idaho National Laboratory was tested at the EFF-TF to assess performance and verify suitability for use in a10 kWe technology

  11. The Sustainable Nuclear Future: Fission and Fusion E.M. Campbell Logos Technologies

    Science.gov (United States)

    Campbell, E. Michael

    2010-02-01

    Global industrialization, the concern over rising CO2 levels in the atmosphere and other negative environmental effects due to the burning of hydrocarbon fuels and the need to insulate the cost of energy from fuel price volatility have led to a renewed interest in nuclear power. Many of the plants under construction are similar to the existing light water reactors but incorporate modern engineering and enhanced safety features. These reactors, while mature, safe and reliable sources of electrical power have limited efficiency in converting fission power to useful work, require significant amounts of water, and must deal with the issues of nuclear waste (spent fuel), safety, and weapons proliferation. If nuclear power is to sustain its present share of the world's growing energy needs let alone displace carbon based fuels, more than 1000 reactors will be needed by mid century. For this to occur new reactors that are more efficient, versatile in their energy markets, require minimal or no water, produce less waste and more robust waste forms, are inherently safe and minimize proliferation concerns will be necessary. Graphite moderated, ceramic coated fuel, and He cooled designs are reactors that can satisfy these requirements. Along with other generation IV fast reactors that can further reduce the amounts of spent fuel and extend fuel resources, such a nuclear expansion is possible. Furthermore, facilities either in early operations or under construction should demonstrate the next step in fusion energy development in which energy gain is produced. This demonstration will catalyze fusion energy development and lead to the ultimate development of the next generation of nuclear reactors. In this presentation the role of advanced fission reactors and future fusion reactors in the expansion of nuclear power will be discussed including synergies with the existing worldwide nuclear fleet. )

  12. The technology vicinity: a location based view on technology

    NARCIS (Netherlands)

    Steenhuis, H.J.; de Bruijn, E.J.; Kocaoglu, D.F.; Anderson, T.R.

    2001-01-01

    The issue of technology transfer has been viewed from many different perspectives. In this case the focus is on the process of (production) technology transfer. One of the difficulties in studying international technology transfer is the definition of technology. The many technology definitions that

  13. 核热推进技术综述%Overview of nuclear thermal propulsion technologies

    Institute of Scientific and Technical Information of China (English)

    廖宏图

    2011-01-01

    The advantages of nuclear thermal propulsion (NTP) over existing traditional propulsion technologies are analyzed. Some technical approaches which are possible to be realized are presented. The current state-of-the-art technologies of NTP using solid nuclear reactor are introduced emphatically. The space mission analysis results reported by by some articles about solid phase NTD technology are summarized. The current conditions of development are analyzed after introduction on the deevelopment history of NTP. Some suggestions on future development of NTP in China are made.%分析了核热推进相对于现有传统推进技术的优势,介绍了可能的技术实现途径,重点是目前已经实现的固相核热推进技术,并归纳了有关文献对于固相核热推进技术的空间应用分析结果;介绍了核热推进技术的发展历程,并对当前发展态势进行了分析;最后针对我国发展核热推进技术提出几点考虑。

  14. Nuclear Medicine.

    Science.gov (United States)

    Badawi, Ramsey D.

    2001-01-01

    Describes the use of nuclear medicine techniques in diagnosis and therapy. Describes instrumentation in diagnostic nuclear medicine and predicts future trends in nuclear medicine imaging technology. (Author/MM)

  15. Development of technology-neutral safety requirements for the regulation of future nuclear power reactors: Back to basics

    Energy Technology Data Exchange (ETDEWEB)

    Tronea, Madalina, E-mail: madalina.tronea@gmail.co [Faculty of Physics, University of Bucharest (Romania)

    2011-03-15

    This paper explores the current trends as regards the development of technology-neutral safety requirements to be used in the regulation of future nuclear power reactors and the role of the quantitative safety goals in the design of reactor safety systems. The use of the recommendations of the International Commission on Radiological Protection (ICRP) on protection against potential exposure could form the basis of a technology-neutral framework for safety requirements on new reactor designs and could contribute to international harmonisation of nuclear safety assessment practices as part of the licensing processes for future nuclear power plants.

  16. WDM PONs based on colorless technology

    Science.gov (United States)

    Saliou, Fabienne; Simon, Gael; Chanclou, Philippe; Pizzinat, Anna; Lin, Huafeng; Zhou, Enyu; Xu, Zhiguang

    2015-12-01

    Wavelength Division Multiplexing (WDM) Passive Optical Network (PON) is foreseen to be part of the Next Generation Passive Optical Networks. Business and mobile fronthaul networks already express the need to develop WDM PONs in the access segment. Fixed wavelength transceivers based on Coarse WDM are already available to respond to today's market needs but Dense WDM technologies will be needed and colorless technologies are essential to provide simple and cost-effective WDM PON systems. We propose in this paper to demonstrate the capabilities of a DWDM PON system prototype based on self-seeded RSOAs and designed to transmit CPRI over 60 km of fiber at 2.5 Gbit/s.

  17. Use of liquid metals in nuclear and thermonuclear engineering, and in other innovative technologies

    Science.gov (United States)

    Rachkov, V. I.; Arnol'dov, M. N.; Efanov, A. D.; Kalyakin, S. G.; Kozlov, F. A.; Loginov, N. I.; Orlov, Yu. I.; Sorokin, A. P.

    2014-05-01

    By now, a good deal of experience has been gained with using liquid metals as coolants in nuclear power installations; extensive knowledge has been gained about the physical, thermophysical, and physicochemical properties of these coolants; and the scientific principles and a set of methods and means for handling liquid metals as coolants for nuclear power installations have been elaborated. Prototype and commercialgrade sodium-cooled NPP power units have been developed, including the BOR-60, BN-350, and BN-600 power units (the Soviet Union); the Rapsodie, Phenix, and Superphenix power units (France), the EBR-II power unit (the United States); and the PFR power unit (the United Kingdom). In Russia, dedicated nuclear power installations have been constructed, including those with a lead-bismuth coolant for nuclear submarines and with sodium-potassium alloy for spacecraft (the Buk and Topol installations), which have no analogs around the world. Liquid metals (primarily lithium and its alloy with lead) hold promise for use in thermonuclear power engineering, where they can serve not only as a coolant, but also as tritium-producing medium. In this article, the physicochemical properties of liquid metal coolants, as well as practical experience gained from using them in nuclear and thermonuclear power engineering and in innovative technologies are considered, and the lines of further research works are formulated. New results obtained from investigations carried out on the Pb-Bi and Pb for the SVBR and BREST fast-neutron reactors (referred to henceforth as fast reactors) and for controlled accelerator systems are described.

  18. ICT security- aspects important for nuclear facilities; Information and Communication Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Thunem, Atoosa P-J.

    2005-09-15

    Rapid application growth of complex Information and Communication Technologies (ICT) in every society and state infrastructure as well as industry has revealed vulnerabilities that eventually have given rise to serious security breaches. These vulnerabilities together with the course of the breaches from cause to consequence are gradually about to convince the field experts that ensuring the security of ICT-driven systems is no longer possible by only relying on the fundaments of computer science, IT, or telecommunications. Appropriating knowledge from other disciplines is not only beneficial, but indeed very necessary. At the same time, it is a common observation today that ICT-driven systems are used everywhere, from the nuclear, aviation, commerce and healthcare domains to camera-equipped web-enabled cellular phones. The increasing interdisciplinary and inter-sectoral aspects of ICT security worldwide have been providing updated and useful information to the nuclear domain, as one of the emerging users of ICT-driven systems. Nevertheless, such aspects have also contributed to new and complicated challenges, as ICT security for the nuclear domain is in a much more delicate manner than for any other domains related to the concept of safety, at least from the public standpoint. This report addresses some important aspects of ICT security that need to be considered at nuclear facilities. It deals with ICT security and the relationship between security and safety from a rather different perspective than usually observed and applied. The report especially highlights the influence on the security of ICT-driven systems by all other dependability factors, and on that basis suggests a framework for ICT security profiling, where several security profiles are assumed to be valid and used in parallel for each ICT-driven system, sub-system or unit at nuclear facilities. The report also covers a related research topic of the Halden Project with focus on cyber threats and

  19. Communicating Customer Value Based on Modern Technologies

    Directory of Open Access Journals (Sweden)

    Slawomir Czarniewski

    2014-06-01

    Full Text Available The article presents the idea of gaining a position of competitive advantage by companies operating in the knowledge-based economy and in the age of modern technology. The rate of change in companies’ environments forces organizations to react quickly to clients’ needs. In recent years, there has been an observed systematic increase in the importance of communicating customer value in Poland. This paper shows changes (trends in the system of market communication in the age of modern technology and changes in the economy. The author presents the mechanisms and effects of communication in age new technology in Poland. Modern technologies enable the collection, storage and transmission of information. Reflections contained in the paper do not have definite characteristics and should be treated as an opinion in the discussion.

  20. Tests for manufacturing technology of disposal canisters for nuclear spent fuel; Loppusijoituskapselin valmistustekniset kokeet

    Energy Technology Data Exchange (ETDEWEB)

    Raiko, H. [VTT Energy (Finland); Salonen, T. [Outokumpu Poricopper Oy (Finland); Meuronen, I. [Suomen Teknohaus Oy (Finland); Lehto, K. [Valmet Oyj Rautpohja Foundry (Finland)

    1999-06-01

    The summary and status of the results of the manufacturing technology programmes concerning the disposal canister for spent nuclear fuel conducted by Posiva Oy are given in this report. Posiva has maintained a draft plan for a disposal canister design and an assessment of potential manufacturing technologies for about ten years in Finland. Now, during the year 1999, the first full scale demonstration canister is manufactured in Finland. The technology used for manufacturing of this prototype is developed by Posiva Oy mainly in co-operation with domestic industry. The main partner in developing the manufacturing technology for the copper shell has been Outokumpu Poricopper Oy, Pori, Finland, and the main partner in developing the technology for the iron insert of the canister has been Valmet Oyj Rautpohja Foundry, Jyvaeskylae, Finland. In both areas many subcontractors have been used, predominantly domestic engineering workshops, but also some foreign subcontractors, e.g. for EB-welding, who have had large enough welding equipment. This report describes the developing programmes for canister manufacturing, evaluates the results and presents some alternative methods, and tries to evaluate the pros and contras of them. In addition, the adequacy of the achieved technological know-how is assessed in respect of the required quality of the disposal canister. The following manufacturing technologies have been the concrete topics of the development programme: Electron beam welding technology development for thick-walled copper, Casting of massive copper billets, Hot rolling of thick-walled copper plates, Hot pressing and forging in lid manufacture, Extrusion and drawing of copper tubes, Bending of copper plates by roller or press, Machining of copper, Residual stress removal by heat treatment, Non-destructive testing, Long-term strength of EB-welds, Casting and machining of the iron insert of the canister The specialists from all the main developing partner companies have

  1. New technologies of information treatment in the ERP of the Almaraz and Trillo nuclear power plants; Nuevas tecnologias de tratamiento de la informacion en el ERP de las centrales nucleares de Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Lopez-Suevos, C.; Gonzalez Crego, E.

    2013-03-01

    The Almaraz and Trillo Nuclear Power Plants are equipped with an Integrated Operation Management System (SIGE), which covers practically all of their transactional and management needs in all areas, with the exception of some specific engineering and simulation tools. In recent years, applications based on new computer technologies have been developed and integrated into the SIGE, including a Maintenance Dashboard, an Admissions Office ant the use of bar code readers, all of which are described in this article. (Author)

  2. V-Model based Configuration Management Program for New-Build Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Kyungik [PartDB Co. Ltd., Daejeon (Korea, Republic of); Cho, Yoon Sang [KHNP Co. Ltd., Daejeon (Korea, Republic of); Freeland, Kent R. [Industrial Analysts Incorporated, New Hampshire (United States)

    2014-05-15

    As NPP operators undertook design basis reconstitution efforts, they began to realize that the design basis is a foundation for Configuration Management (CM). This realization was made evident in the magnitude of the problems that were being observed. This experience also raised serious questions about how the information being developed to produce the design basis documents would be kept up to date in the future. A process to reconstitute the design basis is likely to be ineffective if CM controls are not in place. The right IT solution for CM depends upon a number of factors, including the nuclear power plant culture, budget, target technology, and the nuclear power plant owner/operator's standards, requirements and limitations for its generating fleet. Comprehensive CM Program for NPP is the single greatest strategy to meet the commitment to nuclear excellence. The safety and viability of nuclear power, particularly at the fleet level, depends upon the development of positive design control and design basis to better understanding plant operating dynamics and margin management, along with technology to control the realization of such design in the physical plant. However the most of plant facilities are modified many times, often without suitable support needed to confirm with their design base and to update their engineering data, maintenance rules and operating procedures. This lack of equilibrium between the requirements, design information and physical plant still remains a important issue. This study focuses on how to manage the configuration information of NPP using systems engineering V-model approach, and proposes data model to manage the configuration information in relation to manage their life cycle. Comprehensive CM Program and IMS for NPP life cycle support is the greatest strategy to meet the commitment to nuclear safety.

  3. Principles and status of neutron-based inspection technologies

    Science.gov (United States)

    Gozani, Tsahi

    2011-06-01

    and energetically significantly different from the background, thus making them readily distinguishable. The penetrability of neutrons as probes and signatures as well as the gamma ray signatures make neutron interrogation applicable to the inspection of large conveyances such as cars, trucks, marine containers and also smaller objects like explosive mines concealed in the ground. The application of nuclear interrogation techniques greatly depends on operational requirements. For example explosive mines and IED detection clearly require one-sided inspection, which excludes transmission based inspection (e.g., transmission radiography) and greatly limits others. The technologies developed over the last decades are now being implemented with good results. Further advances have been made over the last several years that increase the sensitivity, applicability and robustness of these systems. The principle, applications and status of neutron-based inspection techniques will be reviewed.

  4. [Advances in peroxide-based decontaminating technologies].

    Science.gov (United States)

    Xi, Hai-ling; Zhao, San-ping; Zhou, Wen

    2013-05-01

    With the boosting demand for eco-friendly decontaminants, great achievements in peroxide-based decontaminating technologies have been made in recent years. These technologies have been applied in countering chemical/biological terrorist attacks, dealing with chemical/biological disasters and destructing environmental pollutants. Recent research advances in alpha-nucleophilic/oxidative reaction mechanisms of peroxide-based decontamination against chemical warfare agents were reviewed, and some classical peroxide-based decontaminants such as aqueous decontaminating solution, decontaminating foam, decontaminating emulsions, decontaminating gels, decontaminating vapors, and some newly developed decontaminating media (e.g., peroxide-based self-decontaminating materials and heterogeneous nano-catalytic decontamination systems) were introduced. However, currently available peroxide-based decontaminants still have some deficiencies. For example, their decontamination efficiencies are not as high as those of chlorine-containing decontaminants, and some peroxide-based decontaminants show relatively poor effect against certain agents. More study on the mechanisms of peroxide-based decontaminants and the interfacial interactions in heterogeneous decontamination media is suggested. New catalysts, multifunctional surfactants, self-decontaminating materials and corrosion preventing technologies should be developed before peroxide-based decontaminants really become true "green" decontaminants.

  5. 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.)

  6. Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.

    2000-02-01

    A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state.

  7. Public dialogue on physics and related technology after the Fukushima Daiichi nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Sasao, Mamiko [Organization for Research Initiatives and Development, Doshisha University, Kyoto (Japan)

    2015-12-31

    After the Fukushima Daiichi Nuclear Accident, the importance of bottom-up and two-way dialogue between scientists and the public has been recognized. In such dialogue, information provided must accurately match the public’s interest and ability regarding science and technology. We have started to investigate what people want to know about physics. Some were interested in energy security (a particular concern in Japan), but others were concerned about radioactivity in food and natural radiation background. The conversations revealed that physicists often give insufficient explanations of the biological effects of radiation and highlighted key points for physicists to make when talking with the public.

  8. NASA thermionic converter research and technology program. [nuclear electric propulsion application

    Science.gov (United States)

    Lundholm, J. G.

    1975-01-01

    This paper describes the NASA/ERDA research and technology program that was initiated in mid-FY 1974 with the objective of doubling the efficiency of thermionic power conversion with decreased emitter temperature. Also discussed are the potential uses of thermionic power conversion systems. Emphasis in this paper is placed on potential space applications, especially nuclear-electric propulsion (NEP). Possible development schedules are shown that would allow NEP systems to be ready for use in the 1990 time period for missions to the outer planets.

  9. Materials technology for an advanced space power nuclear reactor concept: Program summary

    Science.gov (United States)

    Gluyas, R. E.; Watson, G. K.

    1975-01-01

    The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C coolant outlet), lithium-cooled, nuclear space power reactor concept are reviewed and discussed. Fabrication methods and compatibility and property data were developed for candidate materials for fuel pins and, to a lesser extent, for potential control systems, reflectors, reactor vessel and piping, and other reactor structural materials. The effects of selected materials variables on fuel pin irradiation performance were determined. The most promising materials for fuel pins were found to be 85 percent dense uranium mononitride (UN) fuel clad with tungsten-lined T-111 (Ta-8W-2Hf).

  10. Public dialogue on physics and related technology after the Fukushima Daiichi nuclear accident

    Science.gov (United States)

    Sasao, Mamiko

    2015-12-01

    After the Fukushima Daiichi Nuclear Accident, the importance of bottom-up and two-way dialogue between scientists and the public has been recognized. In such dialogue, information provided must accurately match the public's interest and ability regarding science and technology. We have started to investigate what people want to know about physics. Some were interested in energy security (a particular concern in Japan), but others were concerned about radioactivity in food and natural radiation background. The conversations revealed that physicists often give insufficient explanations of the biological effects of radiation and highlighted key points for physicists to make when talking with the public.

  11. Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods

    Science.gov (United States)

    Mariani, Robert Dominick

    2014-09-09

    Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350.degree. C. to 750.degree. C., and a second additive having a solubility in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350.degree. C. to 750.degree. C. and a solubility of the second additive in the first additive over the temperature range extending from 350.degree. C. to 750.degree. C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

  12. Sensitivity-Uncertainty Based Nuclear Criticality Safety Validation

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of New Mexico, Albuquerque, NM (United States). Nuclear Engineering Dept.

    2016-09-20

    These are slides from a seminar given to the University of Mexico Nuclear Engineering Department. Whisper is a statistical analysis package developed to support nuclear criticality safety validation. It uses the sensitivity profile data for an application as computed by MCNP6 along with covariance files for the nuclear data to determine a baseline upper-subcritical-limit for the application. Whisper and its associated benchmark files are developed and maintained as part of MCNP6, and will be distributed with all future releases of MCNP6. Although sensitivity-uncertainty methods for NCS validation have been under development for 20 years, continuous-energy Monte Carlo codes such as MCNP could not determine the required adjoint-weighted tallies for sensitivity profiles. The recent introduction of the iterated fission probability method into MCNP led to the rapid development of sensitivity analysis capabilities for MCNP6 and the development of Whisper. Sensitivity-uncertainty based methods represent the future for NCS validation – making full use of today’s computer power to codify past approaches based largely on expert judgment. Validation results are defensible, auditable, and repeatable as needed with different assumptions and process models. The new methods can supplement, support, and extend traditional validation approaches.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-08-15

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

  14. Nuclear Power Plant Operator Reliability Research Based on Fuzzy Math

    Directory of Open Access Journals (Sweden)

    Fang Xiang

    2011-01-01

    Full Text Available This paper makes use of the concept and theory of fuzzy number in fuzzy mathematics, to research for the response time of operator in accident of Chinese nuclear power plant. Through the quantitative analysis for the performance shape factors (PSFs which influence the response time of operators, the formula of the operator response time is obtained based on the possibilistic fuzzy linear regression model which is used for the first time in this kind of research. The research result shows that the correct research method can be achieved through the analysis of the information from a small sample. This method breaks through the traditional research method and can be used not only for the reference to the safe operation of nuclear power plant, but also in other areas.

  15. Cement-Based Materials for Nuclear Waste Storage

    CERN Document Server

    Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

    2013-01-01

    As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

  16. 7. Annual seminar of the scientific initiation of the Center for Development of Nuclear Technology. Abstracts; 7. Seminario anual de iniciacao cientifica do Centro de Desenvolvimento da Tecnologia Nuclear. Resumos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-01

    This seminar presents the Scientific Initiation Program developed at the CDTN - Brazilian Center for the Development of Nuclear Technology and focuses on activities of the sectors of: radiopharmaceutical production; radiation applied to health; waste management; structural integrity; environment; nanotechnology and nuclear materials; reactor technology; mineral technology; reactor and analytical techniques.

  17. Biomimetic Cilia Based on MEMS Technology

    Institute of Scientific and Technical Information of China (English)

    Zhi-guo Zhou; Zhi-wen Liu

    2008-01-01

    A review on the research of Micro Electromechanical Systems (MEMS) technology based biomimetic cilia is presented. Biomimetic cilia, enabled by the advancement of MEMS technology, have been under dynamic development for the past decade. After a brief description of the background of cilia and MEMS technology, different biomimetic cilia applications are reviewed. Biomimetic cilia micro-actuators, including micromachined polyimide bimorph biomimetic cilia micro-actuator, electro-statically actuated polymer biomimetic cilia micro-actuator, and magnetically actuated nanorod array biomimetic cilia micro-actuator, are presented. Subsequently micromachined underwater flow biomimetic cilia micro-sensor is studied, followed by acoustic flow micro-sensor. The fabrication of these MEMS-based biomimetic cilia devices, characterization of their physical properties, and the results of their application experiments are discussed.

  18. Recover of the nuclear energy: strategic option and technological innovation - vision 2005; Retomada da energia nuclear: opcao estrategica e inovacao tecnologica - visao 2005

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Marcio Soares; Mattos, Joao Roberto Loureiro de; Vasconcelos, Vanderley de [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mails: jrmattos@cdtn.br; marciod@cdtn.br; vasconv@cdtn.br; Jordao, Elizabete [Universidade Estadual de Campinas (UNICAMP), Campinas, SP (Brazil). Faculdade de Engenharia Quimica

    2006-07-01

    Considering the projections for the electric power demand, forecasted to first 25 years of the 21 century, and the technological innovations under demonstration in the mitigation of radioactive wastes, the nuclear option was included on a definitive way in the agenda of the countries as an environmental, economic and political acceptable option.

  19. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-15

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities.

  20. Methodology for gathering nuclear energy literature; Metodologia de coleta para alimentacao de uma base de dados em energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, Maria B.M.A.

    1996-12-31

    Several activities related to gathering information and documents -conventional and non-conventional primary literature - to include in a bibliographic nuclear energy database are described and arranged, using as model the communication and information process in science and technology and the analysis of the indexed documents in the database. Methodological steps are identified and a collecting system model is presented. 112 refs., 4 tabs.

  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. Technology-based Mergers and Acquisitions

    DEFF Research Database (Denmark)

    Wang, Daojuan; Moini, Hamid

    2014-01-01

    The purpose of this chapter is to provide an updated review of what is known about the performance of technology-based mergers and acquisitions (TBM&As) and their determinants. This review brings together papers published from 1990 to 2012 in top-rated academic journals within nearly all fields...

  3. DWDM Devices Based on Planar Waveguide Technologies

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    A review is presented on some of our recent results for designs, simulations and fabrication of several photonic integrated devices, such as arrayed-waveguide gratings (AWGs) and etched diffraction gratings (EDGs), based on planar waveguide technologies. Some novel designs for flat-top AWGs and EDGs with flat-top spectral responses are presented.

  4. Designing Personalization in Technology-Based Services

    Science.gov (United States)

    Lee, Min Kyung

    2013-01-01

    Personalization technology has the potential to optimize service for each person's unique needs and characteristics. One way to optimize service is to allow people to customize the service themselves; another is to proactively tailor services based on information provided by people or inferred from their past behaviors. These approaches function…

  5. Technology-based Mergers and Acquisitions

    DEFF Research Database (Denmark)

    Wang, Daojuan; Moini, Hamid

    2014-01-01

    The purpose of this chapter is to provide an updated review of what is known about the performance of technology-based mergers and acquisitions (TBM&As) and their determinants. This review brings together papers published from 1990 to 2012 in top-rated academic journals within nearly all fields...

  6. Establishment of nuclear knowledge and information infrastructure; establishment of web-based database system for nuclear events

    Energy Technology Data Exchange (ETDEWEB)

    Park, W. J.; Kim, K. J. [Korea Atomic Energy Research Institute , Taejeon (Korea); Lee, S. H. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2001-05-01

    Nuclear events data reported by nuclear power plants are useful to prevent nuclear accidents at the power plant by examine the cause of initiating events and removal of weak points in the aspects of operational safety, and to improve nuclear safety in design and operation stages by backfitting operational experiences and practices 'Nuclear Event Evaluation Database : NEED' system distributed by CD-ROM media are upgraded to the NEED-Web (Web-based Nuclear Event Evaluation Database) version to manage event data using database system on network basis and the event data and the statistics are provided to the authorized users in the Nuclear Portal Site and publics through Internet Web services. The efforts to establish the NEED-Web system will improve the integrity of events data occurred in Korean nuclear power plant and the usability of data services, and enhance the confidence building and the transparency to the public in nuclear safety. 11 refs., 27 figs. (Author)

  7. Attutude-action consistency and social policy related to nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Lindell, M.K.; Perry, R.W.; Greene, M.

    1980-06-01

    This study reports the results of a further analysis of questionnaire data--parts of which have been previously reported by Lindell, Earle, Hebert and Perry (1978)--that are related to the issue of consistency of attitudes and behavior toward nuclear power and nuclear waste management. Three factors are considered that might be expected to have a significant bearing on attitude-action consistency: social support, attitude object importance and past activism. Analysis of the data indicated that pronuclear respondents were more likely to show consistency of attitudes and actions (66%) than were antinuclear respondents (51%) although the difference in proportions is not statistically significant. Further analyses showed a strong positive relation between attitude-action consistency and perceived social support, measured by the degree to which the respondent believed that close friends and work associated agreed with his attitude. This relationship held up even when controls for attitude object importance and past activism were introduced. Attitude object importance--the salience of the issue of energy shortage--had a statistically significant effect only when perceived social support was low. Past activism had no significant relation to attitude-action consistency. These data suggest that the level of active support for or opposition to nuclear technology will be affected by the distribution of favorable and unfavorable attitudes among residents of an area. Situations in which pro- and antinuclear attitudes are concentrated among members of interacting groups, rather than distributed randomly, are more likely to produce high levels of polarization.

  8. Study on the establishment of the IAEA Asian Network for Education in Nuclear Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Lee, H. Y. [and others

    2005-05-01

    The purpose of this project is to establish a web-portal including a database for the exchange of information and materials for nuclear education and training among ANENT members, and eventually contribute to the sustainable development of nuclear technology for peaceful uses in the Asian IAEA member countries. The project has resulted in the development of a web-portal for ANENT (www.anent-iaea.org). The portal primarily includes a Database for Nuclear Education and Training (NET DB). and functions to deal with group activities which were identified in the first ANENT Coordination Committee meeting. NET DB contains information about relevant education and training institutions/universities in terms of their faculty members or researchers, curricula, education and training materials, etc. While, the group activities are exchange of information and materials for education and training, e-learning, establishment of a reference curricula and a system for a mutual recognition of credits, and cooperation with other networks. Finally, an IAEA regional workshop was held to review the developed web-portal and an agreement was reached on the use of the web-portal with some revisions. Furthermore, the IAEA has requested the NTC/KAERI to develop ANENT Cyber-Platform for the continued upgrading of ANENT Web-portal.

  9. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    Energy Technology Data Exchange (ETDEWEB)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

  10. SPACE-R Thermionic Space Nuclear Power System: Design and Technology Demonstration Program

    Science.gov (United States)

    1993-05-01

    This semiannual technical progress report summarizes the technical progress and accomplishments for the Thermionic Space Nuclear Power System (TI-SNPS) Design and Technology Demonstration Program of the prime contractor, Space Power Incorporated (SPI), its subcontractors, and supporting national laboratories during the first half of the government fiscal year (GFY) 1993. SPI's subcontractors and supporting national laboratories include: Babcock & Wilcox for the reactor core and externals; Space Systems/Loral for the spacecraft integration; Thermocore for the radiator heat pipes and the heat exchanger; INERTEK of CIS for the TFE, core elements, and nuclear tests; Argonne National Laboratories for nuclear safety, physics, and control verification; and Oak Ridge National laboratories for materials testing. Parametric trade studies are near completion. However, technical input from INERTEK has yet to be provided to determine some of the baseline design configurations. The INERTEK subcontract is expected to be initiated soon. The point design task has been initiated. The thermionic fuel element (TFE) is undergoing several design iterations. The reactor core vessel analysis and design has also been started.

  11. Nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Sang, David (Bishop Luffa Comprehensive School, Chichester (UK))

    1990-01-01

    Nuclear Physics covers the aspects of radioactivity and nuclear physics dealt with in the syllabuses of all the A-level examination boards; in particular, it provides detailed coverage of the Joint Matriculation Board option in nuclear physics. It deals with the discovery of the atomic nucleus, the physics of nuclear processes, and nuclear technology. (author).

  12. Scientometric mapping of vacuum research in nuclear science & technology: a global perspective

    Science.gov (United States)

    Kademani, B. S.; Sagar, A.; Kumar, A.; Kumar, V.

    2008-05-01

    This paper attempts to analyse the growth and development of Vacuum research in Nuclear Science and Technology, as reflected in publication output covered by International Nuclear Information System (INIS) database during 2002-2006. A total of 12027 papers were published in the field of vacuum science. United States topped the list with 1936 (16.10%) publications followed by Japan with 1770 (14.70%) publications, The highest number of publications (3276) were published in 2004. The average number of publications published per year were 2405.4. The highest number of publications were in 'Physics of Elementary Particles and Fields' with 2644 (21.98%) publications. The authorship and collaboration trend is towards multi-authored papers. The highly productive institutions were: Japan Atomic Energy Research Institute (Japan) with 366 publications, University of Tokyo (Japan) with 274 publications, Hiroshima University (Japan) with 245 publications, Osaka University Japan (Japan) with 224 publications and Chinese Academy of Science (P-R-China) with 223 publications. The most preferred journals for publication were: Journal of Vacuum Science and Technology-A with 857 papers, Physical Review -D with 765 papers, Journal of High Energy Physics with 500 papers, Thin Solid Films with 311 papers, Journal of Electron Spectroscopy and Related Phenomena with 309 papers, and AIP Conference Proceedings with 308 papers.

  13. Proposal for the decision making in sensitive technology: application to the nuclear area; Proposta de modelo decisorio em tecnologia sensivel: aplicacao a area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Eduardo Ramos Ferreira da [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: erfsilva@ipen.br

    2007-07-01

    In a previous article, a correlation is made among the phases of the nuclear technology development and the decision making processes, showing that from the 70's decade, such processes are connected to the national security doctrines, influenced by the Brazilian War College. In this paper it is shown the developed model for the decision making when the sensitive technologies are involved that in our special case will be specific oriented to the nuclear technology. An assessment are made for such decisions must having the the population approval, showing the main existent obstacles and how the present model, although defined at the end of the year 2003, will not be succeeded in a short period of time. It is mainly shown that the linear models must be abandoned, essential since the Word War II, for a holistic model more realistic with a new global state of affairs.

  14. Proceedings of the first international seminar on seismic base isolation for nuclear power facilities

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The First International Seminar on Seismic Base Isolation of Nuclear Power Facilities was organized by the authors of this paper. It was held in San Francisco, California, USA, on August 21--22, 1989, in conjunction with the tenth International Conference on Structural Mechanics in Reactor Technology (SMiRT-10). The purpose of the seminar was to provide an international forum for discussion on the application of base isolation to nuclear power plants and of its effectiveness in reducing seismic loads and permitting standard plant designs. It also provided an opportunity for technical interchange between base isolation system designers, structural engineers, and nuclear power plant engineers. Seismic isolation is certainly one of the most significant earthquake engineering developments in recent years. This was clearly demonstrated by the very large attendance at this seminar and the various papers presented. Isolation system act as filters that reduce the seismic forces and increase the ability of isolated structures and their contents to withstand the damaging effects of earthquake motions. Each individual paper has been cataloged separately.

  15. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.

    2001-08-24

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I&C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I&C system upgrades of present-day nuclear power plants, as well as I&C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I&C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC

  16. 10th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technologies, San Francisco, CA, USA, June 11–15, 2017

    Energy Technology Data Exchange (ETDEWEB)

    Rashdan, Ahmad Al; Oxstrand, Johanna; Agarwal, Vivek

    2017-02-01

    As part of the ongoing efforts at the U.S. Department of Energy’s Light Water Reactor Sustainability Program, Idaho National Laboratory is conducting several pilot projects in collaboration with the nuclear industry to improve the reliability, safety, and economics of the nuclear power industry, especially as the nuclear power plants extend their operating licenses to 80 years. One of these pilot projects is the automated work package (AWP) pilot project. An AWP is an electronic intelligent and interactive work package. It uses plant condition, resources status, and user progress to adaptively drive the work process in a manner that increases efficiency while reducing human error. To achieve this mission, the AWP acquires information from various systems of a nuclear power plant’s and incorporates several advanced instrumentation and control technologies along with modern human factors techniques. With the current rapid technological advancement, it is possible to envision several available or soon-to-be-available capabilities that can play a significant role in improving the work package process. As a pilot project, the AWP project develops a prototype of an expanding set of capabilities and evaluates them in an industrial environment. While some of the proposed capabilities are based on using technological advances in other applications, others are conceptual; thus, require significant research and development to be applicable in an AWP. The scope of this paper is to introduce a set of envisioned capabilities, their need for the industry, and the industry difficulties they resolve.

  17. Nuclear physics: Elusive transition spotted in thorium

    Science.gov (United States)

    Safronova, Marianna

    2016-05-01

    The highly precise atomic clocks used in science and technology are based on electronic transitions in atoms. The discovery of a nuclear transition in thorium-229 raises hopes of making nuclear clocks a reality. See Article p.47

  18. Space Nuclear Thermal Propulsion (SNTP) tests

    Science.gov (United States)

    Allen, George C.

    1993-01-01

    Viewgraphs on the space nuclear thermal propulsion (SNTP) program are presented. The objective of the research is to develop advanced nuclear thermal propulsion (NTP) technology based on the particle bed reactor concept. A strong philosophical commitment exists in the industry/national laboratory team to emphasize testing in development activities. Nuclear testing currently underway to support development of SNTP technology is addressed.

  19. A Fusion Neutron Source Driven Sub-Critical Nuclear Energy System: A Way for Early Application of Fusion Technology

    Institute of Scientific and Technical Information of China (English)

    吴宜灿

    2001-01-01

    This paper proposes a sub-critical nuclear energy system driven by fusion neutron source, FDS, which can be used to transmute long-lived radioactive wastes and to produce fissile nuclear fuel as a way for early application of fusion technology. The necessity and feasibility to develop that system in China are illustrated on the basis of prediction of the demand of energy source in the first half of the 21th century, the status of current fission energy supply and the progress in fusion technology in the vorld. The characteristics of fusion neutron driver and the potential for transmutation of long-lived nuclear wastes and breeding of fissile nuclear fuel in a blanket are analyzed. A scenario of development steps is proposed.``

  20. 2010 ANNUAL MEETING ON NUCLEAR TECHNOLOGY. Pt. 3. Section reports; JAHRESTAGUNG KERNTECHNIK 2010. T. 3. Sektionsberichte Technische Sitzungen

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, Uwe; Baumann, Erik [AREVA NP GmbH, Erlangen (Germany); Fischer, Ulrich; Bohnstedt, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany); Gehring, Michael [Babcock Noell GmbH, Wuerzburg (Germany); Roedig, Manfred [Forschungszentrum Juelich GmbH (Germany); Willschuetz, Hans-Georg [E.ON Kernkraft GmbH, Hannover (Germany); Goers, Stefan [TUEV NORD SysTec GMbH und Co. KG, Hamburg (Germany); Schoenfelder, Christian [AREVA NP GmbH, Offenbach (Germany)

    2010-12-15

    Summary report on these 6 - out of 12 - Sessions of the Annual Conference on Nuclear Technology held in Berlin on May 3 to 6, 2010: - Decommissioning of Nuclear Installations (Session 7), - Fusion Technology (Session 8), - Energy Industry and Economics (Session 10), - Radiation Protection (Session 11), - New Build and Innovations (Session 12), and - Education, Expert Knowledge, Know-how-Transfer (Session 13). The other Sessions: - Reactor Physics and Methods of Calculation (Session 1), - Thermodynamics and Fluid Dynamics (Session 2), - Safety of Nuclear Installations - Methods, Analysis, Results (Session 3), - Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage (Session 4), - Front End of the Fuel Cycle, Fuel Elements and Core Components (Session 5), - Operation of Nuclear Installations (Session 6) have been covered in atw issues 10 and 11 (2010). (orig.)

  1. Nuclear Technique and Agriculture in China

    Institute of Scientific and Technical Information of China (English)

    Xu B.J.

    2004-01-01

    @@ Nuclear technique is a powerful scientific tool in agricultural research, an area with fruitful achievements in China. Application of nuclear technique in agriculture (Nuclear Agricultural Sciences) based on the development of related science and technology is a high-tech area, and also a significant aspect of non-electrical power application of nuclear technique.

  2. Nuclear Technique and Agriculture in China

    Institute of Scientific and Technical Information of China (English)

    Xu; B.J.

    2004-01-01

      Nuclear technique is a powerful scientific tool in agricultural research, an area with fruitful achievements in China. Application of nuclear technique in agriculture (Nuclear Agricultural Sciences) based on the development of related science and technology is a high-tech area, and also a significant aspect of non-electrical power application of nuclear technique.……

  3. The internet based on presence system technology*

    Science.gov (United States)

    Styugin, M.; Kaygorodov, A.

    2016-04-01

    In our study we analyze how to create the systems based on “communication-resource-presence”- technology. We formulate functional and architectural requirements. It is shown some new features in this systems that pertain to communication and information search on the Internet. The Internet passed three infrastructure stages from the communication between two hosts to the resource intermediation and communication in real presence systems. The systems based on the presence technologies have just started to develop. Our study shows what criteria’s they must meet. One of this criteria is the division of site resources into the "rooms" logically separated from each other. The users can see and connect to each other. The contextual data of user presence in a particular "room" can be used when searching for them in the context of professional competence.

  4. Consideration of economic risks in a comparative analysis of nuclear technologies with different maturity levels

    Directory of Open Access Journals (Sweden)

    A.A. Andrianov

    2017-06-01

    Evaluation of risk indicators requires calculation of characteristics for probabilistic distributions of economic performance indicators and systemic use of statistical approaches based on Monte Carlo methods. Demonstration analysis results for the risk indicator evaluation have been discussed as applied to different economic performance indicators based on the example of a comparative analysis for two hypothetical light water reactor technologies to be considered in the selection of the most attractive option. Use of economic risk indicators for the comparative evaluation of reactor technologies appears to be helpful to decision makers not familiar with the technical characteristics and performance measures of reactor technologies but informed about the economic risk concepts. Such methodology may be employed efficiently to interpret the ranking results in a multi-criteria comparative evaluation of less and more mature reactor technologies.

  5. Thermal-hydraulics, physical chemistry, and technology at nuclear power stations equipped with fast-neutron sodium-cooled reactors

    Science.gov (United States)

    Alekseev, V. V.; Efanov, A. D.; Kozlov, F. A.; Sorokin, A. P.

    2007-12-01

    Main results of investigations aimed at developing a verified system of computer codes that take into account the interrelation among nuclear-physical, thermal-hydraulic, physicochemical, thermal-mechanical, mass-transfer, and technological processes in nuclear power installations and at substantiating the models used as the core of these codes are presented together with the results of tests carried out to obtain data for verifying the codes.

  6. Technology enables value-based nursing care.

    Science.gov (United States)

    Simpson, Roy L

    2012-01-01

    Although America spends more per capita on health care than any other nation in the world, care is neither consistent nor effective. The rising prominence of value-based care initiatives gives nurse executives an opportunity to lead clinical practice into a new evidence-fueled decision-making era. Technology holds the key to making emerging better practices and the latest clinical breakthroughs available at the point of care.

  7. Additive Technologies Based on Composite Powder Nanomaterials

    Science.gov (United States)

    Gorynin, I. V.; Oryshchenko, A. S.; Malyshevskii, V. A.; Farmakovskii, B. V.; Kuznetsov, P. A.

    2015-01-01

    The possibilities of application of promising adaptive technologies of bulk laser deposition and selective laser sintering in machine building with the aim of creation of complex-configuration parts and reconditioning of worn components of various-purpose articles from metallic powder materials are considered. The possibilities of the production chain from making of metallic powders to creation of ready coatings and articles on the base of a single unit are described.

  8. The nuclear research and technology development in the GDR from 1945 to 1965. Framework conditions, policy of the State party and implementation; Die Kernforschung und Kerntechnologieentwicklung in der DDR 1945-1965. Rahmenbedingungen, Politik der Staatspartei und Umsetzung

    Energy Technology Data Exchange (ETDEWEB)

    Strauss, Olaf

    2012-06-07

    The study follows the development of the nuclear research and nuclear technology in the GDR between 1945 and 1965. The GDR as an industrial country was highly dependent on brown coal, which was the only available primal energy source in the former GDR. Therefore the civil use of nuclear power called the attention of the executive and party leadership. This consideration was supported by the fact of large uranium deposits on the territory of former East Germany. After the foundation of the GDR, a first attempt to establish an independent nuclear power industry had failed. From 1955 on, the efforts in this direction have been stepped up. Despite the enormous effort of material and human resources the development of an independent East German nuclear industry never got off the ground. In 1965 it was decided to continue the buildup of an East German nuclear industry on base of the nuclear technology of the former Soviet Union. This decision marked a turning point in the East German energy policy and the end to ambitious plans of an independent nuclear industry. The research shows the frame, the preconditions and objectives of the development of the East German nuclear industry on the base of relevant documents from the government of the former GDR, the political machine of the Communist Party (SED) and the Academy of Science Berlin. The research is implementing the context of international nuclear research and technical progress against the background of the Cold War and the international nuclear euphoria as well as within the range of global politics. The discussion focusses on two points. Along with high expectations to an independent energy production and an exporting nuclear industry, the Communist party aimed for clear political results. The author will show the connection between plans of the executive and party leadership of the SED for an ambitious nuclear energy development and the international acceptance of the East German State in the German-German rivalry.

  9. The application of mature dry storage technology and remote handling robotics to nuclear plant extension, clean-up and decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Blackwell, W.C. [GEC ALSTHOM Engineering Systems Ltd., Leicester (United Kingdom)

    1997-08-01

    This paper reviews a mature dry storage technology developed by GEC ALSTHOM Engineering Systems Limited (GAES) which offers a passive, economical and licensable method of providing irradiated fuel storage capacity at operational nuclear power stations. The evolution of the modular vault dry store (MVDS) technology has taken place over 25 years of operational experience, culminating in a product which meets all of the concerns of licensing authorities regarding safety and fuel integrity. The application of remote handling robotics to nuclear fuel and active component handling as a routine process rather than as an intervention technique is also reviewed. The growth of the application of this technology is governed by several factors which include: statutory requirements, safety assurance, risk reduction and economic pressures. The availability of a mature MVDS technology with an evolving process-capable robotics technology opens up opportunities for exploring proven UK products. (Author).

  10. Open access for ALICE analysis based on virtualization technology

    CERN Document Server

    Buncic, P; Schutz, Y

    2015-01-01

    Open access is one of the important leverages for long-term data preservation for a HEP experiment. To guarantee the usability of data analysis tools beyond the experiment lifetime it is crucial that third party users from the scientific community have access to the data and associated software. The ALICE Collaboration has developed a layer of lightweight components built on top of virtualization technology to hide the complexity and details of the experiment-specific software. Users can perform basic analysis tasks within CernVM, a lightweight generic virtual machine, paired with an ALICE specific contextualization. Once the virtual machine is launched, a graphical user interface is automatically started without any additional configuration. This interface allows downloading the base ALICE analysis software and running a set of ALICE analysis modules. Currently the available tools include fully documented tutorials for ALICE analysis, such as the measurement of strange particle production or the nuclear modi...

  11. Nuclear-Renewable Hybrid Energy Systems: 2016 Technology Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Bragg-Sitton, Shannon M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boardman, Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Suk Kim, Jong [Idaho National Lab. (INL), Idaho Falls, ID (United States); McKellar, Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sabharwall, Piyush [Idaho National Lab. (INL), Idaho Falls, ID (United States); Chen, Jun [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cetiner, M. Sacit [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, T. Jay [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Qualls, A. Lou [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-03-01

    renewable technologies will aid in achieving reduced GHG emissions, it also presents new challenges to grid management that must be addressed. These challenges primarily derive from the fundamental characteristics of variable renewable generators, such as wind and solar: non-dispatchability, variable production, and reduced electromechanical inertia. This document presents a preliminary research and development (R&D) plan for detailed dynamic simulation and analysis of nuclear-renewable hybrid energy systems (N-R HES), coupled with integrated energy system design, component development, and integrated systems testing. N-R HES are cooperatively-controlled systems that dynamically apportion thermal and/or electrical energy to provide responsive generation to the power grid.

  12. Virtual reality technology as a tool for human factors requirements evaluation in design of the nuclear reactors control desks

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Mol, Antonio C.A.; Carvalho, Paulo V.R.; Silva, Antonio C.F.; Ferreira, Francisco J.O.; Dutra, Marco A.M. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: grecco@ien.gov.br; luquetti@ien.gov.br; mol@ien.gov.br; paulov@ien.gov.br; tonico@ien.gov.br; fferreira@ien.gov.br; dutra@ien.gov.br

    2007-07-01

    The Virtual Reality (VR) is an advanced computer interface technology that allows the user to internet or to explore a three-dimensional environment through the computer, as was part of the virtual world. This technology presents great applicability in the most diverse areas of the human knowledge. This paper presents a study on the use of the VR as tool for human factors requirements evaluation in design of the nuclear reactors control desks. Moreover, this paper presents a case study: a virtual model of the control desk, developed using virtual reality technology to be used in the human factors requirements evaluation. This case study was developed in the Virtual Reality Laboratory at IEN, and understands the stereo visualization of the Argonauta research nuclear reactor control desk for a static ergonomic evaluation using check-lists, in accordance to the standards and human factors nuclear international guides (IEC 1771, NUREG-0700). (author)

  13. Perspectives for Fluidized Bed Nuclear Reactor Technology using Rotating Fluidized Beds in a Static Geometry

    Science.gov (United States)

    Broqueville, Axel De; Wilde, Juray De

    The new concept of a rotating fluidized bed in a static geometry opens perspectives for fluidized bed nuclear reactor technology and is experimentally and numerically investigated. With conventional fluidized bed technology, the maximum attainable power is rather limited and maximum at a certain fluidization gas flow rate. Using a rotating fluidized bed in a static geometry, the fluidization gas drives both the centrifugal force and the counteracting radial gas-solid drag force in a similar way. This allows operating the reactor at any chosen sufficiently high solids loading over a much wider fluidization gas flow rate range and in particular at much higher fluidization gas flow rates than with conventional fluidized bed reactor technology, offering increased flexibility with respect to cooling via the fluidization gas. Furthermore, the centrifugal force can be a multiple of earth gravity, allowing radial gas-solid slip velocities much higher than in conventional fluidized beds. The latter result in gas-solid heat transfer coefficients one or multiple orders of magnitude higher than in conventional fluidized beds. The combination of dense operation and high fluidization gas flow rates allows process intensification and a more compact reactor design.

  14. Experience of technological and natural disasters and their impact on the perceived risk of nuclear accidents after the Fukushima nuclear disaster in Japan 2011: A cross-country analysis.

    OpenAIRE

    Yamamura, Eiji

    2012-01-01

    This paper uses cross-country data compiled immediately after the Fukushima nuclear accident to investigate how the experience of such disasters affects the perception of the risk of nuclear accidents. Estimation results show that the perceived risk of a nuclear accident is positively associated with experiencing technological disasters but not with that of natural disasters.

  15. Goals, Objectives, and Requirements (GOR) of the Ground-based Nuclear Detonation Detection (GNDD) Team for the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D)

    Energy Technology Data Exchange (ETDEWEB)

    Casey, Leslie A.

    2014-01-13

    The goal, objectives, and requirements (GOR) presented in this document define a framework for describing research directed specifically by the Ground-based Nuclear Detonation Detection (GNDD) Team of the National Nuclear Security Administration (NNSA). The intent of this document is to provide a communication tool for the GNDD Team with NNSA management and with its stakeholder community. It describes the GNDD expectation that much of the improvement in the proficiency of nuclear explosion monitoring will come from better understanding of the science behind the generation, propagation, recording, and interpretation of seismic, infrasound, hydroacoustic, and radionuclide signals and development of "game-changer" advances in science and technology.

  16. Goals, Objectives, and Requirements (GOR) of the Ground-based Nuclear Detonation Detection (GNDD) Team for the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D)

    Energy Technology Data Exchange (ETDEWEB)

    Casey, Leslie A.

    2014-01-13

    The goal, objectives, and requirements (GOR) presented in this document define a framework for describing research directed specifically by the Ground-based Nuclear Detonation Detection (GNDD) Team of the National Nuclear Security Administration (NNSA). The intent of this document is to provide a communication tool for the GNDD Team with NNSA management and with its stakeholder community. It describes the GNDD expectation that much of the improvement in the proficiency of nuclear explosion monitoring will come from better understanding of the science behind the generation, propagation, recording, and interpretation of seismic, infrasound, hydroacoustic, and radionuclide signals and development of "game-changer" advances in science and technology.

  17. Study on fault diagnosis method for nuclear power plant based on hadamard error-correcting output code

    Science.gov (United States)

    Mu, Y.; Sheng, G. M.; Sun, P. N.

    2017-05-01

    The technology of real-time fault diagnosis for nuclear power plants(NPP) has great significance to improve the safety and economy of reactor. The failure samples of nuclear power plants are difficult to obtain, and support vector machine is an effective algorithm for small sample problem. NPP is a very complex system, so in fact the type of NPP failure may occur very much. ECOC is constructed by the Hadamard error correction code, and the decoding method is Hamming distance method. The base models are established by lib-SVM algorithm. The result shows that this method can diagnose the faults of the NPP effectively.

  18. Study of Teaching Methods of Nuclear Engineering and Nuclear Technology Professional Virtual Practice%核工程与核技术专业虚拟实习教学方式研究

    Institute of Scientific and Technical Information of China (English)

    王虎; 陈建华

    2011-01-01

    Due to the particularity of its own nuclear power plants, nuclear engineering and nuclear technology professional school students not in-depth awareness training nuclear power plant site. In order to solve this problem, this paper proposed the establishment of nuclear-based virtual training methods, through the establish- ment of three-dimensional software 3ds Max nuclear power plant equipment, the basic model, and import the model into three-dimensional interactive simulation platform VRP,the realization of a user roaming in nuclear power plants the effect of cognitive training, to stimulate student interest in learning, to solve students'problems during production practice to improve the effectiveness of teachers .%由于核电站自身的特殊性,核工程与核技术专业的在校学生不能深入核电站现场进行认知实习,为了解决这一问题,本文提出建立核电站虚拟实习基地的方法,通过三维软件3dsMax建立核电站设备基本模型,并将模型导入到三维互动仿真平台VRP中,实现使用者在核电站漫游认知实习的效果,达到激发学生的学习兴趣、解决学生生产实习过程中的问题,提升教师的教学效果。

  19. Beta-decay total absorption measurements for nuclear technology and astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Taina, J.L. [Instituto de Fisica Corpuscular, C.S.I.C.-U. Valencia (Spain)

    2008-07-01

    An accurate determination of the beta-decay intensity distribution is of importance for basic nuclear physics but also in the fields of reactor technology, astrophysics and fundamental interactions. Most of present information comes from experiments performed with high resolution low efficiency Ge {gamma}-ray spectroscopy, which fails to locate the beta intensity at high excitation energies in complex decays. The total absorption spectroscopy technique with large 4{pi} scintillation detectors can give the correct answer but requires an involved procedure in order to extract the information. Recent work on the systematization of the analysis methods and on the evaluation of the associated systematic uncertainties shows that reliable beta strength distributions can indeed be obtained. (author)

  20. Decontamination of paint-coated concrete in nuclear plants using laser technology

    Energy Technology Data Exchange (ETDEWEB)

    Anthofer, Anton; Lippmann, Wolfgang; Hurtado, Antonio [Technische Univ. Dresden (Germany). Chair of Hydrogen and Nuclear Technology

    2013-07-01

    A review of the state of the art shows the technical novelty of the combined project. The development of an all-in-one process for treatment hazard chemical contamination on concrete structures with online monitoring method reduces the laborious mechanic decontamination and post-treatment. For safe experimental investigations, a three-barrier-system was constructed and can be used for tests with - first - epoxy paint in order to analyze and optimize the process. Simulation models help to formulate a mathematic scheme of the decontamination process by laser technology. The goal is a decontamination system with an online analyzing system of the flue gas for a mobile and extensive component in nuclear and conventional decommission. (orig.)

  1. 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.

  2. RADIATION SAFETY JUSTIFICATION FOR THE LONG-TERM STORAGE OF GAS CONDENSATE IN THE UNDERGROUND RESERVOURS FORMED BY THE NUCLEAR EXPLOSION TECHNOLOGY

    Directory of Open Access Journals (Sweden)

    I. K. Romanovich

    2010-01-01

    Full Text Available The paper presents approaches to the safety justification of the gas condensate and brine long-term storage in the underground reservoirs formed by the nuclear explosion technology. Gas condensate and brine are the intermediate level liquid radioactive waste containing isotopes: 3Н, 137Cs and 90Sr, in traces - 239Pu, 235U, 241Am.Safety of the gas condensate and brine long-term storage in the underground reservoirs is assessed on the base of the multi-barrier principle implementation, used during radioactive waste disposal. It is shown that the gas condensate and brine long-term storage in the sealed underground reservoirs formed by nuclear explosion technologies in salt domes does not lead to the surface radioactive contamination and population exposure.

  3. The State-of-the-Art of Materials Technology Used for Fossil and Nuclear Power Plants in China

    Science.gov (United States)

    Weng, Yuqing

    Combined with the development of energy in China during the past 30 years, this paper clarified that high steam parameters ultra-supercritical (USC) coal-fired power plants and 1000MW nuclear power plants are the most important method to optimize energy structure and achieve national goals of energy saving and CO2 emission in China. Additionally, requirement of materials technology in high steam parameters USC coal-fired power plants and 1000MW nuclear power plants, current research and major development of relevant materials technology in China were briefly described in this paper.

  4. Organizational factors in design and implementation of technological and organizational solutions in the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Macchi, L.; Reiman, T.; Savioja, P. (VTT Technical Research Centre of Finland (Finland)); Kahlbom, U. (Risk Pilot AB, Stockholm (Sweden)); Rollenhagen, C. (Vattenfall (Sweden))

    2012-03-15

    Design is often found as one of the contributing factors in accident in the nuclear industry. The design of new technological systems and organisational structures has to take into account and be driven by the future users' needs and has to consider how their role and work practices within the organisation will be affected. The SADE project explores to which extend the concepts of safety culture and resilience engineering can contribute to the prevention of design errors when no hindsight data are available. In 2011, the SADE project focused on gathering experience and clarifying the current issues and challenges related to the design process. During 2011 seventeen interviews have been conducted in Finland and Sweden to identify some of the major challenges the nuclear industry is currently facing. At the same time a literature review has been conducted to establish a sound common theoretical ground. This progress report presents some of the relevant theoretical findings and preliminary results from the interviews. (Author)

  5. Application of modern computer technology to EPRI (Electric Power Research Institute) nuclear computer programs: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Feinauer, L.R.

    1989-08-01

    Many of the nuclear analysis programs in use today were designed and developed well over a decade ago. Within this time frame, tremendous changes in hardware and software technologies have made it necessary to revise and/or restructure most of the analysis programs to take advantage of these changes. As computer programs mature from the development phase to being production programs, program maintenance and portability become very important issues. The maintenance costs associated with a particular computer program can generally be expected to exceed the total development costs by as much as a factor of two. Many of the problems associated with high maintenance costs can be traced back to either poorly designed coding structure, or ''quick fix'' modifications which do not preserve the original coding structure. The lack of standardization between hardware designs presents an obstacle to the software designer in providing 100% portable coding; however, conformance to certain guidelines can ensure portability between a wide variety of machines and operating systems. This report presents guidelines for upgrading EPRI nuclear computer programs to conform to current programming standards while maintaining flexibility for accommodating future hardware and software design trends. Guidelines for development of new computer programs are also presented. 22 refs., 10 figs.

  6. Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project

    Energy Technology Data Exchange (ETDEWEB)

    Ian McKirdy

    2011-07-01

    The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

  7. Development of RPS trip logic based on PLD technology

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jong Gyun; Lee, Dong Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-08-15

    The majority of instrumentation and control (I and C) systems in today's nuclear power plants (NPPs) are based on analog technology. Thus, most existing I and C systems now face obsolescence problems. Existing NPPs have difficulty in repairing and replacing devices and boards during maintenance because manufacturers no longer produce the analog devices and boards used in the implemented I and C systems. Therefore, existing NPPs are replacing the obsolete analog I and C systems with advanced digital systems. New NPPs are also adopting digital I and C systems because the economic efficiencies and usability of the systems are higher than the analog I and C systems. Digital I and C systems are based on two technologies: a microprocessor based system in which software programs manage the required functions and a programmable logic device (PLD) based system in which programmable logic devices, such as field programmable gate arrays, manage the required functions. PLD based systems provide higher levels of performance compared with microprocessor based systems because PLD systems can process the data in parallel while microprocessor based systems process the data sequentially. In this research, a bistable trip logic in a reactor protection system (RPS) was developed using very high speed integrated circuits hardware description language (VHDL), which is a hardware description language used in electronic design to describe the behavior of the digital system. Functional verifications were also performed in order to verify that the bistable trip logic was designed correctly and satisfied the required specifications. For the functional verification, a random testing technique was adopted to generate test inputs for the bistable trip logic.

  8. Monoclonal antibodies based on hybridoma technology.

    Science.gov (United States)

    Yagami, Hisanori; Kato, Hiroshi; Tsumoto, Kanta; Tomita, Masahiro

    2013-03-01

    Based on the size and scope of the present global market for medicine, monoclonal antibodies (mAbs) have a very promising future, with applications for cancers through autoimmune ailments to infectious disease. Since mAbs recognize only their target antigens and not other unrelated proteins, pinpoint medical treatment is possible. Global demand is dramatically expanding. Hybridoma technology, which allows production of mAbs directed against antigens of interest is therefore privileged. However, there are some pivotal points for further development to generate therapeutic antibodies. One is selective generation of human mAbs. Employment of transgenic mice producing human antibodies would overcome this problem. Another focus is recognition sites and conformational epitopes in antigens may be just as important as linear epitopes, especially when membrane proteins such as receptors are targeted. Recognition of intact structures is of critical importance for medical purposes. In this review, we describe patent related information for therapeutic mAbs based on hybridoma technology and also discuss new advances in hybridoma technology that facilitate selective production of stereospecific mAbs.

  9. The CEIDEN technology platform. A collaborative effort to promote nuclear R and D in Spain; La Plataforma Tecnologica Ceiden. Un esfuerzo colaborativo para promover la I+D nuclear en Espana

    Energy Technology Data Exchange (ETDEWEB)

    Carmena Servet, P.

    2012-11-01

    The Spanish fission nuclear energy research and development Technological Platform, CEIDEN, is an entity aimed to coordinate the R and D needs and efforts related to fission nuclear technology in all the Spanish nuclear sector. Its activities are aimed to propose and develop joint projects by the partners that have to deal with similar problems and to present a single national position related to international proposals and compromises. All the Sectors related to the Spanish nuclear R and D are represented in the CEIDEN Technological Platform, that is involved both in plants in operation and future reactor designs. (Author)

  10. 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).

  11. Pulsed Power Science and Technology: A Strategic Outlook for the National Nuclear Security Administration (Summary)

    Energy Technology Data Exchange (ETDEWEB)

    Sinars, Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Scott, Kimberly Carole [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Edwards, M. John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Olson, Russell Teall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-10-17

    Major advances in pulsed power technology and applications over the last twenty years have expanded the mission areas for pulsed power and created compelling new opportunities for the Stockpile Stewardship Program (SSP). This summary document is a forward look at the development of pulsed power science and technology (PPS&T) capabilities in support of the next 20 years of the SSP. This outlook was developed during a three-month-long tri-lab study on the future of PPS&T research and capabilities in support of applications to: (1) Dynamic Materials, (2) Thermonuclear Burn Physics and Inertial Confinement Fusion (ICF), and (3) Radiation Effects and Nuclear Survivability. It also considers necessary associated developments in next-generation codes and pulsed power technology as well as opportunities for academic, industry, and international engagement. The document identifies both imperatives and opportunities to address future SSP mission needs. This study was commissioned by the National Nuclear Security Administration (NNSA). A copy of the memo request is contained in the Appendix. NNSA guidance received during this study explicitly directed that it not be constrained by resource limitations and not attempt to prioritize its findings against plans and priorities in other areas of the national weapons program. That prioritization, including the relative balance amongst the three focus areas themselves, must of course occur before any action is taken on the observations presented herein. This unclassified summary document presents the principal imperatives and opportunities identified in each mission and supporting area during this study. Preceding this area-specific outlook, we discuss a cross-cutting opportunity to increase the shot capacity on the Z pulsed power facility as a near-term, cost-effective way to broadly impact PPS&T for SSP as well as advancing the science and technology to inform future SSMP milestones over the next 5-10 years. The final page of the

  12. Pulsed Power Science and Technology: A Strategic Outlook for the National Nuclear Security Administration (Summary)

    Energy Technology Data Exchange (ETDEWEB)

    Sinars, Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Scott, Kimberly Carole [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Edwards, M. John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Olson, Russell Teall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-10-17

    Major advances in pulsed power technology and applications over the last twenty years have expanded the mission areas for pulsed power and created compelling new opportunities for the Stockpile Stewardship Program (SSP). This summary document is a forward look at the development of pulsed power science and technology (PPS&T) capabilities in support of the next 20 years of the SSP. This outlook was developed during a three month long tri-lab study on the future of PPS&T research and capabilities in support of applications to: (1) Dynamic Materials, (2) Thermonuclear Burn Physics and Inertial Confinement Fusion (ICF), and (3) Radiation Effects and Nuclear Survivability. It also considers necessary associated developments in next-generation codes and pulsed power technology as well as opportunities for academic, industry, and international engagement. The document identifies both imperatives and opportunities to address future SSP mission needs. This study was commissioned by the National Nuclear Security Administration (NNSA). A copy of the memo request is contained in the Appendix. NNSA guidance received during this study explicitly directed that it not be constrained by resource limitations and not attempt to prioritize its findings against plans and priorities in other areas of the national weapons program. That prioritization, including the relative balance amongst the three focus areas themselves, must of course occur before any action is taken on the observations presented herein. This unclassified summary document presents the principal imperatives and opportunities identified in each mission and supporting area during this study. Proceeding this area-specific outlook, we discuss a cross-cutting opportunity to increase the shot capacity on the Z pulsed power facility as a near term, cost effective way to broadly impact PPS&T for SSP as well as advancing the science and technology to inform future SSMP milestones over the next 5-10 years. The final page of the

  13. Information-Technology Based Physics Education

    Science.gov (United States)

    Kim, J. S.; Lee, K. H.

    2001-04-01

    Developing countries emphasize expansion of the educated population but demand for quality improvement follows later. Current science education reform is driven in part by post cold war restructuring of the global economy and associated focus on the education of a more scientifically literate society, due to the industrial change from labor-intensive to high-technology type, and the societal change inherent in the present information era. Industry needs employees of broad and flexible background with inter disciplinary training, engineers with better physics training, and well trained physicists. Education researches have proved that active-learning based methods are superior to the traditional methods and the information technology (IT) has lot to offer in this. Use of IT for improving physics education is briefly discussed with prospects for collaboration in the Asia-Pacific region via Asian Physics Education Network (ASPEN), UNESCO University Foundation Course in Physics (UUFCP), etc.

  14. Terahertz wireless communications based on photonics technologies.

    Science.gov (United States)

    Nagatsuma, Tadao; Horiguchi, Shogo; Minamikata, Yusuke; Yoshimizu, Yasuyuki; Hisatake, Shintaro; Kuwano, Shigeru; Yoshimoto, Naoto; Terada, Jun; Takahashi, Hiroyuki

    2013-10-07

    There has been an increasing interest in the application of terahertz (THz) waves to broadband wireless communications. In particular, use of frequencies above 275 GHz is one of the strong concerns among radio scientists and engineers, because these frequency bands have not yet been allocated at specific active services, and there is a possibility to employ extremely large bandwidths for ultra-broadband wireless communications. Introduction of photonics technologies for signal generation, modulation and detection is effective not only to enhance the bandwidth and/or the data rate, but also to combine fiber-optic (wired) and wireless networks. This paper reviews recent progress in THz wireless communications using telecom-based photonics technologies towards 100 Gbit/s.

  15. Clock comparison based on laser ranging technologies

    Science.gov (United States)

    Samain, Etienne

    2015-06-01

    Recent progress in the domain of time and frequency standards has required some important improvements of existing time transfer links. Several time transfer by laser link (T2L2) projects have been carried out since 1972 with numerous scientific or technological objectives. There are two projects currently under exploitation: T2L2 and Lunar Reconnaissance Orbiter (LRO). The former is a dedicated two-way time transfer experiment embedded on the satellite Jason-2 allowing for the synchronization of remote clocks with an uncertainty of 100 ps and the latter is a one-way link devoted for ranging a spacecraft orbiting around the Moon. There is also the Laser Time Transfer (LTT) project, exploited until 2012 and designed in the frame of the Chinese navigation constellation. In the context of future space missions for fundamental physics, solar system science or navigation, laser links are of prime importance and many missions based on that technology have been proposed for these purposes.

  16. Nuclear Thermal Rocket/Stage Technology Options for NASA's Future Human Exploration Missions to the Moon and Mars

    Science.gov (United States)

    Borowski, Stanley K.; Corban, Robert R.; McGuire, Melissa L.; Beke, Erik G.

    1994-07-01

    The nuclear thermal rocket (NTR) provides a unique propulsion capability to planners and designers of future human exploration missions to the Moon and Mars. In addition to its high specific impulse (Isp ~ 850-1000 seconds) and engine thrust-to-weight ratio (~ 3-10), the NTR can also be configured as a ``dual mode'' system capable of generating stage electrical power. At present, NASA is examining a variety of mission applications for the NTR ranging from an expendable, ``single burn'' trans-lunar injection (TLI) stage for NASA's ``First Lunar Outpost'' (FLO) mission to all propulsive, ``multi-burn,'' spacecraft supporting a ``split cargo/piloted sprint'' Mars mission architecture. Two ``proven'' solid core NTR concepts are examined -one based on NERVA (Nuclear Engine for Rocket Vehicle Application)-derivative reactor (NDR) technology, and a second concept which utilizes a ternary carbide ``twisted ribbon'' fuel form developed by the Commonwealth of Independent States (CIS). Integrated systems and mission study results are used in designing ``aerobraked'' and ``all propulsive'' Mars vehicle concepts which are mass-, and volume-compatible with both a reference 240 metric tonne (t) heavy lift launch vehicle (HLLV) and a smaller 120 t HLLV option. For the ``aerobraked'' scenario, the 2010 piloted mission determines the size of the expendable trans-Mars injection (TMI) stage which is a growth version of the FLO TLI stage. An ``all-propulsive'' Moon/Mars mission architecture is also described which uses common ``modular'' engine and stage hardware consisting of: (1) clustered 15 thousand pounds force (klbf) NDR or CIS engines; (2) two ``standardized'' liquid hydrogen (LH2) tank sizes; and (3) ``dual mode'' NTR and refrigeration system technologies for long duration missions. The ``modular'' NTR approach can form the basis for a ``faster, safer, and cheaper'' space transportation system for tomorrow's piloted missions to the Moon and Mars.

  17. Ablation study of tungsten-based nuclear thermal rocket fuel

    Science.gov (United States)

    Smith, Tabitha Elizabeth Rose

    The research described in this thesis has been performed in order to support the materials research and development efforts of NASA Marshall Space Flight Center (MSFC), of Tungsten-based Nuclear Thermal Rocket (NTR) fuel. The NTR was developed to a point of flight readiness nearly six decades ago and has been undergoing gradual modification and upgrading since then. Due to the simplicity in design of the NTR, and also in the modernization of the materials fabrication processes of nuclear fuel since the 1960's, the fuel of the NTR has been upgraded continuously. Tungsten-based fuel is of great interest to the NTR community, seeking to determine its advantages over the Carbide-based fuel of the previous NTR programs. The materials development and fabrication process contains failure testing, which is currently being conducted at MSFC in the form of heating the material externally and internally to replicate operation within the nuclear reactor of the NTR, such as with hot gas and RF coils. In order to expand on these efforts, experiments and computational studies of Tungsten and a Tungsten Zirconium Oxide sample provided by NASA have been conducted for this dissertation within a plasma arc-jet, meant to induce ablation on the material. Mathematical analysis was also conducted, for purposes of verifying experiments and making predictions. The computational method utilizes Anisimov's kinetic method of plasma ablation, including a thermal conduction parameter from the Chapman Enskog expansion of the Maxwell Boltzmann equations, and has been modified to include a tangential velocity component. Experimental data matches that of the computational data, in which plasma ablation at an angle shows nearly half the ablation of plasma ablation at no angle. Fuel failure analysis of two NASA samples post-testing was conducted, and suggestions have been made for future materials fabrication processes. These studies, including the computational kinetic model at an angle and the

  18. Performance Based Failure Criteria of the Base Isolation System for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Han; Kim, Min Kyu; Choi, In Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The realistic approach to evaluate the failure state of the base isolation system is necessary. From this point of view, several concerns are reviewed and discussed in this study. This is the preliminary study for the performance based risk assessment of a base isolated nuclear power plant. The items to evaluate the capacity and response of an individual base isolator and a base isolation system were briefly outlined. However, the methodology to evaluate the realistic fragility of a base isolation system still needs to be specified. For the quantification of the seismic risk for a nuclear power plant structure, the failure probabilities of the structural component for the various seismic intensity levels need to be calculated. The failure probability is evaluated as the probability when the seismic response of a structure exceeds the failure criteria. Accordingly, the failure mode of the structural system caused by an earthquake vibration should be defined first. The type of a base isolator appropriate for a nuclear power plant structure is regarded as an elastometric rubber bearing with a lead core. The failure limit of the lead-rubber bearing (LRB) is not easy to be predicted because of its high nonlinearity and a complex loading condition by an earthquake excitation. Furthermore, the failure mode of the LRB system installed below the nuclear island cannot be simply determined because the basemat can be sufficiently supported if the number of damaged isolator is not much.

  19. 4'' + D VR technology for structural analysis and integrated maintenance of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, I. S.; Yoon, S. H.; Shim, K. W.; Yu, Y. H.; Suh, K. Y. [PhiloSOPhIA, Inc. Seoul (Korea, Republic of)

    2002-05-01

    There continues to be an increasing demand of electricity around the globe to fuel the industrial growth and to promote the human welfare. The economic activities have brought about richness in our material and cultural lives, in which process the electric power has been at the heart of the versatile energy sources. In order to timely and competitively respond to rapidly changing energy environment in the twenty-first century there is a growing need to build the advanced nuclear power plants in the unlimited K, which were confirmed by FTIR and {sup 51}V Ncommissioning. One can then realistically evaluate their construction time and cost per varying methods and options available from the leading-edge technology. In particular a great deal of efforts have yet to be made for time- and cost-dependent plant simulation and dynamically coupled database construction in the VR space. The operator training and personnel education may also benefit from the VR technology. The present work is being proposed in the three-dimensional space and time plus cost coordinates, i.e. four plus dimensional (4{sup +} D) coordinates. The 4{sup +} D VR application will enable the nuclear industry to narrow the technological gap from the other leading industries that have long since been employing the VR engineering. The 4{sup +} D technology will help nurture public understanding of the special discipline of nuclear power plants. The technology will also facilitate public access to the knowledge on the nuclear science and engineering which has so far been monopolized by the academia, national laboratories and the heavy industry. The 4{sup +} D virtual design and construction will open up the new horizon for revitalization of the nuclear industry over the globe in the foreseeable future. Considering the long construction and operation time for the nuclear power plants, the preliminary VR simulation capability for the plants will supply the vital information not only for the actual design and

  20. The European Nuclear Science network touches base at CERN

    CERN Multimedia

    Antonella Del Rosso

    2012-01-01

    ENSAR (European Nuclear Science and Applications Research) is an EU-supported project, which aims at fostering cooperation within the European low-energy nuclear physics community through the active sharing of expertise and best practices. The project also includes a transnational access programme to allow a large community of users to access the participating facilities, which include CERN’s ISOLDE. In the last week of April, CERN hosted the General Assembly and Programme Coordination Committee meetings, about 18 months after the project’s kick-off.   Participants in the ENSAR project. ENSAR involves 30 partner institutes, which include the seven large nuclear physics facilities in Europe. A large part of the European nuclear physics community is represented in ENSAR, in particular scientists who are performing research related to nuclear structure, nuclear astrophysics and applications of nuclear science. In 2010, the project was awarded 8 million euros from the Europe...