WorldWideScience

Sample records for nuclear engineering institute

  1. Nuclear engineering in the National Polytechnic Institute; Ingenieria nuclear en el Instituto Politecnico Nacional

    Energy Technology Data Exchange (ETDEWEB)

    Del Valle G, E. [IPN, Unidad Profesional Adolfo Lopez Mateos, Anexo del Edif. 9, 1er. piso, Av. Instituto Politecnico Nacional s/n, Col. San Pedro Zacatenco, Mexico 07738 D. F. (Mexico)

    2008-12-15

    In the National Polytechnic Institute the bachelor degree in physics and mathematics, consists of 48 subjects in the common trunk. For the nuclear engineering option, from the fifth semester undergoing 9 specific areas within the Nuclear Engineering Department : introduction to nuclear engineering, power cycles thermodynamics, heat transfer, two courses of nuclear reactors theory, two of nuclear engineering, one course of laboratory and other of radiation protection. There is also a master in nuclear engineering aims train human resources in the area of power and research nuclear reactors to meet the needs of the nuclear industry in Mexico, as well as train highly qualified personnel in branches where are used equipment involving radiation and radioisotopes tale as Medicine, Agriculture and Industry. Among its compulsory subjects are: radiation interaction with the matter, measurements laboratory, reactor physics I and II, reactor engineering, reactor laboratory and thesis seminar. Optional, are: engineering of the radiation protection, computers in the nuclear engineering, nuclear systems dynamics, power plants safety, flow in two phases, reliability and risk analysis, nuclear power systems design, neutron transport theory. Many graduates of this degree have been and are involved in various phases of the nuclear project of Laguna Verde. The Nuclear Engineering Department has a subcritical nuclear reactor of light water and natural uranium and one isotopic source of Pu-Be neutrons of 5 Ci. It also has a multichannel analyzers, calibrated sources of alpha, beta and gamma radiation, a gamma spectrometer of high resolution and low background, a specialized library and one data processing center. In relation particularly to radiation protection, it is clear that there is a lack of specialists, as reflected in radiological control problems in areas such as medicine and industry. Given this situation, it is perceived to be required post-graduate studies at Master and Ph

  2. TLD environmental monitoring at the Institute of Nuclear Engineering in Brazil.

    Science.gov (United States)

    Taam, I H; da Rosa, L A R; Crispim, V R

    2008-09-01

    Since 2003 the Institute of Nuclear Engineering in Rio de Janeiro city, Brazil, operates a new cyclotron, RDS-111, to produce (18)F-Fluorodeoxyglucose to be used in nuclear medicine. Additionally, the IEN radioactive waste repository has been enlarged during the past last years, receiving a considerable amount of radioactive materials. Therefore, it became necessary to evaluate a possible increase of the environmental gamma exposure rates at the institute site due to the operation of the new accelerator and the enlargement of the institute waste repository as well. LiF:Mg,Cu,P, TLD-100H, and TL detectors were employed for environmental kerma rate evaluation and the results were compared with previous results obtained before the RDS-111 operation initialisation and the enlargement of IEN waste repository. No significant contribution for the enhancement of environmental gamma kerma rates was detected.

  3. AMS at the National Institute of Nuclear Physics and Engineering in Bucharest

    Science.gov (United States)

    Stan-Sion, C.; Ivascu, M.; Plostinaru, D.; Catana, D.; Marinescu, L.; Radulescu, M.; Nolte, E.

    2000-10-01

    A new beam line and injector deck for AMS measurements have been built at the 8 MV tandem accelerator of the National Institute of Nuclear Physics and Engineering, Bucharest, Romania. The main components on the low-energy side are a high-current cesium sputter source, a 90° injection magnet and a pre-acceleration stage. At the high-energy side the beam line is achromatic, consisting of two 90° analysing magnets with mass energy product 120 MeV amu and a gas-filled ionization chamber. The system will be complete with a Wien filter and a multi-anode gas detector with time-of-flight discrimination. Presently, the AMS facility is undergoing tests and routine measurements are expected to start soon.

  4. AMS at the National Institute of Nuclear Physics and Engineering in Bucharest

    Energy Technology Data Exchange (ETDEWEB)

    Stan-Sion, C. E-mail: stansion@ifin.nipne.ro; Ivascu, M.; Plostinaru, D.; Catana, D.; Marinescu, L.; Radulescu, M.; Nolte, E

    2000-10-01

    A new beam line and injector deck for AMS measurements have been built at the 8 MV tandem accelerator of the National Institute of Nuclear Physics and Engineering, Bucharest, Romania. The main components on the low-energy side are a high-current cesium sputter source, a 90 deg. injection magnet and a pre-acceleration stage. At the high-energy side the beam line is achromatic, consisting of two 90 deg. analysing magnets with mass energy product 120 MeV amu and a gas-filled ionization chamber. The system will be complete with a Wien filter and a multi-anode gas detector with time-of-flight discrimination. Presently, the AMS facility is undergoing tests and routine measurements are expected to start soon.

  5. Information model for management and preservation of scientific digital memory of the Institute of Nuclear Engineering, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Sales, Luana Farias, E-mail: lsales@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Sayao, Luis Fernando, E-mail: isayao@cnen.gov.br [Centro de Informacoes Nucleares (CIN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    In the context of the data-oriented science (eScience), a considerable part of the results of research activities has been created in digital formats. This means that the memory of the scientific institutions involved in this new scientific paradigm may be at risk of being lost by rapid technological obsolescence, the known fragility of digital media and also by the fragmentation of information and knowledge scattered across multiples repositories. Thus, management of research data in a digital networked and distributed environment becomes an increasing challenge for the research world and the whole area of information: information science, librarianship, knowledge management, archival science and information technology; moreover, in the dynamic environment featuring eScience, there is a need for novel concepts of documents establishing a linkage between traditional documents - printed or digital - stored in repositories, with the data sets stored in data repositories. In this new research environment, an important issue is how to preserve these new complex documents so that they maintain their structure, meaning and authenticity and also its ability to be retrieved, accessed and reused through time and space. In this sense, this paper proposes an information model focused on the curation of scientific memory of the Institute of Nuclear Engineering of the Brazilian Commission of Nuclear Energy (CNEN/IEN). The model considers the traditional scientific documents (theses, articles, books, etc.) in digital formats and all other relevant data and information related to them, such as: scientific data, software, simulations, photos, videos, historical facts, news, etc., compounding an enhanced publication type oriented to the nuclear area. (author)

  6. Dictionary of nuclear engineering

    Energy Technology Data Exchange (ETDEWEB)

    Sube, R.

    1985-01-01

    Ralf Sube, an experienced compiler of three wellknown four-language reference works has now prepared this glossary of nuclear engineering terms in English, German, French and Russian. Based on the proven lexicography of the Technik-Worterbuch series, it comprises about 30,000 terms in each language covering the following: Nuclear and Atomic Physics; Nuclear Radiation and Isotopes; Nuclear Materials; Nuclear Facilties; Nuclear Power Industry; Nuclear Weapons.

  7. Implementation of the Immersive Virtual Reality Laboratory in Nuclear Engineering Institute

    Energy Technology Data Exchange (ETDEWEB)

    Mol, Antonio Carlos de Abreu; Grecco, Claudio Henrique dos Santos; Carvalho, Paulo Victor R.; Oliveira, Mauro Vitor de; Santos, Isaac J.A. Luquetti; Augusto, Silas Cordeiro; Viana Filho, Alfredo Marques [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)]. E-mail: mol@ien.gov.br; grecco@ien.gov.br; paulov@ien.gov.br; mvitor@ien.gov.br; luqietti@ien.gov.br; silas@ien.gov.br; marques@ien.gov.br

    2005-07-01

    The Immersive Virtual Reality Laboratory under development in Human System Interface Laboratory constitute a powerful general-purpose facility for experimental and computational work on human perception and perceptually guided action. Virtual reality or virtual environment are computer generated environments with and within people can interact. The advantage of VR is that people can be immersed by the simulated environment, which would sometimes be unavailable due to cost, safety, or perceptual restrictions in the real environment. There are many applications of virtual reality on the nuclear area. Training is one of the most common of them. A significant advantage of a virtual training environment over a real one is it's enormous flexibility. A virtual environment can be used as the basis for training in any number of different scenarios, so that trainees can learn to cope with many different situations, some of which may be impossible to prepare for any other way. Another advantage of using virtual environments for training purposes is that trainees learn by actively performing actions. This has a significant effect on their ability to retain what they learn, and is clearly superior to passive training techniques, such as videos and books, for training where spatial understanding is important. This kind of Laboratory is the first in Brazilian nuclear area. A safe virtual environment can be used to simulate a real environment that is either too dangerous, complex, or expensive to training. Virtual environments can therefore be used to increase safety standards, improve efficiency, and reduce overall training costs. (author)

  8. High performance computing in Nuclear Engineering Institute, IEN, Rio de Janeiro, Brazil; Computacao de alto desempenho no Instituto de Engenharia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Sampaio, Paulo A.B. de; Lapa, Celso M.F.; Jospin, Reinaldo J.; Pereira, Claudio M.N.A.; Moreira, Maria de L.; Lapa, Nelbia da Silva; Nery, Domingos E. de Sa; Mol, Antonio C. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)

    2000-07-01

    Recently, advanced computational methods have been used for resolution of nuclear engineering problems. Examples of this are the utilization of computational simulation methods in fluid dynamics for thermal stratification problems analysis in PWR and the utilization of genetic algorithms for nuclear reactor core optimization, as well as, preventive maintenance scheduling optimization. The objective of this article is presents to national nuclear community the project of Parallel Computing Laboratory of IEN, and also discuss its aspects related to parallel processing philosophy and the new possibilities for nuclear engineering applications.

  9. Nuclear engineering vocabulary

    Energy Technology Data Exchange (ETDEWEB)

    Dumont, X. [FRAMATOME, Dept. Corporate R and D, 92 - Paris-La-Defence (France); Andrieux, C. [CEA Saclay, Direction des Technologies de l' Information, DTI, 91 - Gif sur Yvette (France)

    2001-07-01

    The members of the CSTNIN - the Special Commission for Nuclear Engineering Terminology and Neology - have just produced a Nuclear Engineering Vocabulary, published by SFEN. A 120-page document which, to date, includes 400 nuclear engineering terms or expressions. For each term or expression, this Glossary gives: the primary and secondary subject field in which it is applied, a possible abbreviation, its definition, a synonym if appropriate, any relevant comments, any associated word(s), the English equivalent, its status on the date of publication of the Glossary. (author)

  10. Nuclear Engineering Enrollments and Degrees, 1982.

    Science.gov (United States)

    Sweeney, Deborah H.; And Others

    This report presents data on the number of students enrolled and the number of bachelor's, master's, and doctoral degrees awarded in academic year 1981-82 from 72 United States institutions offering degree programs in nuclear engineering or nuclear options within other engineering fields. Presented as well are historical data for the last decade…

  11. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-06

    We needed to find a space reactor concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled reactors coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.

  12. Job Prospects for Nuclear Engineers.

    Science.gov (United States)

    Basta, Nicholas

    1985-01-01

    As the debate over nuclear safety continues, the job market remains healthy for nuclear engineers. The average salary offered to new nuclear engineers with bachelor's degrees is $27,400. Salary averages and increases compare favorably with other engineering disciplines. Various job sources in the field are noted. (JN)

  13. Earthquake engineering for nuclear facilities

    CERN Document Server

    Kuno, Michiya

    2017-01-01

    This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground...

  14. Nuclear Rocket Engine Reactor

    CERN Document Server

    Lanin, Anatoly

    2013-01-01

    The development of a nuclear rocket engine reactor (NRER ) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  15. Institute of Electrical and Electronics Engineers, Nuclear Science Symposium, 18th, and Nuclear Power Systems Symposium, 3rd, San Francisco, Calif., November 3-5, 1971, Proceedings.

    Science.gov (United States)

    1972-01-01

    Potential advantages of fusion power reactors are discussed together with the protection of the public from radioactivity produced in nuclear power reactors, and the significance of tritium releases to the environment. Other subjects considered are biomedical instrumentation, radiation damage problems, low level environmental radionuclide analysis systems, nuclear techniques in environmental research, nuclear instrumentation, and space and plasma instrumentation. Individual items are abstracted in this issue.

  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. Nuclear Reactor Engineering Analysis Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Carlos Chavez-Mercado; Jaime B. Morales-Sandoval; Benjamin E. Zayas-Perez

    1998-12-31

    The Nuclear Reactor Engineering Analysis Laboratory (NREAL) is a sophisticated computer system with state-of-the-art analytical tools and technology for analysis of light water reactors. Multiple application software tools can be activated to carry out different analyses and studies such as nuclear fuel reload evaluation, safety operation margin measurement, transient and severe accident analysis, nuclear reactor instability, operator training, normal and emergency procedures optimization, and human factors engineering studies. An advanced graphic interface, driven through touch-sensitive screens, provides the means to interact with specialized software and nuclear codes. The interface allows the visualization and control of all observable variables in a nuclear power plant (NPP), as well as a selected set of nonobservable or not directly controllable variables from conventional control panels.

  18. Social Institutions and Nuclear Energy

    Science.gov (United States)

    Weinberg, Alvin M.

    1972-01-01

    Nuclear technologists can offer an all but infinite source of relatively cheap and clean energy" but society must decide whether the price of eternal vigilance needed to ensure proper and safe operation of its nuclear energy system" is worth the benefits. (Author/AL)

  19. Social Institutions and Nuclear Energy

    Science.gov (United States)

    Weinberg, Alvin M.

    1972-01-01

    Nuclear technologists can offer an all but infinite source of relatively cheap and clean energy" but society must decide whether the price of eternal vigilance needed to ensure proper and safe operation of its nuclear energy system" is worth the benefits. (Author/AL)

  20. Midwest Nuclear Science and Engineering Consortium

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Wynn Volkert; Dr. Arvind Kumar; Dr. Bryan Becker; Dr. Victor Schwinke; Dr. Angel Gonzalez; Dr. DOuglas McGregor

    2010-12-08

    The objective of the Midwest Nuclear Science and Engineering Consortium (MNSEC) is to enhance the scope, quality and integration of educational and research capabilities of nuclear sciences and engineering (NS/E) programs at partner schools in support of the U.S. nuclear industry (including DOE laboratories). With INIE support, MNSEC had a productive seven years and made impressive progress in achieving these goals. Since the past three years have been no-cost-extension periods, limited -- but notable -- progress has been made in FY10. Existing programs continue to be strengthened and broadened at Consortium partner institutions. The enthusiasm generated by the academic, state, federal, and industrial communities for the MNSEC activities is reflected in the significant leveraging that has occurred for our programs.

  1. 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.

  2. Gamma radiation measurements in F-18 production in the RDS-111 Cyclotron from the Nuclear Engineering Institute; Medicao de radiacao gama na producao de F-18 no ciclotron RDS-111 do Instituto de Engenharia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Taam, Ilka H.; Bellido, Luis F.; Vinagre Filho, Ubirajara M. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2005-07-01

    With the acquisition of RDS-111 particle accelerator, the Institute of Nuclear Engineering in Rio de Janeiro city (IEN) operates a new cyclotron to produce 1{sup 8F} to obtain the fluorodeoxyglucose (FDG), a radiopharmaceutical used in positron emission tomography (PET), a technique well advanced which allows obtaining images with high resolution for diagnoses in medicine. To evaluate and detect the gamma exposure during 1{sup 8F} production, in the routine operation, i.e. current of 30 {mu}A and the operating time 120 minutes, it was used a portable detector hyperpure germanium (HPGe) coupled to an electronic system for acquisition of 4096 data channels. To obtain a wide energy spectrum from 0.1 to 20 MeV were performed measurements with different gains of amplification. The energy average of gamma radiation, calculated from the energy spectra of gamma rays obtained, was 1.59 {+-} 0.05 MeV. Meanwhile, measurements were made with a MIR 7026 monitor and with thermoluminescent detectors (TLD) of LiF: Mg, Cu, P to calculate the dose equivalent rates H{sup *}(10) of the installation.

  3. Final Technical Report; NUCLEAR ENGINEERING RECRUITMENT EFFORT

    Energy Technology Data Exchange (ETDEWEB)

    Kerrick, Sharon S.; Vincent, Charles D.

    2007-07-02

    This report provides the summary of a project whose purpose was to support the costs of developing a nuclear engineering awareness program, an instruction program for teachers to integrate lessons on nuclear science and technology into their existing curricula, and web sites for the exchange of nuclear engineering career information and classroom materials. The specific objectives of the program were as follows: OBJECTIVE 1: INCREASE AWARENESS AND INTEREST OF NUCLEAR ENGINEERING; OBJECTIVE 2: INSTRUCT TEACHERS ON NUCLEAR TOPICS; OBJECTIVE 3: NUCLEAR EDUCATION PROGRAMS WEB-SITE; OBJECTIVE 4: SUPPORT TO UNIVERSITY/INDUSTRY MATCHING GRANTS AND REACTOR SHARING; OBJECTIVE 5: PILOT PROJECT; OBJECTIVE 6: NUCLEAR ENGINEERING ENROLLMENT SURVEY AT UNIVERSITIES

  4. Institute of Industrial Engineers Asian Conference 2013

    CERN Document Server

    Tsao, Yu-Chung; Lin, Shi-Woei

    2013-01-01

    This book is based on the research papers presented during The Institute of Industrial Engineers Asian Conference 2013 held at Taipei in July 2013. It presents information on the most recent and relevant research, theories and practices in industrial and systems engineering. Key topics include: Engineering and Technology Management Engineering Economy and Cost Analysis Engineering Education and Training Facilities Planning and Management Global Manufacturing and Management Human Factors Industrial & Systems Engineering Education Information Processing and Engineering Intelligent Systems Manufacturing Systems Operations Research Production Planning and Control Project Management Quality Control and Management Reliability and Maintenance Engineering Safety, Security and Risk Management Supply Chain Management Systems Modeling and Simulation Large scale complex systems.

  5. Unique nuclear thermal rocket engine

    Energy Technology Data Exchange (ETDEWEB)

    Culver, D.W. (Aerojet Propulsion Division, P.O. Box 13222, Sacramento, California 95813-6000 (United States)); Rochow, R. (Babcock Wilcox Space Nuclear Systems, P.O. Box 11165, Lynchburg, Virginia 24506-1165 (United States))

    1993-01-15

    Earlier this year Aerojet Propulsion Division (APD) introduced a new, advanced nuclear thermal rocket engine (NTRE) concept intended for manned missions to the moon and to Mars. This NTRE promises to be both shorter and lighter in weight than conventionally designed engines, because its forward flowing reactor is located within an expansion-deflection (E-D) rocket nozzle. The concept has matured during the year, and this paper discusses a nearer term version that resolves four open issues identified in the initial concept: (1)Reactor design and cooling scheme simplification while retaining a high pressure power balance option; (2)Eliminate need for a new, uncooled nozzle throat material suitable for long life application; (3)Practical provision for reactor power control; and (4)Use near term, long life turbopumps.

  6. Unique nuclear thermal rocket engine

    Science.gov (United States)

    Culver, Donald W.; Rochow, Richard

    1993-06-01

    In January, 1992, a new, advanced nuclear thermal rocket engine (NTRE) concept intended for manned missions to the moon and to Mars was introduced (Culver, 1992). This NTRE promises to be both shorter and lighter in weight than conventionally designed engines, because its forward flowing reactor is located within an expansion-deflection rocket nozzle. The concept has matured during the year, and this paper discusses a nearer term version that resolves four open issues identified in the initial concept: (1) the reactor design and cooling scheme simplification while retaining a high pressure power balance option; (2) elimination need for a new, uncooled nozzle throat material suitable for long life application; (3) a practical provision for reactor power control; and (4) use of near-term, long-life turbopumps.

  7. US nuclear engineering education: Status and prospects

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    This study, conducted under the auspices of the Energy Engineering Board of the National Research Council, examines the status of and outlook for nuclear engineering education in the United States. The study resulted from a widely felt concern about the downward trends in student enrollments in nuclear engineering, in both graduate and undergraduate programs. Concerns have also been expressed about the declining number of US university nuclear engineering departments and programs, the aging of their faculties, the appropriateness of their curricula and research funding for industry and government needs, the availability of scholarships and research funding, and the increasing ratio of foreign to US graduate students. A fundamental issue is whether the supply of nuclear engineering graduates will be adequate for the future. Although such issues are more general, pertaining to all areas of US science and engineering education, they are especially acute for nuclear engineering education. 30 refs., 12 figs., 20 tabs.

  8. Evolution of nuclear spectroscopy at Saha Institute of Nuclear Physics

    Indian Academy of Sciences (India)

    P Mukherjee

    2001-07-01

    Experimental studies of nuclear excitations have been an important subject from the earliest days when the institute was established. The construction of 4 MeV proton cyclotron was mainly aimed to achieve this goal. Early experiments in nuclear spectroscopy were done with radioactive nuclei with the help of beta and gamma ray spectrometers. Small NaI(Tl) detectors were used for gamma–gamma coincidence, angular correlation and life time measurements. The excited states nuclear magnetic moments were measured in perturbed gamma–gamma angular correlation experiments. A high transmission magnetic beta ray spectrometer was used to measure internal conversion coefficients and beta–gamma coincidence studies. A large number of significant contributions were made during 1950–59 using these facilities. Proton beam in the cyclotron was made available in the late 1950’s and together with 14 MeV neutrons obtained from a C-W generator a large number of short-lived nuclei were investigated during 1960’s and 1970’s. The introduction of high resolution Ge gamma detectors and the improved electronics helped to extend the spectroscopic work which include on-line (,') and (,) reaction studies. Nuclear spectroscopic studies entered a new phase in the 1980’s with the availability of 40–80 MeV alpha beam from the variable energy cyclotron at VECC, Calcutta. A number of experimental groups were formed in the institute to study nuclear level schemes with (,) reactions. Initially only two unsuppressed Ge detectors were used for coincidence studies. Later in 1989 five Ge detectors with a large six segmented NaI(Tl) multiplicitysum detector system were successfully used to select various channels in (,) reactions. From 1990 to date a variety of medium energy heavy ions were made available from the BARC-TIFR Pelletron and the Nuclear Science Centre Pelletron. The state of the art gamma detector arrays in these centres enabled the Saha Institute groups to undertake more

  9. Quality assurance for measurements of the radioactivity in the area of the"Horia Hulubei" National Institute for Physics and Nuclear Engineering, IFIN-HH.

    Science.gov (United States)

    Stochioiu, Ana; Luca, Aurelian; Sahagia, Maria; Margineanu, Romul Mircea; Tudor, Ion

    2012-10-01

    This paper presents one part of the activities deployed by the Laboratory for Environment and Personnel Dosimetry (LDPM) of IFIN-HH, namely the radiological monitoring of the environment within the Institute's area and its surrounding influence zone, according to the program approved by the National Regulatory Body for Nuclear Activities, CNCAN. The representative reports regard the radioactive content of soil, surface and underground water, cultivated and spontaneous vegetation, aerosols and atmospheric fallout, sediments. The common requirement is that the measured quantities be precise and the reported values be reliable and credible. This goal is achieved by maintaining a Quality System, verified within the obtaining and maintaining of the laboratory accreditation, according to the international standard ISO/IEC 17025:2005.The LDPM is accredited by the Romanian accreditation body, RENAR, member of the European Accreditation, EA and is designed by CNCAN as a notified testing laboratory. Many measurements were performed in collaboration with the Radionuclide Metrology Laboratory (RML) from IFIN-HH, RENAR accredited and CNCAN notified for calibration and for testing in the field of radioactivity measurement. This paper proposes a short presentation of the important aspects in our activity: i. description of equipment, samplingmethods, processing and measurement of environmental samples; ii. validation of equipment and methods by participation in international and national proficiency tests; iii. a five year follow chart, containing the results in measurement of samples; iv. a recent application, with a wide impact in Romanian mass media: the credible daily report on the possible influence of Fukushima accident over the Romanian environmental radioactivity.

  10. Activities of the Institute for Mechanical Engineering

    Science.gov (United States)

    The Institute of Mechanical Engineering (IME) is part of Canada's National Research Council. Its mission is to undertake, support, promote, and disseminate research and development in the mechanical engineering aspects of three vital sectors of the Canadian economy: transportation, resource industries, and manufacturing. The IME achieves its mission by performing research and development in its own facilities; by developing, providing, and transferring expertise and knowledge; by making its research facilities available to collaborators and clients; and by participating in international liaison and collaborative research activities. Six research programs are conducted in the IME: Advanced Manufacturing Technology; Coastal Zone Engineering; Cold Regions Engineering; Combustion and Fluids Engineering; Ground Transportation Technology; and Machinery and Engine Technology. The rationale and major research thrusts of each program are described, and specific achievements in 1991-92 are reviewed. Lists of technical reports and papers presented by IME personnel are also included.

  11. The Swiss Institute for Nuclear Research SIN

    CERN Document Server

    Pritzker, Andreas

    2014-01-01

    This book tells the story of the Swiss Institute for Nuclear Research (SIN). The institute was founded in 1968 and became part of the Paul Scherrer Institute (PSI) in 1988. Its founding occurred at a time when physics was generally considered the key discipline for technological and social development. This step was unusual for a small country like Switzerland and showed courage and foresight. Equally unusual were the accomplishments of SIN, compared with similar institutes in the rest of the world, as well as its influence on Swiss, and partially also on international politics of science. That this story is now available in a widely understandable form is due to the efforts of some physicists, who took the initiative as long as contemporary witnesses could still be questioned. As is usually the case, official documents always show just an excerpt of what really happened. An intimate portrayal of people who contributed to success requires personal memories. This text relies on both sources. In addition, the e...

  12. International Institute for Hydraulic and Environmental Engineering

    Science.gov (United States)

    Mostertman, L. J.

    1977-01-01

    Describes the activities of the International Institute for Hydraulic and Environmental Engineering (IHE), whose primary function is the promotion of the better use of water resources as a vehicle of development by the transfer of knowledge and experience. (Author/RK)

  13. Nuclear Engineering Technologists in the Nuclear Power Era

    Science.gov (United States)

    Wang, C. H.; And Others

    1974-01-01

    Describes manpower needs in nuclear engineering in the areas of research and development, architectural engineering and construction supervision, power reactor operations, and regulatory tasks. Outlines a suitable curriculum to prepare students for the tasks related to construction and operation of power reactors. (GS)

  14. Final Report: Performance Engineering Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Mellor-Crummey, John [Rice Univ., Houston, TX (United States)

    2014-10-27

    This document is a final report about the work performed for cooperative agreement DE-FC02-06ER25764, the Rice University effort of Performance Engineering Research Institute (PERI). PERI was an Enabling Technologies Institute of the Scientific Discovery through Advanced Computing (SciDAC-2) program supported by the Department of Energy's Office of Science Advanced Scientific Computing Research (ASCR) program. The PERI effort at Rice University focused on (1) research and development of tools for measurement and analysis of application program performance, and (2) engagement with SciDAC-2 application teams.

  15. Nuclear Engineering at Colleges and Universities

    Science.gov (United States)

    Duffey, Dick

    1973-01-01

    Presents five statistical tables relating to nuclear engineering education, namely, course offerings by U.S. and Canadian schools; degrees and enrollment; enrollment, courses, and staff by schools; degrees granted by schools; and research contributions to the American Nuclear Society meetings. (CC)

  16. Current challenges for education of nuclear engineers. Beyond nuclear basics

    Energy Technology Data Exchange (ETDEWEB)

    Schoenfelder, Christian [AREVA GmbH, Offenbach (Germany). Training Center

    2014-07-15

    In past decades, curricula for the education of nuclear engineers (either as a major or minor subject) have been well established all over the world. However, from the point of view of a nuclear supplier, recent experiences in large and complex new build as well as modernization projects have shown that important competences required in these projects were not addressed during the education of young graduates. Consequently, in the past nuclear industry has been obliged to either accept long periods for job familiarization, or to develop and implement various dedicated internal training measures. Although the topics normally addressed in nuclear engineering education (like neutron and reactor physics, nuclear materials or thermohydraulics and the associated calculation methods) build up important competences, this paper shows that the current status of nuclear applications requires adaptations of educational curricula. As a conclusion, when academic nuclear engineering curricula start taking into account current competence needs in nuclear industry, it will be for the benefit of the current and future generation of nuclear engineers. They will be better prepared for their future job positions and career perspectives, especially on an international level. The recommendations presented should not only be of importance for the nuclear fission field, but also for the fusion community. Here, the Horizon 2020 Roadmap to Fusion as published in 2012 now is focusing on ITER and on a longer-term development of fusion technology for a future demonstration reactor DEMO. The very challenging work program is leading to a strong need for exactly those skills that are described in this article.

  17. Nuclear corrosion science and engineering

    CERN Document Server

    2012-01-01

    Understanding corrosion mechanisms, the systems and materials they affect, and the methods necessary for accurately measuring their incidence is of critical importance to the nuclear industry for the safe, economic and competitive running of its plants. This book reviews the fundamentals of nuclear corrosion. Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechani...

  18. 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.

  19. Russian scientists make desperate plea to save nuclear institute

    CERN Multimedia

    2003-01-01

    Scientists from a Russian nuclear research institute recently held a news conference in Moscow to publicize their work on a revolutionary new type of nuclear reactor. However, it transpired that the scientists were worried about their institute being closed down, and saw the news conference as an opportunity to draw attention to their plight (1 page).

  20. Nuclear thermal rocket engine operation and control

    Science.gov (United States)

    Gunn, Stanley V.; Savoie, Margarita T.; Hundal, Rolv

    1993-06-01

    The operation of a typical Rover/Nerva-derived nuclear thermal rocket (NTR) engine is characterized and the control requirements of the NTR are defined. A rationale for the selection of a candidate diverse redundant NTR engine control system is presented and the projected component operating requirements are related to the state of the art of candidate components and subsystems. The projected operational capabilities of the candidate system are delineated for the startup, full-thrust, shutdown, and decay heat removal phases of the engine operation.

  1. Nuclear Targeting Terms for Engineers and Scientists

    Energy Technology Data Exchange (ETDEWEB)

    St Ledger, John W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-02-01

    The Department of Defense has a methodology for targeting nuclear weapons, and a jargon that is used to communicate between the analysts, planners, aircrews, and missile crews. The typical engineer or scientist in the Department of Energy may not have been exposed to the nuclear weapons targeting terms and methods. This report provides an introduction to the terms and methodologies used for nuclear targeting. Its purpose is to prepare engineers and scientists to participate in wargames, exercises, and discussions with the Department of Defense. Terms such as Circular Error Probable, probability of hit and damage, damage expectancy, and the physical vulnerability system are discussed. Methods for compounding damage from multiple weapons applied to one target are presented.

  2. 2009 UK/US Nuclear Engineering Workshop Report

    Energy Technology Data Exchange (ETDEWEB)

    Richard Rankin

    2009-04-01

    This report summarizes the 2009 UK/US Nuclear Engineering Workshop held April 20-21, 2010, in Washington, D.C. to discuss opportunities for nuclear engineering collaboration between researchers in the United States and the United Kingdom.

  3. 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

  4. 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.

  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. Virtual Visit to the ATLAS Control Room by Institute of Nuclear Physics, Cracow, Poland

    CERN Multimedia

    ATLAS Experiment

    2012-01-01

    The 12 Festival of Science "Theory-knowledge-experience...". Fest will be located on the traditional Main Square, which is visited by thousands of citizens and tourists. Institute of Nuclear Physics as usual participates in this annual event. Our visitors will learn the secrets of the CERN experiments on the Large Hadron Collider - ATLAS, LHCb, ALICE, CMS, find out more about the Higgs particles, antimatter quark-gluon plasma (beeing guided by our scientists and PhD students). One of the attractions will be ATLAS Control Room Virtual Visit. Visiting people will have an opportunity to see how ATLAS is controlled and operated to collect its exciting data and ask questions to scientists and engineers involved in LHC program at CERN. Institute of Nuclear Physics has prepared also several interactive demonstrations of Atomic Force Microscopy, Magnetic Resonance, Hadron Therapy and Crystal Physics. The Institute of Nuclear Physics of the Polish Academy of Sciences carries out basic and applied research in physics, ...

  7. MINA 2008: an approach to professionalization in Nuclear Engineering; MINA 2008: una via de profesionalizacion en Ingenieria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Herranz, L. E.; Garcia Cuesta, J. C.; Falcon, S.; Marco, M.

    2008-07-01

    At present there are evident signs around the world of what has been called the Nuclear Renaissance. The anticipated nuclear revival is coinciding in time with the retirement of a generation of professionals who have been responsible for the design, construction and operation of the second generation nuclear power plants and, with them, a large part of the experience gained. Whatever its future energy strategy may be, Spain is already recognizing this reality through projects that national companies, engineering firms and institutions are undertaking beyond the country borders. Consequently, it is expected that the nuclear sector will be demanding competent human capital. National support for nuclear power would increase this need even more. In this national and international panorama, CIEMAT and the UAM have recognized the opportunity to adopt a new concept, as ambitious as it is stimulating, for training of nuclear professionals: the Masters in Nuclear Engineering and Applications (MINA). CIEMAT long tradition of training in nuclear technology and the background of collaboration between CIEMAT and the UAM have been the fundamental basis for defining MINA-2008. Born with a multi-institutional vocation, MINA aims to address the needs of the nuclear sector and promote the interest of young people in nuclear technology. (Author) 3 refs.

  8. Decommissioning of nuclear facilities at the Nuclear Research Institute Rez plc

    Directory of Open Access Journals (Sweden)

    Podlaha Josef

    2010-01-01

    Full Text Available The Nuclear Research Institute Rez has been a leading institution in all areas of nuclear R&D in the Czech Republic since it was established in 1955. After more than 50 years of activities in the field, there are some environmental liabilities that need to be remedied. The remediation of old environmental liabilities concerning the Nuclear Research Institute is the only ongoing decommissioning project in the Czech Republic. The nature of these environmental liabilities is very specific and requires special remediation procedures. The process begun in 2003 and is expected to be finished by 2014.

  9. CAS Institute of Information Engineering sees a good start

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    The Institute of Information Engineering (liE), a new institute under CAS approved for establishment in 2011, has made a good start in its development in a recent year, By far, it has set up several statelevel innovation platforms, including the State Key Laboratory of Information Security, the State Engineering Laboratory of Information Contenl. Security Technology, the National Engineering Research Center of Information Security, and the

  10. Summary of aerospace and nuclear engineering activities

    Science.gov (United States)

    1988-01-01

    The Texas A&M Nuclear and Aerospace engineering departments have worked on five different projects for the NASA/USRA Advanced Design Program during the 1987/88 year. The aerospace department worked on two types of lunar tunnelers that would create habitable space. The first design used a heated cone to melt the lunar regolith, and the second used a conventional drill to bore its way through the crust. Both used a dump truck to get rid of waste heat from the reactor as well as excess regolith from the tunneling operation. The nuclear engineering department worked on three separate projects. The NEPTUNE system is a manned, outer-planetary explorer designed with Jupiter exploration as the baseline mission. The lifetime requirement for both reactor and power-conversion systems was twenty years. The second project undertaken for the power supply was a Mars Sample Return Mission power supply. This was designed to produce 2 kW of electrical power for seven years. The design consisted of a General Purpose Heat Source (GPHS) utilizing a Stirling engine as the power conversion unit. A mass optimization was performed to aid in overall design. The last design was a reactor to provide power for propulsion to Mars and power on the surface. The requirements of 300 kW of electrical power output and a mass of less than 10,000 Rg were set. This allowed the reactor and power conversion unit to fit within the Space Shuttle cargo bay.

  11. Festschrift. The Institute of Nuclear Medicine. 50 years

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-01

    The Institute of Nuclear Medicine, founded in 1961, celebrates with this Festschrift, its Golden Jubilee. It has been a remarkable 50 years of progress of the radionuclide tracer methodology. From initial, physiology based experimentation, a full independent medical discipline evolved, and with it, a comprehensive clinical service. Diagnosis and Treatment with radiotracers have established the basis for Nuclear Medicine. Technological advances have permeated the field like none other, its multidisciplinary character and its translational research are embedded in the history of the Institute and its success. Recent and latest advances in the field promise a future as bright as has been witnessed and documented in the last 50 years.

  12. Development of undergraduate nuclear security curriculum at College of Engineering, Universiti Tenaga Nasional

    Science.gov (United States)

    Hamid, Nasri A.; Mujaini, Madihah; Mohamed, Abdul Aziz

    2017-01-01

    The Center for Nuclear Energy (CNE), College of Engineering, Universiti Tenaga Nasional (UNITEN) has a great responsibility to undertake educational activities that promote developing human capital in the area of nuclear engineering and technology. Developing human capital in nuclear through education programs is necessary to support the implementation of nuclear power projects in Malaysia in the near future. In addition, the educational program must also meet the nuclear power industry needs and requirements. In developing a certain curriculum, the contents must comply with the university's Outcomes Based Education (OBE) philosophy. One of the important courses in the nuclear curriculum is in the area of nuclear security. Basically the nuclear security course covers the current issues of law, politics, military strategy, and technology with regard to weapons of mass destruction and related topics in international security, and review legal regulations and political relationship that determine the state of nuclear security at the moment. In addition, the course looks into all aspects of the nuclear safeguards, builds basic knowledge and understanding of nuclear non-proliferation, nuclear forensics and nuclear safeguards in general. The course also discusses tools used to combat nuclear proliferation such as treaties, institutions, multilateral arrangements and technology controls. In this paper, we elaborate the development of undergraduate nuclear security course at the College of Engineering, Universiti Tenaga Nasional. Since the course is categorized as mechanical engineering subject, it must be developed in tandem with the program educational objectives (PEO) of the Bachelor of Mechanical Engineering program. The course outcomes (CO) and transferrable skills are also identified. Furthermore, in aligning the CO with program outcomes (PO), the PO elements need to be emphasized through the CO-PO mapping. As such, all assessments and distribution of Bloom Taxonomy

  13. Creation of security engineering programs by the Southwest Surety Institute

    Science.gov (United States)

    Romero, Van D.; Rogers, Bradley; Winfree, Tim; Walsh, Dan; Garcia, Mary Lynn

    1998-12-01

    The Southwest Surety Institute includes Arizona State University (ASU), Louisiana State University (LSU), New Mexico Institute of Mining and Technology (NM Tech), New Mexico State University (NMSU), and Sandia National Laboratories (SNL). The universities currently offer a full spectrum of post-secondary programs in security system design and evaluation, including an undergraduate minor, a graduate program, and continuing education programs. The programs are based on the methodology developed at Sandia National Laboratories over the past 25 years to protect critical nuclear assets. The programs combine basic concepts and principles from business, criminal justice, and technology to create an integrated performance-based approach to security system design and analysis. Existing university capabilities in criminal justice (NMSU), explosives testing and technology (NM Tech and LSU), and engineering technology (ASU) are leveraged to provide unique science-based programs that will emphasize the use of performance measures and computer analysis tools to prove the effectiveness of proposed systems in the design phase. Facility managers may then balance increased protection against the cost of implementation and risk mitigation, thereby enabling effective business decisions. Applications expected to benefit from these programs include corrections, law enforcement, counter-terrorism, critical infrastructure protection, financial and medical care fraud, industrial security, and border security.

  14. Institutional Strain and Precarious Values in Meeting Future Nuclear Challenges

    Energy Technology Data Exchange (ETDEWEB)

    Bruce Matthews; Todd R. LaPorte

    1998-11-01

    This paper explores the implications of moderately expanding plutonium "pit" production capability within the strongly R&D culture of Los Alamos National Laboratory, especially in terms of the lab's current capacity or "fitness for the future" in which institutional stewardship of the nation's nuclear deterrent capability becomes a primary objective. The institutional properties needed to assure "future fitness" includes the organizational requisites highly reliable operations and sustained institutional constancy in a manner that evokes deep public trust and confidence. Estimates are made of the degree to which the key Division and most relevant Program office in this evolution already exhibits them.

  15. 4{sup +} Dimensional nuclear systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Kune Y. [PHILOSOPHIA, Seoul (Korea, Republic of)

    2009-04-15

    Nuclear power plants (NPPs) require massive quantity of data during the design, construction, operation, maintenance and decommissioning stages because of their special features like size, cost, radioactivity, and so forth. The system engineering thus calls for a fully integrated way of managing the information flow spanning their life cycle. This paper proposes digital systems engineering anchored in three dimensional (3D) computer aided design (CAD) models. The signature in the proposal lies with the four plus dimensional (4{sup +}D) Technology{sup TM}, a critical know how for digital management. ESSE (Engineering Super Simulation Emulation) features a 4{sup +}D Technology{sup TM}for nuclear energy systems engineering. The technology proposed in the 3D space and time plus cost coordinates, i.e. 4{sup +}D, is the backbone of digital engineering in the nuclear systems design and management. Dased on an integrated 3D configuration management system, ESSE consists of solutions JANUS (Junctional Analysis Neodynamic Unit SoftPower), EURUS (Engineering Utilities Research Unit SoftPower), NOTUS (Neosystemic Optimization Technical Unit SoftPower), VENUS (Virtual Engineering Neocybernetic Unit SoftPower) and INUUS (Informative Neographic Utilities Unit SoftPower). NOTUS contributes to reducing the construction cost of the NPPs 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 3D visualization of construction processes and the resulting products intrinsically afford most of the advantages realized by incorporating a purely schedule level detail based the 4{sup +}D system. Problems with equipment positioning and manpower congestion in certain areas can be visualized prior to the actual operation, thus preventing accidents and safety problems such as collision between

  16. XIAO Liye: New head of the Institute of Electrical Engineering

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    @@ Prof. XIAO Liye, an expert in superconducting technology, has been appointed new director of the Institute of Electrical Engineering(IEE), a research arm of CAS dedicating to the promotion of technical level of power generation and electrical equipment manufacturing.

  17. The nuclear energy, public opinion and the awareness of work of nuclear institutions

    Energy Technology Data Exchange (ETDEWEB)

    Pastura, Valeria; Mol, Antonio Carlos de A.; Legey, Ana Paula; Lapa, Celso Marcelo F., E-mail: vpastura@ien.gov.br, E-mail: mol@ien.gov.br, E-mail: analegey@hotmail.com, E-mail: lapa@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Programa de Pos-graduacao em Ciencia e Tecnologia Nucleares

    2015-07-01

    With Brazil facing a prospect of expanding its nuclear-energy sources and the development of new nuclear techniques there is a need for imminent integration in the nuclear industry with the tool information. In this paper we propose the creation of a program aimed at the servers of the institutions that make up the Brazilian Nuclear Sector, with a view to preparing these to become multipliers in the dissemination of activities developed by the institution so that they can, with strong arguments, defending the work of industry criticism of this form of energy. The goal is to create an important process of change of mentality and attitude among people who relate to the servers in the industry, expanding the debate on the subject, so that society, clearly and free of prejudices can understand the benefits the use of nuclear energy. (author)

  18. Summer Institute in Biomedical Engineering for College Teachers

    Science.gov (United States)

    Cleaver, T. G.; And Others

    1973-01-01

    Discusses the objectives, curricula, and accomplishments of an interdisciplinary summer institute designed to prepare college teachers qualified in both the life sciences and engineering. Indicates that joint educational programs between engineering, science, and medical faculties are completely feasible if each group is interested in the other…

  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. The engineering institute of Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Farrar, Charles R [Los Alamos National Laboratory; Park, Gyuhae [Los Alamos National Laboratory; Cornwell, Phillip J [Los Alamos National Laboratory; Todd, Michael D [UCSD

    2008-01-01

    Los Alamos National Laboratory (LANL) and the University of California, San Diego (UCSD) have taken the unprecedented step of creating a collaborative, multi-disciplinary graduate education program and associated research agenda called the Engineering Institute. The mission of the Engineering Institute is to develop a comprehensive approach for conducting LANL mission-driven, multidisciplinary engineering research and to improve recruiting, revitalization, and retention of the current and future staff necessary to support the LANL' s national security responsibilities. The components of the Engineering Institute are (1) a joint LANL/UCSD degree program, (2) joint LANL/UCSD research projects, (3) the Los Alamos Dynamic Summer School, (4) an annual workshop, and (5) industry short courses. This program is a possible model for future industry/government interactions with university partners.

  1. Joint Institute for Nuclear Research Exhibition Science Bringing Nations Together

    CERN Multimedia

    2000-01-01

    The JOINT INSTITUTE FOR NUCLEAR RESEARCH, JINR, was established by its founding countries in 1956 with the purpose of joining together the scientific and material potential of Member States in studies of the fundamental properties of matter. JINR is an international inter-governmental scientific research organization, whose activities are based on the principles of openness for participation to all interested states and of their equal, mutually beneficial collaboration.

  2. FEL development at the Budker Institute of Nuclear Physics

    Science.gov (United States)

    Vinokurov, N. A.

    1993-07-01

    There are three different FEL projects at the Budker Institute of Nuclear Physics: 1) the FEL on the VEPP-3 storage ring which operates in the visible and ultraviolet region; 2) the high power FEL using a racetrack microtron recuperator (this machine will provide an average power of about tens of kilowatt in the infrared region); and 3) the compact infrared FEL project, using a microton, and a powerful FEL on a dedicated superconducting storage ring, which is under consideration now.

  3. Joint Institute for Nuclear Research Exhibition Science Bringing Nations Together

    CERN Multimedia

    1999-01-01

    The JOINT INSTITUTE FOR NUCLEAR RESEARCH, JINR, was established by its founding countries in 1956 with the purpose of joining together the scientific and material potential of Member States in studies of the fundamental properties of matter. JINR is an international inter-governmental scientific research organization, the activities of which are based on the principles of openness for participation to all interested states of their equal, mutually beneficial collaboration.

  4. Anti-seismic research on nuclear engineering siting

    Institute of Scientific and Technical Information of China (English)

    Li CHEN; Lei NIE; Jijiang LI; Delong WANG; Xiangyu REN

    2006-01-01

    Nuclear engineering belongs to significant project; there is higher requirement on sitings. The study has discussed basic factors of selecting sites, anti-seismic research on sitings including the seismic ground motion, probability methods of seismic hazard analysis as well as interaction about structure and foundation, meanwhile provide the reason for nuclear engineering selecting sites.

  5. Teaching Problem-Solving Skills to Nuclear Engineering Students

    Science.gov (United States)

    Waller, E.; Kaye, M. H.

    2012-01-01

    Problem solving is an essential skill for nuclear engineering graduates entering the workforce. Training in qualitative and quantitative aspects of problem solving allows students to conceptualise and execute solutions to complex problems. Solutions to problems in high consequence fields of study such as nuclear engineering require rapid and…

  6. Teaching Problem-Solving Skills to Nuclear Engineering Students

    Science.gov (United States)

    Waller, E.; Kaye, M. H.

    2012-01-01

    Problem solving is an essential skill for nuclear engineering graduates entering the workforce. Training in qualitative and quantitative aspects of problem solving allows students to conceptualise and execute solutions to complex problems. Solutions to problems in high consequence fields of study such as nuclear engineering require rapid and…

  7. Rocketdyne/Westinghouse nuclear thermal rocket engine modeling

    Science.gov (United States)

    Glass, James F.

    1993-01-01

    The topics are presented in viewgraph form and include the following: systems approach needed for nuclear thermal rocket (NTR) design optimization; generic NTR engine power balance codes; rocketdyne nuclear thermal system code; software capabilities; steady state model; NTR engine optimizer code-logic; reactor power calculation logic; sample multi-component configuration; NTR design code output; generic NTR code at Rocketdyne; Rocketdyne NTR model; and nuclear thermal rocket modeling directions.

  8. Introducing the Institute of Physics in Engineering and Medicine (IPEM)

    Science.gov (United States)

    Keevil, Stephen F.

    2014-04-01

    Physics in Medicine and Biology is one of three journals owned by the UK based Institute of Physics and Engineering in Medicine (IPEM), along with Physiological Measurement and Medical Engineering and Physics. IPEM is a charity and journal revenues are a vital part of our income stream. By subscribing to our journals, you are helping to support the work of IPEM, so you may be interested to learn more about who we are and what we do. IPEM aims to advance physics and engineering applied to medicine and biology for the public good. Our membership comprises over 4000 physicists, engineers and technologists working in healthcare, academia and industry. Most of our work depends on these members generously volunteering their expert knowledge and extensive experience to work in the following areas. Promoting research and innovation Along with the scientific journals mentioned above, we also regularly produce scientific reports. There are currently 40 IPEM reports in print, as well as reference books such as The Gamma Camera—A Comprehensive Guide and the recently published Physicists and Physicians: A History of Medical Physics from the Renaissance to Röntgen. Publishing is just one way in which we encourage R&D and increase the uptake of new knowledge and innovations. We also support scientific conferences, such as the International Conference on Medical Physics 50th anniversary meeting, which we hosted in 2013 on behalf of the International Organization for Medical Physics (IOMP). This four-day event explored the contribution that physics and engineering can make to healthcare and showcased the latest developments via 312 international speakers, 212 posters and an exhibition. Our awards, travel bursaries and grants enable us to facilitate, recognize and reward the work of our members. In 2012 we awarded almost #95 000 (around 155 000) this way. Championing the sector IPEM provides a unified voice with which to represent the views of our membership and raise the

  9. 75 FR 10444 - Nuclear Energy Institute; Denial of Petition for Rulemaking

    Science.gov (United States)

    2010-03-08

    ... COMMISSION 10 CFR Part 73 Nuclear Energy Institute; Denial of Petition for Rulemaking AGENCY: Nuclear... (NRC) is denying a petition for rulemaking (PRM) submitted by the Nuclear Energy Institute (NEI) (the... rulemaking. The petitioner states that the nuclear energy industry has fully implemented numerous new...

  10. 76 FR 28192 - Petition for Rulemaking Submitted by the Nuclear Energy Institute

    Science.gov (United States)

    2011-05-16

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION 10 CFR Part 26 Petition for Rulemaking Submitted by the Nuclear Energy Institute AGENCY: Nuclear... rulemaking (PRM) submitted by Anthony R. Pietrangelo, on behalf of the Nuclear Energy Institute (NEI), the...

  11. Cyclotron laboratory of the Institute for Nuclear Research and Nuclear Energy

    Science.gov (United States)

    Tonev, D.; Goutev, N.; Georgiev, L. S.

    2016-06-01

    An accelerator laboratory is presently under construction in Sofia at the Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences. The laboratory will use a TR24 type of cyclotron, which provides a possibility to accelerate a proton beam with an energy of 15 to 24 MeV and current of up to 0.4 mA. An accelerator with such parameters allows to produce a large variety of radioisotopes for development of radiopharmaceuticals. The most common radioisotopes that could be produced with such a cyclotron are PET isotopes like: 11C, 13N, 15O, 18F, 124I, 64Cu, 68Ge/68Ga, and SPECT isotopes like: 123I, 111In, 67Ga, 57Co, 99m Tc. Our aim is to use the cyclotron facility for research in the fields of radiopharmacy, radiochemistry, radiobiology, nuclear physics, solid state physics, applied research, new materials and for education in all these fields including nuclear energy. The building of the laboratory will be constructed nearby the Institute for Nuclear Research and Nuclear Energy and the cyclotron together with all the equipment needed will be installed there.

  12. Brief 70 Nuclear Engineering Enrollments and Degrees, 2011 Summary Information

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Don Johnson

    2012-10-31

    The survey includes degrees granted between September 1, 2010 and August 31, 2011. Enrollment information refers to the fall term 2011. The enrollment and degree data include students majoring in nuclear engineering or in an option program equivalent to a major. Thirty-two academic programs reported having nuclear engineering programs during 2011, and data was received from all thirty-two programs. The data for two nuclear engineering programs include enrollments and degrees in health physics options that are also reported in the health physics enrollments and degrees data.

  13. Brief 74 Nuclear Engineering Enrollments and Degrees Survey, 2014 Data

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-15

    The 2014 survey includes degrees granted between September 1, 2013 and August 31, 2014, and enrollments for fall 2014. There are three academic programs new to this year's survey. Thirty-five academic programs reported having nuclear engineering programs during 2014, and data were provided by all thirty-five. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Two nuclear engineering programs have indicated that health physics option enrollments and degrees are also reported in the health physics enrollments and degrees survey.

  14. Brief 76 Nuclear Engineering Enrollments and Degrees Survey, 2015 Data

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2016-03-15

    The 2015 Nuclear Engineering Enrollments and Degrees Survey reports degrees granted between September 1, 2014 and August 31, 2015. Enrollment information refers to the fall term 2015. The enrollments and degrees data comprises students majoring in nuclear engineering or in an option program equivalent to a major. Thirty-five academic programs reported having nuclear engineering programs during 2015, and data was received from all thirty-five programs. The report includes enrollment information on undergraduate students and graduate students and information by degree level for post-graduation plans.

  15. Nuclear Engine System Simulation (NESS) version 2.0

    Science.gov (United States)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-01-01

    The topics are presented in viewgraph form and include the following; nuclear thermal propulsion (NTP) engine system analysis program development; nuclear thermal propulsion engine analysis capability requirements; team resources used to support NESS development; expanded liquid engine simulations (ELES) computer model; ELES verification examples; NESS program development evolution; past NTP ELES analysis code modifications and verifications; general NTP engine system features modeled by NESS; representative NTP expander, gas generator, and bleed engine system cycles modeled by NESS; NESS program overview; NESS program flow logic; enabler (NERVA type) nuclear thermal rocket engine; prismatic fuel elements and supports; reactor fuel and support element parameters; reactor parameters as a function of thrust level; internal shield sizing; and reactor thermal model.

  16. Human factor engineering applied to nuclear power plant design

    Energy Technology Data Exchange (ETDEWEB)

    Manrique, A. [TECNATOM SA, BWR General Electric Business Manager, Madrid (Spain); Valdivia, J.C. [TECNATOM SA, Operation Engineering Project Manager, Madrid (Spain); Jimenez, A. [TECNATOM SA, Operation Engineering Div. Manager, Madrid (Spain)

    2001-07-01

    For the design and construction of new nuclear power plants as well as for maintenance and operation of the existing ones new man-machine interface designs and modifications are been produced. For these new designs Human Factor Engineering must be applied the same as for any other traditional engineering discipline. Advantages of implementing adequate Human Factor Engineering techniques in the design of nuclear reactors have become not only a fact recognized by the majority of engineers and operators but also an explicit requirement regulated and mandatory for the new designs of the so called advanced reactors. Additionally, the big saving achieved by a nuclear power plant having an operating methodology which significantly decreases the risk of operating errors makes it necessary and almost vital its implementation. The first step for this is preparing a plan to incorporate all the Human Factor Engineering principles and developing an integral design of the Instrumentation and Control and Man-machine interface systems. (author)

  17. Human Factors in Nuclear Power Engineering in Polish Conditions

    Directory of Open Access Journals (Sweden)

    Agnieszka Kaczmarek-Kacprzak

    2014-09-01

    Full Text Available The paper “Human factors in nuclear power engineering in Polish conditions” focuses on analysis of dynamics of preparing Polish society to build fi rst nuclear power plant in XXI century in Poland. Authors compare experience from constructing nuclear power plant Sizewell B (Great Britain and Sizewell C, which is in preparation phase with polish nuclear power program. Paper includes aspects e.g. of creating nuclear safety culture and social opinion about investment. Human factors in nuclear power engineering are as well important as relevant economical and technical factors, but very often negligible. In Poland where history about Czarnobyl is still alive, and social opinion is created on emotions after accident in Fukushima, human factors are crucial and should be under comprehensive consideration.

  18. Engineering possibilities versus practical implementation. Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2015-06-15

    Europe's energy transition has placed the nuclear sector at a crossroads, and members of POWER-GEN Europe's Advisory Board have considered the role of nuclear in Europe's drive towards energy decarbonisation, ahead of the conference. Simon Hobday, Jacob Klimstra, David Porter and Ulla Pettersson talked about the role of nuclear in Europe's energy decarbonisation, nations in Europe where new nuclear generation appears likely, and the future role of the European Commission.

  19. 77 FR 9273 - WORKSHOP Sponsored by the Nuclear Regulatory Commission and the Electric Power Research Institute...

    Science.gov (United States)

    2012-02-16

    ... COMMISSION WORKSHOP Sponsored by the Nuclear Regulatory Commission and the Electric Power Research Institute...), Office of Nuclear Regulatory Research (RES), in cooperation with the Electric Power Research Institute..., Performance and Reliability Branch, Division of Risk Analysis, Office of Nuclear Regulatory Research, United...

  20. 75 FR 63725 - Nuclear Energy Institute; Consideration of Petition in the Rulemaking Process

    Science.gov (United States)

    2010-10-18

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION 10 CFR Part 70 Nuclear Energy Institute; Consideration of Petition in the Rulemaking Process... raised in a petition submitted by the Nuclear Energy Institute (NEI), and is denying the remaining four...

  1. Annual Report 2011 : Institute for Nuclear Waste Disposal. (KIT Scientific Reports ; 7617)

    OpenAIRE

    Geckeis, H.; Stumpf, T. [Hrsg.

    2012-01-01

    The R&D at the Institute for Nuclear Waste Disposal, INE, (Institut für Nukleare Entsorgung) of the Karlsruhe Institute of Technology (KIT) focuses on (i) long term safety research for nuclear waste disposal, (ii) immobilization of high level radioactive waste (HLW), (iii) separation of minor actinides from HLW and (iv) radiation protection.

  2. Development of nuclear power plant real-time engineering simulator

    Institute of Scientific and Technical Information of China (English)

    LIN Meng; YANG Yan-Hua; ZHANG Rong-Hua; HU Rui

    2005-01-01

    A nuclear power plant real-time engineering simulator was developed based on general-purpose thermal-hydraulic system simulation code RELAP5. It main1y consists of three parts: improved thermal-hydraulic system simulation code RELAP5, control and protection system and human-machine interface. A normal transient of CHASHMA nuclear power plant turbine step load change from 100% to 90% of full power, was simulated by the engineering simulator as an application example. This paper presents structure and main features of the engineering simulator, and application results are shown and discussed.

  3. Process technology activities at the Software Engineering Institute

    Energy Technology Data Exchange (ETDEWEB)

    Christie, A.M. [Carnegie Mellon Univ., Pittsburgh, PA (United States)

    1996-12-31

    This paper provides a brief overview of the rationale for, and direction of the software process technology work being pursued at the Software Engineering Institute. The paper then describes some of the activities that the SEI has recently been involved in. Finally, it relates in more detail an example of one specific effort; namely the development of a process modeling formalism and its use in process simulation.

  4. Engineering Knowledge and Student Development: An Institutional and Pedagogical Critique of Engineering Education

    Science.gov (United States)

    Tang, Xiaofeng

    Educators have recommended the integration of engineering and the liberal arts as a promising educational model to prepare young engineers for global economic, environmental, sociotechnical, and ethical challenges. Drawing upon philosophy of technology, engineering studies, and educational psychology, this dissertation examines diverse visions and strategies for integrating engineering and liberal education and explores their impacts on students' intellectual and moral development. Based on archival research, interviews, and participant observation, the dissertation presents in-depth case studies of three educational initiatives that seek to blend engineering with the humanities, social sciences, and arts: Harvey Mudd College, the Picker Engineering Program at Smith College, and the Programs in Design and Innovation at Rensselaer Polytechnic Institute. The research finds that learning engineering in a liberal arts context increases students' sense of "owning" their education and contributes to their communication, teamwork, and other non-technical professional skills. In addition, opportunities for extensive liberal arts learning in the three cases encourage some students to pursue alternative, less technocentric approaches to engineering. Nevertheless, the case studies suggest that the epistemological differences between the engineering and liberal arts instructors help maintain a technical/social dualism among most students. Furthermore, the dissertation argues a "hidden curriculum," which reinforces the dominant ideology in the engineering profession, persists in the integrated programs and prevents the students from reflecting on the broad social context of engineering and critically examining the assumptions upheld in the engineering profession.

  5. Nuclear Engineering: Enrollments and Degrees. Enrollments-Fall 1973, Degrees Granted-July 1965-June 1973.

    Science.gov (United States)

    Atomic Energy Commission, Washington, DC. Office of Industrial Relations.

    This document presents statistical data concerning enrollments for fall 1973 and degrees granted 1965-June 1973 in nuclear engineering. Highlights of this survey of educational institutions indicated: (1) Ph.D.'s decreased to 126 from 149 in 1971-72 and from 181 in 1969-70. (2) MS's increased to 442 from 428 in 1971-72. (3) BS's increased to 551…

  6. Near-term lunar nuclear thermal rocket engine options

    Science.gov (United States)

    Pelaccio, Dennis G.; Scheil, Christine M.; Collins, John T.

    1991-01-01

    The Nuclear Thermal Rocket (NTR) is an attractive candidate propulsion system option for manned planetary missions. Its high performance capability for such missions translates into a substantial reduction in low-earth-orbit (LEO) required mass and trip times with increased operational flexibility. This study examined NTR engine options that could support near-term lunar mission operations. Expander and gas generator cycle, solid-core NERVA derivative reactor-based NTR engines were investigated. Weight, size, operational characteristics, and design features for representative NTR engine concepts are presented. The impact of using these NTR engines for a typical lunar mission scenario is also examined.

  7. Idaho National Engineering and Environmental Laboratory institutional plan -- FY 2000--2004

    Energy Technology Data Exchange (ETDEWEB)

    Enge, R.S.

    1999-12-01

    In this first institutional plan prepared by Bechtel BWXT Idaho, LLC, for the Idaho National Engineering and Environmental Laboratory, the INEEL will focus its efforts on three strategic thrusts: (1) Environmental Management stewardship for DOE-EM, (2) Nuclear reactor technology for DOE-Nuclear Energy (NE), and (3) Energy R and D, demonstration, and deployment (initial focus on biofuels and chemicals from biomass). The first strategic thrust focuses on meeting DOE-EMs environmental cleanup and long-term stewardship needs in a manner that is safe, cost-effective, science-based, and approved by key stakeholders. The science base at the INEEL will be further used to address a grand challenge for the INEEL and the DOE complex--the development of a fundamental scientific understanding of the migration of subsurface contaminants. The second strategic thrust is directed at DOE-NEs needs for safe, economical, waste-minimized, and proliferation-resistant nuclear technologies. As NE lead laboratories, the INEEL and ANL will pursue specific priorities. The third strategic thrust focuses on DOE's needs for clean, efficient, and renewable energy technology. As an initial effort, the INEEL will enhance its capability in biofuels, bioprocessing, and biochemicals. The content of this institutional plan is designed to meet basic DOE requirements for content and structure and reflect the key INEEL strategic thrusts. Updates to this institutional plan will offer additional content and resource refinements.

  8. Engineering on abolishment measure of nuclear fuel facilities. Application of 3D-CAD to abolishment measure of nuclear fuel facilities

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-12-01

    The Japan Nuclear Cycle Development Institute (JNC) progresses some advancing R and Ds required for establishment of the nuclear fuel cycle under considering on safety, economical efficiency, environmental compatibility, and so on. An important item among them is a technology on safe abolishment of a nuclear energy facility ended its role, which is called the abolishment measure technique. Here was introduced at a center of viewpoint called on use of three dimensional CAD (3D-CAD), on outlines of engineering system for abolishment measure (subdivision engineering system) under an object of nuclear fuel facilities, constructed through subdivision and removal of refinement conversion facilities, by the Ningyo-toge Environmental Engineering Center of JNC. (G.K.)

  9. Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Duran, Felicia Angelica [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.; Waymire, Russell L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.

    2013-10-01

    Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

  10. Ultra-relativistic nuclear collisions: event shape engineering

    CERN Document Server

    Schukraft, Jurgen; Voloshin, Sergei A

    2013-01-01

    The evolution of the system created in a high energy nuclear collision is very sensitive to the fluctuations in the initial geometry of the system. In this letter we show how one can utilize these large fluctuations to select events corresponding to a specific initial shape. Such an "event shape engineering" opens many new possibilities in quantitative test of the theory of high energy nuclear collisions and understanding the properties of high density hot QCD matter.

  11. Coaxial Ring Cyclotron as a Perspective Nuclear Power Engineering Machine

    OpenAIRE

    Tumanyan, A. R.; Simonyan, Kh. A.; Mkrtchyan, R. L.; Amatuni, A. Ts.; Avakyan, R. O.; Khudaverdyan, A. G.

    1995-01-01

    The circuit arrangement of the proposed coaxial ring cyclotron (CRC) is described, and its main advantages, such as simple injection technique, several injected beams summation option, high efficiency, are considered. The proposed proton accelerator is a perspective machine for the solution of the main problems of the present day nuclear power engineering as well as for the next-generation nuclear power plants, representing a combination of subcritical reactors and particle accelerators. The ...

  12. Nuclear electric propulsion mission engineering study. Volume 2: Final report

    Science.gov (United States)

    1973-01-01

    Results of a mission engineering analysis of nuclear-thermionic electric propulsion spacecraft for unmanned interplanetary and geocentric missions are summarized. Critical technologies associated with the development of nuclear electric propulsion (NEP) are assessed, along with the impact of its availability on future space programs. Outer planet and comet rendezvous mission analysis, NEP stage design for geocentric and interplanetary missions, NEP system development cost and unit costs, and technology requirements for NEP stage development are studied.

  13. The open-cycle gas-core nuclear rocket engine - Some engineering considerations.

    Science.gov (United States)

    Taylor, M. F.; Whitmarsh, C. L., Jr.; Sirocky, P. J., Jr.; Iwanczyk, L. C.

    1971-01-01

    A preliminary design study of a conceptual 6000-MW open-cycle gas-core nuclear rocket engine system was made. The engine has a thrust of 44,200 lb and a specific impulse of 4400 sec. The nuclear fuel is uranium-235 and the propellant is hydrogen. Critical fuel mass was calculated for several reactor configurations. Major components of the reactor (reflector, pressure vessel) and the waste heat rejection system were considered conceptually and were sized.

  14. Grooved Fuel Rings for Nuclear Thermal Rocket Engines

    Science.gov (United States)

    Emrich, William

    2009-01-01

    An alternative design concept for nuclear thermal rocket engines for interplanetary spacecraft calls for the use of grooved-ring fuel elements. Beyond spacecraft rocket engines, this concept also has potential for the design of terrestrial and spacecraft nuclear electric-power plants. The grooved ring fuel design attempts to retain the best features of the particle bed fuel element while eliminating most of its design deficiencies. In the grooved ring design, the hydrogen propellant enters the fuel element in a manner similar to that of the Particle Bed Reactor (PBR) fuel element.

  15. Nuclear engineering vocabulary; Vocabulaire de l'ingenierie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The terms, expressions and definitions presented in this booklet come from the works carried out by the French specialized commission of nuclear engineering terminology and neology. This selection of terms cannot be found, in general, in classical dictionaries, or can be found but with a different meaning than the one used in nuclear engineering. All terms and expressions contained in this booklet have been already published in different issues of the Official Journal of the French Republic. This publication makes their use mandatory in replacement of foreign language equivalents inside all government services and public buildings. (J.S.)

  16. Nuclear Explosion Monitoring Research and Engineering Program - Strategic Plan

    Energy Technology Data Exchange (ETDEWEB)

    Casey, Leslie A. [DOE/NNSA

    2004-09-01

    The Department of Energy (DOE)/National Nuclear Security Administration (NNSA) Nuclear Explosion Monitoring Research and Engineering (NEM R&E) Program is dedicated to providing knowledge, technical expertise, and products to US agencies responsible for monitoring nuclear explosions in all environments and is successful in turning scientific breakthroughs into tools for use by operational monitoring agencies. To effectively address the rapidly evolving state of affairs, the NNSA NEM R&E program is structured around three program elements described within this strategic plan: Integration of New Monitoring Assets, Advanced Event Characterization, and Next-Generation Monitoring Systems. How the Program fits into the National effort and historical accomplishments are also addressed.

  17. Systematic Approach to Training for System Engineers in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kwak, Jeong-keun [Korea Hydro and Nuclear Power Co., Ulsan (Korea, Republic of)

    2015-10-15

    In my paper, comprehensive preparations, tangible applications, and final establishments of training for system engineers are described using practical materials in KHNP. The purpose of this paper is to formulate SAT based training in KHNP, especially for system engineers. Hence, to achieve this goal, over one year study was performed considering voluminous materials and working experiences. Through the process, SAT based training package for system engineers was finished, in the end. In terms of training in NPPs, SAT methodology is the unwavering trend in South Korea since NPPs export to UAE. Therefore, materialization of SAT based training for system engineers from the origin of SAT to the finalization of SAT should not be overlooked. A variety of accident preventive approaches have been adopted since the first commercial NPP operation in Calder Hall, United Kingdom. Among diverse event preventive ways, training has played an important role for the improvement of NPPs reliability and safety. This is reason why nuclear industry in every country has established and maintained own training institutes and methods. Since the Three Mile Island (TMI) accident, United States Nuclear Regulatory Commission (USNRC) recommended many betterment plans to US nuclear industry for the elevation of NPPs safety. In the suggested considerations, systematic approach to training, so called SAT appeared in the world. Basically, SAT is composed of five stages, what is called ADDIE. Hence, through ADDIE process, holistic and trustworthy training could be realized in the actual NPPs operation and maintenance. For this reason, SAT is the representative training methodology in the US nuclear business.

  18. Hyperthermal Environments Simulator for Nuclear Rocket Engine Development

    Science.gov (United States)

    Litchford, Ron J.; Foote, John P.; Clifton, W. B.; Hickman, Robert R.; Wang, Ten-See; Dobson, Christopher C.

    2011-01-01

    An arc-heater driven hyperthermal convective environments simulator was recently developed and commissioned for long duration hot hydrogen exposure of nuclear thermal rocket materials. This newly established non-nuclear testing capability uses a high-power, multi-gas, wall-stabilized constricted arc-heater to produce hightemperature pressurized hydrogen flows representative of nuclear reactor core environments, excepting radiation effects, and is intended to serve as a low-cost facility for supporting non-nuclear developmental testing of hightemperature fissile fuels and structural materials. The resulting reactor environments simulator represents a valuable addition to the available inventory of non-nuclear test facilities and is uniquely capable of investigating and characterizing candidate fuel/structural materials, improving associated processing/fabrication techniques, and simulating reactor thermal hydraulics. This paper summarizes facility design and engineering development efforts and reports baseline operational characteristics as determined from a series of performance mapping and long duration capability demonstration tests. Potential follow-on developmental strategies are also suggested in view of the technical and policy challenges ahead. Keywords: Nuclear Rocket Engine, Reactor Environments, Non-Nuclear Testing, Fissile Fuel Development.

  19. Qualitative knowledge engineering for nuclear applications

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae H.; Kim, Ko R.; Lee, Jae C.

    1996-01-01

    After the TMI nuclear power plant accident, the two topics of plant safety and operational efficiency became more important areas of artificial intelligence, which have difference characteristics. Qualitative deep model is the recently prospective technology of AI, that can overcome several handicaps of the existing expert systems such as lack of common sense reasoning. The application of AI to the large and complex system like nuclear power plants is typically and effectively done through a module-based hierarchical system. As each module has to be built with suitable AI system. Through the experiences of hierarchical system construction, we aimed to develop basic AI application schemes for the power plant safety and operational efficiency as well as basic technologies for autonomous power plants. The goal of the research is to develop qualitative reasoning technologies for nuclear power plants. For this purpose, the development of qualitative modeling technologies and qualitative behaviour prediction technologies of the power plant are accomplished. In addition, the feasibility of application of typical qualitative reasoning technologies to power plants is studied . The goal of the application is to develop intelligent control technologies of power plants, support technologies. For these purposes, we analyzed the operation of power plants according to its operation purpose: power generation operation, shut-down and start-up operation. As a result, qualitative model of basic components were sketched, including pipes, valves, pumps and heat exchangers. Finally, plant behaviour prediction technologies through qualitative plant heat transfer model and design support technologies through 2nd-order differential equation were developed. For the construction of AI system of power plants, we have studied on the mixed module based hierarchical software. As a testbed, we have considered the spent fuel system and the feedwater system. We also studied the integration

  20. Training of nuclear criticality safety engineers

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, R.G. [Oak Ridge Y-12 Plant, TN (United States)

    1997-06-01

    The site specific analysis of nuclear criticality training needs is very briefly described. Analysis indicated that the four major components required were analysis, surveillance, business practices or administration, and emergency preparedness. The analysis component was further divided into process analysis, accident analysis, and transportation analysis. Ten subject matter areas for the process analysis component were identified as candidates for class development. Training classes developed from the job content analysis have demonstrated that the specialized information can be successfully delivered to new entrants. 1 fig.

  1. Institute for Nuclear Theory. Annual report No. 3, 1 March 1992--28 February 1993

    Energy Technology Data Exchange (ETDEWEB)

    Haxton, W.; Bertsch, G.; Henley, E.M.

    1993-07-01

    This report briefly discussion the following programs of the Institute for Nuclear Theory: fundamental interactions in nuclei; strangeness in hadrons and nuclei; microscopic nuclear structure theory; nuclear physics in atoms and molecules; phenomenology and lattice QCD; and large amplitude collective motion.

  2. The neutron's children nuclear engineers and the shaping of identity

    CERN Document Server

    Johnston, Sean

    2012-01-01

    This account tracks the Allied atomic energy experts who emerged from the Manhattan Project to explore optimistic but distinct paths in the USA, UK and Canada. Characterised successively as admired atomic scientists, mistrusted spies and heroic engineers, their identities were ultimately shaped by nuclear accidents.

  3. Nuclear magnetic resonance in environmental engineering: principles and applications.

    NARCIS (Netherlands)

    Lens, P.N.L.; Hemminga, M.A.

    1998-01-01

    This paper gives an introduction to nuclear magnetic resonance spectroscopy (NMR) and magnetic resonance imaging (MRI) in relation to applications in the field of environmental science and engineering. The underlying principles of high resolution solution and solid state NMR, relaxation time measure

  4. U.S. Nuclear Engineering Education: Status and Prospects.

    Science.gov (United States)

    National Academy of Sciences - National Research Council, Washington, DC. Commission on Engineering and Technical Systems.

    This study examines the status of and outlook for nuclear engineering (NE) in the United States. The study resulted from a concern about the downward trends in student enrollments in NE, in both graduate and undergraduate programs. Concerns have also been expressed about the declining number of U.S. university NE departments and programs, the…

  5. An introduction to the engineering of fast nuclear reactors

    CERN Document Server

    Judd, Anthony M

    2014-01-01

    An invaluable resource for both graduate-level engineering students and practising nuclear engineers who want to expand their knowledge of fast nuclear reactors, the reactors of the future! This book is a concise yet comprehensive introduction to all aspects of fast reactor engineering. It covers topics including neutron physics; neutron flux spectra; flux distribution; Doppler and coolant temperature coefficients; the performance of ceramic and metal fuels under irradiation, structural changes, and fission-product migration; the effects of irradiation and corrosion on structural materials, irradiation swelling; heat transfer in the reactor core and its effect on core design; coolants including sodium and lead-bismuth alloy; coolant circuits; pumps; heat exchangers and steam generators; and plant control. The book includes new discussions on lead-alloy and gas coolants, metal fuel, the use of reactors to consume radioactive waste, and accelerator-driven subcritical systems.

  6. Computer simulation in nuclear science and engineering

    Energy Technology Data Exchange (ETDEWEB)

    Akiyama, Mamoru; Miya, Kenzo; Iwata, Shuichi; Yagawa, Genki; Kondo, Shusuke (Tokyo Univ. (Japan)); Hoshino, Tsutomu; Shimizu, Akinao; Takahashi, Hiroshi; Nakagawa, Masatoshi

    1992-03-01

    The numerical simulation technology used for the design of nuclear reactors includes the scientific fields of wide range, and is the cultivated technology which grew in the steady efforts to high calculation accuracy through safety examination, reliability verification test, the assessment of operation results and so on. Taking the opportunity of putting numerical simulation to practical use in wide fields, the numerical simulation of five basic equations which describe the natural world and the progress of its related technologies are reviewed. It is expected that numerical simulation technology contributes to not only the means of design study but also the progress of science and technology such as the construction of new innovative concept, the exploration of new mechanisms and substances, of which the models do not exist in the natural world. The development of atomic energy and the progress of computers, Boltzmann's transport equation and its periphery, Navier-Stokes' equation and its periphery, Maxwell's electromagnetic field equation and its periphery, Schroedinger wave equation and its periphery, computational solid mechanics and its periphery, and probabilistic risk assessment and its periphery are described. (K.I.).

  7. Health status of radiation workers in an institute of nuclear research

    Energy Technology Data Exchange (ETDEWEB)

    Popescu, F.; Paunescu, G.; Stroe, F. [Inst. of Public Health, Bucharest (Romania); Andrei, N.

    2000-05-01

    The aim of this study was the identification of the changes in health condition of workers from an institute of nuclear research. Thirty-five workers (25 male and 10 female) radiation exposed to low doses of ionizing radiation were admitted in the Radiopathology Centre Bucharest, after a selection performed during the annual check-up. The workers have had different professions: nuclear fuel processor, engineer laboratory technician, electrician, instrument technician. The time of exposure to ionizing radiation was between 6 to 25 years. Medical specialists in occupational health, dermatology, ophthalmology, O.R.L., endocrinology, haematology, neurology and psychology investigated them. The following lab tests were performed: haematological examination, biochemical examination, immunology tests, alergology skin tests, functional lung tests and cardiogram. No special problems concerning the exposure to ionizing radiation were found, but the following diseases were detected in some extent: neurasthenia, high blood pressure, ischemic heart disease, digestive system disorders, endocrinology disorders and anaemia. High blood pressure, ischemic heart disease and digestive system disorders were related with stress or job strain. Anaemia occurred in connection with gynaecological disorders. Some thyroid dysfunction appeared because of low dietary iodine content in the Sub-Carpathian region. The focus of the psychological exam was the identification of the effect of different factors (exogenous, endogenous or multidimensional) over a person, that could influence the psychological potential. The psychological exam reveals the following disturbances: asthenia, tiredness, chronic fatigue, psycho-emotional impairment, lapses of attention, anxiety. These disturbances may be in relation both with job strain (especially a substantial stress factor for nuclear fuel processor and engineer laboratory technician) and the syndrome of workplace. (author)

  8. Training in nuclear engineering companies; La formacion en las empresas de ingenieria del ambito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Perezagua, R. L.

    2013-03-01

    The importance of training is growing in all business areas and fields and especially in hi-tech companies like engineering firms. Nuclear projects are highly multidisciplinary and, even in the initial awarding and pre-construction phases, need to be staffed with personnel that is well-prepared and highly-qualified in areas that, in most cases, are not covered by university studies. This article examines the variables that influence the design of specific training for nuclear projects in engineering firms, along with new training technologies (e-learning) and new regulatory aspects (IS-12). (Author)

  9. Engine System Model Development for Nuclear Thermal Propulsion

    Science.gov (United States)

    Nelson, Karl W.; Simpson, Steven P.

    2006-01-01

    In order to design, analyze, and evaluate conceptual Nuclear Thermal Propulsion (NTP) engine systems, an improved NTP design and analysis tool has been developed. The NTP tool utilizes the Rocket Engine Transient Simulation (ROCETS) system tool and many of the routines from the Enabler reactor model found in Nuclear Engine System Simulation (NESS). Improved non-nuclear component models and an external shield model were added to the tool. With the addition of a nearly complete system reliability model, the tool will provide performance, sizing, and reliability data for NERVA-Derived NTP engine systems. A new detailed reactor model is also being developed and will replace Enabler. The new model will allow more flexibility in reactor geometry and include detailed thermal hydraulics and neutronics models. A description of the reactor, component, and reliability models is provided. Another key feature of the modeling process is the use of comprehensive spreadsheets for each engine case. The spreadsheets include individual worksheets for each subsystem with data, plots, and scaled figures, making the output very useful to each engineering discipline. Sample performance and sizing results with the Enabler reactor model are provided including sensitivities. Before selecting an engine design, all figures of merit must be considered including the overall impacts on the vehicle and mission. Evaluations based on key figures of merit of these results and results with the new reactor model will be performed. The impacts of clustering and external shielding will also be addressed. Over time, the reactor model will be upgraded to design and analyze other NTP concepts with CERMET and carbide fuel cores.

  10. Nuclear structure studies at Saha Institute of Nuclear Physics using gamma detector arrays

    Indian Academy of Sciences (India)

    P Banerjee

    2001-07-01

    In-beam gamma-ray spectroscopy, carried out at the Saha Institute of Nuclear Physics in the recent past, using heavy-ion projectiles from the pelletron accelerator centres in the country and multi-detector arrays have yielded significant data on the structure of a large number of nuclei spanning different mass regions. The experiments included the study of two-fold -coincidence events for establishing decay schemes, directional correlation of oriented nuclei (DCO) for help in spin assignments and Doppler shift attenuation for lifetime information. The studies have led to the observation of rotational sequences of states in nuclei near closed shell in the mass = 110 region, vibrational spectra in nuclei with ∼ 60, interplay between single-particle and collective modes of excitation in the doubly-odd bromine isotopes, decoupled bands with large quadrupole deformation in 77Br, shape transition with rotational frequency within a band in 138Pm and octupole collectivity in 153Eu. Particle-rotor-model and cranked-shell-model calculations have been carried out to provide an understanding of the underlying nuclear structure

  11. Performance Engineering Research Institute SciDAC-2 Enabling Technologies Institute Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Lucas, Robert

    2013-04-20

    Enhancing the performance of SciDAC applications on petascale systems had high priority within DOE SC at the start of the second phase of the SciDAC program, SciDAC-2, as it continues to do so today. Achieving expected levels of performance on high-end computing (HEC) systems is growing ever more challenging due to enormous scale, increasing architectural complexity, and increasing application complexity. To address these challenges, the University of Southern California?s Information Sciences Institute organized the Performance Engineering Research Institute (PERI). PERI implemented a unified, tripartite research plan encompassing: (1) performance modeling and prediction; (2) automatic performance tuning; and (3) performance engineering of high profile applications. Within PERI, USC?s primary research activity was automatic tuning (autotuning) of scientific software. This activity was spurred by the strong user preference for automatic tools and was based on previous successful activities such as ATLAS, which automatically tuned components of the LAPACK linear algebra library, and other recent work on autotuning domain-specific libraries. Our other major component was application engagement, to which we devoted approximately 30% of our effort to work directly with SciDAC-2 applications. This report is a summary of the overall results of the USC PERI effort.

  12. γ-ray shielding behaviors of some nuclear engineering materials

    Energy Technology Data Exchange (ETDEWEB)

    Mann, Kulwinder Singh [Dept. of Physics, D.A.V. College, Punjab (India)

    2017-06-15

    The essential requirement of a material to be used for engineering purposes at nuclear establishments is its ability to attenuate the most penetrating ionizing radiations, gamma (γ)-rays. Mostly, high-Z materials such as heavy concrete, lead, mercury, and their mixtures or alloys have been used in the construction of nuclear establishments and thus termed as nuclear engineering materials (NEM). The NEM are classified into two categories, namely opaque and transparent, depending on their behavior towards the visible spectrum of EM waves. The majority of NEM are opaque. By contrast, various types of glass, which are transparent to visible light, are necessary at certain places in the nuclear establishments. In the present study, γ-ray shielding behaviors (GSB) of six glass samples (transparent NEM) were evaluated and compared with some opaque NEM in a wide range of energy (15 keV–15 MeV) and optical thickness (OT). The study was performed by computing various γ-ray shielding parameters (GSP) such as the mass attenuation coefficient, equivalent atomic number, and buildup factor. A self-designed and validated computer-program, the buildup factor-tool, was used for various computations. It has been established that some glass samples show good GSB, thus can safely be used in the construction of nuclear establishments in conjunction with the opaque NEM as well.

  13. γ-Ray Shielding Behaviors of Some Nuclear Engineering Materials

    Directory of Open Access Journals (Sweden)

    Kulwinder Singh Mann

    2017-06-01

    Full Text Available The essential requirement of a material to be used for engineering purposes at nuclear establishments is its ability to attenuate the most penetrating ionizing radiations, gamma (γ-rays. Mostly, high-Z materials such as heavy concrete, lead, mercury, and their mixtures or alloys have been used in the construction of nuclear establishments and thus termed as nuclear engineering materials (NEM. The NEM are classified into two categories, namely opaque and transparent, depending on their behavior towards the visible spectrum of EM waves. The majority of NEM are opaque. By contrast, various types of glass, which are transparent to visible light, are necessary at certain places in the nuclear establishments. In the present study, γ-ray shielding behaviors (GSB of six glass samples (transparent NEM were evaluated and compared with some opaque NEM in a wide range of energy (15 keV–15 MeV and optical thickness (OT. The study was performed by computing various γ-ray shielding parameters (GSP such as the mass attenuation coefficient, equivalent atomic number, and buildup factor. A self-designed and validated computer-program, the buildup factor-tool, was used for various computations. It has been established that some glass samples show good GSB, thus can safely be used in the construction of nuclear establishments in conjunction with the opaque NEM as well.

  14. Nuclear morphology and deformation in engineered cardiac myocytes and tissues.

    Science.gov (United States)

    Bray, Mark-Anthony P; Adams, William J; Geisse, Nicholas A; Feinberg, Adam W; Sheehy, Sean P; Parker, Kevin K

    2010-07-01

    Cardiac tissue engineering requires finely-tuned manipulation of the extracellular matrix (ECM) microenvironment to optimize internal myocardial organization. The myocyte nucleus is mechanically connected to the cell membrane via cytoskeletal elements, making it a target for the cellular response to perturbation of the ECM. However, the role of ECM spatial configuration and myocyte shape on nuclear location and morphology is unknown. In this study, printed ECM proteins were used to configure the geometry of cultured neonatal rat ventricular myocytes. Engineered one- and two-dimensional tissue constructs and single myocyte islands were assayed using live fluorescence imaging to examine nuclear position, morphology and motion as a function of the imposed ECM geometry during diastolic relaxation and systolic contraction. Image analysis showed that anisotropic tissue constructs cultured on microfabricated ECM lines possessed a high degree of nuclear alignment similar to that found in vivo; nuclei in isotropic tissues were polymorphic in shape with an apparently random orientation. Nuclear eccentricity was also increased for the anisotropic tissues, suggesting that intracellular forces deform the nucleus as the cell is spatially confined. During systole, nuclei experienced increasing spatial confinement in magnitude and direction of displacement as tissue anisotropy increased, yielding anisotropic deformation. Thus, the nature of nuclear displacement and deformation during systole appears to rely on a combination of the passive myofibril spatial organization and the active stress fields induced by contraction. Such findings have implications in understanding the genomic consequences and functional response of cardiac myocytes to their ECM surroundings under conditions of disease.

  15. Nuclear electric propulsion mission engineering study. Volume 1: Executive summary

    Science.gov (United States)

    1973-01-01

    Results of a mission engineering analysis of nuclear-thermionic electric propulsion spacecraft for unmanned interplanetary and geocentric missions are summarized. Critical technologies associated with the development of nuclear electric propulsion (NEP) are assessed. Outer planet and comet rendezvous mission analysis, NEP stage design for geocentric and interplanetary missions, NEP system development cost and unit costs, and technology requirements for NEP stage development are studied. The NEP stage design provides both inherent reliability and high payload mass capability. The NEP stage and payload integration was found to be compatible with the space shuttle.

  16. Handbook of nuclear engineering: vol 1: nuclear engineering fundamentals; vol 2: reactor design; vol 3: reactor analysis; vol 4: reactors of waste disposal and safeguards

    CERN Document Server

    2013-01-01

    The Handbook of Nuclear Engineering is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all academic levels, this five volume set provides the latest findings in nuclear data and experimental techniques, reactor physics, kinetics, dynamics and control. Readers will also find a detailed description of data assimilation, model validation and calibration, sensitivity and uncertainty analysis, fuel management and cycles, nuclear reactor types and radiation shielding. A discussion of radioactive waste disposal, safeguards and non-proliferation, and fuel processing with partitioning and transmutation is also included. As nuclear technology becomes an important resource of non-polluting sustainable energy in the future, The Handbook of Nuclear Engineering is an excellent reference for practicing engineers, researchers and professionals.

  17. Educational Innovation in the Design of an Online Nuclear Engineering Curriculum

    Science.gov (United States)

    Hall, Simin; Jones, Brett D.; Amelink, Catherine; Hu, Deyu

    2013-01-01

    The purpose of this paper is to describe the development and implementation phases of online graduate nuclear engineering courses that are part of the Graduate Nuclear Engineering Certificate program at Virginia Tech. Virginia Tech restarted its nuclear engineering program in the Fall of 2007 with 60 students, and by 2009, the enrollment had grown…

  18. Structured system engineering methodologies used to develop a nuclear thermal propulsion engine

    Science.gov (United States)

    Corban, R.; Wagner, R.

    1993-01-01

    To facilitate the development of a space nuclear thermal propulsion engine for manned flights to Mars, requirements must be established early in the technology development cycle. The long lead times for the acquisition of the engine system and nuclear test facilities demands that the engine system size, performance and safety goals be defined at the earliest possible time. These systems are highly complex and require a large multidisciplinary systems engineering team to develop and track requirements, and to ensure that the as-built system reflects the intent of the mission. A methodology has been devised which uses sophisticated computer tools to effectively develop and interpret functional requirements, and furnish these to the specification level for implementation.

  19. NATO Advanced Study Institute on New Aspects of Nuclear Dynamics

    CERN Document Server

    Huberts, P

    1989-01-01

    The 1988 Summer School on New Aspects of Nuclear Dynamics took place in the style that by now has become a tradition: a series of lectures by well known scientists on modem topics of nuclear physics, where special emphasis is placed on the didactic aspects of the lectures. In the past few years, we have witnessed a rapid evolution of the field of nuclear physics towards novel directions of research. This development is accompanied by the construction of some of the largest experimental facilities ever built for nuclear research. The subjects covered by the Summer School focussed on two main issues currently under active investigation and which will be pursued with the new facilities: the transition from nucleonic to quark degrees of freedom in the decription of nuclear reactions, and the behavior of nuclear matter as one approaches extreme densities and temperatures. These topics in many respects go beyond traditional nuclear physics and the speakers therefore also included high energy physicists. From the re...

  20. 75 FR 65249 - Anthony R. Pietrangelo on Behalf of the Nuclear Energy Institute; Receipt of Petition for Rulemaking

    Science.gov (United States)

    2010-10-22

    ...; ] NUCLEAR REGULATORY COMMISSION 10 CFR Part 26 Anthony R. Pietrangelo on Behalf of the Nuclear Energy Institute; Receipt of Petition for Rulemaking AGENCY: Nuclear Regulatory Commission. ACTION: Petition for... the NRC by Anthony R. Pietrangelo on behalf of the Nuclear Energy Institute (NEI). The petition was...

  1. Nuclear magnetic resonance in environmental engineering: principles and applications.

    Science.gov (United States)

    Lens, P N; Hemminga, M A

    1998-01-01

    This paper gives an introduction to nuclear magnetic resonance spectroscopy (NMR) and magnetic resonance imaging (MRI) in relation to applications in the field of environmental science and engineering. The underlying principles of high resolution solution and solid state NMR, relaxation time measurements and imaging are presented. Then, the use of NMR is illustrated and reviewed in studies of biodegradation and biotransformation of soluble and solid organic matter, removal of nutrients and xenobiotics, fate of heavy metal ions, and transport processes in bioreactor systems.

  2. Human factors engineering plan for reviewing nuclear plant modernization programs

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

  3. Institute for Nuclear Theory annual report No. 4, 1 March 1993--28 February 1994

    Energy Technology Data Exchange (ETDEWEB)

    Haxton, W.; Bertsch, G.; Henley, E.M.

    1994-06-01

    The Institute for Nuclear Theory was created as a national center by the Department of Energy. It began operations March 1, 1990. This annual report summarizes the INT`s activities during its fourth year of operations.

  4. XV and XVI SERC Main Schools in Theoretical High Energy Physics held at the Saha Institute of Nuclear Physics and Harish-Chandra Research Institute

    CERN Document Server

    2005-01-01

    Current research in High Energy Physics focuses on a number of enigmatic issues that go beyond the very successful Standard Model of particle physics. Among these are the problem of neutrino mass, the (as yet) unobserved Higgs particle, the quark-gluon plasma, quantum aspects of gravity, and the so--called hierarchy problem. Satisfactory resolution of these important questions will take much research effort in both theory and experiment. The Science & Engineering Research Council, Department of Science & Technology has sponsored a series of SERC Schools in Theoretical High Energy Physics over the past several years, to provide instruction and training to graduate students working for research degrees. This book is an outcome of the schools held at the Saha Institute of Nuclear Physics, Kolkata in 2000, and at the Harish-Chandra Research Institute, Allahabad in 2001. Based on lectures by active researchers in the field---Rajiv Gavai, Debashis Ghoshal, Dileep Jatkar, Anjan Joshipura, Biswarup Mukhopadhy...

  5. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Klinkenberg, M.; Neumeier, S.; Bosbach, D. (eds.)

    2011-07-01

    Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

  6. Engineering thinking in emergency situations: A new nuclear safety concept.

    Science.gov (United States)

    Guarnieri, Franck; Travadel, Sébastien

    2014-11-01

    The lessons learned from the Fukushima Daiichi accident have focused on preventive measures designed to protect nuclear reactors, and crisis management plans. Although there is still no end in sight to the accident that occurred on March 11, 2011, how engineers have handled the aftermath offers new insight into the capacity of organizations to adapt in situations that far exceed the scope of safety standards based on probabilistic risk assessment and on the comprehensive identification of disaster scenarios. Ongoing crises in which conventional resources are lacking, but societal expectations are high, call for "engineering thinking in emergency situations." This is a new concept that emphasizes adaptability and resilience within organizations-such as the ability to create temporary new organizational structures; to quickly switch from a normal state to an innovative mode; and to integrate a social dimension into engineering activities. In the future, nuclear safety oversight authorities should assess the ability of plant operators to create and implement effective engineering strategies on the fly, and should require that operators demonstrate the capability for resilience in the aftermath of an accident.

  7. Nuclear Engine System Simulation (NESS). Volume 1: Program user's guide

    Science.gov (United States)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-03-01

    A Nuclear Thermal Propulsion (NTP) engine system design analysis tool is required to support current and future Space Exploration Initiative (SEI) propulsion and vehicle design studies. Currently available NTP engine design models are those developed during the NERVA program in the 1960's and early 1970's and are highly unique to that design or are modifications of current liquid propulsion system design models. To date, NTP engine-based liquid design models lack integrated design of key NTP engine design features in the areas of reactor, shielding, multi-propellant capability, and multi-redundant pump feed fuel systems. Additionally, since the SEI effort is in the initial development stage, a robust, verified NTP analysis design tool could be of great use to the community. This effort developed an NTP engine system design analysis program (tool), known as the Nuclear Engine System Simulation (NESS) program, to support ongoing and future engine system and stage design study efforts. In this effort, Science Applications International Corporation's (SAIC) NTP version of the Expanded Liquid Engine Simulation (ELES) program was modified extensively to include Westinghouse Electric Corporation's near-term solid-core reactor design model. The ELES program has extensive capability to conduct preliminary system design analysis of liquid rocket systems and vehicles. The program is modular in nature and is versatile in terms of modeling state-of-the-art component and system options as discussed. The Westinghouse reactor design model, which was integrated in the NESS program, is based on the near-term solid-core ENABLER NTP reactor design concept. This program is now capable of accurately modeling (characterizing) a complete near-term solid-core NTP engine system in great detail, for a number of design options, in an efficient manner. The following discussion summarizes the overall analysis methodology, key assumptions, and capabilities associated with the NESS presents an

  8. Nuclear Engine System Simulation (NESS). Volume 1: Program user's guide

    Science.gov (United States)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-01-01

    A Nuclear Thermal Propulsion (NTP) engine system design analysis tool is required to support current and future Space Exploration Initiative (SEI) propulsion and vehicle design studies. Currently available NTP engine design models are those developed during the NERVA program in the 1960's and early 1970's and are highly unique to that design or are modifications of current liquid propulsion system design models. To date, NTP engine-based liquid design models lack integrated design of key NTP engine design features in the areas of reactor, shielding, multi-propellant capability, and multi-redundant pump feed fuel systems. Additionally, since the SEI effort is in the initial development stage, a robust, verified NTP analysis design tool could be of great use to the community. This effort developed an NTP engine system design analysis program (tool), known as the Nuclear Engine System Simulation (NESS) program, to support ongoing and future engine system and stage design study efforts. In this effort, Science Applications International Corporation's (SAIC) NTP version of the Expanded Liquid Engine Simulation (ELES) program was modified extensively to include Westinghouse Electric Corporation's near-term solid-core reactor design model. The ELES program has extensive capability to conduct preliminary system design analysis of liquid rocket systems and vehicles. The program is modular in nature and is versatile in terms of modeling state-of-the-art component and system options as discussed. The Westinghouse reactor design model, which was integrated in the NESS program, is based on the near-term solid-core ENABLER NTP reactor design concept. This program is now capable of accurately modeling (characterizing) a complete near-term solid-core NTP engine system in great detail, for a number of design options, in an efficient manner. The following discussion summarizes the overall analysis methodology, key assumptions, and capabilities associated with the NESS presents an

  9. Hyperthermal Environments Simulator for Nuclear Rocket Engine Development

    Science.gov (United States)

    Litchford, R. J.; Foote, J. P.; Clifton, W. B.; Hickman, R. R.; Wang, T.-S.; Dobson, C. C.

    An arc-heater driven hyperthermal convective environments simulator was recently developed and commissioned for long duration hot hydrogen exposure of nuclear thermal rocket materials. This newly established non-nuclear testing capability uses a high-power, multi-gas, wall-stabilised constricted arc-heater to produce high-temperature pressurised hydrogen flows representative of nuclear reactor core environments, excepting radiation effects, and is intended to serve as a low-cost facility for supporting non-nuclear developmental testing of high-temperature fissile fuels and structural materials. The resulting reactor environments simulator represents a valuable addition to the available inventory of non-nuclear test facilities and is uniquely capable of investigating and characterising candidate fuel/structural materials, improving associated processing/ fabrication techniques, and simulating reactor thermal hydraulics. This paper summarizes facility design and engineering development efforts and reports baseline operational characteristics as determined from a series of performance mapping and long duration capability demonstration tests. Potential follow-on developmental strategies are also suggested in view of the technical and policy challenges ahead.

  10. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Szeflinski, Z.; Kirejczyk, M.; Popkiewicz, M. [eds.

    1998-08-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Institute of Experimental Physics (Warsaw University) in year 1997 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contain the lists of personnel, seminars held at the Nuclear Physics Division and published papers. A summary of the (NPD) activities are briefly presented in ``Preface`` written by NDP director prof. K. Siwek-Wilczynska

  11. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University Annual Report 1996

    Energy Technology Data Exchange (ETDEWEB)

    Szeflinski, Z.; Popkiewicz, M. [eds.

    1997-12-31

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Institute of Experimental Physics (Warsaw University) in year 1996 are described. The report is divided into three parts: Reaction mechanisms and nuclear structure; Experimental methods and instrumentation and the third part contains the list of personnel, seminars held at the Nuclear Physics Division and published papers. A summary of the (NPD) activities are briefly presented in ``Preface`` by NPD director prof. Ch. Droste.

  12. Physics Competence Assessment in Engineering Higher Education Institution

    Directory of Open Access Journals (Sweden)

    A. F. An

    2015-01-01

    Full Text Available In designing the undergraduate programmes, a development of objectified procedures to assess students and graduates’ level of skills and learning outcomes aimed at achieving the ultimate goals of training is an important task for Higher Education Institutions (HEI.The purpose of this work is to develop a description of the physics course objectives differentiated according to levels of learning achievements for engineering HEI, as well as the assessment procedures and diagnostic means associated with this description to specify and define the degree of their achievement.The taxonomy of levels to master learning content is proposed and tested. Its aim is to assess rapidly a degree of achieved objectives i.e. meeting requirements for student and graduate’s competences in physics. Classification is given according to which the reproductive activity is a manifestation of the levels of recognition, reproduction and reproductive use of knowledge while the productive activity is an ability to use previously learned information, methods of action for the new scenarios, situations, conditions. The paper presents content of the main features of learning the study materials in physics at each taxonomic level. It offers a developed package of assessment materials based on traditional (tests, training tasks and competence-oriented control methods (professionally oriented and case studies, integrative assignments. The paper proves that when designing the diagnostic means it is expedient to take into consideration the analysis results of the expert assessments that the physics course curricular elements are of significance for fundamental and ideological studies and successful learning of the module of professional disciplines. It also shows that there is a need to use the content of typical tasks in disciplines of professional cycle of the undergraduate programme.The proposed approaches and results can serve as a basis for teaching improvement in physics

  13. Toward ethical norms and institutions for climate engineering research

    Science.gov (United States)

    Morrow, David R.; Kopp, Robert E.; Oppenheimer, Michael

    2009-10-01

    Climate engineering (CE), the intentional modification of the climate in order to reduce the effects of increasing greenhouse gas concentrations, is sometimes touted as a potential response to climate change. Increasing interest in the topic has led to proposals for empirical tests of hypothesized CE techniques, which raise serious ethical concerns. We propose three ethical guidelines for CE researchers, derived from the ethics literature on research with human and animal subjects, applicable in the event that CE research progresses beyond computer modeling. The Principle of Respect requires that the scientific community secure the global public's consent, voiced through their governmental representatives, before beginning any empirical research. The Principle of Beneficence and Justice requires that researchers strive for a favorable risk-benefit ratio and a fair distribution of risks and anticipated benefits, all while protecting the basic rights of affected individuals. Finally, the Minimization Principle requires that researchers minimize the extent and intensity of each experiment by ensuring that no experiments last longer, cover a greater geographical extent, or have a greater impact on the climate, ecosystem, or human welfare than is necessary to test the specific hypotheses in question. Field experiments that might affect humans or ecosystems in significant ways should not proceed until a full discussion of the ethics of CE research occurs and appropriate institutions for regulating such experiments are established.

  14. Toward ethical norms and institutions for climate engineering research

    Energy Technology Data Exchange (ETDEWEB)

    Morrow, David R [Department of Philosophy, Hunter College, City University of New York, 695 Park Avenue, New York, NY 10065 (United States); Kopp, Robert E; Oppenheimer, Michael, E-mail: morrow@uchicago.ed [Woodrow Wilson School of Public and International Affairs and Department of Geosciences, Princeton University, Princeton, NJ 08544 (United States)

    2009-10-15

    Climate engineering (CE), the intentional modification of the climate in order to reduce the effects of increasing greenhouse gas concentrations, is sometimes touted as a potential response to climate change. Increasing interest in the topic has led to proposals for empirical tests of hypothesized CE techniques, which raise serious ethical concerns. We propose three ethical guidelines for CE researchers, derived from the ethics literature on research with human and animal subjects, applicable in the event that CE research progresses beyond computer modeling. The Principle of Respect requires that the scientific community secure the global public's consent, voiced through their governmental representatives, before beginning any empirical research. The Principle of Beneficence and Justice requires that researchers strive for a favorable risk-benefit ratio and a fair distribution of risks and anticipated benefits, all while protecting the basic rights of affected individuals. Finally, the Minimization Principle requires that researchers minimize the extent and intensity of each experiment by ensuring that no experiments last longer, cover a greater geographical extent, or have a greater impact on the climate, ecosystem, or human welfare than is necessary to test the specific hypotheses in question. Field experiments that might affect humans or ecosystems in significant ways should not proceed until a full discussion of the ethics of CE research occurs and appropriate institutions for regulating such experiments are established.

  15. Russian Nuclear Rocket Engine Design for Mars Exploration

    Institute of Scientific and Technical Information of China (English)

    Vadim Zakirov; Vladimir Pavshook

    2007-01-01

    This paper is to promote investigation into the nuclear rocket engine (NRE) propulsion option that is considered as a key technology for manned Mars exploration. Russian NRE developed since the 1950 s in the former Soviet Union to a full-scale prototype by the 1990 s is viewed as advantageous and the most suitable starting point concept for manned Mars mission application study. The main features of Russian heterogeneous core NRE design are described and the most valuable experimental performance results are summarized. These results have demonstrated the significant specific impulse performance advantage of the NRE over conventional liquid rocket engine (LRE) propulsion technologies. Based on past experience,the recent developments in the field of high-temperature nuclear fuels, and the latest conceptual studies, the developed NRE concept is suggested to be upgraded to the nuclear power and propulsion system (NPPS),more suitable for future manned Mars missions. Although the NRE still needs development for space application, the problems are solvable with additional effort and funding.

  16. Best Practices for Quality Improvement--Lessons from Top Ranked Engineering Institutions

    Science.gov (United States)

    Rao, Potti Srinivasa; Viswanadhan, K. G.; Raghunandana, K.

    2015-01-01

    Maximum number of privately funded engineering institutions have been established in India in the last two decades to meet the growing needs of technical manpower required by the Engineering and IT companies as well as aspiring students after completion of the Pre-University Program. However, a large number of institutions have not been able to…

  17. Paul Scherrer Institut annual report 1995. Annex IV: PSI nuclear energy and safety

    Energy Technology Data Exchange (ETDEWEB)

    Birchley, J.; Roesel, R.; Doesburg, R. van [eds.] [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-09-01

    Nuclear energy research in Switzerland is concentrated at PSI`s Department F4. It is explicitly mentioned in the Institute`s official charter and commands about one fifth of the Institute`s federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI`s activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs.

  18. Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

    Energy Technology Data Exchange (ETDEWEB)

    Hamid, Nasri A., E-mail: Nasri@uniten.edu.my; Mohamed, Abdul Aziz; Yusoff, Mohd. Zamri [Nuclear Energy Center, College of Engineering, Universiti Tenaga Nasional, Jalan IKRAM-UNITEN, 43000 Kajang, Selangor (Malaysia)

    2015-04-29

    Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO{sub 2} emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper

  19. Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

    Science.gov (United States)

    Hamid, Nasri A.; Mohamed, Abdul Aziz; Yusoff, Mohd. Zamri

    2015-04-01

    Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO2 emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper describes

  20. Engineering for new-built nuclear power plant projects; Ingenieria para proyectos de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A.

    2012-11-01

    This article reviews the opportunities existing in the market (electrical utilities and reactor vendors) for an engineering company with the profile of Empresarios Agrupados (EA) in new-built nuclear power plant projects. To do this, reference is made to some representative examples of projects in which EA has been participating recently. the article concludes sharing with the reader some lessons learned from this participation. (Author)

  1. Understanding Latino Students' Sense of Belonging in Engineering: The Impact of Institutional Agents at one Predominantly White Institution

    Science.gov (United States)

    Alva, Desiree D.

    This study explores the ways in which institutional agents (i.e., faculty, staff, and advisors) influence Latino engineering students' sense of belonging at a predominantly White institution (PWI). Research (e.g., Museus, Palmer, Davis, & Maramba, 2011) has shown the struggles that Latino students face in pursuing higher education (e.g., culture shock, marginalization, financial barriers), as well as the obstacles that some of them face related to their undocumented status (e.g., out-of-state tuition, ineligibility for federal student aid) (Gildersleeve & Ranero, 2010; Gildersleeve, Rumann, & Mondragon, 2010). However, there is little to no empirical research that describes how successful Latino engineering students connect socially in order to feel a sense of belonging in competitive majors, such as engineering, at a PWI. To explore this phenomenon, this study addressed the following research questions: (a) How do Latino students describe their social connections with institutional agents? (b) According to Latino students, how have those social connections influenced their sense of belonging in engineering at a PWI? (c) How are the social connections and their influence on sense of belonging in engineering alike or different for Latinos who identify as undocumented? Using a qualitative case study design (i.e., on-site observations, interviews, and a constant comparative method), the social connections that seven Latino students made at one Midwestern university were explored in an effort to understand the influence that institutional agents had on their sense of belonging in engineering at a PWI. The findings revealed that while Latinos felt marginalized, they eventually felt a sense of belonging in engineering through developing their engineering identity with the support of institutional agents and peers. Further implications for theory, methodology, policy, and practice were also explored.

  2. Ground test facilities for evaluating nuclear thermal propulsion engines and fuel elements

    Science.gov (United States)

    Allen, G. C.; Beck, D. F.; Harmon, C. D.; Shipers, L. R.

    Interagency panels evaluating nuclear thermal propulsion development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and design issues of a proposed ground test complex for evaluating nuclear thermal propulsion engines and fuel elements being developed for the Space Nuclear Thermal Propulsion (SNTP) program.

  3. Implanting a Discipline: The Academic Trajectory of Nuclear Engineering in the USA and UK

    Science.gov (United States)

    Johnston, Sean F.

    2009-01-01

    The nuclear engineer emerged as a new form of recognised technical professional between 1940 and the early 1960s as nuclear fission, the chain reaction and their applications were explored. The institutionalization of nuclear engineering--channelled into new national laboratories and corporate design offices during the decade after the war, and…

  4. 10 CFR Appendix S to Part 50 - Earthquake Engineering Criteria for Nuclear Power Plants

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Earthquake Engineering Criteria for Nuclear Power Plants S... FACILITIES Pt. 50, App. S Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power Plants..., as specified in § 50.54(ff), nuclear power plants that have implemented the earthquake...

  5. Legal, institutional, and political issues in transportation of nuclear materials at the back end of the LWR nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Lippek, H.E.; Schuller, C.R.

    1979-03-01

    A study was conducted to identify major legal and institutional problems and issues in the transportation of spent fuel and associated processing wastes at the back end of the LWR nuclear fuel cycle. (Most of the discussion centers on the transportation of spent fuel, since this activity will involve virtually all of the legal and institutional problems likely to be encountered in moving waste materials, as well.) Actions or approaches that might be pursued to resolve the problems identified in the analysis are suggested. Two scenarios for the industrial-scale transportation of spent fuel and radioactive wastes, taken together, high-light most of the major problems and issues of a legal and institutional nature that are likely to arise: (1) utilizing the Allied General Nuclear Services (AGNS) facility at Barnwell, SC, as a temporary storage facility for spent fuel; and (2) utilizing AGNS for full-scale commercial reprocessing of spent LWR fuel.

  6. The efficiency of the use of penetration nuclear logging in hydrogeology and engineering geology

    Energy Technology Data Exchange (ETDEWEB)

    Ferronsky, V.I. (AN SSSR, Moscow (USSR). Water Problems Inst.); Griaznov, T.A.; Selivanov, L.V. (All-Union Research Inst. for Hydrogeology and Engineering Geology, Moscow (USSR))

    1992-03-01

    The latest developments in equipment and techniques for nuclear and combined non-nuclear logging in friable unconsolidated deposits, including marine bottom sediments are described. The effectiveness of these techniques in hydrogeological and engineering geological investigations is discussed. (Author).

  7. Development of Nuclear Engineering Educational Program at Ibaraki University with Regional Collaboration

    Science.gov (United States)

    Matsumura, Kunihito; Kaminaga, Fumito; Kanto, Yasuhiro; Tanaka, Nobuatsu; Saigusa, Mikio; Kikuchi, Kenji; Kurumada, Akira

    The College of Engineering, Ibaraki University is located at the Hitachi city, in the north part of Ibaraki prefecture. Hitachi and Tokai areas are well known as concentration of advanced technology center of nuclear power research organizations. By considering these regional advantages, we developed a new nuclear engineering educational program for students in the Collage of Engineering and The Graduate School of Science and Engineering of Ibaraki University. The program is consisted of the fundamental lectures of nuclear engineering and nuclear engineering experiments. In addition, several observation learning programs by visiting cooperative organizations are also included in the curriculum. In this paper, we report about the progress of the new educational program for nuclear engineering in Ibaraki University.

  8. A Review on the Regulatory Strategy of Human Factors Engineering Consideration in Pakistan Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sohail, Sabir [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Choi, Seong Nam [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    In this paper, the legal and regulatory infrastructure available in Pakistan for HFE requirements is assessed, and the methodology for strengthening of legal infrastructure is presented. The regulatory strategy on evaluation of HFE consideration should provide reviewers with guidance on review process. Therefore, the suggested methodology is based on preparation of guidance documents such as checklist, working procedures, S and Gs etc.; incorporation of PRM elements in regulatory system; and finally the development of PRM implementation criteria. Altogether, the scheme provide the enhancement in regulatory infrastructure and also the effective and efficient review process. The Three Mile Island (TMI) accident brought the general consensus among the nuclear community on the integration of human factors engineering (HFE) principles in all phases of nuclear power. This notion has further strengthened after the recent Fukushima nuclear accident. Much effort has been put over to incorporate the lesson learned and continuous technical evolution on HFE to device different standards. The total of 174 ergonomics standards are alone identified by Dul et al. (2004) published by International Organization for Standardization (ISO) and the European Committee for Standardization (CEN) and number of standards and HFE guidelines (S and Gs) are also published by organizations like Institute for Electrical and Electronics Engineering (IEEE), International Electrotechnical Commission (IEC), International Atomic Energy Agency (IAEA), United States Nuclear Regulatory Commission (USNRC), etc. The ambition of effective review on HFE integration in nuclear facility might be accomplished through the development of methodology for systematic implementation of S and Gs. Such kind of methodology would also be beneficial for strengthening the regulatory framework and practices for countries new in the nuclear arena and with small scale nuclear program. The objective of paper is to review the

  9. Paul Scherrer Institut Scientific Report 2002. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, B.; Gschwend, B. (eds.)

    2003-03-01

    contributions have been accepted by the FIT Board. The planning document is currently in circulation for comment. PSI has updated its 'Guiding Principles' to include its own research capabilities, in particular in regard to sustainable energy technologies. At the end of an intensive 'bottom-up approach', an R+D planning document for the year 2003 has been issued for the first time by NES; this exercise should be formalised in a more compact form in the future. Backfitting of the Hot Lab has been completed in 4 years, at a cost of 14 MCHF (compared with the initial estimates of 3 years and 9.8 MCHF); the NPP operators have agreed to contribute to the Hot Lab infrastructure costs to the extent of 3 MCHF per annum. With regard to education and training, in view of the necessity to maintain a continuous education programme in nuclear technology at university level, the Swiss utilities have conditionally agreed, following the retirement of Prof. Yadigaroglu, to fund an ETHZ Chair in Nuclear (Systems) Engineering. The appointee will become a central part of the new Master of Nuclear Engineering programme, to be offered by ETHZ and EPFL, and will be given the opportunity by NES to perform large-scale research at PSI. The new Masters programme will become an integral part of the emerging European Network on Nuclear Energy (ENEN). At the technical teaching level, PSI's own Technical School for reactor operators has, after some years of reduced participation, again registered an increase in the number of students: in 2002, courses had to be offered on an annual basis, instead of every 2 years, in response to the increased demand. A publication list for 2002 is also provided. (author)

  10. Scientific and technological activity in the National Institute of Nuclear Research; Actividad cientifica y tecnologica en el Instituto Nacional de Investigaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Escobar A, L.; Monroy G, F.; Morales R, P.; Romero H, S. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)

    2008-07-01

    The present book was published on the occasion of the 50 years of the existence of the Institute, from its creation in 1956 like National Commission of Nuclear Energy to 1979 that arises like National Institute of Nuclear Research. The objective of this publication is the one to leave a writing testimony of all the activities that are realized in the National Institute of Nuclear Research and an accessible language within the diverse subjects boarded. Referring subjects to the activities of nuclear physics, radiochemistry, research and development of materials, dosimetry, plasma physics, production of radiopharmaceuticals, tissue sterilization by radiation, food irradiation and other included. (Author)

  11. Nuclear engineering vocabulary; Vocabulaire de l'ingenierie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Dumont, X. [FRAMATOME, 92 - Paris-La-Defense (France); Andrieux, C. [CEA/Saclay, Direction des Technologies de l' Information (DTI), 91 - Gif-sur-Yvette (France)] [and others

    2000-06-01

    The aim of this book is to bring together the French technical terms and expressions as defined by the specialized commission of terminology and neology of nuclear engineering (CSTNIN). For each term or expression is given: a possible abbreviation, its domain of use, its definition, sometimes a synonymous, eventually some notes, the related terms, the English equivalent, and its status at the date of publication of the book. This status comprises several steps: the eventual publication in the Journal Officiel de la Republique Francaise (official journal of the French republic, with its date), the related reference list and working group, the position of the enable authorities (CSTNIN, COGETERM, French Academy, minister), the last date of review, and some possible additional details. (J.S.)

  12. Producing hydrogen from water for nuclear hydrogen power engineering

    Energy Technology Data Exchange (ETDEWEB)

    Gorbachev, A.K.; Andryushchenko, F.K.; Bochin, V.P.; Ishchenko, L.I.; Nechiporenko, N.N.; Nikiforov, V.K.; Soldat, Ye.F.; Zadorozhnyy, P.S.; Zhuk, G.G.

    1980-01-01

    The prospects of production of H/sub 2/ for nuclear-hydrogen power engineering using the sulphuric acid cycle with depolarization of the anode by sulphur gas are demonstrated. The kinetics of oxidation of sulphur gas on porous activated graphite anodes depending on the concentration of H/sub 2/SO/sub 4/ and the presence of a homogeneous catalyst in the solution is examined. The results for kinetics of separation of H/sub 2/ in 5 M solution H/sub 2/SO/sub 4/ on titanium nitride, alloys E194, EP496, EP567, E159 and an alloy of titanium and miludimum 4201 are cited. Electroysis of aqueous solutions of H/sub 2/SO/sub 4/ with depolarization of the anode process can be carried out on technically accessible materials. The voltage on the electrolyzer is approximately 1 volt when carrying out the process on recommended materials.

  13. Research in progress at the Institute for Computer Applications in Science and Engineering

    Science.gov (United States)

    1987-01-01

    This report summarizes research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics, numerical analysis, and computer science during the period April 1, 1987 through October 1, 1987.

  14. X-ray fluorescence activities at Saha Institute of Nuclear Physics, India

    Indian Academy of Sciences (India)

    Manoranjan Sarkar

    2011-02-01

    This paper covers different aspects related to X-ray fluorescence activities at Saha Institute of Nuclear Physics, Kolkata, India. In its first part, experiments on basic physical problems are illustrated and in the second part, some applications related to X-ray fluorescence are discussed.

  15. A Hydrogen Containment Process For Nuclear Thermal Engine Ground Testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric; Canabal, Francisco

    2016-01-01

    A hydrogen containment process was proposed for ground testing of a nuclear thermal engine. The hydrogen exhaust from the engine is contained in two unit operations: an oxygen-rich burner and a tubular heat exchanger. The burner burns off the majority of the hydrogen, and the remaining hydrogen is removed in the tubular heat exchanger through the species recombination mechanism. A multi-dimensional, pressure-based multiphase computational fluid dynamics methodology was used to conceptually sizing the oxygen-rich burner, while a one-dimensional thermal analysis methodology was used to conceptually sizing the heat exchanger. Subsequently, a steady-state operation of the entire hydrogen containment process, from pressure vessel, through nozzle, diffuser, burner and heat exchanger, was simulated numerically, with the afore-mentioned computational fluid dynamics methodology. The computational results show that 99% of hydrogen reduction is achieved at the end of the burner, and the rest of the hydrogen is removed to a trivial level in the heat exchanger. The computed flammability at the exit of the heat exchanger is less than the lower flammability limit, confirming the hydrogen containment capability of the proposed process.

  16. A Curriculum Model: Engineering Design Graphics Course Updates Based on Industrial and Academic Institution Requirements

    Science.gov (United States)

    Meznarich, R. A.; Shava, R. C.; Lightner, S. L.

    2009-01-01

    Engineering design graphics courses taught in colleges or universities should provide and equip students preparing for employment with the basic occupational graphics skill competences required by engineering and technology disciplines. Academic institutions should introduce and include topics that cover the newer and more efficient graphics…

  17. A Curriculum Model: Engineering Design Graphics Course Updates Based on Industrial and Academic Institution Requirements

    Science.gov (United States)

    Meznarich, R. A.; Shava, R. C.; Lightner, S. L.

    2009-01-01

    Engineering design graphics courses taught in colleges or universities should provide and equip students preparing for employment with the basic occupational graphics skill competences required by engineering and technology disciplines. Academic institutions should introduce and include topics that cover the newer and more efficient graphics…

  18. Current state of nuclear fuel cycles in nuclear engineering and trends in their development according to the environmental safety requirements

    Science.gov (United States)

    Vislov, I. S.; Pischulin, V. P.; Kladiev, S. N.; Slobodyan, S. M.

    2016-08-01

    The state and trends in the development of nuclear fuel cycles in nuclear engineering, taking into account the ecological aspects of using nuclear power plants, are considered. An analysis of advantages and disadvantages of nuclear engineering, compared with thermal engineering based on organic fuel types, was carried out. Spent nuclear fuel (SNF) reprocessing is an important task in the nuclear industry, since fuel unloaded from modern reactors of any type contains a large amount of radioactive elements that are harmful to the environment. On the other hand, the newly generated isotopes of uranium and plutonium should be reused to fabricate new nuclear fuel. The spent nuclear fuel also includes other types of fission products. Conditions for SNF handling are determined by ecological and economic factors. When choosing a certain handling method, one should assess these factors at all stages of its implementation. There are two main methods of SNF handling: open nuclear fuel cycle, with spent nuclear fuel assemblies (NFAs) that are held in storage facilities with their consequent disposal, and closed nuclear fuel cycle, with separation of uranium and plutonium, their purification from fission products, and use for producing new fuel batches. The development of effective closed fuel cycles using mixed uranium-plutonium fuel can provide a successful development of the nuclear industry only under the conditions of implementation of novel effective technological treatment processes that meet strict requirements of environmental safety and reliability of process equipment being applied. The diversity of technological processes is determined by different types of NFA devices and construction materials being used, as well as by the composition that depends on nuclear fuel components and operational conditions for assemblies in the nuclear power reactor. This work provides an overview of technological processes of SNF treatment and methods of handling of nuclear fuel

  19. THE INTEGRATION OF ENGINEERED AND INSTITUTIONAL CONTROLS: A CASE STUDY APPROACH WITH LESSONS LEARNED FROM PREVIOUSLY CLOSED SITES

    Energy Technology Data Exchange (ETDEWEB)

    Kevin M. Kostelnik; James H. Clarke; Jerry L. Harbour

    2005-02-01

    Environmental remediation efforts that are underway at hundreds of contaminated sites in the United States will not be able to remediate large portions of those sites to conditions that would permit unrestricted access. Rather, large volumes of waste materials, contaminated soils and cleanup residuals will have to be isolated either in place or in new, often on-site, disposal cells with long term monitoring, maintenance and institutional control needs. The challenge continues to be to provide engineering systems and controls that can ensure the protection of public health and the environment over very long time horizons (hundreds to perhaps thousands of years) with minimal intervention. Effective long term management of legacy hazardous and nuclear waste requires an integrated approach that addresses both the engineered containment and control system itself and the institutional controls and other responsibilities that are needed. Decisions concerning system design, monitoring and maintenance, and the institutional controls that will be employed are best done through a "risk-nformed, performance-based" approach. Such an approach should incorporate an analysis of potential "failure" modes and consequences for all important system features, together with lessons learned from experience with systems already in place. The authors will present the preliminary results of a case study approach that included several sites where contamination isolation systems including institutional controls have been implemented. The results are being used together with failure trees and logic diagrams that have been developed for both the engineered barriers and the institutional controls. The use of these analytical tools to evaluate the potential for different levels of failure and associated consequences will be discussed. Of special interest is the robustness of different approaches to providing long-term protection through redundancy and defense in depth.

  20. 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

  1. Reflections on the Fukushima Daiichi nuclear accident toward social-scientific literacy and engineering resilience

    CERN Document Server

    Carson, Cathryn; Jensen, Mikael; Juraku, Kohta; Nagasaki, Shinya; Tanaka, Satoru

    2015-01-01

    This book focuses on nuclear engineering education in the post-Fukushima era. It was edited by the organizers of the summer school held in August 2011 in University of California, Berkeley, as part of a collaborative program between the University of Tokyo and UC Berkeley. Motivated by the particular relevance and importance of social-scientific approaches to various crucial aspects of nuclear technology, special emphasis was placed on integrating nuclear science and engineering with social science. The book consists of the lectures given in 2011 summer school and additional chapters that cover developments in the past three years since the accident. It provides an arena for discussions to find and create a renewed platform for engineering practices, and thus nuclear engineering education, which are essential in the post-Fukushima era for nurturing nuclear engineers who need to be both technically competent and trusted in society.

  2. STEM Leader from the Roeper School: An Interview with Nuclear Engineer Clair J. Sullivan

    Science.gov (United States)

    Ambrose, Don

    2016-01-01

    Clair J. Sullivan is an assistant professor in the Department of Nuclear, Plasma and Radiological Engineering at the University of Illinois at Urbana-Champaign (UIUC). Her research interests include radiation detection and measurements; gamma-ray spectroscopy; automated isotope identification algorithms; nuclear forensics; nuclear security;…

  3. Educational Programs and Facilities in Nuclear Science and Engineering. Fifth Edition.

    Science.gov (United States)

    Oak Ridge Associated Universities, TN.

    This publication contains detailed descriptions of nuclear programs and facilities of 182 four-year educational institutions. Instead of chapters, the contents are presented in five tables. Table I presents the degrees, graduate appointments, special facilities and programs of the institutions. The institutions are arranged in alphabetical order…

  4. Management of communication area in a nuclear research and development institute

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Wellington Antonio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil). Servico de Negocios e Comunicacao]. E-mail: soaresw@cdtn.br

    2005-07-01

    Nuclear energy to the general public is always associated to the production of nuclear weapons or to nuclear and radiological accidents. Public communication actions done by the National Commission of Nuclear Energy (CNEN) have been contributing to make known the social and peaceful applications of nuclear energy, reaching different kinds of public. Interaction programs with society and in particular with students have also been carried out by the Nuclear Technology Development Center (CDTN/CNEN). Measuring public communication results can help to show that financial resource in this area should be considered as investment and not as expenses. One needs therefore a well-established managing system. Fundamentals of the National Quality Award Criteria for Excellence - PNQ are being applied in the area in charge of business and public communication at CDTN. Systematic registration of results started in 2000 and a gradual increase in the number of means of communication for the internal public has occurred in the last five years. The Center has now a bimonthly newspaper edition. Communication indicators have shown an increasing number of students received in the Center or provided with lectures in schools. Results of satisfaction inquiry from these students show good results. The implemented management system has allowed informing the nature and quantity of people reached by the information on nuclear applications and the improvement in the institutional image. (author)

  5. Production of gel {sup 99m}Tc generators for Nuclear Medicine at the Nuclear Power Institute of China, Chengdu

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, R.E

    1996-07-01

    The development and testing of the gel-type {sup 99m}Tc generator technology has been going on for several years at the Nuclear Power Institute of China. This generator type has already been licensed by the Ministry of Health. With the co-operation of the IAEA, under Model Project CPR/2/006,it is intended to upgrade and optimise the existing facility for large scale production and continue to improve the generator performance in terms of quality and reliability of its use in nuclear medicine. The expert mission objective was to carry out final laboratory tests to assess the performance of the gel- type {sup 99m}Tc, locally produced, as well as to assess the suitability of the corresponding {sup 99m}Tc eluate for nuclear medicine studies. In particular, the expert tested the suitability of the {sup 99m}Tc for the labelling of sensitive biomolecules and its general performance in a nuclear medicine service

  6. [Survey questionnaire of pediatric nuclear medicine examinations in 14 Japanese institutes].

    Science.gov (United States)

    Karasawa, Kensuke; Kamiyama, Hiroshi; Hashimoto, Teisuke; Koizumi, Kiyoshi

    2013-05-01

    Under the auspices of the Japanese Society of Pediatric Nuclear Medicine, an annual aggregate from a 5-year period, 2007 to 2011, of a survey questionnaire of pediatric nuclear medicine examinations performed at 14 institutes in the Kanto region was conducted. The subjects were pediatric patients 15 years old or younger. The survey questions included the determination method for administered dose of radiopharmaceuticals, the items examined and number of examinations. Of 14 institutes, 11 determined administered doses using the formula: adult dose X (age +1) / (age+7), while the remaining 3 used the adult dose as the maximum dose and used a conversion formula based on age and physical condition. In 2011, in a total of 3,884 pediatric patients, renoscintigraphy accounted for 41.5%, brain 14.4%, pulmonary scintigraphy 12.9%, oncology 9.0%, hepatobiliary scintigraphy 6.3%, gastrointestinal scintigraphy 4.8%, musculoskeletal scintigraphy 4.3%, cardiology 2.5%, and other 4.9% of all nuclear medicine examinations. Pediatric nuclear medicine examinations in general hospitals accounted for only 3.4% of all examinations. A similar trend was observed in previous years. Since pediatric patients have a longer reproductive term and higher sensitivity to radiation exposure, pediatric nuclear medicine requires a strict selection of appropriate studies and administered dose. These results show the current practice and would warrant further consideration.

  7. Bibliography of Connecticut Advanced Nuclear Engineering Laboratory reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-01

    This report, published in two, volumes, is a bibliography of the reports published at the Connecticut Advanced Nuclear Engineering Laboratory (CANEL). The reports cover the period 1952 through 1965 and include the Aircraft Nuclear Propulsion program, the Advanced Liquid Metal Cooled Reactor program, the Advanced Reactor Materials program and the SNAP-50 program. The bibliography contains the report number, title, author, date published, and classification. In some cases where the writing of a report was a group effort, and in some reports containing compilations of certain types of data, the author column is not applicable. This is indicated by a {open_quotes}n.a.{close_quotes} in the author column. The following types of reports are included: PWAC`s, TIM`s, CNLM`s. FXM`s and miscellaneous reports. PWAC and TIM reports conform to the requirements of AEC Manual Chapter 3202-041 and 3202-042, respectively. Most of the technical information of interest generated by this project is documented in these reports, CNLM and FXM reports were written primarily for internal distribution. However, these reports contain enough information of technical interest to warrant their inclusion. All CNLM`s and those FXM`s considered to be of interest are included in this bibliography. The MPR`s (Monthly Progress Reports) are the most important of the miscellaneous categories of reports. The other miscellaneous categories relate primarily to equipment and reactor specifications. The Division of Technical Information Extension (DTIE) at Oak Ridge, Tennessee has been designated as the primary recipient of the reports in the CANEL library. When more than one copy of a report was available, the additional copies were delivered to the Lawrence Radiation Laboratory, Livermore, California.

  8. Bibliography of Connecticut Advanced Nuclear Engineering Laboratory reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-01

    This report, published in two volumes, is a bibliography of the reports published at the Connecticut Advanced Nuclear Engineering Laboratory (CANEL). The reports cover the period 1952 through 1965 and include the Aircraft Nuclear Propulsion program, the Advanced Liquid Metal Cooled Reactor program, the Advanced Reactor Materials program and the SNAP-50 program. The bibliography contains the report number, title, author, date published, and classification. In some cases where the writing of a report was a group effort, and in some reports containing compilations of certain types of data, the author column is not applicable. This is indicated by a {open_quotes}n.a.{close_quotes} in the author column. The following types of reports are included: PWAC`s, TIM`s, CNLM`s, FXM`s and miscellaneous reports. PWAC and TIM reports conform to the requirements of AEC Manual Chapter 3202-041 and 3202-042, respectively. Most of the technical information of interest generated by this project is documented in these reports. CNLM and FXM reports were written primarily for internal distribution. However, these reports contain enough information of technical interest to warrant their inclusion. All CNLM`s and those FXM`s considered to be of interest are included in this bibliography. The MPR`s (Monthly Progress Reports) are the most important of the miscellaneous categories of reports. The other miscellaneous categories relate primarily to equipment and reactor specifications. The Division of Technical Information Extension (DTIE) at Oak Ridge, Tennessee has been designated as the primary recipient of the reports in the CANEL library. When more than one copy of a report was available, the additional copies were delivered to the Lawrence Radiation Laboratory, Livermore, California.

  9. Nuclear Physics Division Institute of Experimental Physics Warsaw University annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Osuch, S. [ed.

    1995-12-31

    In the presented Annual Report the activities of the Nuclear Physics Division of the Institute of Experimental Physics of the Warsaw University in 1994 are described. The report consist of three sections: (i) Reaction Mechanism and Nuclear Structure (12 articles); (ii) Experimental Methods and Instrumentation (2 articles); (iii) Other Research (1 article). Additionally the list of seminars held at the NPD, personnel list and list of published papers is also given. In the first, leading article of the report written by head of NPD prof. Ch. Droste the general description of the Department activity is presented.

  10. Developing Technologies for Space Resource Utilization: Concept for a Planetary Engineering Research Institute

    Science.gov (United States)

    Blacic, J. D.; Dreesen, D.; Mockler, T.

    2000-01-01

    There are two principal factors that control the economics and ultimate utilization of space resources: 1) space transportation, and 2) space resource utilization technologies. Development of space transportation technology is driven by major government (military and civilian) programs and, to a lesser degree, private industry-funded research. Communication within the propulsion and spacecraft engineering community is aided by an effective independent professional organization, the American Institute of Aeronautics and Astronautics (AIAA). The many aerospace engineering programs in major university engineering schools sustain professional-level education in these fields. NASA does an excellent job of public education in space science and engineering at all levels. Planetary science, a precursor and supporting discipline for space resource utilization, has benefited from the establishment of the Lunar and Planetary Institute (LPI) which has served, since the early post-Apollo days, as a focus for both professional and educational development in the geosciences of the Moon and other planets. The closest thing the nonaerospace engineering disciplines have had to this kind of professional nexus is the sponsorship by the American Society of Civil Engineers of a series of space engineering conferences that have had a predominantly space resource orientation. However, many of us with long-standing interests in space resource development have felt that an LPI-like, independent institute was needed to focus and facilitate both research and education on the specific engineering disciplines needed to develop space resource utilization technologies on an on-going basis.

  11. Engineering and maintenance applied to safety-related valves in nuclear power plants; Ingenieria y mantenimiento aplicado a valvulas relacionadas con la seguridad en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Verdu, M. F.; Perez-Aranda, J.

    2014-04-01

    Nuclear Division in Iberdrola engineering and Construction has a team with extensive experience on engineering and services works related to valves. Also, this team is linked to UNESA as Technical support and Reference Center. Iberdrola engineering and construction experience in nuclear power plants valves, gives effective response to engineering and maintenance works that can be demanded in a nuclear power plant and it requires a high degree of qualification and knowledge both in Operation and Outages. (Author)

  12. The IRSN Institute of radiation protection and nuclear safety Cadarache Center; L'IRSN Institut de Radioprotection et de Surete Nucleaire Centre de Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The research programs of the IRSN in the Cadarache Center concern the nuclear safety (reactor safety, nuclear fuels behavior during accidents, fires in nuclear installations), the protection and the control of radioactive materials, the human and the environment protection. The programs are presented and discussed. This presentation includes also the regional impact of the Institute at Cadarache (economical impact, relations with the universities and international meetings). (A.L.B.)

  13. Parameter Study of the LIFE Engine Nuclear Design

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, K J; Meier, W R; Latkowski, J F; Abbott, R P

    2009-07-10

    LLNL is developing the nuclear fusion based Laser Inertial Fusion Energy (LIFE) power plant concept. The baseline design uses a depleted uranium (DU) fission fuel blanket with a flowing molten salt coolant (flibe) that also breeds the tritium needed to sustain the fusion energy source. Indirect drive targets, similar to those that will be demonstrated on the National Ignition Facility (NIF), are ignited at {approx}13 Hz providing a 500 MW fusion source. The DU is in the form of a uranium oxycarbide kernel in modified TRISO-like fuel particles distributed in a carbon matrix forming 2-cm-diameter pebbles. The thermal power is held at 2000 MW by continuously varying the 6Li enrichment in the coolants. There are many options to be considered in the engine design including target yield, U-to-C ratio in the fuel, fission blanket thickness, etc. Here we report results of design variations and compare them in terms of various figures of merit such as time to reach a desired burnup, full-power years of operation, time and maximum burnup at power ramp down and the overall balance of plant utilization.

  14. Master’s degree in Nuclear Engineering UPC-ENDESA. Creating synergy at industrial and academic levels

    Energy Technology Data Exchange (ETDEWEB)

    Batet, I.; Calviño, F.; Duch, M.A.; Dies, J.; León, P.; Fernández-Olano, P.

    2015-07-01

    The Master’s degree in Nuclear Engineering, born from the alignment of objectives of Academy and Industry, aims to prepare competent engineers to assume managerial positions within the Nuclear Industry. MNE is completely taught in English. Synergies are established at both industrial and academic levels. MNE syllabus has been designed (and is being continuously improved) with the help of industrial partners and the Spanish Regulatory Body (CSN). One half of the lectures are delivered by professionals external to the university. Besides ENDESA, other companies (ANAV, AREVA, ENRESA, ENSA, ENUSA, IDOM, Nuclenor, Tecnatom, Westinghouse) collaborate in the master. Lecturers from CSN and CIEMAT (the major Spanish research centre) participate in the Master as well. A large portion of the master contents is delivered as Project Based Learning, In general, active learning and team work activities are thoroughly used so as to help the students achieve the learning objectives and acquire a number of soft skills required by industry. MNE is embedded in EMINE, the European Master in Nuclear Energy (European Institute of Technology, KIC-InnoEnergy). As well, MNE is part of a double degree in the Barcelona Engineering School (ETSEIB) with the official Master in Industrial Engineering (MUEI). Having in the same classroom EMINE and MNE students creates a good working atmosphere, while allowing the future engineers work in a multicultural and international environment. The double degree MNE-MUEI allows students to acquire the MNE competencies and, at the same time, legal engineering attributions. It has been useful to attract good engineering students to the master. (Author)

  15. Study of a conceptual nuclear energy center at Green River, Utah: institutional and licensing issues

    Energy Technology Data Exchange (ETDEWEB)

    Heilman, C.B.; Herman, A.A. Jr.; Vito, D.J.

    1982-04-01

    This document constitutes a segment of a feasibility study investigating the ramification of construcing a nuclear energy center in an arid western region. In this phase of the study, the institutional and licensing issues impacting a NEC were analyzed. The most prominent issue facing such a concept is the ownership form of NEC. In addition, legislation and regulation also have a substantial impact regardless of the ownership format.

  16. Brief 72 Nuclear Engineering Enrollments and Degrees Survey, 2013 Data (2-14)

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-02-15

    The survey includes degrees granted between September 1, 2012 and August 31, 2013. Enrollment information refers to the fall term 2013. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Thirty-two academic programs reported having nuclear engineering programs during 2013, and data was received from all thirty-two programs. The data for two nuclear engineering programs include enrollments and degrees in health physics options that are also reported in the health physics enrollments and degrees data.

  17. NATO Advanced Study Institute on Topics in Atomic and Nuclear Collisions

    CERN Document Server

    Rémaud, B; Zoran, V

    1994-01-01

    The ASI 'Topics in Atomic and Nuclear Collisions' was organized in Predeal from August 31 to September 11. It brought together people with a broad interest in Atomic and Nuclear Physics from several research institutes and universities in Ro­ mania and 16 other countries. The school continues a tradition that started on a small scale back in 1968, fo­ cussing mainly on current problems in nuclear physics. Though the organizing of this edition started very late and in very uncertain economic and financial conditions, it turned out to be the largest meeting of this type ever organized in Romania, both in topics and participation. There were many applicants for participation and grants, considerably more than could be handled. The selection made by the local organizing committee was based on the following criteria: a proper balance of atomic and nuclear physicists, a broad representation of people from Research Institutes and Universities, a balanced par­ ticipat!on with respect to age, sex, nationali...

  18. The impact of re-engineering a multi-institutional residency program on resident perceptions of the individual institutions.

    Science.gov (United States)

    Dobkin, Eric; Fassler, Steven; Horowitz, Sheryl; Kirton, Orlando; Civetta, Joseph

    2002-01-01

    We report on the development of a survey tool used to assess resident perceptions of support and educational quality among multiple institutions in an integrated surgical residency, as well as its use in measuring the impact of re-engineering on that program. The University of Connecticut Integrated General Surgical Residency (UCIGSR) is a multisite program that was placed on probation by the Residency Review Committee in Surgery (RRC) in November 1998. This led to a re-evaluation and a re-engineering of the program. In order to better assess the residents' evaluation of the program, we serially examined their attitudes with a survey of 65 questions. A 4-point grading scale (1 = Poor, 4 = Excellent) was used, and each resident was required to complete a survey beginning shortly after RRC probation was announced and at 6-month intervals. Seven global questions in the survey, directed at residency program support and educational quality, were asked for each of the 4 individual adult hospitals, for a total of 28 questions. Statistical analysis of the data was performed using the Jonckhere-Terpstra and the Mann-Whitney U tests. The results demonstrated significant improvement for all 7 questions in all 4 hospitals between November 1998 (S1) and November 1999 (S3). Average scores for all 7 questions, Hospital Support (HS), Departmental Support (DS), Hospital Teaching (HT), Outpatient Teaching (OTC), Operating Room Teaching (ORT), Grand Rounds (GR), and Morbidity and Mortality Conferences (MM), improved in every hospital by 16-28%. In S1, 1 out of 28 questions received an average score greater than or equal to 3, whereas on the most recent survey, 17 of 28 scored greater than or equal to 3 and 78.5% of the questions demonstrated statistically significant improvement (p < 0.05). Three of the 4 hospitals now have a combined overall average score greater than or equal to 3 for all 7 questions. Areas of strength in each hospital had the least amount of improvement yet

  19. Results and lessons learned of the first edition of the master in nuclear engineering and applications (MINA)

    Energy Technology Data Exchange (ETDEWEB)

    Herranz, Luis E.; Garcia, Juan c.; Falcon, Susana; Marco, Maria l.; Gonzalez Romero, Enrique M. [Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (CIEMAT), Avda. Complutense, 22. 28040 Madrid (Spain); Casas, Jose A. [Universidad Autonoma de Madrid, Seccion Departamental de Ingenieria Quimica, 28049 Cantoblanco, Madrid (Spain)

    2010-07-01

    The Master in Nuclear Engineering and Applications (MINA) was born to build up a bridge between University education and the technical skills demanded by nuclear industry and organizations, particularly in Spain. Motivated by nuclear renaissance, knowledge preservation and the bases of the European Education area, the new approach adopted to accomplish such a challenge has been heavily based on a professional profile defined by the Spanish nuclear community. The first edition success (MINA-2008) has been assessed through a set of indicators, which encompass a broad range of aspects, from the number of registrations to the employment rate. This paper summarizes and discusses such an assessment. Additionally, a critical thorough review has allowed identifying a few aspects that could be improved. All the lessons learned have been translated into specific measures implemented in the MINA-2009 edition. Among the indicators, participation and industrial support were considered of utmost importance. MINA-2008 had 18 students, out of which 60% were financially supported to some extent thanks to the nuclear industry and organizations (during the conduction of the master project, this support was even enhanced). Beyond the economic contribution, nuclear companies and institutions were strongly involved in all the phases of MINA-2008, from the definition of the program up to the supervision of more than 70 % of the master projects. As a result of the lessons learned, the subjects have been grouped in modules and a more practical approach has been pursued in the teaching/learning process. (authors)

  20. UCSD's Institute of Engineering in Medicine: fostering collaboration through research and education.

    Science.gov (United States)

    Chien, Shu

    2012-07-01

    The University of California, San Diego (UCSD) was established in 1961 as a new research university that emphasizes innovation, excellence, and interdisciplinary research and education. It has a School of Medicine (SOM) and the Jacobs School of Engineering (JSOE) in close proximity, and both schools have national rankings among the top 15. In 1991, with the support of the Whitaker Foundation, the Whitaker Institute of Biomedical Engineering was formed to foster collaborations in research and education. In 2008, the university extended the collaboration further by establishing the Institute of Engineering in Medicine (IEM), with the mission of accelerating the discoveries of novel science and technology to enhance health care through teamwork between engineering and medicine, and facilitating the translation of innovative technologies for delivery to the public through clinical application and commercialization.

  1. Role of Database Management Systems in Selected Engineering Institutions of Andhra Pradesh: An Analytical Survey

    Directory of Open Access Journals (Sweden)

    Kutty Kumar

    2016-06-01

    Full Text Available This paper aims to analyze the function of database management systems from the perspective of librarians working in engineering institutions in Andhra Pradesh. Ninety-eight librarians from one hundred thirty engineering institutions participated in the study. The paper reveals that training by computer suppliers and software packages are the significant mode of acquiring DBMS skills by librarians; three-fourths of the librarians are postgraduate degree holders. Most colleges use database applications for automation purposes and content value. Electrical problems and untrained staff seem to be major constraints faced by respondents for managing library databases.

  2. The Swedish Radiation Protection Institute's regulations concerning the final management of spent nuclear fuel and nuclear waste - with background and comments

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-11-01

    This report presents and comments on the Swedish Radiation Protection Institute's Regulations concerning the Protection of Human Health and the Environment in connection with the Final Management of Spent Nuclear Fuel or Nuclear Waste, SSI FS 1998: 1.

  3. Cardiovascular Tissue Engineering Research Support at the National Heart, Lung, and Blood Institute

    OpenAIRE

    Lundberg, Martha Shauck

    2013-01-01

    Tissue engineering aims at building three-dimensional living substitutes that are equal to or better than the damaged tissue to be replaced. The development of such a tissue replacement requires a multidisciplinary approach and careful attention to the optimal cell source, the interactions of growth factors and extracellular milieu, and the scaffolding design. This article is a review of the National Heart, Lung, and Blood Institute's (NHLBI) tissue engineering programs, which support researc...

  4. UMCP-BG and E collaboration in nuclear power engineering in the framework of DOE-Utility Nuclear Power Engineering Education Matching Grant Program

    Energy Technology Data Exchange (ETDEWEB)

    Wolfe, Lothar PhD

    2000-03-01

    The DOE-Utility Nuclear Power Engineering Education Matching Grant Program has been established to support the education of students in Nuclear Engineering Programs to maintain a knowledgeable workforce in the United States in order to keep nuclear power as a viable component in a mix of energy sources for the country. The involvement of the utility industry ensures that this grant program satisfies the needs and requirements of local nuclear energy producers and at the same time establishes a strong linkage between education and day-to-day nuclear power generation. As of 1997, seventeen pairs of university-utility partners existed. UMCP was never a member of that group of universities, but applied for the first time with a proposal to Baltimore Gas and Electric Company in January 1999 [1]. This proposal was generously granted by BG&E [2,3] in the form of a gift in the amount of $25,000 from BG&E's Corporate Contribution Program. Upon the arrival of a newly appointed Director of Administration in the Department of Materials and Nuclear Engineering, the BG&E check was deposited into the University's Maryland Foundation Fund. The receipt of the letter and the check enabled UMCP to apply for DOE's matching funds in the same amount by a proposal.

  5. A Report of the Nuclear Engineering Division Sessions at the 1971 ASEE Annual Conference

    Science.gov (United States)

    Eckley, Wayne; Nelson, George W.

    1972-01-01

    Summarizes the discussions at the conference under the topics, Objective Criteria for the Future" and Teaching Concepts Basic to Nuclear Engineering." Includes comments from personnel representing universities, industries, and government laboratories. (TS)

  6. Master on Nuclear Engineering and Applications (MINA): instrument of knowledge management in the nuclear sector; Master en Ingenieria Nuclear y Aplicaciones (MINA): instrumento de gestion del conocimiento en el sector nuclear espanol

    Energy Technology Data Exchange (ETDEWEB)

    Herranz, L. E.; Garcia Cuesta, J. C.; Falcon, S.; Casas, J. A.

    2013-03-01

    Knowledge Management in nuclear industry is indispensable to ensure excellence in performance and safety of nuclear installations. The Master on Nuclear Engineering and Applications (MINA) is a Spanish education venture which foundations and evolution have meant and adaptation to the European Education system and to the domestic and international changes occurred in the nuclear environment. This paper summarizes the most relevant aspects of such transformation, its motivation and the final outcome. Finally, it discusses the potential benefit of a closer collaboration among the existing national education ventures in the frame of Nuclear Engineering. (Author)

  7. 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.

  8. Western Nuclear Science Alliance

    Energy Technology Data Exchange (ETDEWEB)

    Steve Reese; George Miller; Stephen Frantz; Denis Beller; Denis Beller; Ed Morse; Melinda Krahenbuhl; Bob Flocchini; Jim Elliston

    2010-12-07

    The primary objective of the INIE program is to strengthen nuclear science and engineering programs at the member institutions and to address the long term goal of the University Reactor Infrastructure and Education Assistance Program.

  9. Professor Andrzej Budzanowski, Director General, Henryk Niewodniczanski Institute of Nuclear Physics (HNINP) Poland. Dr. Grzegorz Polok, Deputy Director

    CERN Multimedia

    Maximilien Brice

    2003-01-01

    Andrzej Budzanowski, Director-General of the Cracow Institute of Nuclear Physics (HNINP) and Lyn Evans, LHC Project Leader, signing the collaboration agreement. In the background, from leftto right : Grzegorz Polok, Deputy Director-General of the Cracow Institute of Nuclear Physics, Blazej Skoczen, in charge of the LHC cryomagnet interconnections, Claude Détraz, Director for Fixed Target and Future Programmes, Alain Poncet, AT/CRI Group Leader.

  10. A Multi-Institution Study of Student Demographics and Outcomes in Chemical Engineering

    Science.gov (United States)

    Lord, Susan M.; Layton, Richard A.; Ohland, Matthew W.; Brawner, Catherine E.; Long, Russell A.

    2014-01-01

    Using a large multi-institutional dataset, we describe demographics and outcomes for students starting in and transferring into chemical engineering (ChE). In this dataset, men outnumber women in ChE except among black students. While ChE starters graduate in ChE at rates comparable to or above their racial/ethnic population average for…

  11. Engines without Fuel?--Empirical Findings on Finnish Higher Education Institutions as Education Exporters

    Science.gov (United States)

    Schatz, Monika

    2016-01-01

    In 2010, the Finnish Ministry of Education and Culture formulated Finland's first education export strategy. This policy document attributed Finnish Higher Education Institutions (HEIs) a significant role in the emerging sector by declaring them as "engines" of education export. Situated in a phenomenological approach towards…

  12. Strategies for the Cooperation of Educational Institutions and Companies in Mechanical Engineering

    Science.gov (United States)

    Kettunen, Juha

    2006-01-01

    Purpose: The purpose of this study is to analyse the strategic planning of the Centre for Mechanical Engineering, which is a joint venture of educational institutions and companies in Southwest Finland. Design/methodology/approach: The paper presents the strategies of focus and cost efficiency and how the selected strategies can be adjusted…

  13. Integrating Social Sustainability in Engineering Education at the KTH Royal Institute of Technology

    Science.gov (United States)

    Björnberg, Karin Edvardsson; Skogh, Inga-Britt; Strömberg, Emma

    2015-01-01

    Purpose: The purpose of this paper is to investigate what are perceived to be the main challenges associated with the integration of social sustainability into engineering education at the KTH Royal Institute of Technology, Stockholm. Design/methodology/approach: Semi-structured interviews were conducted with programme leaders and teachers from…

  14. Study Programmes for Engineers from Developing Countries at the Norwegian Institute of Technology.

    Science.gov (United States)

    Lasson, Axel; Hermansen, John

    1989-01-01

    Describes the background of the study and fellowship programs for graduates from the developing countries at the Norwegian Institute of Technology. Discusses some experiences with the programs. Includes a brief description of five courses: (1) "Pulp and Paper Technology"; (2) "Marine Civil Engineering"; (3) "Hydropower…

  15. Integrating Social Sustainability in Engineering Education at the KTH Royal Institute of Technology

    Science.gov (United States)

    Björnberg, Karin Edvardsson; Skogh, Inga-Britt; Strömberg, Emma

    2015-01-01

    Purpose: The purpose of this paper is to investigate what are perceived to be the main challenges associated with the integration of social sustainability into engineering education at the KTH Royal Institute of Technology, Stockholm. Design/methodology/approach: Semi-structured interviews were conducted with programme leaders and teachers from…

  16. A Multi-Institution Study of Student Demographics and Outcomes in Chemical Engineering

    Science.gov (United States)

    Lord, Susan M.; Layton, Richard A.; Ohland, Matthew W.; Brawner, Catherine E.; Long, Russell A.

    2014-01-01

    Using a large multi-institutional dataset, we describe demographics and outcomes for students starting in and transferring into chemical engineering (ChE). In this dataset, men outnumber women in ChE except among black students. While ChE starters graduate in ChE at rates comparable to or above their racial/ethnic population average for…

  17. Performance Engineering Research Institute SciDAC-2 Enabling Technologies Institute Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Hall, Mary [University of Utah

    2014-09-19

    Enhancing the performance of SciDAC applications on petascale systems has high priority within DOE SC. As we look to the future, achieving expected levels of performance on high-end com-puting (HEC) systems is growing ever more challenging due to enormous scale, increasing archi-tectural complexity, and increasing application complexity. To address these challenges, PERI has implemented a unified, tripartite research plan encompassing: (1) performance modeling and prediction; (2) automatic performance tuning; and (3) performance engineering of high profile applications. The PERI performance modeling and prediction activity is developing and refining performance models, significantly reducing the cost of collecting the data upon which the models are based, and increasing model fidelity, speed and generality. Our primary research activity is automatic tuning (autotuning) of scientific software. This activity is spurred by the strong user preference for automatic tools and is based on previous successful activities such as ATLAS, which has automatically tuned components of the LAPACK linear algebra library, and other re-cent work on autotuning domain-specific libraries. Our third major component is application en-gagement, to which we are devoting approximately 30% of our effort to work directly with Sci-DAC-2 applications. This last activity not only helps DOE scientists meet their near-term per-formance goals, but also helps keep PERI research focused on the real challenges facing DOE computational scientists as they enter the Petascale Era.

  18. Practical Education Support to Foster Engineers at Manufacturing and Engineering Design Center in Muroran Institute of Technology

    Science.gov (United States)

    Kazama, Toshiharu; Hanajima, Naohiko; Shimizu, Kazumichi; Satoh, Kohki

    To foster engineers with creative power, Muroran Institute of Technology established Manufacturing and Engineering Design Center (MEDeC) that concentrates on Monozukuri. MEDeC consists of three project groups : i) Education Support Group provides educational support for practical training classes on and off campus and PDCA (plan-do-check-action) -conscious engineering design education related to Monozukuri ; ii) Fundamental Manufacturing Research Group carries out nurture research into fundamental and innovative technology of machining and manufacturing, and iii) Regional Cooperation Group coordinates the activities in cooperation with bureau, schools and industries in and around Muroran City. MEDeC has a fully integrated collection of machine tools and hand tools for manufacturing, an atelier, a tatara workplace, implements for measurement and related equipment designed for practically teaching state-of-the-practice manufacturing methods.

  19. Inauguration of the international Institute of the nuclear energy; Inauguration de l'Institut international de l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2011-07-15

    On June 27, 2011 was inaugurated in Saclay (France) the I2EN (international Institute of the nuclear energy) and the Jannus platform. The I2EN has to particularly centralize and relay, at the international scale, the French formations offer in the field of nuclear energy. On the other hand, the Jannus platform is an example of cooperation between research organisms and universities. (O.M.)

  20. A Programmatic and Engineering Approach to the Development of a Nuclear Thermal Rocket for Space Exploration

    Science.gov (United States)

    Bordelon, Wayne J., Jr.; Ballard, Rick O.; Gerrish, Harold P., Jr.

    2006-01-01

    With the announcement of the Vision for Space Exploration on January 14, 2004, there has been a renewed interest in nuclear thermal propulsion. Nuclear thermal propulsion is a leading candidate for in-space propulsion for human Mars missions; however, the cost to develop a nuclear thermal rocket engine system is uncertain. Key to determining the engine development cost will be the engine requirements, the technology used in the development and the development approach. The engine requirements and technology selection have not been defined and are awaiting definition of the Mars architecture and vehicle definitions. The paper discusses an engine development approach in light of top-level strategic questions and considerations for nuclear thermal propulsion and provides a suggested approach based on work conducted at the NASA Marshall Space Flight Center to support planning and requirements for the Prometheus Power and Propulsion Office. This work is intended to help support the development of a comprehensive strategy for nuclear thermal propulsion, to help reduce the uncertainty in the development cost estimate, and to help assess the potential value of and need for nuclear thermal propulsion for a human Mars mission.

  1. Second conference on nuclear science and engineering in Australia, 1997. Conference handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The conference handbook contains the text of papers presented orally and as posters. Leading experts in various areas of nuclear science and technology discussed the following topics: uranium resources, radioactive waste management, research reactor safety and applications, radiation and related research, applications of accelerators and related facilities and nuclear regulation in Australia. The posters include two from the winners of the David Culley Award in 1995 and 1996, instituted by the Australian Nuclear Association to encourage work in nuclear science and technology in school and colleges.

  2. Appliance of software engineering in development of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Baek, Y. W.; Kim, H. C.; Yun, C. [Chungnam National Univ., Taejon (Korea, Republic of); Kim, B. R. [KINS, Taejon (Korea, Republic of)

    1999-10-01

    Application of computer technology in nuclear power plant is also a necessary transformation as in other industry fields. But until now, application of software technology was not wide-spread because of its potential effect to safety in nuclear field. It is an urgent theme to develop evaluation guide and regulation techniques to guarantee safety, reliability and quality assurance. To meet these changes, techniques for development and operation should be enhanced to ensure the quality of software systems. In this study, we show the difference between waterfall model and software life-cycle needed in development of nuclear power plant and propose the consistent framework needed in development of instrumentation and control system of nuclear power plant.

  3. Paul Scherrer Institut annual report 1994. Annex IV: PSI nuclear energy and safety research progress report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Williams, T.; Kallfelz, J.M.; Mathews, D. [eds.] [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1995-10-01

    Nuclear energy research in Switzerland is concentrated at PSI. It is explicitly mentioned in the Institute`s official charter and commands about one fifth of the Institute`s federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI`s activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs.

  4. Spent nuclear fuel project systems engineering management plan

    Energy Technology Data Exchange (ETDEWEB)

    Womack, J.C., Westinghouse Hanford

    1996-07-19

    The purpose of this document is to describe the systems engineering approach and methods that will be integrated with established WHC engineering practices. The methodology promotes and ensures sound management of the SNF Project. The scope of the document encompasses the efforts needed to manage the WHC implementation of systems engineering on the SNF Project including risk management process, design authority/design agent concept, and documentation responsibilities. This implementation applies to, and is tailored to the needs of the SNF Project and all its Subprojects, including all current and future Subprojects.

  5. [Occupational medicine in nuclear industry and power engineering].

    Science.gov (United States)

    Gus'kova, A K

    2004-01-01

    The author analysed results of medical service in atomic industry and power engineering over 50 years. Those results are beneficial for management in occupational medicine for any new complicated and potentially dangerous technology and activity.

  6. A Hydrogen Containment Process for Nuclear Thermal Engine Ground testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric; Canabal, Francisco

    2016-01-01

    The objective of this study is to propose a new total hydrogen containment process to enable the testing required for NTP engine development. This H2 removal process comprises of two unit operations: an oxygen-rich burner and a shell-and-tube type of heat exchanger. This new process is demonstrated by simulation of the steady state operation of the engine firing at nominal conditions.

  7. Overview of codes and tools for nuclear engineering education

    Science.gov (United States)

    Yakovlev, D.; Pryakhin, A.; Medvedeva, L.

    2017-01-01

    The recent world trends in nuclear education have been developed in the direction of social education, networking, virtual tools and codes. MEPhI as a global leader on the world education market implements new advanced technologies for the distance and online learning and for student research work. MEPhI produced special codes, tools and web resources based on the internet platform to support education in the field of nuclear technology. At the same time, MEPhI actively uses codes and tools from the third parties. Several types of the tools are considered: calculation codes, nuclear data visualization tools, virtual labs, PC-based educational simulators for nuclear power plants (NPP), CLP4NET, education web-platforms, distance courses (MOOCs and controlled and managed content systems). The university pays special attention to integrated products such as CLP4NET, which is not a learning course, but serves to automate the process of learning through distance technologies. CLP4NET organizes all tools in the same information space. Up to now, MEPhI has achieved significant results in the field of distance education and online system implementation.

  8. Intercomparison Contracted Partner Institutes for Nuclear Emergency 2007; Ringonderzoek waakvlaminstituten kernongevallenbestrijding 2007

    Energy Technology Data Exchange (ETDEWEB)

    Overwater-van Buuren, R.M.W.; Glastra, P.; Tukker, K.

    2009-07-01

    The quality of the so-called Contracted Partner Institutes (CPI's) is amply complying with the objectives. Nonetheless, some desirable improvements remain, especially issues concerning the calibration of the measuring equipment. These issues emerged during an investigation performed by RIVM, in which the quality of the analysis of water and air samples was tested. In the Netherlands there are eight CPI's, evenly spread across the country, who can inform the government about radioactivity in air and water. The CPIs are part of the Dutch National Plan for Nuclear Emergency Planning and Response, which has been drawn up after the nuclear disaster in Chernobyl. RIVM is coordinating the activities of the CPI's. The Contracted Partner Institutes are tested on a two-yearly base by way of intercomparisons. In these intercomparisons, testing is done on both the timely reporting of the results and on the agreement with the reference value within pre-defined boundaries. Most CPI's were able to deliver the air results within two hours, and the water results within 24 hours. The results of the air samples for one institute were outside the pre-defined boundaries. Four samples were prepared for the intercomparison: an aerosol filter, a charcoal filter, a charcoal cartridge and a water sample. All four contained radionuclides characteristic for nuclear accidents. [Dutch] De kwaliteit van de zogeheten Waakvlaminstituten (WVI's) voldoet in 2007 ruimschoots aan de doelstellingen. Wel zijn enkele verbeteringen wenselijk, vooral op het gebied van kalibratie van de meetopstellingen. Dit blijkt uit onderzoek van het RIVM waarin de kwaliteit is getest van de analyse van water- en luchtmonsters. In Nederland bestaan er verspreid over het land acht WVI's die bij een kernongeval de overheid informeren over radioactiviteit in lucht en water. De WVI's zijn een onderdeel van het Nationaal Plan Kernongevallenbestrijding (NPK), dat is opgesteld enkele jaren na

  9. Manipulation of dynamic nuclear spin polarization in single quantum dots by photonic environment engineering

    Science.gov (United States)

    Fong, C. F.; Ota, Y.; Iwamoto, S.; Arakawa, Y.

    2017-06-01

    Optically induced dynamic nuclear spin polarization (DNP) in a semiconductor quantum dot (QD) requires many cycles of excitation of spin polarized carriers and carrier recombination. As such, the radiative lifetime of the exciton containing the electron becomes one of the limiting factors of DNP. In principle, changing the radiative lifetime of the exciton will affect DNP and thus the nuclear spin polarization. Here, we demonstrate the manipulation of DNP in single QDs through the engineering of the photonic environment using two-dimensional photonic crystals. We find that the achievable degree of nuclear spin polarization can be controlled through the modification of exciton radiative lifetime. Our results show the promise of achieving a higher degree of nuclear spin polarization via photonic environment engineering, with implications on spin-based quantum information processing.

  10. Process safety management: resources from the American Institute of Chemical Engineers for use by industrial hygienists.

    Science.gov (United States)

    Gideon, J A; Carmody, T W

    1992-06-01

    Industrial hygienists often work closely with engineers to control occupational safety and health hazards. This working relationship involves an educational process in which both engineers and industrial hygienists learn from one another. The Center for Chemical Process Safety (CCPS) of the American Institute of Chemical Engineers (AIChE) is expanding the opportunity for interdisciplinary cooperation and education by producing a series of guidelines publications on the technical and scientific issues critical to preventing and mitigating major releases of toxic materials. Examples of these guidelines include Hazard Evaluation Procedures; Technical Management of Chemical Process Safety; Chemical Process Quantitative Risk Analysis; and Safe Storage and Handling of Highly Toxic Hazardous Materials. Additional topics are addressed in the 8 guidelines in print and the 15 others in preparation. Several guidelines contain specific examples that illustrate how industrial hygienists, engineers, and other readers can use the guidelines to help address chemical process safety problems. Another CCPS activity involves an effort to include an awareness of health, safety, and loss prevention as an integral part of undergraduate chemical engineering education. For practicing engineers and industrial hygienists, a number of continuing education courses on topics such as process hazard analysis, process risk assessment, and process safety are offered by the AIChE. All of these resources are particularly timely in light of the Occupational Safety and Health Administration's recently enacted rule on Process Safety Management of Highly Hazardous Chemicals.

  11. Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    J. D. Bess; J. B. Briggs; A. S. Garcia

    2011-09-01

    One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

  12. PREFACE: Selected papers from the Fourth Topical Conference on Nanoscale Science and Engineering of the American Institute of Chemical Engineers

    Science.gov (United States)

    Wong, Michael S.; Lee, Gil U.

    2005-07-01

    This special issue of Nanotechnology contains research papers contributed by the participants of the Fourth Topical Conference on Nanoscale Science and Engineering at the Annual Meeting of the American Institute of Chemical Engineers (AIChE), which was held in Austin, Texas, USA, 7-12 November, 2004. This conference saw 284 oral presentations from institutions around the world, which is the highest number for this topical conference series to date. These presentations were organized into 64 sessions, covering the range of nanotechnology subject areas in which chemical engineers are currently engaged. These sessions included the following areas. • Fundamentals: thermodynamics at the nanoscale; applications of nanostructured fluids; transport properties in nanophase and nanoscale systems; molecular modelling methods; self and directed assembly at the nanoscale; nanofabrication and nanoscale processing; manipulation of nanophases by external fields; nanoscale systems; adsorption and transport in carbon nanotubes; nanotribology; making the transition from materials and phenomena to new technologies; operation of micro-and nano-systems. • Materials: nanoparticle synthesis and stabilization; nanoscale structure in polymers; nanotemplating of polymers; synthesis of carbon nanotubes and nanotube-based materials; nanowires; nanoparticle assemblies and superlattices; nanoelectronic materials; self-assembly of templated inorganic materials; nanostructured hybrid organic/inorganic materials; gas phase synthesis of nanoparticles; multicomponent structured particles; nano energetic materials; liquid-phase synthesis of nanoparticles. • Energy: synthesis and characterization of nanostructured catalytic materials; nanomaterials and devices for energy applications. • Biotechnology: nanobiotechnology; nanotechnology for the biotechnology and pharmaceuticals industries; nanotechnology and nanobiotechnology for sensors; advances in biomaterials, bionanotechnology, biomimetic

  13. Armouring facility? Nuclear-weapon and reactor reseach at the Kaiser-Wilhelm Institute for Physics; Eine Waffenschmiede? Kernwaffen- und Reaktorforschung am Kaiser-Wilhelm-Institut fuer Physik

    Energy Technology Data Exchange (ETDEWEB)

    Hachtmann, R. (ed.); Walker, M.

    2005-07-01

    The Kaiser Wilhelm Institute for Physics is best known as the place where Werner Heisenberg worked on nuclear weapons for Hitler. Although this is essentially true, there is more to the story. At the start of World War II this institute was taken over by the German Army Ordnance to be the central, but not exclusive site for a research project into the economic and military applications of nuclear fission. The Army physicist Kurt Diebner was installed in the institute as its commissarial director. Heisenberg was affiliated with the institute as an advisor at first, and became the director in 1942. Heisenberg and his colleagues, including in particular Karl-Heinz Hoecker, Carl Friedrich von Weizsaecker, and Karl Wirtz, worked on nuclear reactors and isotope separation with the clear knowledge that these were two different paths to atomic bombs [Atombomben]. However, they were clearly ambivalent about what they were doing. New documents recently returned from Russian archives shed new light on this work and the scientists' motivations. (orig.)

  14. The tissue bank at the national nuclear research institute in Mexico.

    Science.gov (United States)

    Esther Martínez-Pardo, María; Lourdes Reyes-Frías, Ma

    2003-01-01

    The Instituto Nacional de Investigaciones Nucleares (ININ, The National Nuclear Research Institute) received during 1997-1998 strong support of the International Atomic Energy Agency (IAEA), to establish the first and only one tissue bank (BTR ININ tissue bank) in Mexico that uses ionising radiation as sterilising agent. In that time, the BTR staff was trained in different tissue banks in several countries. Basic equipment for tissue processing donated by the IAEA was received in 1998. In July, 1999 the Mexican Health Secretariat gave the Sanitary License No. 1062000001 to the BTR to operate as an official organ and tissue bank. In August, 2001 the ININ and the Hospital Materno Infantil (HMI-ISSEMYM) signed an agreement to collaborate in amnion processing. The hospital is responsible for donor selection, serology tests, tissue procurement and washing, since this hospital is the BTR amnion supplier. The tissues are collected by ININ weekly with complete documentation. The BTR is responsible for processing: cleaning, air drying, packaging, labelling, microbiological control and sterilisation by gamma irradiation. The sterilised tissue is kept under quarantine for 6 months to obtain the results of the donor second serology test. From March to June, 2002 the BTR has processed 347.86 units (50 cm(2) each), is say, 17,393 cm(2). In addition, the pig skin xenograft process has been implemented and a protocol for clinical applications of it is running at the Hospital Central Sur de Alta Especialidad (PEMEX). Also the ININ tissue bank present status and perspectives are described.

  15. Gas core nuclear thermal rocket engine research and development in the former USSR

    Energy Technology Data Exchange (ETDEWEB)

    Koehlinger, M.W.; Bennett, R.G.; Motloch, C.G. [eds.; Gurfink, M.M.

    1992-09-01

    Beginning in 1957 and continuing into the mid 1970s, the USSR conducted an extensive investigation into the use of both solid and gas core nuclear thermal rocket engines for space missions. During this time the scientific and engineering. problems associated with the development of a solid core engine were resolved. At the same time research was undertaken on a gas core engine, and some of the basic engineering problems associated with the concept were investigated. At the conclusion of the program, the basic principles of the solid core concept were established. However, a prototype solid core engine was not built because no established mission required such an engine. For the gas core concept, some of the basic physical processes involved were studied both theoretically and experimentally. However, no simple method of conducting proof-of-principle tests in a neutron flux was devised. This report focuses primarily on the development of the. gas core concept in the former USSR. A variety of gas core engine system parameters and designs are presented, along with a summary discussion of the basic physical principles and limitations involved in their design. The parallel development of the solid core concept is briefly described to provide an overall perspective of the magnitude of the nuclear thermal propulsion program and a technical comparison with the gas core concept.

  16. The creation of IRSN Institute of radiation protection and nuclear safety; La creation de l'IRSN Institut de Radioprotection et de Surete Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-03-01

    The creation of the Institute of Radiation Protection and Nuclear Safety (I.R.S.N.) answers to the government will to modify the organisation of safety and radiation protection, in order to separate the functions of expert, monitor and operator. The I.R.S.N. has for missions to realize expertise by giving to the government advice on nuclear risks; to conduct researches in order to improve the knowledge; to work towards radiation monitoring of environment and workers as well as exposure sources to radiations. (N.C.)

  17. Estimation of metal pollutant loads from Nuclear and Energy Research Institute (Brazil)

    Energy Technology Data Exchange (ETDEWEB)

    Marques, Joyce R.; Monteiro, Lucilena R.; Soares, Sabrina M.V.; Stellato, Thamiris B.; Silva, Tatiane B.S.C.; Silva, Douglas B. da; Faustino, Mainara G.; Pires, Maria A.F.; Cotrim, Marycel E.B., E-mail: joyce.marques@usp.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    According to National Environmental Council's (CONAMA) Resolution 357/05, pollutant load can be defined as the amount of a particular pollutant released in receiving water body; it is commonly expressed in a mass-time ratio. As specified in CONAMA's Resolution 430/11, the responsible for the pollutant source must present the Pollutant Load Declaration to environmental authorities. However, pollutant load knowledge is also important to the water quality maintenance and its environmental rating that must be kept to meet the requirements of the most restrictive use. In the control of metals releases is also important due public health matters, since they can cause harmful environmental contamination and major public health issues. Therefore this work aims to present the estimated metal pollutant load released by Nuclear and Energy Research Institute (IPEN/CNEN - Brazil), between 2013 and 2014. Results of cadmium, lead, copper, chromium, zinc, nickel, manganese, iron, barium, silver, boron and tin in composite samples (weekly) via Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES) and bromide (Br-) released as a tracer, to measure the wastewater flow were used to estimate IPEN's Metal Pollutant load. This study is part of the environmental assessment Program at IPEN, instituted since 2006 to the attendance of the current environmental legislation (CONAMA's Resolution 430/11, Article 19-A of State Decree 8.468/76 and State Decree 15.425/80). (author)

  18. Nuclear Deterrence in the 21st Century: The Role of Science and Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Martz, Joseph C [Los Alamos National Laboratory; Ventura, Jonathan S [Los Alamos National Laboratory

    2008-01-01

    Twenty-first century security challenges are multi-polar and asymmetric. A few nations have substantial nuclear arsenals and active nuclear weapons programs that still threaten vital US national security directly or by supporting proliferation. Maintaining a credible US nuclear deterrent and containing further proliferation will continue to be critical to US national security. Overlaid against this security backdrop, the rising worldwide population and its effects on global climate, food, and energy resources are greatly complicating the degree and number of security challenges before policy makers.This new paradigm requires new ways to assure allies that the United States remains a trusted security partner and to deter potential adversaries from aggressive actions that threaten global stability. Every U.S. President since Truman has affirmed the role of nuclear weapons as a supreme deterrent and protector of last resort of U.S. national security interests. Recently, President Bush called for a nuclear deterrent consistent with the 'lowest number of nuclear weapons' that still protects U.S. interests. How can this be achieved? And how can we continue on a path of nuclear reductions while retaining the security benefits of nuclear deterrence? Science and engineering have a key role to play in a potential new paradigm for nuclear deterrence, a concept known as 'capability-based deterrence.'

  19. Sustainability indicators for innovation and research institutes of nuclear area in Brazil; Indicadores de sustentabilidade para institutos de pesquisa e inovacao da area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alves, S.F.; Barreto, A.A.; Rodrigues, P.C.H.; Feliciano, V.M.D., E-mail: sfa@cdtn.br, E-mail: aab@cdtn.br, E-mail: pchr@cdtn.br, E-mail: vmfj@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2016-11-01

    Indicators are relevant tools for measuring sustainability process. In this study, the relevance of sustainability indicators appropriate for research and innovation institutes in Brazil is discussed. As reference for case study, nuclear research and innovation institutes were chosen. Sixty-nine sustainability indicators were considered. Some of these indicators were obtained from lists in the literature review, distributed between the dimensions environmental, economic, social, cultural and institutional. The other indicators were developed through discussions between professionals from nuclear, environmental, economic, social and cultural areas. Among the investigated indicators, 32 were selected as being the most relevant. Discrepancies were found during the analysis the opinions of the experts in relation to sustainability dimensions proposed. (author)

  20. Groundwater assessment in water resources management at Nuclear and Energy Research Institute, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Sabrina M.V.; Marques, Joyce R.; Monteiro, Lucilena R.; Stellato, Thamiris B.; Silva, Tatiane B.S.C.; Faustino, Mainara G.; Silva, Douglas B. da; Cotrim, Marycel E.B.; Pires, Maria Aparecida F., E-mail: sabrinamoura@usp.br, E-mail: joyce.marques@usp.br, E-mail: luciremo@uol.com.br, E-mail: thamistellato@gmail.com, E-mail: tatianebscs@live.com, E-mail: mainarag@usp.br, E-mail: douglas.sbatista@yahoo.com.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    To comply with the guidelines for environmental control and legal requirements, the Nuclear and Energy Research Institute (IPEN/ CNEN - Brazil/ SP) performs the Environmental Monitoring Program for Chemical Stable Compounds (PMA-Q) since 2007, in attendance to the Term for the Adjustment of Conduct (TAC) signed between IPEN and the Brazilian Institute of Environment and Renewable Natural Resources (IBAMA). The PMA-Q program includes the assessment of the IPEN's wastewater released in water body, and the groundwater assessment, which is carried out in nine monitoring wells. In groundwater is analyzed, by ion chromatography, species regulated by CONAMA 396/08 [01] fluoride, chloride, nitrite-N, nitrate-N, sulfate, sodium, potassium, ammonium, magnesium and calcium, besides other parameters. Furthermore, based on legal requirements, each year the program is reviewed and improvement actions are planned and implemented. Therefore, the integrated monitoring of groundwater should provide information on the quality and dynamics of the aquifer compared to seasonal variations and anthropogenic effects. Thus, this study intends to evaluate the chemical features of the institute groundwater, evaluating the database of the monitoring program from 2011 to 2014, for the ions chloride, nitrate-N, sulfate, sodium, potassium, magnesium, calcium and bicarbonate, using these information diagrams will be developed for the characterization of the wells. This assessment will be essential to support the control actions of environmental pollution and the management of water resources. Making possible the establishment of groundwater Quality Reference Figures (QRF), according to the CONAMA 396/08 [01] rating, in order to demonstrate that the activities developed at IPEN are not affecting on the aquifer features. (author)

  1. Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book

    Energy Technology Data Exchange (ETDEWEB)

    Friesen, H.N.

    1995-06-01

    Nuclear rocket and ramjet engine tests were conducted on the Nevada Test Site (NTS) in Area 25 and Area 26, about 80 miles northwest of Las Vegas, Nevada, from July 1959 through September 1969. This document presents a brief history of the nuclear rocket engine tests, information on the off-site radiological monitoring, and descriptions of the tests.

  2. Effluent Scrubbing of Engine Exhaust of a Nuclear Thermal Propulsion Engine Project

    Data.gov (United States)

    National Aeronautics and Space Administration — This project identified specific knowledge and expertise in radioactive hydrogen effluent filter technology, so that internal resources on NTP engine exhaust...

  3. Enhancement of Teaching and Learning of the Fundamentals of Nuclear Engineering Using Multimedia Courseware.

    Science.gov (United States)

    Keyvan, Shahla A.; Pickard, Rodney; Song, Xiaolong

    1997-01-01

    Computer-aided instruction incorporating interactive multimedia and network technologies can boost teaching effectiveness and student learning. This article describes the development and implementation of network server-based interactive multimedia courseware for a fundamental course in nuclear engineering. A student survey determined that 80% of…

  4. Nuclear Engineering Enrollment and Degree Survey: Enrollments - Fall 1972; Degrees Granted - July 1965-June 1972.

    Science.gov (United States)

    Chewning, June S.

    The Atomic Energy Commission's survey of nuclear engineering degrees granted during the 1971-72 academic year shows a continuing increase in bachelor's recipients, a slight increase in the number of master's, but a continuing decline in new Ph.D.'s. If the present rate of decline persists, by 1974 the number of new Ph.D.'s in the field will be…

  5. Applications of nuclear magnetic resonance imaging in process engineering

    Science.gov (United States)

    Gladden, Lynn F.; Alexander, Paul

    1996-03-01

    During the past decade, the application of nuclear magnetic resonance (NMR) imaging techniques to problems of relevance to the process industries has been identified. The particular strengths of NMR techniques are their ability to distinguish between different chemical species and to yield information simultaneously on the structure, concentration distribution and flow processes occurring within a given process unit. In this paper, examples of specific applications in the areas of materials and food processing, transport in reactors and two-phase flow are discussed. One specific study, that of the internal structure of a packed column, is considered in detail. This example is reported to illustrate the extent of new, quantitative information of generic importance to many processing operations that can be obtained using NMR imaging in combination with image analysis.

  6. Environmental Degradation of Materials for Nuclear Waste Repositories Engineered Barriers

    Energy Technology Data Exchange (ETDEWEB)

    Rebak, R B

    2006-12-24

    Several countries are considering geological repositories for the storage of nuclear waste. Most of the environments for these repositories will be reducing in nature, except for the repository in the US, which is going to be oxidizing. For the reducing repositories, alloys such as carbon steel, copper, stainless steels and titanium are being evaluated. For the repository in the US, some of the most corrosion resistant commercially available alloys are being investigated. This paper presents a summary of the behavior of the different materials under consideration for the repositories and the current understanding of the degradation modes of the proposed alloys in ground water environments from the point of view of general corrosion, localized corrosion and environmentally assisted cracking.

  7. Groundwater Waves in a Coastal Fractured Aquifer of the Third Phase Qinshan Nuclear Power Engineering Field

    Institute of Scientific and Technical Information of China (English)

    ZHOU Nian-qing; TANG Yi-qun; TANG He-ping

    2005-01-01

    Tidal fluctuations of Hangzhou Bay produce progressive pressure waves in adjacent field fractured aquifers, as the pressure waves propagate, groundwater levels and hydraulic gradients continuously fluctuate. The effect of tidal fluctuations on groundwater flow can be determined using the mean hydraulic gradient that can be calculated by comparing mean ground and surface water elevations. Tidal fluctuation is shown to affect the piezometer readings taken in a nearshore fractured aquifer around the nuclear power engineering field. Continuous monitoring of a network of seven piezometers provided relations between the tidal cycle and the piezometer readings. The relations can be expressed in times of a time and amplitude scaling factor. The time lag and the tidal effi ciency factor and wavelength are calculated using these parameters. It provides significant scientific basis to prevent tide and groundwater for the nuclear power engineering construction and safety run of nuclear power station in the future.

  8. Engineering factors influencing Corbicula fouling in nuclear-service water systems

    Energy Technology Data Exchange (ETDEWEB)

    Henager, C.H.; Johnson, K.I.; Page, T.L.

    1983-06-01

    Corbicula fouling is a continuing problem in nuclear-service water systems. More knowledge of biological and engineering factors is needed to develop effective detection and control methods. A data base on Corbicula fouling was compiled from nuclear and non-nuclear power stations and industries using raw water. This data base was used in an analysis to identify systems and components which are conducive to fouling by Corbicula. Bounds on several engineering parameters such as velocity and temperature which support Corbicula growth are given. Service water systems found in BWR and PWR reactors are listed and those that show fouling are identified. Possible safety implications of Corbicula fouling are discussed for specific service water systems. Several effective control methods in current use include backflushing with heated water, centrifugal strainers, and continuous chlorination during spawning seasons.

  9. Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

    Energy Technology Data Exchange (ETDEWEB)

    Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

    1986-03-01

    This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

  10. Nuclear and plastid genetic engineering of plants: comparison of opportunities and challenges.

    Science.gov (United States)

    Meyers, Benjamin; Zaltsman, Adi; Lacroix, Benoît; Kozlovsky, Stanislav V; Krichevsky, Alexander

    2010-01-01

    Plant genetic engineering is one of the key technologies for crop improvement as well as an emerging approach for producing recombinant proteins in plants. Both plant nuclear and plastid genomes can be genetically modified, yet fundamental functional differences between the eukaryotic genome of the plant cell nucleus and the prokaryotic-like genome of the plastid will have an impact on key characteristics of the resulting transgenic organism. So, which genome, nuclear or plastid, to transform for the desired transgenic phenotype? In this review we compare the advantages and drawbacks of engineering plant nuclear and plastid genomes to generate transgenic plants with the traits of interest, and evaluate the pros and cons of their use for different biotechnology and basic research applications, ranging from generation of commercial crops with valuable new phenotypes to 'bioreactor' plants for large-scale production of recombinant proteins to research model plants expressing various reporter proteins.

  11. 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.

  12. 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.

  13. Pengembangan Peta Interaktif Tiga Dimensi Gedung Rektorat Institut Teknologi Sepuluh Nopember Menggunakan Unity3d Engine

    Directory of Open Access Journals (Sweden)

    Muhammad Imam Ghazali

    2015-03-01

    Full Text Available Penggunaan teknologi informasi dalam pemetaan digital sudah lama digunakan. Dahulu orang cenderung melakukan pemetaan digital secara 2D untuk memetakan suatu area atau gedung, namun pemetaan secara 2D sendiri tidak memberikan informasi secara mendetail tentang keadaan dan topografi dari area atau gedung tersebut. Seiring dengan perkembangan teknologi informasi penggunaan teknologi 3D pun mulai digunakan dalam pemetaan secara digital agar dapat memberikan informasi yang lebih mendetail tentang keadaan suatu area atau gedung. Untuk membangun sebuah peta 3D dapat dilakukan menggunakan engine 3D yang biasanya digunakan untuk membuat game. Dengan memanfaatkan Unity3D Engine penulis akan membangun sebuah pemetaan digital secara 3D agar dari pemetaan tersebut dapat memberikan informasi yang akurat dan tepat mengenai keadaan area yang dipetakan sesuai dengan kenyataan. Dalam pembuatan akan dipetakan gedung Rektorat Institut Teknologi Sepuluh Nopember Surabaya. Pemetaan secara 3D ini dapat memberikan informasi yang akurat dan mendetail kepada pengguna peta 3D ini nantinya tentang keadaan dari gedung Rektorat.

  14. Establishment of nuclear knowledge-information base; development of courseware on introductory nuclear engineering and establishment of digital education platform

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jong Soon; Na, Mang Yun; Lee, Goung Jin; Yang, Won Sik [Chosun University, Gwangju (Korea)

    2002-01-01

    In this research, there are two major tasks. The first one is a development of digital course-ware program for introductory nuclear engineering. For this task, a development of lecture note is followed by lecture Slide files in html file format, which is based on web. For this purpose, following activities were performed; collection of related materials. planning of overall courseware, writing of lecture note and exercise plan, and securing the computer programs and codes needed. The second task of this research is to plan and install several hardwares in a multimedia class room as a digital education platform. The platform includes smart board with touch screen functionality, network server and personal computers. The digital education platform was established as a multimedia class room in the 2nd College of Engineering building, room 16210 by using the Server-Client environment and smart board, personal computer, and internet was connected by a TCP/IP way. For the courseware, hypertext was supported to be web-based, and photo, picture, data and related web links including text were developed in a close relation, it is possible for students to study big amounts of information in a systemized way and to maximize the learning efficiency. The whole range of introductory nuclear engineering course was divided into nuclear fuel cycle, reactor theory, heat transport, and reactor control, and digital contents were developed by each experts, but the final format of the courseware was maintained consistently for easy understanding . Also, the reactor experiment courseware developed by Kyunghee University can be utilized on this platform. 5 refs., 36 figs., 4 tabs. (Author)

  15. Research in progress and other activities of the Institute for Computer Applications in Science and Engineering

    Science.gov (United States)

    1993-01-01

    This report summarizes research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics and computer science during the period April 1, 1993 through September 30, 1993. The major categories of the current ICASE research program are: (1) applied and numerical mathematics, including numerical analysis and algorithm development; (2) theoretical and computational research in fluid mechanics in selected areas of interest to LaRC, including acoustic and combustion; (3) experimental research in transition and turbulence and aerodynamics involving LaRC facilities and scientists; and (4) computer science.

  16. Developing a blended learning based model for teaching foreign languages in engineering institutions

    Directory of Open Access Journals (Sweden)

    Kudryashova Alexandra V.

    2016-01-01

    Full Text Available The present paper deals with studying theoretical and methodical background of the concept of blended learning, which is the major didactic tool of the modern methods of foreign languages teaching. It also considers the principles of integrating blended learning in teaching foreign languages in engineering institutions. The basics of pedagogical modelling used for developing a model of integrating blended learning in the foreign language teaching are defined. The schematic model representation is given and the way of implementing the described model into the educational process is shown via the example of the lesson on “Cohesive devices”.

  17. ENHANCING THE QUALITY OF ENGINEERING EDUCATION INSTITUTIONS (EEIs THROUGH GAP ANALYSIS

    Directory of Open Access Journals (Sweden)

    Sri N. Chandra Shekhar

    2010-12-01

    Full Text Available Engineering will be challenged as n ever before to shape the nature and quality of life in the twenty- first century. Engineering education will be at the forefront of the effort to meet this challenge. The aim of this study was to determine the students' preferences based on the quality gap of various services provided by Engineering Education Institutions (EEIs by using an originally SERVQUAL instrument among fresh engineering graduates. In this study, a total of 200 students who have attended the Graduate Apprenticeship Counseling programme were selected randomly and asked to complete a questionnaire which measured students' perceptions and expectations on services provided by the EEIs. The quality gap of educational services was determined based on differences between students' perception s and expectations on thirty two items of service quality. Factor Analysis (FA was carried out to identify the underlying dimensions in the service quality items. In this study, service quality items having higher quality gap are factor analyzed. The results help to focus on items which need immediate attention to enhance the quality of EEIs.

  18. The Multiple-Institution Database for Investigating Engineering Longitudinal Development: An Experiential Case Study of Data Sharing and Reuse

    Science.gov (United States)

    Ohland, Matthew W.; Long, Russell A.

    2016-01-01

    Sharing longitudinal student record data and merging data from different sources is critical to addressing important questions being asked of higher education. The Multiple-Institution Database for Investigating Engineering Longitudinal Development (MIDFIELD) is a multi-institution, longitudinal, student record level dataset that is used to answer…

  19. Non-radioactive waste management in a Nuclear Energy Research Institution

    Energy Technology Data Exchange (ETDEWEB)

    Furusawa, Helio A.; Martins, Elaine A.J.; Cotrim, Marycel E.B.; Pires, Maria A. F., E-mail: helioaf@ipen.br, E-mail: elaine@ipen.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEM-SP), Sao Paulo, SP (Brazil). Centro de Quimica e Meio Ambiente

    2013-07-01

    For more than 50 years, non-radioactive materials have been used in processes at IPEN to support the nuclear fuel development and all related activities. Reagents, raw materials, products and by-products have been stored. Many of these are hazardous highly toxic or reactants materials. Some years ago actions sent part of these non-radioactive waste materials to proper disposal (technical incineration) resulting in an Institutional Non-Radioactive Waste Management Program. In 2005, an internal set of procedures and information entitled - Guia de Procedimentos para Armazenamento, Tratamento e Descarte de Residuos de Laboratorio Quimico - (Guide of Procedures for Storage, Treatment, and Disposal of Chemistry Laboratory Wastes) - was published to be used at the IPEN's facilities. A data base managed by software was created in order to allow the Units to input data and information about the routinely generated wastes and those already existing. Even after disposing so huge amount of wastes, a latent demand still exists. Several goals were achieved notably a well-organized and roomy space; safer storage places; local, state, and nationwide laws enforcement (for radioactive and non-radioactive materials); and improvement in chemicals control as hazardous and aged materials are more frequently disposed. A special stress was conducted to know and follow laws, regulations, and technical norms as the entire process is very detailed and this is not a day-by-day routine for the IPEN's technical personnel. The immediate consequence is that the safer the workplace the safer the nuclear related activities are done. (author)

  20. 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.

  1. Thermocathode radio-frequency gun for the Budker Institute of Nuclear Physics free-electron laser

    Science.gov (United States)

    Volkov, V.; Getmanov, Ya.; Kenjebulatov, E.; Kolobanov, E.; Krutikhin, S.; Kurkin, G.; Ovchar, V.; Petrov, V. M.; Sedlyarov, I.

    2016-12-01

    A radio-frequency (RF) gun for a race-track microtron-recuperator injector driving the free-electron laser (FEL) (Budker Institute of Nuclear Physics) is being tested at a special stand. Electron bunches of the RF gun have an energy of up to 300 keV and a repetition rate of up to 90 MHz. The average electro-beam current can reach 100 mA in the continuous operation regime. The advantages of the new injector are as follows: long lifetime of the cathode for high average beam current; simple scheme of longitudinal beam bunching, which does not require an additional bunching resonator in the injector; absence of dark-current contamination of the injector beam; and comfortable RF gun operation due to the absence of a high potential of 300 kV at the cathode control circuits. In this study we describe the RF gun design, present the main characteristics of the injector with the RF gun, and give the results of testing.

  2. The radioisotope complex project “RIC-80” at the Petersburg Nuclear Physics Institute

    Energy Technology Data Exchange (ETDEWEB)

    Panteleev, V. N., E-mail: vnp@pnpi.spb.ru; Barzakh, A. E.; Batist, L. Kh.; Fedorov, D. V.; Ivanov, V. S.; Moroz, F. V.; Molkanov, P. L.; Orlov, S. Yu.; Volkov, Yu. M. [NRC “Kurchatov Institute” PNPI, 188300 Gatchina (Russian Federation)

    2015-12-15

    The high current cyclotron C-80 capable of producing 40-80 MeV proton beams with a current of up to 200 μA has been constructed at Petersburg Nuclear Physics Institute. One of the main goals of the C-80 is the production of a wide spectrum of medical radionuclides for diagnostics and therapy. The project development of the radioisotope complex RIC-80 (radioisotopes at the cyclotron C-80) at the beam of C-80 has been completed. The RIC-80 complex is briefly discussed in this paper. The combination of the mass-separator with the target-ion source device, available at one of the new target stations for on-line or semi on-line production of a high purity separated radioisotopes, is explored in greater detail. The results of target and ion source tests for a mass-separator method for the production of high purity radioisotopes {sup 82}Sr and {sup 223,224}Ra are also presented.

  3. Comparative analysis of publications on nuclear field in the world, Ukraine and in the institute for nuclear research of the national academy of sciences of Ukraine

    CERN Document Server

    Trofimenko, A P; Lipska, A Y

    2003-01-01

    Comparative analysis of publications in the world, in Ukraine and in the Institute for Nuclear Research of NAS of Ukraine (INR) in nuclear physics and other directions of INR research was performed. Conclusions about the intensity of research, contribution of Ukraine in this research and the INR role in it are presented. It is shown that 30 % of Ukrainian publications in nuclear physics, and about 8 % of them in other fields belong to the INR. Part of Ukrainian authors who publish their works in Ukraine and abroad, as well as the part of foreign authors publishing in Ukraine is shown. Distribution of the INR publications among 16 countries is indicated. Ths mentioned information can be used for profound study of research in Ukraine and INR.

  4. Institute for Nuclear Theory annual report No. 2, 1 March 1991--29 February 1992

    Energy Technology Data Exchange (ETDEWEB)

    Haxton, W.; Henley, E. M. [Washington Univ., Seattle, WA (United States). Dept. of Physics

    1992-01-01

    This report discusses research on the following topics in Nuclear physics: electromagnetic interactions and few-nucleon systems; N*'s and nucleon structure; mesons and fields in nuclei; and nuclear astrophysics of type II supernovae. (LSP).

  5. An improved heat transfer configuration for a solid-core nuclear thermal rocket engine

    Science.gov (United States)

    Clark, John S.; Walton, James T.; Mcguire, Melissa L.

    1992-01-01

    Interrupted flow, impingement cooling, and axial power distribution are employed to enhance the heat-transfer configuration of a solid-core nuclear thermal rocket engine. Impingement cooling is introduced to increase the local heat-transfer coefficients between the reactor material and the coolants. Increased fuel loading is used at the inlet end of the reactor to enhance heat-transfer capability where the temperature differences are the greatest. A thermal-hydraulics computer program for an unfueled NERVA reactor core is employed to analyze the proposed configuration with attention given to uniform fuel loading, number of channels through the impingement wafers, fuel-element length, mass-flow rate, and wafer gap. The impingement wafer concept (IWC) is shown to have heat-transfer characteristics that are better than those of the NERVA-derived reactor at 2500 K. The IWC concept is argued to be an effective heat-transfer configuration for solid-core nuclear thermal rocket engines.

  6. Utilization Practice of the Concept Mapping Program for Nuclear Engineer Training

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bae Joo; Ko, Byung Moo; Heo, Yuk [Korea Hydro and Nuclear Power, Daejeon (Korea, Republic of)

    2009-05-15

    Knowledge is the most important factor in the safe and reliable operation of the NPP. Many methods are used to enhance the knowledge level of the personnel in the NPP. Generally, classroom lecture method is used for nuclear engineers. But this method has some pitfalls as an adult training method because students have already a lot of knowledge, so they want to participate actively in the learning process. KNPEI undertook a research project from March 2006 to September 2007 to capture the experience knowledge from senior staff and transfer it to junior staff. As part of the research activity KNPEI introduced a Concept Mapping Program and set up a Concept Mapping server to capture the experience knowledge of the senior staff. This Concept Mapping Program has some characteristics that can be used in learning about conceptual knowledge. The purpose of this report is to introduce the utilization method and practice at KNPEI for the nuclear engineer training using the Concept Mapping Program.

  7. Reverse engineering nuclear properties from rare earth abundances in the r process

    Science.gov (United States)

    Mumpower, M. R.; McLaughlin, G. C.; Surman, R.; Steiner, A. W.

    2017-03-01

    The bulk of the rare earth elements are believed to be synthesized in the rapid neutron capture process or r process of nucleosynthesis. The solar r-process residuals show a small peak in the rare earths around A∼ 160, which is proposed to be formed dynamically during the end phase of the r process by a pileup of material. This abundance feature is of particular importance as it is sensitive to both the nuclear physics inputs and the astrophysical conditions of the main r process. We explore the formation of the rare earth peak from the perspective of an inverse problem, using Monte Carlo studies of nuclear masses to investigate the unknown nuclear properties required to best match rare earth abundance sector of the solar isotopic residuals. When nuclear masses are changed, we recalculate the relevant β-decay properties and neutron capture rates in the rare earth region. The feedback provided by this observational constraint allows for the reverse engineering of nuclear properties far from stability where no experimental information exists. We investigate a range of astrophysical conditions with this method and show how these lead to different predictions in the nuclear properties influential to the formation of the rare earth peak. We conclude that targeted experimental campaigns in this region will help to resolve the type of conditions responsible for the production of the rare earth nuclei, and will provide new insights into the longstanding problem of the astrophysical site(s) of the r process.

  8. Pluronic F127 nanomicelles engineered with nuclear localized functionality for targeted drug delivery.

    Science.gov (United States)

    Li, Yong-Yong; Li, Lan; Dong, Hai-Qing; Cai, Xiao-Jun; Ren, Tian-Bin

    2013-07-01

    PKKKRKV (Pro-Lys-Lys-Lys-Arg-Lys-Val, PV7), a seven amino acid peptide, has emerged as one of the primary nuclear localization signals that can be targeted into cell nucleus via the nuclear import machinery. Taking advantage of chemical diversity and biological activities of this short peptide sequence, in this study, Pluronic F127 nanomicelles engineered with nuclear localized functionality were successfully developed for intracellular drug delivery. These nanomicelles with the size ~100 nm were self-assembled from F127 polymer that was flanked with two PV7 sequences at its both terminal ends. Hydrophobic anticancer drug doxorubicin (DOX) with inherent fluorescence was chosen as the model drug, which was found to be efficiently encapsulated into nanomicelles with the encapsulation efficiency at 72.68%. In comparison with the non-functionalized namomicelles, the microscopic observation reveals that PV7 functionalized nanomicelles display a higher cellular uptake, especially into the nucleus of HepG2 cells, due to the nuclear localization signal effects. Both cytotoxicity and apoptosis studies show that the DOX-loaded nanomicelles were more potent than drug nanomicelles without nuclear targeting functionality. It was thus concluded that PV7 functionalized nanomicelles could be a potentially alternative vehicle for nuclear targeting drug delivery.

  9. Nuclear chemistry and geochemistry research. Carnegie Institute of Technology and Carnegie--Mellon University. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    Kohman, T.P.

    1976-05-28

    A summary is presented of the activities and results of research in nuclear chemistry, nuclear geochemistry, nuclear cosmochemistry, and other minor areas from 1950 to 1976. A complete listing is given of publications, doctoral dissertations, and reports resulting from the research. A chronological list provides an overview of the activities at any particular time. (JSR)

  10. Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge

    Energy Technology Data Exchange (ETDEWEB)

    Smith, M.J.

    1980-05-01

    This document represents a compilation of data and interpretive studies conducted as part of the engineered barriers program of the Basalt Waste Isolation Project. The overall objective of these studies is to provide information on barrier system designs, emplacement and isolation techniques, and chemical reactions expected in a nuclear waste repository located in the basalts underlying the Hanford Site within the state of Washington. Backfills, waste-basalt interactions, sorption, borehole plugging, etc., are among the topics discussed.

  11. "Cloud" functions and templates of engineering calculations for nuclear power plants

    Science.gov (United States)

    Ochkov, V. F.; Orlov, K. A.; Ko, Chzho Ko

    2014-10-01

    The article deals with an important problem of setting up computer-aided design calculations of various circuit configurations and power equipment carried out using the templates and standard computer programs available in the Internet. Information about the developed Internet-based technology for carrying out such calculations using the templates accessible in the Mathcad Prime software package is given. The technology is considered taking as an example the solution of two problems relating to the field of nuclear power engineering.

  12. THE DEVELOPMENT OF AN ENTERPRISE RESOURCE PLANNING SYSTEM (ERP FOR A RESEARCH AND TECHNOLOGY INSTITUTE: THE CASE OF THE NUCLEAR AND ENERGY RESEARCH INSTITUTE -IPEN

    Directory of Open Access Journals (Sweden)

    Willy Hoppe de Souza

    2011-05-01

    Full Text Available This paper reports the history of the development of an enterprise resource planning (ERP dedicated to managing the technical activities of the Nuclear and Energy Research Institute, a governmental research and technology institute in Brazil. After the implementation of the new planning process, the development of a new management information system named SIGEPI was immediately initiated. The implementation of this system followed a strategy of integrating databases already available and developing new ones in order to facilitate the data collecting process and to improve the quality and the reliability of these data. This paper describes the evolution of SIGEPI, its main features and it also reports the difficulties faced for almost ten years of developments. The success factors of the case were classified into three groups: strategic, technical and behavioral ones. The impact of these factors and recommendation for future similar developments are presented.

  13. THE DEVELOPMENT OF AN ENTERPRISE RESOURCE PLANNING SYSTEM (ERP FOR A RESEARCH AND TECHNOLOGY INSTITUTE: THE CASE OF THE NUCLEAR AND ENERGY RESEARCH INSTITUTE -IPEN

    Directory of Open Access Journals (Sweden)

    Willy Hoppe de Souza

    2011-01-01

    Full Text Available This paper reports the history of the development of an enterprise resource planning (ERPdedicated to managing the technical activities of the Nuclear and Energy Research Institute, agovernmental research and technology institute in Brazil. After the implementation of the newplanning process, the development of a new management information system named SIGEPIwas immediately initiated. The implementation of this system followed a strategy of integratingdatabases already available and developing new ones in order to facilitate the data collectingprocess and to improve the quality and the reliability of these data. This paper describes theevolution of SIGEPI, its main features and it also reports the difficulties faced for almost tenyears of developments. The success factors of the case were classified into three groups:strategic, technical and behavioral ones. The impact of these factors and recommendation forfuture similar developments are presented.

  14. Enrico Fermi and the Physics and Engineering of a nuclear pile: the retrieval of novel documents

    CERN Document Server

    Esposito, S

    2008-01-01

    We give a detailed account of the recent retrieval of a consistent amount (about 600 pages) of documents written by Enrico Fermi and/or his collaborators, coming from different sources previously unexplored. These documents include articles, patents, reports, notes on scientific and technical meetings and other papers, mainly testifying Fermi's activity in the 1940s about nuclear pile physics and engineering. All of them have been carefully described, pointing out the relevance of the given papers for their scientific or even historical content. From the analysis of these papers, a number of important scientific and technical points comes out, putting a truly new light on the Fermi's (and others') scientific activity about nuclear piles and their applications. Quite unexpectedly intriguing historical remarks, such as those regarding the relationships between U.S. and Britain, just after the end of the war, about nuclear power for pacific and/or military use, or even regarding long term physics research and po...

  15. [Prospects of systemic radioecology in solving innovative tasks of nuclear power engineering].

    Science.gov (United States)

    Spiridonov, S I

    2014-01-01

    A need of systemic radioecological studies in the strategy developed by the atomic industry in Russia in the XXI century has been justified. The priorities in the radioecology of nuclear power engineering of natural safety associated with the development of the radiation-migration equivalence concept, comparative evaluation of innovative nuclear technologies and forecasting methods of various emergencies have been identified. Also described is an algorithm for the integrated solution of these tasks that includes elaboration of methodological approaches, methods and software allowing dose burdens to humans and biota to be estimated. The rationale of using radioecological risks for the analysis of uncertainties in the environmental contamination impacts,at different stages of the existing and innovative nuclear fuel cycles is shown.

  16. The MaPLE device of Saha Institute of Nuclear Physics: construction and its plasma aspects.

    Science.gov (United States)

    Pal, Rabindranath; Biswas, Subir; Basu, Subhasis; Chattopadhyay, Monobir; Basu, Debjyoti; Chaudhuri, Manis; Chowdhuri, Manis

    2010-07-01

    The Magnetized Plasma Linear Experimental (MaPLE) device is a low cost laboratory plasma device at Saha Institute of Nuclear Physics fabricated in-house with the primary aim of studying basic plasma physics phenomena such as plasma instabilities, wave propagation, and their nonlinear behavior in magnetized plasma regime in a controlled manner. The machine is specially designed to be a versatile laboratory device that can provide a number of magnetic and electric scenario to facilitate such studies. A total of 36 number of 20-turn magnet coils, designed such as to allow easy handling, is capable of producing a uniform, dc magnetic field of about 0.35 T inside the plasma chamber of diameter 0.30 m. Support structure of the coils is planned in an innovative way facilitating straightforward fabrication and easy positioning of the coils. Further special feature lies in the arrangement of the spacers between the coils that can be maneuvered rather easily to create different magnetic configurations. Various methods of plasma production can be suitably utilized according to the experimental needs at either end of the vacuum vessel. In the present paper, characteristics of a steady state plasma generated by electron cyclotron resonance method using 2.45 GHz microwave power are presented. Scans using simple probe drives revealed that a uniform and long plasma column having electron density approximately 3-5x10(10) cm(-3) and temperature approximately 7-10 eV, is formed in the center of the plasma chamber which is suitable for wave launching experiments.

  17. Complex composite engineering architectures for nuclear and high-radiation environments

    Energy Technology Data Exchange (ETDEWEB)

    Kornreich, Drew E [Los Alamos National Laboratory; Vaidya, Rajendra U [Los Alamos National Laboratory; Ammerman, Curtt N [Los Alamos National Laboratory

    2010-01-01

    Integrated Computational Materials Engineering (ICME) is a novel overarching approach to bridge length and time scales in computational materials science and engineering. This approach integrates all elements of multi-scale modeling (including various empirical and science-based models) with materials informatics to provide users the opportunity to tailor material selections based on stringent application needs. Typically, materials engineering has focused on structural requirements (stress, strain, modulus, fracture toughness etc.) while multi-scale modeling has been science focused (mechanical threshold strength model, grain-size models, solid-solution strengthening models etc.). Materials informatics (mechanical property inventories) on the other hand, is extensively data focused. All of these elements are combined within the framework of ICME to create architecture for the development, selection and design new composite materials for challenging environments. We propose development of the foundations for applying ICME to composite materials development for nuclear and high-radiation environments (including nuclear-fusion energy reactors, nuclear-fission reactors, and accelerators). We expect to combine all elements of current material models (including thermo-mechanical and finite-element models) into the ICME framework. This will be accomplished through the use of a various mathematical modeling constructs. These constructs will allow the integration of constituent models, which in tum would allow us to use the adaptive strengths of using a combinatorial scheme (fabrication and computational) for creating new composite materials. A sample problem where these concepts are used is provided in this summary.

  18. Pluronic F127 nanomicelles engineered with nuclear localized functionality for targeted drug delivery

    Energy Technology Data Exchange (ETDEWEB)

    Li, Yong-Yong; Li, Lan; Dong, Hai-Qing, E-mail: inano_donghq@tongji.edu.cn; Cai, Xiao-Jun; Ren, Tian-Bin, E-mail: rentianbin@yeah.net

    2013-07-01

    PKKKRKV (Pro-Lys-Lys-Lys-Arg-Lys-Val, PV7), a seven amino acid peptide, has emerged as one of the primary nuclear localization signals that can be targeted into cell nucleus via the nuclear import machinery. Taking advantage of chemical diversity and biological activities of this short peptide sequence, in this study, Pluronic F127 nanomicelles engineered with nuclear localized functionality were successfully developed for intracellular drug delivery. These nanomicelles with the size ∼ 100 nm were self-assembled from F127 polymer that was flanked with two PV7 sequences at its both terminal ends. Hydrophobic anticancer drug doxorubicin (DOX) with inherent fluorescence was chosen as the model drug, which was found to be efficiently encapsulated into nanomicelles with the encapsulation efficiency at 72.68%. In comparison with the non-functionalized namomicelles, the microscopic observation reveals that PV7 functionalized nanomicelles display a higher cellular uptake, especially into the nucleus of HepG2 cells, due to the nuclear localization signal effects. Both cytotoxicity and apoptosis studies show that the DOX-loaded nanomicelles were more potent than drug nanomicelles without nuclear targeting functionality. It was thus concluded that PV7 functionalized nanomicelles could be a potentially alternative vehicle for nuclear targeting drug delivery. - Highlights: ► A new nuclear targeted drug delivery system based on micelles is developed. ► This micellar system features a core-shell structure with the size peaked at 100 nm. ► PV7, a short peptide sequence, is adopted as a nuclear targeting ligand. ► PV7 functionalized drug loaded micelles are more potent in killing tumor cells.

  19. From Nanostructure to Nano Biosensor: Institute of Nano Electronic Engineering (INEE, UniMAP Experience

    Directory of Open Access Journals (Sweden)

    U Hashim

    2012-02-01

    Full Text Available Nanostructure is defined as something that has a physical dimension smaller than 100 nanometers, ranging from clusters and/or to dimensional layers of atoms. There are three most important nanostructures that are extensively studied and researched in various organizations including Institute of Nano Electronic Engineering (INEE in UniMAP. These include quantum dot, nanowire, and nanogap, which have been successfully designed and fabricated using in-house facilities available. These are subsequently used as a main sensing component in nanostructures based biosensor. This fabrication, characterization and testing job were done within four main interlinked laboratories namely microfabrication cleanroom, nanofabrication cleanroom, failure analysis laboratory and nano biochip laboratory.  Currently, development of Nano Biosensor is the main research focus in INEE. In principle, biosensor is an analytical device which converts a biological response into an electrical signal.   Keywords: Nanostructure, INEE , nanowire , nanogap and Nano Biosensor

  20. NATO Advanced Study Institute on Synthetic Membranes : Science, Engineering and Applications

    CERN Document Server

    Lonsdale, H; Pinho, M

    1986-01-01

    The chapters in this book are based upon lectures given at the NATO Advanced Study Institute on Synthetic Membranes (June 26-July 8, 1983, Alcabideche, Portugal), which provided an integrated presentation of syn­ thetic membrane science and technology in three broad areas. Currently available membrane formation mechanisms are reviewed, as well as the manner in which synthesis conditions can be controlled to achieve desired membrane structures. Membrane performance in a specific separa­ tionprocess involves complex phenomena, the understanding of which re­ quires a multidisciplinary approach encompassing polymer chemistry, phys­ ical chemistry, and chemical engineering. Progress toward a global understanding of membrane phenomena is described in chapters on the principles of membrane transport. The chapters on membrane processes and applications highlight both established and emerging membrane processes, and elucidate their myriad applications. It is our hope that this book will be an enduring, comprehensi...

  1. 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, ...

  2. Nuclear Engine System Simulation (NESS). Version 2.0: Program user's guide

    Science.gov (United States)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman

    1993-01-01

    This Program User's Guide discusses the Nuclear Thermal Propulsion (NTP) engine system design features and capabilities modeled in the Nuclear Engine System Simulation (NESS): Version 2.0 program (referred to as NESS throughout the remainder of this document), as well as its operation. NESS was upgraded to include many new modeling capabilities not available in the original version delivered to NASA LeRC in Dec. 1991, NESS's new features include the following: (1) an improved input format; (2) an advanced solid-core NERVA-type reactor system model (ENABLER 2); (3) a bleed-cycle engine system option; (4) an axial-turbopump design option; (5) an automated pump-out turbopump assembly sizing option; (6) an off-design gas generator engine cycle design option; (7) updated hydrogen properties; (8) an improved output format; and (9) personal computer operation capability. Sample design cases are presented in the user's guide that demonstrate many of the new features associated with this upgraded version of NESS, as well as design modeling features associated with the original version of NESS.

  3. International Joint Project of Engineering Design Education among Three Institutions in Japan, U.S. and Singapore

    Science.gov (United States)

    Matsuishi, Masakatsu; Takemata, Kazuya; Furukawa, Tetsuro; Sanders, Wayne; Loo, Chin Non

    An international joint program of Engineering Design has started in 2004 between Kanazawa Institute of Technology, Singapore Polytechnic in Singapore, and Rose-Hulman Institute of Technology in the United States. Students from the three institutions worked on the same engineering design project, the main theme of which was, “Bus Transportation/Urban Transportation System in the 21st Century”. Student teams chose their own project themes from specific design areas, which were related to the main theme. Their achievements were unique in their solutions due to the differences in society and culture in Japan, the United States and Singapore, although all the design teams followed the same engineering design procedures. In this paper, the international joint project is discussed in details.

  4. Engineered Zircaloy Cladding Modifications for Improved Accident Tolerance of LWR Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Heuser, Brent [Univ. of Illinois, Urbana-Champaign, IL (United States); Stubbins, James [Univ. of Illinois, Urbana-Champaign, IL (United States); Kozlowski, Tomasz [Univ. of Illinois, Urbana-Champaign, IL (United States); Uddin, Rizwan [Univ. of Illinois, Urbana-Champaign, IL (United States); Trinkle, Dallas [Univ. of Illinois, Urbana-Champaign, IL (United States); Downar, Thoms [Univ. of Michigan, Ann Arbor, MI (United States); Was, Gary [Univ. of Michigan, Ann Arbor, MI (United States); ang, Yong [Univ. of Florida, Gainesville, FL (United States); Phillpot, Simon [Univ. of Florida, Gainesville, FL (United States); Sabharwall, piyush [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-07-25

    The DOE NEUP sponsored IRP on accident tolerant fuel (ATF) entitled Engineered Zircaloy Cladding Modifications for Improved Accident Tolerance of LWR Nuclear Fuel involved three academic institutions, Idaho National Laboratory (INL), and ATI Materials (ATI). Detailed descriptions of the work at the University of Illinois (UIUC, prime), the University of Florida (UF), the University of Michigan (UMich), and INL are included in this document as separate sections. This summary provides a synopsis of the work performed across the IRP team. Two ATF solution pathways were initially proposed, coatings on monolithic Zr-based LWR cladding material and selfhealing modifications of Zr-based alloys. The coating pathway was extensively investigated, both experimentally and in computations. Experimental activities related to ATF coatings were centered at UIUC, UF, and UMich and involved coating development and testing, and ion irradiation. Neutronic and thermal hydraulic aspects of ATF coatings were the focus of computational work at UIUC and UMich, while materials science aspects were the focus of computational work at UF and INL. ATI provided monolithic Zircaloy 2 and 4 material and a binary Zr-Y alloy material. The selfhealing pathway was investigated with advanced computations only. Beryllium was identified as a valid self-healing additive early in this work. However, all attempts to fabricate a Zr-Be alloy failed. Several avenues of fabrication were explored. ATI ultimately declined our fabrication request over health concerns associated with Be (we note that Be was not part of the original work scope and the ATI SOW). Likewise, Ames Laboratory declined our fabrication request, citing known litigation dating to the 1980s and 1990s involving the U.S. Federal government and U.S. National Laboratory employees involving the use of Be. Materion (formerly, Brush Wellman) also declined our fabrication request, citing the difficulty in working with a highly reactive Zr and Be

  5. Success factors of Black science, technology, engineering and mathematics faculty at predominantly White institutions

    Science.gov (United States)

    Currie, Michelle A.

    Black faculty at predominantly White institutions (PWIs) have historically been underrepresented and made to endure with academic isolation, scholarship marginalization and other challenges to the tenure process. When it comes to science, technology, engineering and math, also known as STEM, as it relates to race and success, little is known of how tenured Black STEM faculty have developed an interest in STEM, navigated the unfamiliar waters of academia and maintained longevity at their respective postsecondary institutions. The purpose of this study is to look at the similar experiences of this population and provide insight regarding any factors and or influences that have impacted their success. Grounded in critical race theory (CRT), this qualitative study will utilize a Delphi technique to determine the similar experiences and influences of 17 Black STEM, tenured (and tenure-track) faculty working at PWIs in a Southern Regional Education Board (SREB) states. The study highlighted the importance of: mentoring in college, graduate school and as a junior faculty and; STEM related opportunities such as summer camps or programs, internships, and research.

  6. Engineering

    National Research Council Canada - National Science Library

    Includes papers in the following fields: Aerospace Engineering, Agricultural Engineering, Chemical Engineering, Civil Engineering, Electrical Engineering, Environmental Engineering, Industrial Engineering, Materials Engineering, Mechanical...

  7. Reverse engineering nuclear properties from rare earth abundances in the $r$ process

    CERN Document Server

    Mumpower, M R; Surman, R; Steiner, A W

    2016-01-01

    The bulk of the rare earth elements are believed to be synthesized in the rapid neutron capture process or $r$ process of nucleosynthesis. The solar $r$-process residuals show a small peak in the rare earths around $A\\sim 160$, which is proposed to be formed dynamically during the end phase of the $r$ process by a pileup of material. This abundance feature is of particular importance as it is sensitive to both the nuclear physics inputs and the astrophysical conditions of the main $r$ process. We explore the formation of the rare earth peak from the perspective of an inverse problem, using Monte Carlo studies of nuclear masses to investigate the unknown nuclear properties required to best match rare earth abundance sector of the solar isotopic residuals. When nuclear masses are changed, we recalculate the relevant $\\beta$-decay properties and neutron capture rates in the rare earth region. The feedback provided by this observational constraint allows for the reverse engineering of nuclear properties far from ...

  8. Engineering and management experience at Texas A&M Transportation Institute

    Science.gov (United States)

    Chowdhury, Arif Tahjibul

    This manuscript presents the author's engineering and management experience during his internship in the Materials and Pavements (M&P) Division at the Texas A&M Transportation Institute (TTI), and is a record of study for the Doctor of Engineering at Texas A&M University. Through this internship, he met his established internship objectives of gaining technical knowledge as well as knowledge and skills in project management, organizational communication, and quality management of pavement condition data, and of attaining professional development. In meeting these objectives, the author describes the history, mission, and organizational structure of his workplace. He also presents his experience of developing and delivering a two-week training course on pavement design and construction in Kosovo. Participating in a number of professional development training courses and other activities prepared him for working as an engineering manager. These activities include Delta-T leadership training, an instructor development course, a time management and organizational skills course, and the M&P Division lecture series. Leadership and skills learned through the Delta-T program were beneficial for the employee as well as the employer. For the class project, the author and his teammates performed a study dealing with improving TTI's deliverables. The Delta-T team composed a report summarizing their efforts of examining the current state of TTI's project deliverables, the deliverables' shortcomings, and potential enhancements to expand the deliverables' appeal to additional types of potential users outside the traditional research community. The team also developed a prototype web-based model of deliverables and presented some implementation recommendations. Participating in the Texas Department of Transportation's (TxDOT's) pavement surface distress data collection program enabled the author to become familiar with pavement distress data quality management and thus attain the

  9. 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.

  10. Interdisciplinary Team-Teaching Experience for a Computer and Nuclear Energy Course for Electrical and Computer Engineering Students

    Science.gov (United States)

    Kim, Charles; Jackson, Deborah; Keiller, Peter

    2016-01-01

    A new, interdisciplinary, team-taught course has been designed to educate students in Electrical and Computer Engineering (ECE) so that they can respond to global and urgent issues concerning computer control systems in nuclear power plants. This paper discusses our experience and assessment of the interdisciplinary computer and nuclear energy…

  11. A Study to Determine the Basic Science and Mathematics Topics Most Needed by Engineering Technology Graduates of Wake Technical Institute in Performing Job Duties.

    Science.gov (United States)

    Edwards, Timothy I.; Roberson, Clarence E., Jr.

    A survey of 470 graduates of the six engineering technology programs at Wake Technical Institute--Architectural, Chemical, Civil Engineering, Computer, Electronic Engineering, and Industrial Engineering Technologies--and 227 of their employers was conducted in October, 1979, to determine the science and mathematics topics most needed by…

  12. Joining the Nuclear Renaissance with the Engineering Business Unit of AREVA

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, Nathalie; Menguy, Stephane [SGN, AREVA Group, 1 rue des Herons, 78182 Saint-Quentin en Yvelines Cedex (France); Valery, Jean-Francois [AREVA NC, AREVA Group, Tour AREVA, 1 place de la Coupole, 92084 Paris La Defense Cedex (France)

    2008-07-01

    The reality of the nuclear renaissance is no longer a question. All over the world, new nuclear plants are going to be deployed; the whole fuel cycle has to be adjusted to fulfil their needs, the front-end to produce the fuel and the back-end to properly manage radioactive waste. AREVA fuel cycle engineering teams have been involved in the design of a variety of industrial plants covering the entire fuel cycle for 50 years. The consistency of the French nuclear policy has been a major factor to acquire and renew the competencies and workforce of AREVA Engineering Business Unit. Our partnership with our customers, French ones but also Japanese, Americans and from other countries, has led us to develop a comprehensive approach of the services that we can deliver, in order to give them the best answer. SGN teams have been involved in the R and D phases in order to take into account the industrialisation aspects as early as possible, and our work does not end with the delivery of the plants; it includes assistance to the operators to optimise and keep their facilities in line with the changing rules and constraints, which ensures the integration of a wide operational experience feedback and the ability to design flexible facilities. This paper will present through our experience how this global approach has been developed and continuously improved and how we are preparing our teams to be ready to answer to the coming needs. (authors)

  13. The institutional change towards a self managing organization case study: NEL Nuclear Electronics Company

    OpenAIRE

    Köseoğlu, Dilek

    1992-01-01

    Ankara : The Department of Management and The Institute of Business Administration of Bilkent University, 1992. Thesis (Master's) -- Bilkent University, 1992. Includes bibliographical references leaves 68-71. Toward 2000's the institution building process is a becoitiming phenomenon. The term institution is generally understood as a large bureaucratic organizations. From the extensive literature survey it is observed that little has been written from the human resources p...

  14. The Need for Cyber-Informed Engineering Expertise for Nuclear Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, Robert Stephen [Idaho National Laboratory

    2015-12-01

    Engineering disciplines may not currently understand or fully embrace cyber security aspects as they apply towards analysis, design, operation, and maintenance of nuclear research reactors. Research reactors include a wide range of diverse co-located facilities and designs necessary to meet specific operational research objectives. Because of the nature of research reactors (reduced thermal energy and fission product inventory), hazards and risks may not have received the same scrutiny as normally associated with power reactors. Similarly, security may not have been emphasized either. However, the lack of sound cybersecurity defenses may lead to both safety and security impacts. Risk management methodologies may not contain the foundational assumptions required to address the intelligent adversary’s capabilities in malevolent cyber attacks. Although most research reactors are old and may not have the same digital footprint as newer facilities, any digital instrument and control function must be considered as a potential attack platform that can lead to sabotage or theft of nuclear material, especially for some research reactors that store highly enriched uranium. This paper will provide a discussion about the need for cyber-informed engineering practices that include the entire engineering lifecycle. Cyber-informed engineering as referenced in this paper is the inclusion of cybersecurity aspects into the engineering process. A discussion will consider several attributes of this process evaluating the long-term goal of developing additional cyber safety basis analysis and trust principles. With a culture of free information sharing exchanges, and potentially a lack of security expertise, new risk analysis and design methodologies need to be developed to address this rapidly evolving (cyber) threatscape.

  15. A field release of genetically engineered gypsy moth (Lymantria dispar L.) Nuclear Polyhedrosis Virus (LdNPV)

    Science.gov (United States)

    Vincent D' Amico; Joseph S. Elkinton; John D. Podgwaite; James M. Slavicek; Michael L. McManus; John P. Burand

    1999-01-01

    The gypsy moth (Lymantria dispar L.) nuclear polyhedrosis virus was genetically engineered for nonpersistence by removal of the gene coding for polyhedrin production and stabilized using a coocclusion process. A β-galactosidase marker gene was inserted into the genetically engineered virus (LdGEV) so that infected larvae could be tested for...

  16. NUPEC (Nuclear Power Engineering Corporation) annual report 1998, activities in fiscal 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    NUPEC was founded in March, 1976 under the initiative of scholars and private corporations including electric power companies, electric machinery and general construction companies. Ever since, NUPEC has been proceeding with its operations to meet the needs of the times with the support and cooperation of the government and academic circles. The specific activities so far include solving problems in the initial stage of light water reactors(LWRs) operation, engineering tests for improvement and standardization programs to develop domestic LWRs, seismic technology development and testing, assistance with accident analysis during safety examinations by government agency, human factor research, safety analysis of nuclear facilities, research of safety-related information, countermeasures for aging of LWRs and public acceptance activities. For such purposes, NUPEC has engineering laboratories in Tadotsu, Takasago, Isogo and Katsuta as well as a high performance parallel computer system for safety analysis at its headquarters. Among these facilities, the large-scale high-performance shaking table at Tadotsu Engineering Laboratory is attracting international attention for its capability for seismic testing. NUPEC is actively promoting international cooperation with international organizations and partners in the U.S., France, Germany, Russia and Asian countries through joint projects, information exchange, etc. NUPEC`s testing and analysis have contributed to improvement of safety and credibility of Nuclear power generation and to establishment and improvement of Japanese-originated LWR technology. A summary of our achievements in fiscal 1997 is presented in this annual report. (J.P.N.)

  17. [The characteristics of morbidity of workers of nuclear power engineering enterprise].

    Science.gov (United States)

    Pischugina, A V; Ivanov, A G; Belyakova, N A

    2013-01-01

    The article considers the morbidity endocrine, pathology included, of workers of nuclear power station and body-abled population of the district employed in other areas of professional activities. The statistically reliable exceeding of the level of primarily diagnosed endocrine morbidity in the group of working population of the district as compared with the group of workers of nuclear power station is established. In the compared groups, the structure of pathology of endocrine system is characterized by the prevalence of diseases of thyroid gland and obesity. The official statistics data reflects the level of morbidity of working population depending on appealability to curative preventive institutions, ratio and scope of the periodic medical examinations, availability of shop therapeutic service and possibility to involve physicians-specialists to health posts enterprises. Therefore, the foundation of enhancement of quality of medical care to workers is the improvemnent of organizational activities at the level of primary health care.

  18. "A pesar de todo" (Despite Everything): The Persistence of Latina Graduate Engineering Students at a Hispanic-Serving Institution

    Science.gov (United States)

    Aguirre-Covarrubias, Sandra; Arellano, Eduardo; Espinoza, Penelope

    2015-01-01

    This chapter discusses a mixed-methods study of personal and programmatic factors that affected persistence of Latina graduate engineering students at a Hispanic-serving institution (HSI). The study's findings enabled us to share recommendations that may be useful to HSIs and other colleges and universities.

  19. Gender Equality in Public Higher Education Institutions of Ethiopia: The Case of Science, Technology, Engineering, and Mathematics

    Science.gov (United States)

    Egne, Robsan Margo

    2014-01-01

    Ensuring gender equality in higher education system is high on the agenda worldwide particularly in science disciplines. This study explores the problems and prospects of gender equality in public higher education institutions of Ethiopia, especially in science, technology, engineering, and mathematics. Descriptive survey and analytical research…

  20. "A pesar de todo" (Despite Everything): The Persistence of Latina Graduate Engineering Students at a Hispanic-Serving Institution

    Science.gov (United States)

    Aguirre-Covarrubias, Sandra; Arellano, Eduardo; Espinoza, Penelope

    2015-01-01

    This chapter discusses a mixed-methods study of personal and programmatic factors that affected persistence of Latina graduate engineering students at a Hispanic-serving institution (HSI). The study's findings enabled us to share recommendations that may be useful to HSIs and other colleges and universities.

  1. Gender Equality in Public Higher Education Institutions of Ethiopia: The Case of Science, Technology, Engineering, and Mathematics

    Science.gov (United States)

    Egne, Robsan Margo

    2014-01-01

    Ensuring gender equality in higher education system is high on the agenda worldwide particularly in science disciplines. This study explores the problems and prospects of gender equality in public higher education institutions of Ethiopia, especially in science, technology, engineering, and mathematics. Descriptive survey and analytical research…

  2. Concept study of a hydrogen containment process during nuclear thermal engine ground testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric T.; Canabal, Francisco

    A new hydrogen containment process was proposed for ground testing of a nuclear thermal engine. It utilizes two thermophysical steps to contain the hydrogen exhaust. First, the decomposition of hydrogen through oxygen-rich combustion at higher temperature; second, the recombination of remaining hydrogen with radicals at low temperature. This is achieved with two unit operations: an oxygen-rich burner and a tubular heat exchanger. A computational fluid dynamics methodology was used to analyze the entire process on a three-dimensional domain. The computed flammability at the exit of the heat exchanger was less than the lower flammability limit, confirming the hydrogen containment capability of the proposed process.

  3. 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.

  4. The use of low power dual mode nuclear thermal rocket engines to support space exploration missions

    Science.gov (United States)

    Zubrin, Robert M.

    1991-01-01

    The evolution of dual mode concepts is presented, focusing on advantages and problems associated with both low and high temperature dual mode conversion systems. It is concluded that dual mode nuclear thermal rocket (NTR) systems using high temperature Brayton cycle conversion technology offer a high payoff enhancement of conventional NTR, with a comparatively minor increase of technological challenge. It is recommended that NTR engines be designed so that dual mode conversion systems can be attached to them in a modular way, thus enabling the production of electric power on all missions where it is needed.

  5. Environmental dose in the Nuclear Medicine Department of the National Institute of Cancer;Dosis ambiental en el Departamento de Medicina Nuclear del Instituto Nacional de Cancerologia

    Energy Technology Data Exchange (ETDEWEB)

    Torres U, C. L.; Avila A, O. L. [ININ, Carretera Mexico-Toluca s/n, Ocoyoacac 52750, Estado de Mexico (Mexico); Medina V, L. A.; Buenfil B, A. E.; Brandan S, M. E. [UNAM, Instituto de Fisica, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Trujillo Z, F. E. [Instituto Nacional de Cancerologia, Av. San Fernando No. 22, Col. Seccion XVI, 14080 Mexico D. F. (Mexico); Gamboa de Buen, I. [UNAM, Instituto de Ciencias Nucleares, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2009-07-01

    The dosimeters TLD-100 and TLD-900 were used to know the levels of environmental dose in areas of the Nuclear Medicine Department of the National Institute of Cancer. The dosimeters calibration was carried out in the Metrology Department of the National Institute of Nuclear Research. The radioisotopes used in the studied areas are {sup 131}I, {sup 18}F, {sup 67}Ga, {sup 99m}Tc, {sup 111}In, {sup 201}Tl and {sup 137}Cs with gamma energies between 93 and 662 KeV. Dosimeters were placed during five months in the diagnostic, injection, waiting and PET rooms as well as hot room, waste room, enclosed corridors to patient rooms treated with {sup 131}I and {sup 137}Cs and witness dosimeters to know the bottom. The values found vary between 0.3 and 70 major times that those of bottom. The maximum doses were measured in the waste room and in the enclosed corridor to the patient rooms with cervical uterine cancer treated with {sup 137}Cs. (Author)

  6. Paul Scherrer Institute Scientific Report 1999. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Brian; Gschwend, Beatrice [eds.

    2000-07-01

    Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The total effort invested in nuclear energy research in 1999 amounted to about 185 py/a and 4.7 MCHF of investment and maintenance costs. Approximately half of the salary, investment and maintenance costs are externally funded, primarily by the Swiss Utilities, the national co-operative for the disposal of nuclear waste (NAGRA), the Federal Office of Energy (BFE) through the nuclear safety inspectorate (HSK) and the Federal Office for Science and Education (BBW) in connection with the EU Framework Programmes; an increasing part of external funding is coming from domestic and foreign industry (nuclear component and fuel suppliers). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. 4 % of the total resources are invested in addressing more global aspects of energy. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 1999 in these topical areas is described in this report. A list of scientific publications in 1999 is also provided.

  7. Paul Scherrer Institute Scientific Report 1998. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Birchley, Jon; Ringele, Ruth [eds.

    1999-09-01

    Nuclear energy related research in Switzerland is concentrated at PSI`s Nuclear Energy and Safety Research Department (NES). The total effort invested in nuclear energy research in 1998 amounted to about 195 py/a and 4.5 millions CHF of investment and maintenance costs. Approximately half of the salary, investment and maintenance costs are externally funded, primarily by the Swiss Utilities, the national co-operative for the disposal of nuclear waste (NAGRA), the Federal Office of Energy (BFE) through the nuclear safety inspectorate (HSK) and the Federal Office for Science and Education (BBW) in connection with the EC Framework Programmes; an increasing part of external funding is coming from domestic and foreign industry (nuclear component and fuel suppliers). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. 4 % of the total resources are invested in addressing more global aspects of energy. Many of the programs are part of collaborations with universities, industry, or international organisations. A list of scientific publications in 1998 is included. (author) figs., tabs., refs.

  8. 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.

  9. Engineering of Deinococcus radiodurans R1 for bioprecipitation of uranium from dilute nuclear waste.

    Science.gov (United States)

    Appukuttan, Deepti; Rao, Amara Sambasiva; Apte, Shree Kumar

    2006-12-01

    Genetic engineering of radiation-resistant organisms to recover radionuclides/heavy metals from radioactive wastes is an attractive proposition. We have constructed a Deinococcus radiodurans strain harboring phoN, a gene encoding a nonspecific acid phosphatase, obtained from a local isolate of Salmonella enterica serovar Typhi. The recombinant strain expressed an approximately 27-kDa active PhoN protein and efficiently precipitated over 90% of the uranium from a 0.8 mM uranyl nitrate solution in 6 h. The engineered strain retained uranium bioprecipitation ability even after exposure to 6 kGy of 60Co gamma rays. The PhoN-expressing D. radiodurans offers an effective and eco-friendly in situ approach to biorecovery of uranium from dilute nuclear waste.

  10. Design and analysis of a single stage to orbit nuclear thermal rocket reactor engine

    Energy Technology Data Exchange (ETDEWEB)

    Labib, Satira, E-mail: Satira.Labib@duke-energy.com; King, Jeffrey, E-mail: kingjc@mines.edu

    2015-06-15

    Graphical abstract: - Highlights: • Three NTR reactors are optimized for the single stage launch of 1–15 MT payloads. • The proposed rocket engines have specific impulses in excess of 700 s. • Reactivity and submersion criticality requirements are satisfied for each reactor. - Abstract: Recent advances in the development of high power density fuel materials have renewed interest in nuclear thermal rockets (NTRs) as a viable propulsion technology for future space exploration. This paper describes the design of three NTR reactor engines designed for the single stage to orbit launch of payloads from 1 to 15 metric tons. Thermal hydraulic and rocket engine analyses indicate that the proposed rocket engines are able to reach specific impulses in excess of 800 s. Neutronics analyses performed using MCNP5 demonstrate that the hot excess reactivity, shutdown margin, and submersion criticality requirements are satisfied for each NTR reactor. The reactors each consist of a 40 cm diameter core packed with hexagonal tungsten cermet fuel elements. The core is surrounded by radial and axial beryllium reflectors and eight boron carbide control drums. The 40 cm long reactor meets the submersion criticality requirements (a shutdown margin of at least $1 subcritical in all submersion scenarios) with no further modifications. The 80 and 120 cm long reactors include small amounts of gadolinium nitride as a spectral shift absorber to keep them subcritical upon submersion in seawater or wet sand following a launch abort.

  11. Implementing Total Quality Management to Improve Facilities and Resources of Departments in Engineering Institute

    Directory of Open Access Journals (Sweden)

    Sumit P. Raut,

    2014-01-01

    Full Text Available This research work aims to understand Total Quality Management concepts and evaluating the extent of TQM implementation in Mechanical Engineering Department through student feedback survey. In keeping with the newer demands that have been placed on the self financed educational system by the various stakeholders, the technical educational system in particular, has been pressured to shift its focus from one in quantitative expansion to one with emphasis on quality. Growth and survival of these institutes is fully depending on their competitive working style, opinions of their customers/students about their performance, and contribution to economic growth. It is being increasingly recognized that high quality of products and services are associated with customer satisfaction and they are the key points for survival for any organization whether educational or otherwise. Not oblivious to the need for adaptation to serve the interests of its stakeholders, in terms of greater responsiveness, the educational system has begun to realize the significance of total quality management (TQM in education.

  12. Longitudinal Patent Analysis for Nanoscale Science and Engineering: Country, Institution and Technology Field

    Science.gov (United States)

    Huang, Zan; Chen, Hsinchun; Yip, Alan; Ng, Gavin; Guo, Fei; Chen, Zhi-Kai; Roco, Mihail C.

    2003-08-01

    Nanoscale science and engineering (NSE) and related areas have seen rapid growth in recent years. The speed and scope of development in the field have made it essential for researchers to be informed on the progress across different laboratories, companies, industries and countries. In this project, we experimented with several analysis and visualization techniques on NSE-related United States patent documents to support various knowledge tasks. This paper presents results on the basic analysis of nanotechnology patents between 1976 and 2002, content map analysis and citation network analysis. The data have been obtained on individual countries, institutions and technology fields. The top 10 countries with the largest number of nanotechnology patents are the United States, Japan, France, the United Kingdom, Taiwan, Korea, the Netherlands, Switzerland, Italy and Australia. The fastest growth in the last 5 years has been in chemical and pharmaceutical fields, followed by semiconductor devices. The results demonstrate potential of information-based discovery and visualization technologies to capture knowledge regarding nanotechnology performance, transfer of knowledge and trends of development through analyzing the patent documents.

  13. Thirty years of naa developments and applications at the THETIS reactor of the Institute for Nuclear Sciences, Gent

    Science.gov (United States)

    de Corte, F.

    1999-01-01

    A survey is given of the past and present fundamental developments and practical applications of neutron activation analysis performed at the reactor THETIS of the Institute for Nuclear Sciences, Gent, which has already now for more than 30 years played an internationally appreciated pioneering role in this domain. Whereas the applications were mainly dealing with the analysis of semiconductor and high-purity materials, biomedical matrices, geological materials, environmental samples and artefacts, the developments were directed towards the elaboration of irradiation, separation and counting schemes, the determination of nuclear activation and decay constants, and especially towards the introduction of a modern (so-called k0-) standardization method which—especially combined with a dedicated software package such as KAYZERO/SOLCOI© issued by DSM Research—proved to make NAA to a manageable and competitive analytical tool, nowadays applied in more than 50 NAA-labs worldwide.

  14. Calibration of chromosomal aberrations in the National Institute of Nuclear Research; Calibracion de aberraciones cromosomicas en el ININ

    Energy Technology Data Exchange (ETDEWEB)

    Guerrero C, C.; Arceo M, C.; Brena V, M. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: cgc@nuclear.inin.mx

    2008-07-01

    In the laboratory of biological dosimetry of the National Institute of Nuclear Research one carried out a calibration of chromosomal aberrations. The result obtained by the different participants does not mark to significant differences between the readings of the cells and the considered one of dose for each one of the cases. The biological material for this intercomparison was prepared in the Republic of Argentina like part of the activities of the Project Regional OIEA-RLA/9/054 {sup S}trengthening of the National Systems for the Preparation and Answer in Radiological and Nuclear Emergencies{sup .} In this regional project participates seven countries of the area and in October of this year will be presented the results of each one of them. Part of the objectives of this project is the one to conform a network of mutual aid in case of radiological accidents for which the participants must unify criteria. (Author)

  15. Research activity of institute of physical chemistry of Russian Academy of sciences in the field of nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Pikaev, A.K. [Institute of Physical Chemistry of Russian Academy of Sciences, Moscow (Russian Federation)

    2000-07-01

    The report is a brief review of the most important directions in research activity of the Institute of Physical Chemistry of RAS (Moscow) in the field of nuclear fuel cycle. The main attention is paid to researches and developments on liquid radioactive waste management including the removal of wastes to deep geological formations and the immobilization of the wastes. In particular, the data from the study on the properties of new, basaltic-like matrices for the immobilization are presented. The results of research on gas evolution from the systems modeling liquid high-level radioactive wastes are considered. The separation of some radionuclides from irradiated nuclear and the production of radiation sources by various methods are discussed. (author)

  16. Educating nuclear engineers at German universities; Die Ausbildung von Kerntechnikern an deutschen Hochschulen

    Energy Technology Data Exchange (ETDEWEB)

    Knorr, J. [Fakultaet Maschinenwesen, Inst. fuer Energietechnik, Lehrstuhl fuer Kernenergietechnik, Technische Univ. Dresden (Germany)

    1995-05-01

    Nuclear technology is a relatively young university discipline. Yet, as a consequence of the declining public acceptance of the peaceful use of nuclear power, its very existence is already being threatened at many universities. However, if Germany needs nuclear power, which undoubtedly is the case, highly qualified, committed experts are required above all. Nuclear technology develops internationally. Consequently, also university education must meet international standards. Generally, university education has been found to be the most effective way of increasing the number of scientific and engineering personnel. Nuclear techniques have meanwhile found acceptance in many other scientific disciplines, thus advancing those branches of science. Teaching needs research; like research in nucelar technology at the national research centers, also the universities are suffering massive financial disadvantages. Research is possible only if outside funds are solicited, which increase dependency and decreases basic research. (orig.) [Deutsch] An den Hochschulen ist das Studium der Kerntechnik noch relativ jung, und doch schon - bedingt durch die sinkende Akzeptanz der friedlichen Nutzung der Kernenergie in der Oeffentlichkeit - an vielen Wissenschaftsstandorten in seiner Existenz bedroht. Wenn Deutschland jedoch die Kernkraft braucht - und daran besteht kein Zweifel - dann werden in erster Linie hochqualifizierte, engagierte Fachleute benoetigt. Die Entwicklung der Kerntechnik vollzieht sich international. Darum muss auch die Hochschulausbildung internationalen Massstaeben genuegen. Die universitaere Ausbildung hat sich generell als die effektivste Form zur Reproduktion wissenschaftlichen und ingenieurtechnischen Personals erwiesen. Kerntechnische Methoden haben Eingang in viele andere Wissenschaftsdisziplinen gefunden und dadurch deren Entwicklung vorangetrieben. Lehre lebt von der Forschung; wie die kerntechnische Forschung in den Grossforschungseinrichtungen, so werden

  17. Convergence Nanorobot Analysis for Radiation Therapy-Industrial Innovations in Nuclear Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Taeho [Yonsei Univ., Wonju (Korea, Republic of)

    2015-10-15

    The important step of the commercialization is the make the prototype nanorobot where lots of applications could be introduced for the industry. For the much more advanced operations of the nanorobot, it is needed to imagine the strategy for the operation in the non-regular shaped organs like the lung which shows the different feature following breaths. The biological stuffs are usually in the irregular shape and could be changed by the external force or the infected viruses. The biological substance could be made by the amorphous material which is used frequently in the industry. The antibody reaction is a particular matter which could be happen in the human body. So, the adaptations of the nanorobot could be increased for the practical purposed. Fig. 7 is the newly imagined convergence nuclear technology with nanorobotics for nuclear engineering fields in which many kinds of applications are imagined. Following the new applications of the nanorobot, it is possible to challenge for the difficult matters in the conventional nuclear industry. Fig. 8 shows the historic mistakes in commercialized nuclear power plants (NPPs) considering the nuclear reactor analysis and safety system induced by the accident. Firstly, the non-matched flux shapes made by the multiplications of Bessel function and cosine function by the cylindrical core shape, which is different from the spherical or rectangular core shape, couldn't describe the exact flux shape. Secondly, the safety system installed to start in the accident is the piping-based injection equipment. However, the safety injection systems have failed in three major sever accidents as Three Mile Island (TMI), Chernobyl, and Fukushima cases due to the significant piping failures.

  18. Virtual Visit to the ATLAS Control Room during Researchers Night by Institute of Nuclear Physics Polish Academy of Sciences, Cracow

    CERN Multimedia

    ATLAS Experiment

    2012-01-01

    We invite our "6-th Ma?opolska Researchers Night" guests for Virtual Visits in ATLAS Control Room. They could ask Polish scientists and experts during a lecture "How a mass is created - the Higgs boson discovery" to be given by dr Anna Kaczmarska. "Ma?opolska Researchers Night" is a part of European Researchers Night events to be held in more than 200 cities. Institute of Nuclear Physics Polish Academy of Sciences invites Cracow citizens and tourists visiting our town to its laboratories and to the "Science Garden" formed, especially for this event, in front of the main building. Visitors will have an unique opportunity to discuss science problems with researches and students. Wide range of demonstrations of interesting activities performed in our institute will be presented, these include among others: - AIC 144 Cyclotron with hadrons' therapy facility for eye treatment - Dosimetry and environmental pollution monitoring - Large Hadron Collider experiments - Van de Graff linear accelerator with proton micro b...

  19. Present status of contamination monitoring at the Dalat Nuclear Research Institute (DNRI)

    Energy Technology Data Exchange (ETDEWEB)

    Hoang Van Nguyen [Dalat Nuclear Research Inst. (Viet Nam)

    1997-06-01

    The Dalat nuclear research reactor was renovated and upgraded from the previous TRIGA reactor. In Vietnam, it is a unique nuclear device having suitable neutron flux for the radioisotope production and neutron activation analysis. Soon after the reactor reached its initial criticality in November 1983, a programme has been formed to develop the application of nuclear techniques in various fields. In addition, the use of radioisotopes for diagnostic, therapeutic and other research purposes has been in progress. In order to support these activities, the radiation protection, especially the radiation contamination monitoring has been properly paid attention to. In DNRI, the Radiation Protection Department is responsible for controlling and supervising radiation and working safety for all activities. In this paper, the following items are described on radiation contamination monitoring: controlled area, surface contamination monitoring, and airborne concentration monitoring. (G.K.)

  20. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Osuch, S. [ed.

    1996-12-31

    In the presented Annual Report the activities of Nuclear Physics Division (NPD) of Warsaw University in 1995 are described. The report consists of three sections: (i) Reaction Mechanism and Nuclear Structure (11 articles); (ii) Instrumentation and Experimental Methods (9 articles); (iii) Other Research (1 article). Additionally the list of seminars held at the NPD, personnel list and list of published papers are also given. The first, leading article in the report written by head of NPD prof. Ch. Droste the general description of the Department activity is presented.

  1. Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Brian; Gschwend, Beatrice [eds.

    2001-03-01

    Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. Comprehensive assessments of energy systems are carried out in cooperation with PSI's General Energy Research Department. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 2000 in these topical areas is described in this report. A list of scientific publications in 2000 is also provided.

  2. Thermohydraulic Design Analysis Modeling for Korea Advanced NUclear Thermal Engine Rocket for Space Application

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Seung Hyun; Choi, Jae Young; Venneria, Paolo F.; Jeong, Yong Hoon; Chang, Soon Heung [KAIST, Daejeon (Korea, Republic of)

    2015-05-15

    Space exploration is a realistic and profitable goal for long-term humanity survival, although the harsh space environment imposes lots of severe challenges to space pioneers. To date, almost all space programs have relied upon Chemical Rockets (CRs) rating superior thrust level to transit from the Earth's surface to its orbit. However, CRs inherently have insurmountable barrier to carry out deep space missions beyond Earth's orbit due to its low propellant efficiency, and ensuing enormous propellant requirement and launch costs. Meanwhile, nuclear rockets typically offer at least two times the propellant efficiency of a CR and thus notably reduce the propellant demand. Particularly, a Nuclear Thermal Rocket (NTR) is a leading candidate for near-term manned missions to Mars and beyond because it satisfies a relatively high thrust as well as a high efficiency. The superior efficiency of NTRs is due to both high energy density of nuclear fuel and the low molecular weight propellant of Hydrogen (H{sub 2}) over the chemical reaction by-products. A NTR uses thermal energy released from a nuclear fission reactor to heat the H{sub 2} propellant and then exhausted the highly heated propellant through a propelling nozzle to produce thrust. A propellant efficiency parameter of rocket engines is specific impulse (I{sub s}p) which represents the ratio of the thrust over the propellant consumption rate. If the average exhaust H{sub 2} temperature of a NTR is around 3,000 K, the I{sub s}p can be achieved as high as 1,000 s as compared with only 450 - 500 s of the best CRs. For this reason, NTRs are favored for various space applications such as orbital tugs, lunar transports, and manned missions to Mars and beyond. The best known NTR development effort was conducted from 1955 to1974 under the ROVER and NERVA programs in the USA. These programs had successfully designed and tested many different reactors and engines. After these projects, the researches on NERVA derived

  3. Design and Development of the MITEE-B Bi-Modal Nuclear Propulsion Engine

    Science.gov (United States)

    Paniagua, John C.; Powell, James R.; Maise, George

    2003-01-01

    Previous studies of compact, ultra-lightweight high performance nuclear thermal propulsion engines have concentrated on systems that only deliver high thrust. However, many potential missions also require substantial amounts of electric power. Studies of a new, very compact and lightweight bi-modal nuclear engine that provides both high propulsive thrust and high electric power for planetary science missions are described. The design is a modification of the MITEE nuclear thermal engine concept that provided only high propulsive thrust. In the new design, MITEE-B, separate closed cooling circuits are incorporated into the reactor, which transfers useful amounts of thermal energy to a small power conversion system that generates continuous electric power over the full life of the mission, even when the engine is not delivering propulsive thrust. Two versions of the MITEE-B design are described and analyzed. Version 1 generates 1 kW(e) of continuous power for control of the spacecraft, sensors, data transmission, etc. This power level eliminates the need for RTG's on missions to the outer planets, and allowing considerably greater operational capability for the spacecraft. This, plus its high thrust and high specific impulse propulsive capabilities, makes MITEE-B very attractive for such missions. In Version 2, of MITEE-B, a total of 20 kW(e) is generated, enabling the use of electric propulsion. The combination of high open cycle propulsion thrust (20,000 Newtons) with a specific impulse of ~1000 seconds for short impulse burns, and long term (months to years), electric propulsion greatly increases MITEE's ΔV capability. Version 2 of MITEE-B also enables the production and replenishment of H2 propellant using in-situ resources, such as electrolysis of water from the ice sheet on Europa and other Jovian moons. This capability would greatly increase the ΔV available for certain planetary science missions. The modifications to the MITEE multiple pressure tube

  4. Engineering Ethics In Islam: An Evaluative And Comparative Study Between Code Of Ethics Of Institution Of Engineers, Bangladesh (Ieb And Code Of Professional Conduct Of Board Of Engineers Malaysia (BEM

    Directory of Open Access Journals (Sweden)

    Muhammad Amanullah

    2012-01-01

    Full Text Available During the past two centuries or so a number of buildings and bridges had been structurally failed and collapsed all over the world. Some of these incidents caused a sizeable number of human casualties. For instance, collapse of Tay Bridge in 1879 killed at least sixty persons. Beside the problems related to their design and construction, probably the failure to follow engineering ethics properly was partially responsible for these incidents. Growing engineering professionalism during the nineteenth century gave rise to the development of a number of famous engineering societies, such as American Institute of Electrical Engineers (AIEE ( (1884, American Institute of Mining Engineers (AIME (1871, etc. On the other hand, responding to series of significant structural failures mentioned above, some engineering societies developed formal codes of ethics. Following these societies, engineers of Bangladesh (previous East Pakistan established Institution of Engineers, Bangladesh (IEB. Likewise, Malaysian engineers established Board of Engineers Malaysia (BEM. Both of these societies have their codes of ethics. Islam also has offered a number of ethics to be followed by the engineers. Analyzing the related verses of the Qur'an and ahadith of the Prophet (pbuh, this paper intends to highlight these Islamic ethics and in light of them, tries to evaluate the codes of ethics of these two societies and compare between them. The paper may conclude that although the codes of ethics of IEB and BEM are supported by Islamic ethics they require further modification.ABSTRAK - Sejak lebih kurang dua abad kebelakangan ini, banyak binaan yang gagal dari segi strukturnya dan juga jambatan yang runtuh di merata dunia. Sesetengah tragedi yang berlaku juga mengakibatkan kehilangan nyawa manusia. Contohnya, robohnya Jambatan Tay pada 1879 telah meragut nyawa lebih kurang enam puluh orang. Selain daripada masalah yang berkaitan dengan reka bentuk dan pembinaanya, mungkin

  5. Multiphysics Computational Analysis of a Solid-Core Nuclear Thermal Engine Thrust Chamber

    Science.gov (United States)

    Wang, Ten-See; Canabal, Francisco; Cheng, Gary; Chen, Yen-Sen

    2007-01-01

    The objective of this effort is to develop an efficient and accurate computational heat transfer methodology to predict thermal, fluid, and hydrogen environments for a hypothetical solid-core, nuclear thermal engine - the Small Engine. In addition, the effects of power profile and hydrogen conversion on heat transfer efficiency and thrust performance were also investigated. The computational methodology is based on an unstructured-grid, pressure-based, all speeds, chemically reacting, computational fluid dynamics platform, while formulations of conjugate heat transfer were implemented to describe the heat transfer from solid to hydrogen inside the solid-core reactor. The computational domain covers the entire thrust chamber so that the afore-mentioned heat transfer effects impact the thrust performance directly. The result shows that the computed core-exit gas temperature, specific impulse, and core pressure drop agree well with those of design data for the Small Engine. Finite-rate chemistry is very important in predicting the proper energy balance as naturally occurring hydrogen decomposition is endothermic. Locally strong hydrogen conversion associated with centralized power profile gives poor heat transfer efficiency and lower thrust performance. On the other hand, uniform hydrogen conversion associated with a more uniform radial power profile achieves higher heat transfer efficiency, and higher thrust performance.

  6. Structural Analyses of the Support Trusses for the Nuclear Thermal Rocket Engines and Drop Tanks

    Science.gov (United States)

    Myers, David E.; Kosareo, Daniel N.

    2006-01-01

    Finite element structural analyses were performed on the support trusses of the Nuclear Thermal Rocket (NTR) engines and drop tanks to verify that the proper amount of mass was allocated for these components in the vehicle sizing model. The verification included a static stress analysis, a modal analysis, and a buckling analysis using the MSC/NASTRAN™ structural analysis software package. In addition, a crippling stress analysis was performed on the truss beams using a handbook equation. Two truss configurations were examined as possible candidates for the drop tanks truss while a baseline was examined for the engine support thrust structure. For the drop tanks trusses, results showed that both truss configurations produced similar results although one performed slightly better in buckling. In addition, it was shown that the mass allocated in the vehicle sizing model was adequate although the engine thrust structure may need to be modified slightly to increase its lateral natural frequency above the minimum requirement of 8 Hz that is specified in the Delta IV Payload Planners Guide.

  7. Functions of an engineered barrier system for a nuclear waste repository in basalt

    Energy Technology Data Exchange (ETDEWEB)

    Coons, W.E.; Moore, E.L.; Smith, M.J.; Kaser, J.D.

    1980-01-01

    Defined in this document are the functions of components selected for an engineered barrier system for a nuclear waste repository in basalt. The definitions provide a focal point for barrier material research and development by delineating the purpose and operative lifetime of each component of the engineered system. A five-component system (comprised of waste form, canister, buffer, overpack, and tailored backfill) is discussed in terms of effective operation throughout the course of repository history, recognizing that the emplacement environment changes with time. While components of the system are mutually supporting, redundancy is provided by subsystems of physical and chemical barriers which act in concert with the geology to provide a formidable barrier to transport of hazardous materials to the biosphere. The operating philosophy of the conceptual engineered barrier system is clarified by examples pertinent to storage in basalt, and a technical approach to barrier design and material selection is proposed. A method for system validation and qualification is also included which considers performance criteria proposed by external agencies in conjunction with site-specific models and risk assessment to define acceptable levels of system performance.

  8. Highly sensitive detection of protein biomarkers via nuclear magnetic resonance biosensor with magnetically engineered nanoferrite particles.

    Science.gov (United States)

    Jeun, Minhong; Park, Sungwook; Lee, Hakho; Lee, Kwan Hyi

    Magnetic-based biosensors are attractive for on-site detection of biomarkers due to the low magnetic susceptibility of biological samples. Here, we report a highly sensitive magnetic-based biosensing system that is composed of a miniaturized nuclear magnetic resonance (NMR) device and magnetically engineered nanoferrite particles (NFPs). The sensing performance, also identified as the transverse relaxation (R2) rate, of the NMR device is directly related to the magnetic properties of the NFPs. Therefore, we developed magnetically engineered NFPs (MnMg-NFP) and used them as NMR agents to exhibit a significantly improved R2 rate. The magnetization of the MnMg-NFPs was increased by controlling the Mn and Mg cation concentration and distribution during the synthesis process. This modification of the Mn and Mg cation directly contributed to improving the R2 rate. The miniaturized NMR system, combined with the magnetically engineered MnMg-NFPs, successfully detected a small amount of infectious influenza A H1N1 nucleoprotein with high sensitivity and stability.

  9. Institute-Industry Interoperation Model: An Industry-Oriented Engineering Education Strategy in China

    Science.gov (United States)

    Wang, Yanqing; Qi, Zhongying; Li, Ziru; Zhang, Lijie

    2011-01-01

    Engineering education has been well implemented in the majority of developed countries such as the USA, Germany, and the United Kingdom so that the gap between engineering science and engineering practice is greatly bridged. However, in China, the gap still exists, and some attempts by Chinese government, even though having made obvious progress,…

  10. The Institutional Degree Production of Master's and Doctorates for Women and Underrepresented Minorities in Engineering

    Science.gov (United States)

    Ostreko, Amanda L.

    2012-01-01

    This study aimed to identify which engineering school characteristics relate to higher advanced degree production rates for women and underrepresented minorities (URMs). Data from the American Society for Engineering Education (ASEE), "U.S. News and World Report" ("USNWR") rankings of engineering graduate programs, Integrated…

  11. Signature of the Agreement between the University of Liverpool, acting on behalf of the Cockcroft Institute, represented by Inaugural Director of Cockcroft Institute S. Chattopadhyay and the European Organization for Nuclear Research represented by Director-General R. Aymar,concerning collaboration between the Cockcroft Institute and CERN in Accelerator Physics and Technologies.

    CERN Multimedia

    Claudia Marcelloni

    2008-01-01

    Signature of the Agreement between the University of Liverpool, acting on behalf of the Cockcroft Institute, represented by Inaugural Director of Cockcroft Institute S. Chattopadhyay and the European Organization for Nuclear Research represented by Director-General R. Aymar,concerning collaboration between the Cockcroft Institute and CERN in Accelerator Physics and Technologies.

  12. Program for upgrading nuclear materials protection, control, and accounting at all facilities within the All-Russian Institute of Experimental Physics (VNIIEF)

    Energy Technology Data Exchange (ETDEWEB)

    Yuferev, V.; Zhikharev, S.; Yakimov, Y. [All-Russian Inst. of Experimental Physics, Moscow (Russian Federation)] [and others

    1998-12-31

    As part of the Department of Energy-Russian program for strengthening nuclear material protection, control, and accounting (MPC and A), plans have now been formulated to install an integrated MPC and A system at all facilities containing large quantities of weapons-usable nuclear material within the All-Russian Institute of Experimental Physics (VNIIEF, Arzamas-16) complex. In addition to storage facilities, the complex houses a number of critical facilities used to conduct nuclear physics research and facilities for developing procedures for disassembly of nuclear weapons.

  13. Announcement of the 7th FOSECO Cup Excellent Foundry Papers of Foundry Institution of Chinese Mechanical Engineering Society 2004

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    @@ The second stage work (final judgment) of the 7th FOSECO Cup Excellent Foundry Papers organized by Foundry Institution of Chinese Mechanical Engineering Society was carried out in Sanya, Hainan province, China, on May 15-19, 2005. Two gold award papers, 10 silver award papers and 1 special award paper were awarded, and the other 44 papers recommended into the final judgment were recognized as excellent papers.

  14. Education for hydraulics and pneumatics in Nippon Institute of Technology, Department of Mechanical Engineering; Nippon Kogyo Daigaku ni okeru yukuatsukyoiku

    Energy Technology Data Exchange (ETDEWEB)

    Terashima, Y. [Nippon Institute of Technology, Saitama (Japan)

    2000-03-15

    Described herein is education of hydraulics and pneumatics in Nippon Institute of Technology. Department of Mechanical Engineering has fluid dynamics, mechatronics II, air conditioning, heat transfer engineering, and facility and equipment engineering as the themes related to hydraulics and pneumatics. The control engineering courses have the pneumatics-related themes of supply of pneumatic pressure for a short time and methods for cutting off pneumatic pressure when the piston reaches the dead center, as the energy-saving type driving methods for pneumatic cylinders; measurement of frictional force by the experiments on low-friction cylinders; and researches on improvement of stiffness of pneumatic cylinder type actuators for control valves, among others. Students are directly involved in equipment designs, fabrication and experiments. Many machines and facilities are now easily handled, and operated according to manuals. To prepare graduation theses only by the aid of personal computers is not adequate for education of students in this age, when they have less chances for education through experiences in affluent environments. The mechanical engineering students are given chances for practical education through experiments and graduation thesis preparation. However, it is necessary for general engineering students to be more exposed to technical practices. (NEDO)

  15. Paul Scherrer Institut Scientific Report 2001. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, B.L. (ed.)

    2002-03-01

    The year 2001 was marked by the extensive audit of energy research at PSI. The audit took place on 21/22 June, and nuclear energy research was evaluated by five international experts. It was possible to present the quality and relevance of our research in a convincing way. This, together with optimal use of the available resources in our department Nuclear Energy and Safety (NES), prompted the highly welcome result that the auditors attested a high degree of scientific quality to the NES projects in general, with some of them judged to be of world-class standard. They recommended all audited projects be maintained, adequate resources to be allocated accordingly and, if necessary, an increase of public funding in nuclear energy research to be granted to achieve this. Finally, it was recommended that energy research should be explicitly mentioned in the statement of the ultimate mission of PSI. At the level of 'daily work', efforts in several directions related to the future of the Hotlab were one of the main focuses during the past year. On the one hand, the safety-related backfitting of the facility (particularly in regard to fire protection) has been continued, and was coupled with intensive planning studies, and with a thorough radiological cleaning of the labs; this invariably led to some impediment to the current research activities. Despite external burdens, which have led to some delays and additional costs, three of the four refurbishment phases have been completed, and the corresponding laboratories were brought back into operation after inspection and approval by the regulatory authority HSK. Given the size and complexity of the project, progress must be considered very satisfactory. A list of scientific publications in 2000 is also provided.

  16. The effects of networks on U.S. institution selection by foreign doctoral students in science and engineering

    Science.gov (United States)

    Tanyildiz, Zeynep Esra

    The United States has been a very attractive destination for foreign Science and Engineering (S&E) graduate students and postdoctoral scholars for a considerable period of time. Several studies have documented significant contributions of foreign students and foreign scientists in S&E. These contributions in turn foster economic development. Recent studies suggest, however, that the U.S. is losing its dominance in attracting foreign talent. Increased competition outside the U.S. contributes to the change as do changes in visa regulations. Despite the important role of foreign doctoral students in the U.S., relatively little is known about factors influencing their decision to attend an institution. One factor that is rarely explored is the effect of networks on institution selection. Through their networks, students learn about application procedures, studying at an institution, housing opportunities, general culture and people. In doing this, they draw both on the experience of the alumni as well as the support of current students and faculty at their target institution. Thus, networks can play an important role in where foreign doctoral students actually end up studying. This study aims to provide both qualitative and quantitative information about the role networks play in foreign doctoral students' institution selection. This three-part study utilizes different methodologies: (1) focus group interviews conducted with Turkish doctoral students at the Georgia Institute of Technology; (2) a web study of research laboratories in science and engineering; and (3) the estimation of Random Utility Model (RUM) of institution selection. These three components build on each other, in addition to the individual contributions that they make. Together they provide an in-depth and comprehensive analysis of the role of networks. The results from guided focus group interviews indicate that students, alumni, faculty and local community of the same nationality influence

  17. Integrating design and communication in engineering education: a collaboration between Northwestern University and the Rehabilitation Institute of Chicago.

    Science.gov (United States)

    Hirsch, Penny L; Yarnoff, Charles

    2011-01-01

    The required course for freshmen in Northwestern University's engineering school - a 2-quarter sequence called Engineering Design and Communication (EDC) - is noteworthy not only for its project-based focus on user-centered design, but also for its innovative integrated approach to teaching communication, teamwork, and ethics. Thanks to the collaboration between EDC faculty and staff at the Rehabilitation Institute of Chicago, EDC students, at the beginning of their education, experience the excitement of solving problems for real clients and users. At the same time, these authentic design projects offer an ideal setting for teaching students how to communicate effectively to different audiences and perform productively as team members and future leaders in engineering.

  18. Delivering Single-Walled Carbon Nanotubes to the Nucleus Using Engineered Nuclear Protein Domains.

    Science.gov (United States)

    Boyer, Patrick D; Ganesh, Sairaam; Qin, Zhao; Holt, Brian D; Buehler, Markus J; Islam, Mohammad F; Dahl, Kris Noel

    2016-02-10

    Single-walled carbon nanotubes (SWCNTs) have great potential for cell-based therapies due to their unique intrinsic optical and physical characteristics. Consequently, broad classes of dispersants have been identified that individually suspend SWCNTs in water and cell media in addition to reducing nanotube toxicity to cells. Unambiguous control and verification of the localization and distribution of SWCNTs within cells, particularly to the nucleus, is needed to advance subcellular technologies utilizing nanotubes. Here we report delivery of SWCNTs to the nucleus by noncovalently attaching the tail domain of the nuclear protein lamin B1 (LB1), which we engineer from the full-length LMNB1 cDNA. More than half of this low molecular weight globular protein is intrinsically disordered but has an immunoglobulin-fold composed of a central hydrophobic core, which is highly suitable for associating with SWCNTs, stably suspending SWCNTs in water and cell media. In addition, LB1 has an exposed nuclear localization sequence to promote active nuclear import of SWCNTs. These SWCNTs-LB1 dispersions in water and cell media display near-infrared (NIR) absorption spectra with sharp van Hove peaks and an NIR fluorescence spectra, suggesting that LB1 individually disperses nanotubes. The dispersing capability of SWCNTs by LB1 is similar to that by albumin proteins. The SWCNTs-LB1 dispersions with concentrations ≥150 μg/mL (≥30 μg/mL) in water (cell media) remain stable for ≥75 days (≥3 days) at 4 °C (37 °C). Further, molecular dynamics modeling of association of LB1 with SWCNTs reveal that the exposure of the nuclear localization sequence is independent of LB1 binding conformation. Measurements from confocal Raman spectroscopy and microscopy, NIR fluorescence imaging of SWCNTs, and fluorescence lifetime imaging microscopy show that millions of these SWCNTs-LB1 complexes enter HeLa cells, localize to the nucleus of cells, and interact with DNA. We postulate that the

  19. 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.

  20. Construction of a bibliographic information database for the Nuclear Science and Engineering (IX)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Whan; Oh, Jeong Hun; Choi, Kwang; Keum, Jong Yong [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    The major goal of this project is to construct a database in nuclear science and engineering information materials, support the R and D activities of users in this field, finally to support KRISTAL(Korea Research Information for Science and Technology Access Line)'s DB through the KREONet(Korea Research Environment Open Network), as one of the five national information networks. The contents of this project are as follows: 1) Materials selection and collection, 2) Indexing and abstract preparation, 3) Data input and transmission, and 4) document delivery service. In this seventh year, 40,000 records, as total of inputted data, are added to the existing SATURN DB. These records are covered with the articles of nuclear-related core journals, proceedings, seminars, and research reports, etc. And using the Web, this project was important for users to get their needed information itself and to receive the materials of online requested information. And then it will give the chance users not only to promote the the effectiveness of R and D activities, but also to obviate the duplicated research works. 1 fig., 1 tab. (Author)

  1. Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    O, J.M.; Higgins, J.; Stephen Fleger - NRC

    2011-09-19

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

  2. Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sudarno [National Nuclear Energy Agency, Batan (Indonesia); Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J. [KAERI, Taejon (Korea, Republic of)

    2003-04-01

    The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback.

  3. Anticipated Degradation Modes of Metallic Engineered Barriers for High-Level Nuclear Waste Repositories

    Science.gov (United States)

    Rodríguez, Martín A.

    2014-03-01

    Metallic engineered barriers must provide a period of absolute containment to high-level radioactive waste in geological repositories. Candidate materials include copper alloys, carbon steels, stainless steels, nickel alloys, and titanium alloys. The national programs of nuclear waste management have to identify and assess the anticipated degradation modes of the selected materials in the corresponding repository environment, which evolves in time. Commonly assessed degradation modes include general corrosion, localized corrosion, stress-corrosion cracking, hydrogen-assisted cracking, and microbiologically influenced corrosion. Laboratory testing and modeling in metallurgical and environmental conditions of similar and higher aggressiveness than those expected in service conditions are used to evaluate the corrosion resistance of the materials. This review focuses on the anticipated degradation modes of the selected or reference materials as corrosion-resistant barriers in nuclear repositories. These degradation modes depend not only on the selected alloy but also on the near-field environment. The evolution of the near-field environment varies for saturated and unsaturated repositories considering backfilled and unbackfilled conditions. In saturated repositories, localized corrosion and stress-corrosion cracking may occur in the initial aerobic stage, while general corrosion and hydrogen-assisted cracking are the main degradation modes in the anaerobic stage. Unsaturated repositories would provide an oxidizing environment during the entire repository lifetime. Microbiologically influenced corrosion may be avoided or minimized by selecting an appropriate backfill material. Radiation effects are negligible provided that a thick-walled container or an inner shielding container is used.

  4. The engineering of a nuclear thermal landing and ascent vehicle utilizing indigenous Martian propellant

    Science.gov (United States)

    Zubrin, Robert M.

    1991-01-01

    The following paper reports on a design study of a novel space transportation concept known as a 'NIMF' (Nuclear rocket using Indigenous Martian Fuel). The NIMF is a ballistic vehicle which obtains its propellant out of the Martian air by compression and liquefaction of atmospheric CO2. This propellant is subsequently used to generate rocket thrust at a specific impulse of 264 s by being heated to high temperature (2800 K) gas in the NIMFs' nuclear thermal rocket engines. The vehicle is designed to provide surface to orbit and surface to surface transportation, as well as housing, for a crew of three astronauts. It is capable of refueling itself for a flight to its maximum orbit in less than 50 days. The ballistic NIMF has a mass of 44.7 tonnes and, with the assumed 2800 K propellant temperature, is capable of attaining highly energetic (250 km by 34,000 km elliptical) orbits. This allows it to rendezvous with interplanetary transfer vehicles which are only very loosely bound into orbit around Mars. If a propellant temperature of 2000 K is assumed, then low Mars orbit can be attained; while if 3100 K is assumed, then the ballistic NIMF is capable of injecting itself onto a minimum energy transfer orbit to Earth in a direct ascent from the Martian surface.

  5. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Volume 1, Appendix B: Idaho National Engineering Laboratory Spent Nuclear Fuel Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.

  6. Investigation of metallic, ceramic, and polymeric materials for engineered barrier applications in nuclear-waste packages

    Energy Technology Data Exchange (ETDEWEB)

    Westerman, R.E.

    1980-10-01

    An effort to develop licensable engineered barrier systems for the long-term (about 1000 yr) containment of nuclear wastes under conditions of deep continental geologic disposal has been underway at Pacific Northwest Laboratory since January 1979, under the auspices of the High-Level Waste Immobilization Program. In the present work, the barrier system comprises the hard or structural elements of the package: the canister, the overpack(s), and the hole sleeve. A number of candidate metallic, ceramic, and polymeric materials were put through mechanical, corrosion, and leaching screening tests to determine their potential usefulness in barrier-system applications. Materials demonstrating adequate properties in the screening tests will be subjected to more detailed property tests, and, eventually, cost/benefit analyses, to determine their ultimate applicability to barrier-system design concepts. The following materials were investigated: two titanium alloys of Grade 2 and Grade 12; 300 and 400 series stainless steels, Inconels, Hastelloy C-276, titanium, Zircoloy, copper-nickel alloys and cast irons; total of 14 ceramic materials, including two grades of alumina, plus graphite and basalt; and polymers such as polyamide-imide, polyarylene, polyimide, polyolefin, polyphenylene sulfide, polysulfone, fluoropolymer, epoxy, furan, silicone, and ethylene-propylene terpolymer (EPDM) rubber. The most promising candidates for further study and potential use in engineered barrier systems were found to be rubber, filled polyphenylene sulfide, fluoropolymer, and furan derivatives.

  7. Idaho Nuclear Technology and Engineering Center (INTEC) (formerly ICPP) ash reutilization study

    Energy Technology Data Exchange (ETDEWEB)

    Langenwalter, T.; Pettet, M.; Ochoa, R.; Jensen, S.

    1998-05-01

    Since 1984, the coal-fired plant at the Idaho Nuclear Technology and Engineering Center (INTEC, formerly Idaho Chemical Processing Plant) has been generating fly ash at a rate of approximately 1,000 tons per year. This ash is hydrated and placed in an ash bury pit near the coal-fired plant. The existing ash bury pit will be full in less than 1 year at its present rate of use. A conceptual design to build a new ash bury pit was completed, and the new pit is estimated to cost $1.7 million. This report evaluates ash reutilization alternatives that propose to eliminate this waste stream and save the $1.7 million required to build a new pit. The alternatives include using ash for landfill day cover, concrete admixture, flowable fill, soil stabilization, waste remediation, and carbon recovery technology. Both physical and chemical testing, under the guidance of the American Society for Testing and Materials, have been performed on ash from the existing pit and from different steps within the facility`s processes. The test results have been evaluated, compared to commercial ash, and are discussed as they relate to reutilization alternatives. This study recommends that the ash be used in flowable fill concrete for Deactivation and Demolition work at the Idaho National Engineering and Environmental Laboratory.

  8. 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.

  9. Opportunities for Russian Nuclear Weapons Institute developing computer-aided design programs for pharmaceutical drug discovery. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-23

    The goal of this study is to determine whether physicists at the Russian Nuclear Weapons Institute can profitably service the need for computer aided drug design (CADD) programs. The Russian physicists` primary competitive advantage is their ability to write particularly efficient code able to work with limited computing power; a history of working with very large, complex modeling systems; an extensive knowledge of physics and mathematics, and price competitiveness. Their primary competitive disadvantage is their lack of biology, and cultural and geographic issues. The first phase of the study focused on defining the competitive landscape, primarily through interviews with and literature searches on the key providers of CADD software. The second phase focused on users of CADD technology to determine deficiencies in the current product offerings, to understand what product they most desired, and to define the potential demand for such a product.

  10. Creating Change in Engineering Education: A Model for Collaboration among Institutions

    Science.gov (United States)

    Plumb, Carolyn; Reis, Richard M.

    2007-01-01

    The United States, as well as the rest of the world, will face critical civil, environmental, energy, communication, manufacturing, and health-care challenges in the coming decades, and more scientists and engineers will be needed to address those problems. The number of jobs in the U.S. labor force requiring science and engineering skills, in…

  11. Conceptual Engine System Design for NERVA derived 66.7KN and 111.2KN Thrust Nuclear Thermal Rockets

    Science.gov (United States)

    Fittje, James E.; Buehrle, Robert J.

    2006-01-01

    The Nuclear Thermal Rocket concept is being evaluated as an advanced propulsion concept for missions to the moon and Mars. A tremendous effort was undertaken during the 1960's and 1970's to develop and test NERVA derived Nuclear Thermal Rockets in the 111.2 KN to 1112 KN pound thrust class. NASA GRC is leveraging this past NTR investment in their vehicle concepts and mission analysis studies, and has been evaluating NERVA derived engines in the 66.7 KN to the 111.2 KN thrust range. The liquid hydrogen propellant feed system, including the turbopumps, is an essential component of the overall operation of this system. The NASA GRC team is evaluating numerous propellant feed system designs with both single and twin turbopumps. The Nuclear Engine System Simulation code is being exercised to analyze thermodynamic cycle points for these selected concepts. This paper will present propellant feed system concepts and the corresponding thermodynamic cycle points for 66.7 KN and 111.2 KN thrust NTR engine systems. A pump out condition for a twin turbopump concept will also be evaluated, and the NESS code will be assessed against the Small Nuclear Rocket Engine preliminary thermodynamic data.

  12. Performance Engineering Research Center and RECOVERY. Performance Engineering Research Institution SciDAC-e Augmentation. Performance enhancement

    Energy Technology Data Exchange (ETDEWEB)

    Hollingsworth, Jeffrey K. [Univ. of Maryland, College Park, MD (United States)

    2015-10-12

    This project concentrated on various ways to improve the measurement and tuning large-scale parallel applications. This project was supplement to the project DE-FC0206ER25763 (“Performance Engineering Research Center”). The research conducted during this project is summarized in this report. The complete details of the work are available in the ten publications listed at the end of the report. It also supported the Ph.D. studies of three students and one research scientist.

  13. Engineering development of a digital replacement protection system at an operating US PWR nuclear power plant: Installation and operational experiences

    Energy Technology Data Exchange (ETDEWEB)

    Miller, M.H. [Duke Power Co., Seneca, SC (United States)

    1995-04-01

    The existing Reactor Protection Systems (RPSs) at most US PWRs are systems which reflect 25 to 30 year-old designs, components and manufacturing techniques. Technological improvements, especially in relation to modern digital systems, offer improvements in functionality, performance, and reliability, as well as reductions in maintenance and operational burden. The Nuclear power industry and the US nuclear regulators are poised to move forward with the issues that have slowed the transition to modern digital replacements for nuclear power plant safety systems. The electric utility industry is now more than ever being driven by cost versus benefit decisions. Properly designed, engineered, and installed digital systems can provide adequate cost-benefit and allow continued nuclear generated electricity. This paper describes various issues and areas related to an ongoing RPS replacement demonstration project which are pertinant for a typical US nuclear plant to consider cost-effective replacement of an aging analog RPS with a modern digital RPS. The following subject areas relative to the Oconee Nuclear Station ISAT{trademark} Demonstrator project are discussed: Operator Interface Development; Equipment Qualification; Validation and Verification of Software; Factory Testing; Field Changes and Verification Testing; Utility Operational, Engineering and Maintenance; Experiences with Demonstration System; and Ability to operate in parallel with the existing Analog RPS.

  14. Exploring the experiences of female students in introductory project-based engineering courses at two- and four-year institutions

    Science.gov (United States)

    Swan, Amy K.

    2011-12-01

    This qualitative study explored the experiential and contextual factors that shaped female students' pathways into introductory project-based engineering classes at two community colleges and one four-year institution, as well as female students' experiences within and outside of these classes. The study was framed by Social Cognitive Career Theory (SCCT) (Lent, Brown & Hackett, 1996) and Bronfenbrenner's (1979) ecological systems theory. Findings were based on analyses of data gathered through multiple methods: observations; individual interviews with female students; focus group interviews with project teams; and document collection. The findings of this study revealed that while positive experiences with math or science were a likely pre-cursor to engineering interest, experiential learning appeared to be a more powerful force in fostering students' engineering interest. Specifically, participants developed an interest in engineering through academic, professional, and extracurricular engineering- and design-related activities that familiarized them with the tasks and skills involved in engineering work and helped them develop a sense of selfefficacy with regard to this work. Interest and self-efficacy, in turn, played a role in students' postsecondary educational decision-making processes, as did contextual factors including families and finances. This study's findings also showed that participants' project teams were a critically important microsystem within participants' ecological environments. Within this sometimes "chilly" microsystem, female students negotiated intrateam processes, which were in some cases affected by gender norms. Intrateam processes that influenced female students' project-based learning experiences included: interpersonal dynamics; leadership; and division of labor. This study also identified several ways in which the lived experiences of participants at the community colleges were different from, or similar to, those of participants

  15. Summary of research in applied mathematics, numerical analysis and computer science at the Institute for Computer Applications in Science and Engineering

    Science.gov (United States)

    1984-01-01

    Research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics, numerical analysis and computer science during the period October 1, 1983 through March 31, 1984 is summarized.

  16. Summary of research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics, numerical analysis and computer science

    Science.gov (United States)

    1989-01-01

    Research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics, numerical analysis, and computer science during the period October 1, 1988 through March 31, 1989 is summarized.

  17. Research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics, numerical analysis and computer science. Final semiannual report, 1 April-30 September 1986

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    Research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics, numerical analysis, and computer science during the period April, 1986 through September 30, 1986 is summarized.

  18. Analysis of technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla'

    National Research Council Canada - National Science Library

    Grbić Maja; Antić Radoslav; Ponoćko Jelena; Mikulović Jovan; Đurišić Željko

    2014-01-01

    This paper presents an analysis of the technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla' in Belgrade...

  19. Engineering light-inducible nuclear localization signals for precise spatiotemporal control of protein dynamics in living cells.

    Science.gov (United States)

    Niopek, Dominik; Benzinger, Dirk; Roensch, Julia; Draebing, Thomas; Wehler, Pierre; Eils, Roland; Di Ventura, Barbara

    2014-07-14

    The function of many eukaryotic proteins is regulated by highly dynamic changes in their nucleocytoplasmic distribution. The ability to precisely and reversibly control nuclear translocation would, therefore, allow dissecting and engineering cellular networks. Here we develop a genetically encoded, light-inducible nuclear localization signal (LINuS) based on the LOV2 domain of Avena sativa phototropin 1. LINuS is a small, versatile tag, customizable for different proteins and cell types. LINuS-mediated nuclear import is fast and reversible, and can be tuned at different levels, for instance, by introducing mutations that alter AsLOV2 domain photo-caging properties or by selecting nuclear localization signals (NLSs) of various strengths. We demonstrate the utility of LINuS in mammalian cells by controlling gene expression and entry into mitosis with blue light.

  20. Nuclear manpower training

    Energy Technology Data Exchange (ETDEWEB)

    Suh, In Suk; Lee, H. Y.; Joe, B. J.; Lee, S. H.; Lee, E. J.; Yoo, B. H.; Seo, K. W.; Lee, W. K.; Jun, H. I.; Yang, K. N.; Kim, Y. J.; Kim, I. H.; Kim, M. Y.; Ju, Y. C.; Hyun, H. Y.; Choi, I. G.; Hong, C. S.; Won, J. Y.; Nam, J. Y.; Lee, H. J.

    1997-01-01

    This report describes the annual results of training courses. the scope and contents are as follows: 1. Regional and interregional training courses 2. Training courses assisted by foreign experts 3. Training courses for nuclear industry personnel 4. Training courses for internal staff-members 5. Training courses under the law. This Nuclear Training Center executed the open-door training courses for 2,400 engineers/scientists from the regulatory body, nuclear industries, research institutes and other related organizations by means of offering 51 training courses during the fiscal year 1996. (author). 23 refs.

  1. TL dosimetry in the new Tandetron ion accelerator site of the National Institute of Nuclear Research (ININ); Dosimetria TL en el area del nuevo acelerador de iones Tandetron del ININ

    Energy Technology Data Exchange (ETDEWEB)

    Valdovinos A, M.; Gonzalez M, P.R. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    The National Institute of Nuclear Research (ININ) acquired a positive ions accelerator type Tandetron 2 MV of the dutch company High Voltage Engineering, Europe B.V., which was finished its installation this year (2000) in an already existing building in the Dr. Nabor Carrillo Flores Nuclear Centre, where it was prepared for the following purposes: the accelerator will be used to realize research through X-ray emission induced by charged particles, Rutherford backscattering analysis, nuclear reaction analysis, gamma ray emission induced by charged particles, resonant dispersion analysis, elastic backward detection analysis and by particle canalization analysis. The accelerator consists of an injection system with two ion sources, ion accelerator tank with voltage in terminal at 2 MV, recovery and recirculation system of charge interchange gas, iman selector analyzer system and with high energy focussing, control system through computer and management and recovery of isolator gas system. For the realization of operation tests of this accelerator, it was had the license authorizing by the National Commission of Nuclear Safety and Safeguards (CNSNS). During the test stage Tl dosemeters were arranged in the Tandetron accelerator area, and also in direction to the beam outlet. In this work, are presented the obtained results of the measurement of radiation levels, as in the area as in the beam outlet. (Author)

  2. Vision of the Training Department of the National Institute of Nuclear Research; Vision del Departamento de Capacitacion del Instituto Nacional de Investigaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Dominguez A, C. E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2008-12-15

    The availability of skilled personnel is an essential element of the national infrastructure, to ensure the safety and security through the strong principles of management and good technology, quality assurance, training and qualification of new personnel, thorough safety evaluations and building on lessons of experience and research. In the national case the General Regulation of Radiation Safety requires that the Radiation Safety Responsible (RSR) must be experienced in issues of radiation safety of the facility in which employed. As experience has been found by chance that some people who have attended courses offered by the National Institute of Nuclear Research and have not achieved a result approval, obtain approval at the respective courses offered by other entities, which may have a potential dilemma (not at all cases since then), in the sense that the aspiration to become experts in the safety basic standards, can be addressed only after ensuring that there is an acceptance at the level of the course and evaluation ways of the present courses to RSR. Viewed another way, one can consider the formation of RSR experience in planning for better training of experts in the safety basic standards. It happens that the courses offered to RSR some of them do not cover the requirements of time, content and practices established in the regulations. The Mexican Society of Radiological Safety can affect as a partner to improve the courses quality. (Author)

  3. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ansley, Shannon L.

    2002-02-20

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  4. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  5. Portraits of Success: A Mixed-Method Study of the Enrollment, Persistence, and Success Experiences of Female Graduate Engineering Students at a Hispanic Serving Institution

    Science.gov (United States)

    Aguirre-Covarrubias, Sandra

    2013-01-01

    The current study addresses the underrepresentation of female graduate engineering students. Specifically, its purpose was to gain insight on how enrollment, persistence, and success factors are experienced by female graduate engineering students at a Hispanic Serving Institution located on the U.S.-Mexico border. The topic of underrepresentation…

  6. Nuclear receptor engineering based on novel structure activity relationships revealed by farnesyl pyrophosphate.

    Science.gov (United States)

    Goyanka, Ritu; Das, Sharmistha; Samuels, Herbert H; Cardozo, Timothy

    2010-11-01

    Nuclear receptors (NRs) comprise the second largest protein family targeted by currently available drugs, acting via specific ligand interactions within the ligand binding domain (LBD). Recently, farnesyl pyrophosphate (FPP) was shown to be a unique promiscuous NR ligand, activating a subset of NR family members and inhibiting wound healing in skin. The current study aimed at visualizing the unique basis of FPP interaction with multiple receptors in order to identify general structure-activity relationships that operate across the NR family. Docking of FPP to the 3D structures of the LBDs of a diverse set of NRs consistently revealed an electrostatic FPP pyrophosphate contact with an NR arginine conserved in the NR family, a hydrophobic farnesyl contact with NR helix-12 and a ligand binding pocket volume between 300 and 430 Å(3) as the minimal requirements for FPP activation of any NR. Lack of any of these structural features appears to render a given NR resistant to FPP activation. We used these structure-activity relationships to rationally design and successfully engineer several mutant human estrogen receptors that retain responsiveness to estradiol but no longer respond to FPP.

  7. DEVELOPMENT, INSTALLATION AND OPERATION OF THE MPC&A OPERATIONS MONITORING (MOM) SYSTEM AT THE JOINT INSTITUTE FOR NUCLEAR RESEARCH (JINR) DUBNA, RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    Kartashov,V.V.; Pratt,W.; Romanov, Y.A.; Samoilov, V.N.; Shestakov, B.A.; Duncan, C.; Brownell, L.; Carbonaro, J.; White, R.M.; Coffing, J.A.

    2009-07-12

    The Material Protection, Control and Accounting (MPC&A) Operations Monitoring (MOM) systems handling at the International Intergovernmental Organization - Joint Institute for Nuclear Research (JINR) is described in this paper. Category I nuclear material (plutonium and uranium) is used in JINR research reactors, facilities and for scientific and research activities. A monitoring system (MOM) was installed at JINR in April 2003. The system design was based on a vulnerability analysis, which took into account the specifics of the Institute. The design and installation of the MOM system was a collaborative effort between JINR, Brookhaven National Laboratory (BNL) and the U.S. Department of Energy (DOE). Financial support was provided by DOE through BNL. The installed MOM system provides facility management with additional assurance that operations involving nuclear material (NM) are correctly followed by the facility personnel. The MOM system also provides additional confidence that the MPC&A systems continue to perform effectively.

  8. Successful Programs for Undergraduate Women in Science and Engineering: "Adapting" versus "Adopting" the Institutional Environment

    Science.gov (United States)

    Fox, Mary Frank; Sonnert, Gerhard; Nikiforova, Irina

    2009-01-01

    This article focuses upon programs for undergraduate women in science and engineering, which are a strategic research site in the study of gender, science, and higher education. The design involves both quantitative and qualitative approaches, linking theory, method, questions, and analyses in ways not undertaken previously. Using a comprehensive,…

  9. Non-Technical Education in the Electrical Engineering Department of the Swiss Federal Institute of Technology.

    Science.gov (United States)

    Davis, Joan S.; Schaufelberger, Walter

    1986-01-01

    Describes curriculum enrichment aimed at giving engineers the background necessary to deal with systems from a holistic point of view. Explains science and society interactions as reasons for implementation of courses in (1) the physiology and psychology of work; (2) law, sociology, technology, and environment; and (3) economic growth and…

  10. SATISFACTION OF QUALIFICATION REQUIREMENTS OF EMPLOYERS APPLIED TO SOFTWARE ENGINEERS IN THE PROCESS OF TRAINING AT HIGHER EDUCATIONAL INSTITUTIONS

    Directory of Open Access Journals (Sweden)

    Vladislav Kruhlyk

    2017-03-01

    Full Text Available In the article, based on the analysis of the problems of the professional training of software engineers in higher educational institutions, was shown that the contents of the curricula for the training of software engineers in basic IT specialties in higher education institutions generally meet the requirements to them at the labor market. It is stated that at the present time there are certain changes in the job market not only in the increasing demand for IT professionals but also in the requirements settled for future specialists. To scientists’ opinion, at present there is a gap between the level of expectation of employers and the level of education of graduates of IT-specialties of universities. Due to the extremely fast pace of IT development, already at the end of the studies, students' knowledge may become obsolete. We are talking about a complex of competencies offered by university during training of specialist for their relevance and competitiveness at the labor market. At the same time, the practical training of students does not fully correspond to the current state of information technology. Therefore, it is necessary to ensure the updating of the contents of the academic disciplines with the aim of providing quality training of specialists.

  11. [The National Institute for Nano-Engineering : a public-private partnership for research, education, and innovation].

    Energy Technology Data Exchange (ETDEWEB)

    Stinnett, Regan White

    2010-10-01

    The National Institute for Nano-Engineering (NINE) is a government/university/industry collaboration formed to help develop the next generation of nano-engineering innovation leaders for the United States. NINE involves students in large scale multi-disciplinary research projects focused on developing nano-enabled solutions to important national problems. The NINE program is based on the growing understanding that science and engineering education and innovation can be strengthened by involvement of university students and faculty with the world-class capabilities and facilities of government laboratories supplemented by guidance and support from industry collaborators. A number of recent reports have highlighted global competitiveness issues that the Unites States faces in the coming decades. Technology innovation, the ability to progress from emerging technologies to products that change the way people live, is a key to global leadership and economic prosperity for nations and their people. One of the top technology and economic drivers for the coming decades will the spectrum of emerging capabilities that fall into the category of nanotechnologies. NINE was established as a national innovation hub in the exciting and rapidly developing field of nano-engineering. It is intended to be a model of a novel partnership between universities and companies throughout the nation and the Department of Energy, with Sandia National Laboratories as the host lab for NINE. Successful technology innovation requires the integration of technical research and development with additional expertise from other areas including manufacturing, business, marketing, intellectual property, and the interface between technology and society. NINE was created to address this need for a new integrated approach to science and engineering research, education and innovation in a way that takes advantage of the nation's investment in facilities and capabilities at the national laboratories.

  12. 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.

  13. E-learning in engineering education: a theoretical and empirical study of the Algerian higher education institution

    Science.gov (United States)

    Benchicou, Soraya; Aichouni, Mohamed; Nehari, Driss

    2010-06-01

    Technology-mediated education or e-learning is growing globally both in scale and delivery capacity due to the large diffusion of the ubiquitous information and communication technologies (ICT) in general and the web technologies in particular. This statement has not yet been fully supported by research, especially in developing countries such as Algeria. The purpose of this paper was to identify directions for addressing the needs of academics in higher education institutions in Algeria in order to adopt the e-learning approach as a strategy to improve quality of education. The paper will report results of an empirical study that measures the readiness of the Algerian higher education institutions towards the implementation of ICT in the educational process and the attitudes of faculty members towards the application of the e-learning approach in engineering education. Three main objectives were targeted, namely: (a) to provide an initial evaluation of faculty members' attitudes and perceptions towards web-based education; (b) reporting on their perceived requirements for implementing e-learning in university courses; (c) providing an initial input for a collaborative process of developing an institutional strategy for e-learning. Statistical analysis of the survey results indicates that the Algerian higher education institution, which adopted the Licence - Master and Doctorate educational system, is facing a big challenge to take advantage of emerging technological innovations and the advent of e-learning to further develop its teaching programmes and to enhance the quality of education in engineering fields. The successful implementation of this modern approach is shown to depend largely on a set of critical success factors that would include: 1. The extent to which the institution will adopt a formal and official e-learning strategy. 2. The extent to which faculty members will adhere and adopt this strategy and develop ownership of the various measures in the

  14. What they have in common the engineering from the Spanish nuclear power plants?; Que tienen en comun las ingenierias de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Mendez, M.

    2012-11-01

    In recent years, Spain Nuclear Power Plant Engineering have switched their project/task management method to Critical Chain multi-project management, developed by Dr. Goldratt, achieving outstanding results in improving quality and productivity. Multitasking reduction, task and resource synchronizing without the need of exact schedules, implementing a real-time priority information system, relying on the software Concerto, and daily decision making are the basis for the management change that has generated productivity increases of between 20% to 50%, opening new horizons for improvement in other scenarios such as optimizing refueling shutdowns. (Author)

  15. Implementing Total Quality Management to Improve Facilities and Resources of Departments in Engineering Institute

    OpenAIRE

    2014-01-01

    This research work aims to understand Total Quality Management concepts and evaluating the extent of TQM implementation in Mechanical Engineering Department through student feedback survey. In keeping with the newer demands that have been placed on the self financed educational system by the various stakeholders, the technical educational system in particular, has been pressured to shift its focus from one in quantitative expansion to one with emphasis on quality. Growth and s...

  16. Foreign Science and Engineering Presence in U.S. Institutions and the Labor Force

    Science.gov (United States)

    2008-07-23

    three-year increments). Typically the specialty occupation includes positions such as scientists, engineers, teachers , computer programmers, medical...doctors, and physical therapists . The application for H-1B status must be filed by (continued...) to 583,921 in 2004.5 It is estimated that by 2010...Marburger, Director, Office of Science and Technology Policy, Speech before the American Association for the Advancement of Science, Science and

  17. Meyerhoff Scholars Program: a strengths-based, institution-wide approach to increasing diversity in science, technology, engineering, and mathematics.

    Science.gov (United States)

    Maton, Kenneth I; Pollard, Shauna A; McDougall Weise, Tatiana V; Hrabowski, Freeman A

    2012-01-01

    The Meyerhoff Scholars Program at the University of Maryland, Baltimore County is widely viewed as a national model of a program that enhances the number of underrepresented minority students who pursue science, technology, engineering, and mathematics PhDs. The current article provides an overview of the program and the institution-wide change process that led to its development, as well as a summary of key outcome and process evaluation research findings. African American Meyerhoff students are 5× more likely than comparison students to pursue a science, technology, engineering, and mathematics PhD. Program components viewed by the students as most beneficial include financial scholarship, being a part of the Meyerhoff Program community, the Summer Bridge program, study groups, and summer research. Qualitative findings from interviews and focus groups demonstrate the importance of the Meyerhoff Program in creating a sense of belonging and a shared identity, encouraging professional development, and emphasizing the importance of academic skills. Among Meyerhoff students, several precollege and college factors have emerged as predictors of successful entrance into a PhD program in the science, technology, engineering, and mathematics fields, including precollege research excitement, precollege intrinsic math/science motivation, number of summer research experiences during college, and college grade point average. Limitations of the research to date are noted, and directions for future research are proposed.

  18. Materials Laboratory at the Institute of Nuclear Fusion: growth and characterization of coatings with nuclear applications; Laboratorio de Materiales en el Instituto de Fusion Nuclear: crecimiento y caracterizacion de recubrimientos con aplicaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez-Arrabal, R.; Gordillo, N.; Panizo-Laiz, M.; Fernandez-Martinez, I.; Wennberg, A.; Rivera, A.; Pena, O.; Briones, F.; Perlado, J. M.

    2013-07-01

    We report on the capabilities of the new materials lab located at the Instituto de Fusion Nuclear to develop coating for nuclear applications. The main objectives of the lab are described: (a) design of coatings which fulfil industrial requirements and (b) development of the need instrumentation to coat non-planar surfaces, i.e. inner and outer surface of pipes. Some examples of radiation resistance materials (self-healing) will be shown. Moreover, we present some new solution with improved corrosion resistance when facing liquid metals to conform the cooling system of future fission and fusion nuclear reactors. (Author)

  19. Thermal Hydraulics Design and Analysis Methodology for a Solid-Core Nuclear Thermal Rocket Engine Thrust Chamber

    Science.gov (United States)

    Wang, Ten-See; Canabal, Francisco; Chen, Yen-Sen; Cheng, Gary; Ito, Yasushi

    2013-01-01

    Nuclear thermal propulsion is a leading candidate for in-space propulsion for human Mars missions. This chapter describes a thermal hydraulics design and analysis methodology developed at the NASA Marshall Space Flight Center, in support of the nuclear thermal propulsion development effort. The objective of this campaign is to bridge the design methods in the Rover/NERVA era, with a modern computational fluid dynamics and heat transfer methodology, to predict thermal, fluid, and hydrogen environments of a hypothetical solid-core, nuclear thermal engine the Small Engine, designed in the 1960s. The computational methodology is based on an unstructured-grid, pressure-based, all speeds, chemically reacting, computational fluid dynamics and heat transfer platform, while formulations of flow and heat transfer through porous and solid media were implemented to describe those of hydrogen flow channels inside the solid24 core. Design analyses of a single flow element and the entire solid-core thrust chamber of the Small Engine were performed and the results are presented herein

  20. An improved ARS2-derived nuclear reporter enhances the efficiency and ease of genetic engineering in Chlamydomonas.

    Science.gov (United States)

    Specht, Elizabeth A; Nour-Eldin, Hussam Hassan; Hoang, Kevin T D; Mayfield, Stephen P

    2015-03-01

    The model alga Chlamydomonas reinhardtii has been used to pioneer genetic engineering techniques for high-value protein and biofuel production from algae. To date, most studies of transgenic Chlamydomonas have utilized the chloroplast genome due to its ease of engineering, with a sizeable suite of reporters and well-characterized expression constructs. The advanced manipulation of algal nuclear genomes has been hampered by limited strong expression cassettes, and a lack of high-throughput reporters. We have improved upon an endogenous reporter gene - the ARS2 gene encoding an arylsulfatase enzyme - that was first cloned and characterized decades ago but has not been used extensively. The new construct, derived from ARS2 cDNA, expresses significantly higher levels of reporter protein and transforms more efficiently, allowing qualitative and quantitative screening using a rapid, inexpensive 96-well assay. The improved arylsulfatase expression cassette was used to screen a new transgene promoter from the ARG7 gene, and found that the ARG7 promoter can express the ARS2 reporter as strongly as the HSP70-RBCS2 chimeric promoter that currently ranks as the best available promoter, thus adding to the list of useful nuclear promoters. This enhanced arylsulfatase reporter construct improves the efficiency and ease of genetic engineering within the Chlamydomonas nuclear genome, with potential application to other algal strains.

  1. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix D, Part B: Naval spent nuclear fuel management

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement.

  2. Innovations in the supply chain and construction engineering of nuclear-based heat transfer components

    Energy Technology Data Exchange (ETDEWEB)

    Perales, A. [Equipos Nucleares, S.A. - Ensa, Jose Ortega y Gasset, 28006 Madrid (Spain); Woolf, G. [Tecnicas Reunidas - TR, Arapiles, 28014 Madrid (Spain)

    2010-07-01

    Equipos Nucleares S.A. (Ensa) and Tecnicas Reunidas S.A. (TR), both long-established Spanish companies, have brought together innovative approaches for the supply of heat transfer solution packages by combining their respective experiences in heat exchanger design (TR), manufacturing (Ensa), and nuclear materials procurement (Ensa and TR), thereby founding a new potent European component supplier for nuclear power plants with over 50 years of experience in the global nuclear market. The combined strategy of the Ensa-TR association which addresses the problems currently faced by nuclear component suppliers is described herein. (authors)

  3. A Strategy Study on the SCI List of Nuclear Engineering and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Yi, Ji Ho; Lee, Yoo Jin; Jeong, Jo Enn [Korea Atomic Energy Reserch Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The number of papers published in SCI (Science Citation Index) journal is used as a standard for evaluating the level of science technology and a comparative ranking among countries; thus, the journal of the Korean Nuclear Society (KNS), in the SCI. For the SCI, there are 3,750 journals of core (standard) and 4,824 journals of expanded versions; however, NET belongs to the expanded version. As of January 2014, only 12 Korean journals were listed in the SCI core journals and 90 journals were listed in the expanded version. In order for NET of KNS to grow as an international journal, it must be listed in the SCI. With a view to pursuing this goal, it is imperative to undertake the following efforts. First, many good papers should be attracted. That is, the publication of invited papers should be promoted, and a special edition should be issued with the inclusion of prestigious scientists in Korea and overseas who are able to raise the If. Also, a contributor should be given direct and indirect incentives, and above all, academic personnel should be actively involved. Second, internationalization of the journals is needed. In other words, the authors, editors, and reviewers should be more international. In particular, the activities of foreign editors should be fortified. Third, promotion should b reinforced. That is, an independent web site of NET should be operated, and in particular, a paper submission system should be composed scientifically. Fourth, the society system should be improved. In other words, for many good papers to be submitted, an institutional improvement is required to revise the regulations under which the results of a citation analysis can be reflected and to strengthen the activities of the editing committee.

  4. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

    1994-10-01

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

  5. Potential contribution of materials investigations in reducing the risks of unavailability of nuclear civil engineering infrastructures

    Energy Technology Data Exchange (ETDEWEB)

    Goy, R.; Gaine, C.; Cornish-Bowden, I.; Auge, L.; Thillard, G.; Capra, B. [Oxand (France)

    2011-07-01

    Many consulting assignments undertaken by Oxand within the framework of life-cycle management of existing nuclear civil engineering structures, relied on taking into account the structure's level of deterioration, the quantitative estimate of its residual strength capacity and the future progression of this capacity over time. The developments of structure assessment techniques allow more and more the integration of the real state of the existing structure by enhancing the value of measures and investigations carried out on structures. On one hand, this information allows to take into account the structure's ageing and therefore estimate the residual resistance and reliability. On the other hand, by investigating the real properties of the structure and of its operation, refined calculations can sometimes highlight a resistance margin of the structure 'such as built' higher than the one considered during design. The precision on the 'real' reliability of the structure allows to refine its management and thus to optimize the infrastructure's performance. Developments of assessment methods are increasingly oriented toward probabilistic approaches. Although they go out of the 'classical regulatory' framework, they bring precision on the 'real' reliability of the structure. Using higher assessment levels needs to have more important and precise input data, what can lead to the need to carry out more detailed investigations. However, these methods offer interesting ways, which can provide, in certain cases, useful additional information for the decision-making of actions to be engaged. The methodology is illustrated with the case of a network of reinforced concrete beams, which are subjected to a rapid increase in their mechanical stresses. In particular this example shows that investigations on the real performances of materials can provided a significant contribution in managing the risks of unavailability

  6. Strengthening the fission reactor nuclear science and engineering program at UCLA. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Okrent, D.

    1997-06-23

    This is the final report on DOE Award No. DE-FG03-92ER75838 A000, a three year matching grant program with Pacific Gas and Electric Company (PG and E) to support strengthening of the fission reactor nuclear science and engineering program at UCLA. The program began on September 30, 1992. The program has enabled UCLA to use its strong existing background to train students in technological problems which simultaneously are of interest to the industry and of specific interest to PG and E. The program included undergraduate scholarships, graduate traineeships and distinguished lecturers. Four topics were selected for research the first year, with the benefit of active collaboration with personnel from PG and E. These topics remained the same during the second year of this program. During the third year, two topics ended with the departure o the students involved (reflux cooling in a PWR during a shutdown and erosion/corrosion of carbon steel piping). Two new topics (long-term risk and fuel relocation within the reactor vessel) were added; hence, the topics during the third year award were the following: reflux condensation and the effect of non-condensable gases; erosion/corrosion of carbon steel piping; use of artificial intelligence in severe accident diagnosis for PWRs (diagnosis of plant status during a PWR station blackout scenario); the influence on risk of organization and management quality; considerations of long term risk from the disposal of hazardous wastes; and a probabilistic treatment of fuel motion and fuel relocation within the reactor vessel during a severe core damage accident.

  7. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

    1994-10-01

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

  8. Development and implementation of an institutional repository within a Science, Engineering and Technology (SET) environment

    CSIR Research Space (South Africa)

    Van der Merwe, Adèle

    2008-10-01

    Full Text Available not be equated to plagiarism nor with inferior quality. 1.2 Benefits and value of an IR Allard et al [2005:170] explains the value of IRs as services that provides members with ‘…the ability to add, or self-archive, items they have authored … thereby... of the CSIR. It was also decided to deviate from the general academic institution approach and to make the repository a sub-set of an existing classified database. The IR therefore will contain all the publicly available publications and special...

  9. Description and Methods of the Automated Document Management System Usage in Scientific Organizational Activities of the Joint Institute for Nuclear Research (ADS SOA JINR)

    CERN Document Server

    Borisovsky, V F; Kekelidze, M G; Nikonov, E G; Senchenko, V A

    2005-01-01

    This paper presents the structure description and user guide for Information program system for automation of a document flow for support of scientific arrangement planning (ADS SOA) which can be used for planning and carrying out seminars, workshops, conferences and other arrangements of research management. This work is intended for automation of scientific research management in the Joint Institute for Nuclear Research. The complex of programs represents the CDS Agenda system used in the European Organization for Nuclear Research (CERN), which is adapted to the conditions of JINR.

  10. Relevance of First-Tier, Peer-Reviewed Journals in the Tenure and Promotion Process at Non-Doctoral Granting Engineering Institutions

    Directory of Open Access Journals (Sweden)

    Amanda S. Florio

    2012-02-01

    Full Text Available The IEEE (formerly the Institute of Electrical and Electronics Engineers is the world's largest professional society dedicated to the advancement of technology. While it is indeed growing into multiple technology areas, the IEEE is still first an organization of electrical, electronics, and computer engineering professionals. It has over 400,000 members and publishes nearly 100, first-tier, peer-reviewed journals. As such a large purveyor of scholarly works, engineering faculty at almost all academic institutions (doctoral granting and non-doctoral granting are familiar with the IEEE. For this reason, the IEEE makes an excellent case study for the relevance of first-tier, peer-reviewed journals in the tenure and promotion process at non-doctoral granting engineering institutions. In our work, we surveyed editors of the 97 IEEE journals. 93% of respondents indicated that 10% or less of their submissions were from non-academic institutions. None (0% of the respondents believed that the number of non-doctoral granting institution submissions would be increasing over the next three years. In fact, a majority of the respondents (55% see the number of non-doctoral granting institution submissions decreasing in the same time frame. To correlate this data, we examined a sample of 2,099 articles published in the first issue of each IEEE journal in 2009. 357 (17% of these 2,099 articles were authored by individuals from academic institutions in the United States. Of the 357, only 35 were published by individuals from non-doctoral granting institutions (1.7%, with only 8 (0.38% from institutions where a bachelor degree is the highest offered.

  11. Pengembangan Peta Tiga Dimensi Interaktif untuk Dharma Wanita, TK dan Wisma Yasmine Institut Teknologi Sepuluh Nopember Menggunakan Unreal Engine

    Directory of Open Access Journals (Sweden)

    Mochamad Rahman Irwandi

    2013-12-01

    Full Text Available Peningkatan teknologi yang berkembang pesat saat ini berdampak pada penyajian informasi mengenai bangunan, yang dahulu menggunakan dua dimensi (2D, tetapi sekarang menggunakan tiga dimensi (3D. Tampilan gambar 3D ini membuat bangunan terlihat lebih detail dan menarik, tak terkecuali pada perguruan tinggi Institut Teknologi Sepuluh Nopember (ITS yang menjadi objek visualisasi 3D sebagai sarana promosi pada konsumen.Pada tugas akhir ini penulis mengembangkan aplikasi peta tiga dimensi dengan menggunakan Unreal Development Kit (UDK Engine. Aplikasi peta 3D ini menyajikan tampilan Gedung Dharma Wanita, TK dan Wisma Yasmine ITS secara interaktif dan akurat, sehingga pengguna mendapatkan pengalaman yang berbeda dengan mengetahui gedung Dharma Wanita, TK dan Wisma Yasmine ITS secara virtual tanpa harus pergi ke tempat tersebut

  12. Superconductivity in the Institute for Low Temperature Physics and Engineering of the National Academy of Sciences of Ukraine

    Science.gov (United States)

    Bondarenko, Stanislav; Koverya, Valentin

    2015-09-01

    The report contains a brief history of the superconductor’s researches and their applications carried out in the Institute for Low Temperature Physics and Engineering (ILTPE) of the National Academy of Sciences of Ukraine since the ILTPE foundation in 1960. The most important results of the researches in the field of the low- and high-temperature superconductors (HTS) are stated more detailed. The experimental validation of an electromagnetic radiation of Josephson junctions; the electron pairing and existence of the distant order in the HTS; a creation of the superconducting quantum interference devices (SQUIDs) on the basis of the HTS; formation and moving of the local frozen magnetic field along the surface of the HTS; the transport properties of new Fe-based superconductors can be referred to such results.

  13. Combinatorial Algorithms to Enable Computational Science and Engineering: The CSCAPES Institute

    Energy Technology Data Exchange (ETDEWEB)

    Pothen, Alex [Purdue University

    2015-01-16

    This final progress report summarizes the work accomplished at the Combinatorial Scientific Computing and Petascale Simulations Institute. We developed Zoltan, a parallel mesh partitioning library that made use of accurate hyeprgraph models to provide load balancing in mesh-based computations. We developed several graph coloring algorithms for computing Jacobian and Hessian matrices and organized them into a software package called ColPack. We developed parallel algorithms for graph coloring and graph matching problems, and also designed multi-scale graph algorithms. Three PhD students graduated, six more are continuing their PhD studies, and four postdoctoral scholars were advised. Six of these students and Fellows have joined DOE Labs (Sandia, Berkeley, as staff scientists or as postdoctoral scientists. We also organized the SIAM Workshop on Combinatorial Scientific Computing (CSC) in 2007, 2009, and 2011 to continue to foster the CSC community.

  14. Combinatorial Algorithms to Enable Computational Science and Engineering: Work from the CSCAPES Institute

    Energy Technology Data Exchange (ETDEWEB)

    Boman, Erik G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Scalable Algorithms Dept.; Catalyurek, Umit V. [The Ohio State Univ., Columbus, OH (United States). Biomedical Informatics. Electrical and Computer Engineering; Chevalier, Cedric [Alternative Energies and Atomic Energy Commission (CEA), Cadarache (France); Devine, Karen D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Scalable Algorithms Dept.; Gebremedhin, Assefaw H. [Purdue Univ., West Lafayette, IN (United States). Computer Science; Hovland, Paul D. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Pothen, Alex [Purdue Univ., West Lafayette, IN (United States). Computer Science; Rajamanickam, Sivasankaran [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Scalable Algorithms Dept.; Safro, Ilya [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Wolf, Michael M. [Massachusetts Inst. of Technology (MIT), Lexington, MA (United States). Lincoln Lab.; Zhou, Min [Rensselaer Polytechnic Inst., Troy, NY (United States). Scientific Computation Research Center

    2015-01-16

    This final progress report summarizes the work accomplished at the Combinatorial Scientific Computing and Petascale Simulations Institute. We developed Zoltan, a parallel mesh partitioning library that made use of accurate hypergraph models to provide load balancing in mesh-based computations. We developed several graph coloring algorithms for computing Jacobian and Hessian matrices and organized them into a software package called ColPack. We developed parallel algorithms for graph coloring and graph matching problems, and also designed multi-scale graph algorithms. Three PhD students graduated, six more are continuing their PhD studies, and four postdoctoral scholars were advised. Six of these students and Fellows have joined DOE Labs (Sandia, Berkeley), as staff scientists or as postdoctoral scientists. We also organized the SIAM Workshop on Combinatorial Scientific Computing (CSC) in 2007, 2009, and 2011 to continue to foster the CSC community.

  15. Investigation of radon level in air and tap water of workplaces at Thailand Institute of Nuclear Technology, Thailand

    Science.gov (United States)

    Sola, P.; Youngchuay, U.; Kongsri, S.; Kongtana, A.

    2017-06-01

    Thailand Institute of Nuclear Technology (TINT) has continuously monitored radiation exposure and radionuclide in workplaces specifically radon gas to estimate effective dose for workers. Radon exposure is the second leading cause of lung cancer in the world. In this study, radon in air and tap water at building no. 3, 7, 8, 9 and 18 on Ongkharak site of TINT have been measured for 5 years from 2012 to 2016. Radon level in air and tap water were investigated on 83 stations (workplaces) and 54 samples, respectively. Radon concentrations in air and tap water were measured by using the pulsed ionization chamber (ATMOS 12 DPX). Indoor radon concentrations in air were in the range of 12-138 Bq.m-3 with an average value of 30.13±17.05 Bq.m-3. Radon concentrations in tap water were in the range of 0.10 to 2.89 Bq.l-1 with an average value of 0.51±0.55 Bq.l-1. The results of radon concentrations at TINT were below the US Environmental Protection Agency (US EPA) safety limit of 148 Bq.m-3 and 150 Bq.l-1, for, air and tap water, respectively. The average effective dose for TINT’s workers due to indoor radon exposure was approximately 0.20±0.11 mSv.y-1. The value is 100 times less than the annual dose limit for limit occupational radiation worker defined by the International Commission on Radiological Protection (ICRP). As a result, the TINT’s workplaces are radiologically safe from radon content in air and tap water.

  16. Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

    The Mathematics and Computation Division of the American Nuclear (ANS) and the Idaho Section of the ANS hosted the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M and C 2013). This proceedings contains over 250 full papers with topics ranging from reactor physics; radiation transport; materials science; nuclear fuels; core performance and optimization; reactor systems and safety; fluid dynamics; medical applications; analytical and numerical methods; algorithms for advanced architectures; and validation verification, and uncertainty quantification.

  17. Deutsches SOFIA Institut (DSI) at the SOFIA Science Center: engineering and scientific contributions to the airborne observatory

    Science.gov (United States)

    Wolf, Jürgen; Colditz, Sebastian; Lachenmann, Michael; Pfüller, Enrico; Schindler, Karsten; Wiedemann, Manuel; Zinnecker, Hans; Krabbe, Alfred

    2016-09-01

    The Stratospheric Observatory for Infrared Astronomy (SOFIA) is a 2.5-meter infrared telescope built into a Boeing 747SP. In 2014 SOFIA reached its "Full Operational Capability" milestone and nowadays takes off about three times a week to observe the infrared sky from altitudes above most of the atmosphere's water vapor content. Despite reaching this major milestone, efforts to improve the observatory's performance are continuing in many areas. The team of the Deutsches SOFIA Institut, DSI (German SOFIA Institute) at the SOFIA Science Center in Moffett Field, CA works in several engineering areas to improve the observatory's performance and its efficiency. DSI supports the allocation process of SOFIA's observation time for guest observers, provides and supports two facility science instruments and conducts an observing program of stellar occultations by small objects of the solar system. This paper summarizes results and ongoing work on a spare secondary mirror made of aluminum, the new and improved Focal Plane Imager (FPI+) that has become a facility science instrument, the Field-Imaging Far-Infrared Line Spectrometer (FIFI-LS), new cameras and optics for the Fine Field and Wide Field Imagers (FFI+ and WFI+), real-time astrometric solution of star field images, ground support equipment and astronomical observations.

  18. Gas-filled position-sensitive detectors of thermal neutrons at the Konstantinov Petersburg Nuclear Physics Institute of the Russian Academy of Sciences

    Science.gov (United States)

    Andreev, V. A.; Ganzha, G. A.; Ivanov, E. A.; Ilyin, D. S.; Kovalenko, S. N.; Kolkhidashvili, M. R.; Krivshich, A. G.; Nadtochy, A. V.; Runov, V. V.; Soloveĭ, V. A.; Shabanov, G. D.

    2010-05-01

    The manufacturing line for the development and fabrication of position-sensitive detectors of thermal neutrons has been organized at the Petersburg Nuclear Physics Institute of the Russian Academy of Sciences. Three detectors with sensitive regions 300 × 170 (prototype), 200 × 200, and 300 × 300 mm in size have been constructed to date. The detectors represent multiwire proportional chambers with cathode data readout to a delay line. The devices are filled with the 3He/CF4 gas mixture. These detectors are intended for modernizing the detector systems of the Vector and Membrana-2 diffractometers (VVR-M reactor, Konstantinov Petersburg Nuclear Physics Institute of the Russian Academy of Sciences, Gatchina, Russia).

  19. Study of The Vector Product using Three Dimensions Vector Card of Engineering in Pathumwan Institute of Technology

    Science.gov (United States)

    Mueanploy, Wannapa

    2015-06-01

    The objective of this research was to offer the way to improve engineering students in Physics topic of vector product. The sampling of this research was the engineering students at Pathumwan Institute of Technology during the first semester of academic year 2013. 1) Select 120 students by random sampling are asked to fill in a satisfaction questionnaire scale, to select size of three dimensions vector card in order to apply in the classroom. 2) Select 60 students by random sampling to do achievement test and take the test to be used in the classroom. The methods used in analysis of achievement test by the Kuder-Richardson Method (KR- 20). The results show that 12 items of achievement test are appropriate to be applied in the classroom. The achievement test gets Difficulty (P) = 0.40-0.67, Discrimination = 0.33-0.73 and Reliability (r) = 0.70.The experimental in the classroom. 3) Select 60 students by random sampling divide into two groups; group one (the controlled group) with 30 students was chosen to study in the vector product lesson by the regular teaching method. Group two (the experimental group) with 30 students was chosen to learn the vector product lesson with three dimensions vector card. 4) Analyzed data between the controlled group and the experimental group, the result showed that experimental group got higher achievement test than the controlled group significant at .01 level.

  20. Science, Technology, Engineering, Math (STEM) in Higher Education from the Perspective of Female Students: An Institutional Ethnography

    Science.gov (United States)

    Parson, Laura J.

    A persistent disadvantage for females is systemically embedded in Science, Technology, Engineering, and Math (STEM) education in postsecondary institutions. As a result, undergraduate women majoring in STEM fields face a uniquely difficult path; yet, for the most part, recommendations made and supported in the literature have focused on recruitment of women to STEM fields or on ways to make women more successful and comfortable in their STEM major. These recommendations have so far proved to be insufficient to remedy a gender gap and serve to replicate the existing male hierarchy. In order to truly make the STEM classroom one in which women are welcome and comfortable and to challenge the existing social and scientific systems, it is necessary to explore and understand the social and political implications embedded within teaching and learning choices. This institutional ethnography addresses that gap. The purpose of this study was to uncover and describe the institutional practices of STEM education at a Midwest research university (MRU) from the standpoint of female undergraduate students. Using the framework of feminist standpoint theory, this study explored the everyday "work" of female undergraduate STEM students to provide a unique perspective on the STEM education teaching and learning environment. Data collection began with in-depth interviews with female undergraduate math and physics students. As the institutional processes shaping undergraduate participant experiences were identified, subsequent data collection included classroom observations, additional interviews with students and faculty, and analysis of the texts that mediate these processes (e.g., syllabi and student handbooks). Data analysis followed Carspecken's process of ethnographic data analysis that began with low-level coding, followed by high-level coding, and concluded by pulling codes together through the creation of themes. Analysis of data led to three key findings. First, undergraduate

  1. Engineering, institutions, and the public interest: Evaluating product quality in the Kenyan solar photovoltaics industry

    Energy Technology Data Exchange (ETDEWEB)

    Jacobson, Arne [Environmental Resources Engineering and Schatz Energy Research Center, Humboldt State University (United States); Kammen, Daniel M. [Energy and Resources Group and Goldman School of Public Policy, University of California, Berkeley (United States)

    2007-05-15

    Solar sales in Kenya are among the highest per capita among developing countries. While this commercial success makes the Kenya market a global leader, product quality problems have been a persistent concern. In this paper, we report performance test results from 2004 to 2005 for five brands of amorphous silicon (a-Si) photovoltaic (PV) modules sold in the Kenya market. Three of the five brands performed well, but two performed well below their advertised levels. These results support previous work indicating that high-quality a-Si PV modules are a good economic value. The presence of the low performing brands, however, confirms a need for market institutions that ensure the quality of all products sold in the market. Prior work from 1999 indicated a similar quality pattern among brands. This confirms the persistent nature of the problem, and the need for vigilant, long-term approaches to quality assurance for solar markets in Kenya and elsewhere. Following the release of our 2004/2005 test results in Kenya, the Kenya Bureau of Standards moved to implement and enforce performance standards for both amorphous and crystalline silicon PV modules. This appears to represent a positive step towards the institutionalization of quality assurance for products in the Kenya solar market. (author)

  2. Assessing controls on perched saturated zones beneath the Idaho Nuclear Technology and Engineering Center, Idaho

    Science.gov (United States)

    Mirus, Benjamin B.; Perkins, Kim S.; Nimmo, John R.

    2011-01-01

    Waste byproducts associated with operations at the Idaho Nuclear Technology and Engineering Center (INTEC) have the potential to contaminate the eastern Snake River Plain (ESRP) aquifer. Recharge to the ESRP aquifer is controlled largely by the alternating stratigraphy of fractured volcanic rocks and sedimentary interbeds within the overlying vadose zone and by the availability of water at the surface. Beneath the INTEC facilities, localized zones of saturation perched on the sedimentary interbeds are of particular concern because they may facilitate accelerated transport of contaminants. The sources and timing of natural and anthropogenic recharge to the perched zones are poorly understood. Simple approaches for quantitative characterization of this complex, variably saturated flow system are needed to assess potential scenarios for contaminant transport under alternative remediation strategies. During 2009-2011, the U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, employed data analysis and numerical simulations with a recently developed model of preferential flow to evaluate the sources and quantity of recharge to the perched zones. Piezometer, tensiometer, temperature, precipitation, and stream-discharge data were analyzed, with particular focus on the possibility of contributions to the perched zones from snowmelt and flow in the neighboring Big Lost River (BLR). Analysis of the timing and magnitude of subsurface dynamics indicate that streamflow provides local recharge to the shallow, intermediate, and deep perched saturated zones within 150 m of the BLR; at greater distances from the BLR the influence of streamflow on recharge is unclear. Perched water-level dynamics in most wells analyzed are consistent with findings from previous geochemical analyses, which suggest that a combination of annual snowmelt and anthropogenic sources (for example, leaky pipes and drainage ditches) contribute to recharge of shallow and

  3. High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Solin, Pavel [Univ. of Reno, NV (United States); Ragusa, Jean [Texas A & M Univ., College Station, TX (United States)

    2014-03-09

    We delivered a series of fundamentally new computational technologies that have the potential to significantly advance the state-of-the-art of computer simulations of transient multiphysics nuclear reactor processes. These methods were implemented in the form of a C++ library, and applied to a number of multiphysics coupled problems relevant to nuclear reactor simulations.

  4. Institute for Scientific and Educational Technology (ISET)-Education, Research and Training Programs in Engineering and Sciences

    Science.gov (United States)

    Tiwari, S. N. (Principal Investigator); Massenberg, Samuel E. (Technical Monitor)

    2002-01-01

    The 'Institute for Scientific and Educational Technology' has been established to provide a mechanism through which universities and other research organizations may cooperate with one another and with different government agencies and industrial organizations to further and promote research, education, and training programs in science, engineering, and related fields. This effort has been undertaken consistent with the national vision to 'promote excellence in America s educational system through enhancing and expanding scientific and technological competence.' The specific programs are directed in promoting and achieving excellence for individuals at all levels (elementary and secondary schools, undergraduate and graduate education, and postdoctoral and faculty research). The program is consistent with the existing activities of the Institute for Computational and Applied Mechanics (ICAM) and the American Society for Engineering Education (ASEE) at NASA Langley Research Center (LaRC). The efforts will be directed to embark on other research, education, and training activities in various fields of engineering, scientific, and educational technologies. The specific objectives of the present program may be outlined briefly as follows: 1) Cooperate in the various research, education, and technology programs of the Office of Education at LaRC. 2) Develop procedures for interactions between precollege, college, and graduate students, and between faculty and students at all levels. 3) Direct efforts to increase the participation by women and minorities in educational programs at all levels. 4) Enhance existing activities of ICAM and ASEE in education, research, and training of graduate students and faculty. 5) Invite distinguished scholars as appropriate and consistent with ISET goals to spend their summers and/or sabbaticals at NASA Langley andor ODU and interact with different researchers and graduate students. Perform research and administrative activities as needed

  5. Pengembangan Peta Interaktif Tiga Dimensi Perpustakaan Pusat Institut Teknologi Sepuluh Nopember Menggunakan Unreal Engine

    Directory of Open Access Journals (Sweden)

    Mazza Fitroni

    2015-03-01

    Full Text Available Teknologi yang semakin berkembang pesat saat ini membuat penyampaian informasi kepada masyarakat sangat cepat dan banyak perubahan terutama mengenai bangunan. Dahulu penyampaian informasi mengenai bangunan hanya menggunakan dua dimensi (2D, namun sekarang dapat menggunakan tiga dimensi (3D. Tampilan informasi bangunan gambar 3D ini menjadi terlihat lebih jelas, menarik, dan detail. Tak terkecuali pada perguruan tinggi Intstitut Teknologi Sepuluh Nopember (ITS menjadi objek visualisasi 3D sebagai sarana promosi terhadap konsumen atau calon mahasiswa baru. Pada paper ini akan berisi tentang aplikasi virtual peta 3D yang akan menampilkan objek sebuah gedung Perpustakaan Pusat ITS. Aplikasi yang nanti akan digunakan dalam pembuatan virtual 3D adalah dengan Unreal Engine, dan adobe Flash sebagai user interface untuk informasi dan interaksi didalamnya. Aplikasi pendukung utama yaitu 3Ds Max untuk modelling benda 3D. Aplikasi virtual peta 3D nantinya akan menyampaikan tampilan sebuah Gedung Perpustakaan Pusat ITS yang memudahkan pengguna / user untuk mengetahui dan mengunjungi gedung tersebut secara virtual seperti dunia nyata

  6. Instrumentation Requirements for the Engineering Evaluation of Nuclear-Electric Spacecraft

    Science.gov (United States)

    Apel, W. C.

    1961-01-01

    Spacecraft employing nuclear-electric propulsion are being proposed for missions to Venus and distances beyond. These spacecraft utilize a nuclear reactor to provide thermal energy to a turboalternator which generates electric power for an ion motor and the other spacecraft systems. This Report discusses the instrumentation and communications system needed to evaluate a nuclear-electric spacecraft in flight, along with the problems expected. A representative spacecraft design is presented, which leads to a discussion of the instrumentation needed to evaluate such a spacecraft. A basic communications system is considered for transmitting the spacecraft data to Earth. The instrumentation and communications system, as well as all electronic systems on a nuclear-electric spacecraft, will be operating in high temperature and nuclear-radiation environments. The problems caused by these environments are discussed, and possible solutions are offered.

  7. Instrumentation Requirements for the Engineering Evaluation of Nuclear-Electric Spacecraft

    Science.gov (United States)

    Apel, W. C.

    1961-01-01

    Spacecraft employing nuclear-electric propulsion are being proposed for missions to Venus and distances beyond. These spacecraft utilize a nuclear reactor to provide thermal energy to a turboalternator which generates electric power for an ion motor and the other spacecraft systems. This Report discusses the instrumentation and communications system needed to evaluate a nuclear-electric spacecraft in flight, along with the problems expected. A representative spacecraft design is presented, which leads to a discussion of the instrumentation needed to evaluate such a spacecraft. A basic communications system is considered for transmitting the spacecraft data to Earth. The instrumentation and communications system, as well as all electronic systems on a nuclear-electric spacecraft, will be operating in high temperature and nuclear-radiation environments. The problems caused by these environments are discussed, and possible solutions are offered.

  8. Neutron Transport and Nuclear Burnup Analysis for the Laser Inertial Confinement Fusion-Fission Energy (LIFE) Engine

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, K J; Latkowski, J F; Abbott, R P; Boyd, J K; Powers, J J; Seifried, J E

    2008-10-24

    Lawrence Livermore National Laboratory is currently developing a hybrid fusion-fission nuclear energy system, called LIFE, to generate power and burn nuclear waste. We utilize inertial confinement fusion to drive a subcritical fission blanket surrounding the fusion chamber. It is composed of TRISO-based fuel cooled by the molten salt flibe. Low-yield (37.5 MJ) targets and a repetition rate of 13.3 Hz produce a 500 MW fusion source that is coupled to the subcritical blanket, which provides an additional gain of 4-8, depending on the fuel. In the present work, we describe the neutron transport and nuclear burnup analysis. We utilize standard analysis tools including, the Monte Carlo N-Particle (MCNP) transport code, ORIGEN2 and Monteburns to perform the nuclear design. These analyses focus primarily on a fuel composed of depleted uranium not requiring chemical reprocessing or enrichment. However, other fuels such as weapons grade plutonium and highly-enriched uranium are also under consideration. In addition, we have developed a methodology using {sup 6}Li as a burnable poison to replace the tritium burned in the fusion targets and to maintain constant power over the lifetime of the engine. The results from depleted uranium analyses suggest up to 99% burnup of actinides is attainable while maintaining full power at 2GW for more than five decades.

  9. White Paper on Nuclear Astrophysics and Low Energy Nuclear Physics - Part 1. Nuclear Astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Arcones, Almudena [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, Jutta E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Others, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-04-04

    This white paper informs the nuclear astrophysics community and funding agencies about the scientific directions and priorities of the field and provides input from this community for the 2015 Nuclear Science Long Range Plan. It summarizes the outcome of the nuclear astrophysics town meeting that was held on August 21 - 23, 2014 in College Station at the campus of Texas A&M University in preparation of the NSAC Nuclear Science Long Range Plan. It also reflects the outcome of an earlier town meeting of the nuclear astrophysics community organized by the Joint Institute for Nuclear Astrophysics (JINA) on October 9 - 10, 2012 Detroit, Michigan, with the purpose of developing a vision for nuclear astrophysics in light of the recent NRC decadal surveys in nuclear physics (NP2010) and astronomy (ASTRO2010). The white paper is furthermore informed by the town meeting of the Association of Research at University Nuclear Accelerators (ARUNA) that took place at the University of Notre Dame on June 12 - 13, 2014. In summary we find that nuclear astrophysics is a modern and vibrant field addressing fundamental science questions at the intersection of nuclear physics and astrophysics. These questions relate to the origin of the elements, the nuclear engines that drive life and death of stars, and the properties of dense matter. A broad range of nuclear accelerator facilities, astronomical observatories, theory efforts, and computational capabilities are needed. With the developments outlined in this white paper, answers to long-standing key questions are well within reach in the coming decade.

  10. Study of advanced professional educational requirements relative to nuclear fuel cycle engineering in industry and government. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Jur, T.A.; Huhns, M.N.; Keating, D.A.; Orloff, D.I.; Rhodes, C.A.; Stanford, T.G.; Stephens, L.M.; Tatterson, G.B.; Van Brunt, V.

    1978-12-01

    An assessment was conducted of educational needs among engineers working in nuclear fuel cycle-related areas, focusing on the nuclear industry in the Southeast. Educational needs addressed were those at the post-baccalaureate professional level. As a result of the study, a list of subject areas has been compiled as best representing the current content of an educational program. In addition to identifying subject areas, a set of course descriptions and reference materials has been developed around each subject. Each course description contains information regarding objectives, anticipated audience, and prerequisites and offers a suggested course outline. An initial modest program of implementation is recommended which would continue to concentrate on the Southeast as a target area.

  11. The outlook for application of powerful nuclear thermionic reactor - powered space electric jet propulsion engines

    Energy Technology Data Exchange (ETDEWEB)

    Semyonov, Y.P.; Bakanov, Y.A.; Synyavsky, V.V.; Yuditsky, V.D. [Rocket-Space Corp. `Energia`, Moscow (Russian Federation)

    1997-12-31

    This paper summarizes main study results for application of powerful space electric jet propulsion unit (EJPUs) which is powered by Nuclear Thermionic Power Unit (NTPU). They are combined in Nuclear Power/Propulsion Unit (NPPU) which serves as means of spacecraft equipment power supply and spacecraft movement. Problems the paper deals with are the following: information satellites delivery and their on-orbit power supply during 10-15 years, removal of especially hazardous nuclear wastes, mining of asteroid resources and others. Evaluations on power/time/mass relationship for this type of mission are given. EJPU parameters are compatible with Russian existent or being under development launch vehicle. (author)

  12. Affordable Development and Demonstration of a Small Nuclear Thermal Rocket (NTR) Engine and Stage: How Small Is Big Enough?

    Science.gov (United States)

    Borowski, Stanley K.; Sefcik, Robert J.; Fittje, James E.; McCurdy, David R.; Qualls, Arthur L.; Schnitzler, Bruce G.; Werner, James E.; Weitzberg, Abraham; Joyner, Claude R.

    2016-01-01

    The Nuclear Thermal Rocket (NTR) derives its energy from fission of uranium-235 atoms contained within fuel elements that comprise the engine's reactor core. It generates high thrust and has a specific impulse potential of approximately 900 specific impulse - a 100 percent increase over today's best chemical rockets. The Nuclear Thermal Propulsion (NTP) project, funded by NASA's Advanced Exploration Systems (AES) program, includes five key task activities: (1) Recapture, demonstration, and validation of heritage graphite composite (GC) fuel (selected as the Lead Fuel option); (2) Engine Conceptual Design; (3) Operating Requirements Definition; (4) Identification of Affordable Options for Ground Testing; and (5) Formulation of an Affordable Development Strategy. During fiscal year (FY) 2014, a preliminary Design Development Test and Evaluation (DDT&E) plan and schedule for NTP development was outlined by the NASA Glenn Research Center (GRC), Department of Energy (DOE) and industry that involved significant system-level demonstration projects that included Ground Technology Demonstration (GTD) tests at the Nevada National Security Site (NNSS), followed by a Flight Technology Demonstration (FTD) mission. To reduce cost for the GTD tests and FTD mission, small NTR engines, in either the 7.5 or 16.5 kilopound-force thrust class, were considered. Both engine options used GC fuel and a common fuel element (FE) design. The small approximately 7.5 kilopound-force criticality-limited engine produces approximately157 thermal megawatts and its core is configured with parallel rows of hexagonal-shaped FEs and tie tubes (TTs) with a FE to TT ratio of approximately 1:1. The larger approximately 16.5 kilopound-force Small Nuclear Rocket Engine (SNRE), developed by Los Alamos National Laboratory (LANL) at the end of the Rover program, produces approximately 367 thermal megawatts and has a FE to TT ratio of approximately 2:1. Although both engines use a common 35-inch (approximately

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. Management of nuclear training center

    Energy Technology Data Exchange (ETDEWEB)

    Seo, In Suk; Lee, Han Young; Cho, Boung Jae; Lee, Seung Hee; Lee, Eoi Jin; You, Byung Hoon; Lee, Won Ku; Jeon, Hyung Ryeon; Seo, Kyung Won; Kim, Young Joong; Kim, Ik Hyun; Hyun, Ha Il; Choi, Il Ki; Hong, Choon Sun; Won, Jong Yeul; Joo, Yong Chang; Nam, Jae Yeul; Sin, Eun Jeong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-02-01

    This report describes the annual results of training courses. The scope and contents are as follows : 1. Regional and interregional training courses, 2. Training courses assisted by foreign experts, 3. Training courses for nuclear industry personnel, 4. Training courses for internal staff-members, 5. Training courses under the law. The nuclear training center executed the open-door training courses for 2,699 engineers/scientists from the regulatory body, nuclear industries, research institutes and other related organizations by means of offering 69 training courses during the fiscal year 1995. (Author) .new.

  2. Nuclear power - the glittering prizes

    Energy Technology Data Exchange (ETDEWEB)

    Horton, C.C.

    The paper on the benefits of nuclear power is based on a lecture given for the Institution of Nuclear Engineers, London, 1986. Suggestions for short term benefits include a clean environment and a cheap energy source, whereas suggestions for long term benefits include freedom from want in the world and avoidance of 'energy wars'. These benefits are discussed along with alternative energy sources, the financial savings to be saved from nuclear power, world energy wealth, depletion of world energy reserves, and risks due to radiation exposure.

  3. Terpene metabolic engineering via nuclear or chloroplast genomes profoundly and globally impacts off-target pathways through metabolite signalling.

    Science.gov (United States)

    Pasoreck, Elise K; Su, Jin; Silverman, Ian M; Gosai, Sager J; Gregory, Brian D; Yuan, Joshua S; Daniell, Henry

    2016-09-01

    The impact of metabolic engineering on nontarget pathways and outcomes of metabolic engineering from different genomes are poorly understood questions. Therefore, squalene biosynthesis genes FARNESYL DIPHOSPHATE SYNTHASE (FPS) and SQUALENE SYNTHASE (SQS) were engineered via the Nicotiana tabacum chloroplast (C), nuclear (N) or both (CN) genomes to promote squalene biosynthesis. SQS levels were ~4300-fold higher in C and CN lines than in N, but all accumulated ~150-fold higher squalene due to substrate or storage limitations. Abnormal leaf and flower phenotypes, including lower pollen production and reduced fertility, were observed regardless of the compartment or level of transgene expression. Substantial changes in metabolomes of all lines were observed: levels of 65-120 unrelated metabolites, including the toxic alkaloid nicotine, changed by as much as 32-fold. Profound effects of transgenesis on nontarget gene expression included changes in the abundance of 19 076 transcripts by up to 2000-fold in CN; 7784 transcripts by up to 1400-fold in N; and 5224 transcripts by as much as 2200-fold in C. Transporter-related transcripts were induced, and cell cycle-associated transcripts were disproportionally repressed in all three lines. Transcriptome changes were validated by qRT-PCR. The mechanism underlying these large changes likely involves metabolite-mediated anterograde and/or retrograde signalling irrespective of the level of transgene expression or end product, due to imbalance of metabolic pools, offering new insight into both anticipated and unanticipated consequences of metabolic engineering.

  4. BEST: A Learner-Centered Workplace Literacy Partnership of the Vermont Institute for Self-Reliance and General Electric Aircraft Engines Rutland, VT. Final Performance Report.

    Science.gov (United States)

    Lashof, Judith R.

    The Vermont Institute for Self Reliance (VISR) conducted a Basic Educational Skills for Training (BEST) program, a national demonstration project in workplace literacy, from April 1990 to March 1992. BEST provided learner-centered, context-based literacy instruction onsite, on company time, at two General Electric (GE) Aircraft Engines Rutland…

  5. Bringing Women into Computer Engineering: Curriculum Reform Processes at Two Institutes of Technology. Linkoping Studies in Education and Psychology Dissertations, No. 60.

    Science.gov (United States)

    Salminen-Karlsson, Minna

    This study examined curricular reform processes at two Swedish institutes of technology through a gender perspective, relating them to two social theories the reproduction theory of Bourdieu and Passeron and the gender contract theory of Yvonne Hirdman. The aim of the reform process was to make educational programs in computer engineering more…

  6. IEEE Milestone at CERN - W Cleon Anderson (right), president of the Institute of Electrical and Electronics Engineers, unveils the Milestone plaque at CERN, together with Georges Charpak

    CERN Multimedia

    Maximilien Brice

    2005-01-01

    At a ceremony on 26 September at CERN, W Cleon Anderson, president of the Institute of Electrical and Electronics Engineers (IEEE), formally dedicated a "Milestone" plaque in recognition of the invention of electronic particle detectors at CERN. The plaque was unveiled by Anderson and Georges Charpak, the Nobel-prize winning inventor of wire-chamber technology at CERN.

  7. The composition of first-year engineering curricula and its relationships to matriculation models and institutional characteristics

    OpenAIRE

    Chen, Xingyu

    2014-01-01

    The preparation of technically excellent and innovative engineering graduates urges for a reform of the engineering curriculum to meet critical challenges in society (National Academy of Engineering, 2005). An examination of the current engineering curricula is needed to offer a baseline to further discuss if the curriculum reform meets the critical challenges. Meanwhile, concern about engineering retention prioritizes a review of the first-year engineering curricula. The existing literature ...

  8. Institute of Nuclear Solid State Physics (INFP). Progress report on research and development in 1994; Institut fuer Nukleare Festkoerperphysik. Ergebnisbericht ueber Forschung und Entwicklung 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    About 90 percent of the research activities of the INFP in 1994 were devoted to superconductivity as the priority research field of the Institute. In the domain of fundamental research, the work on oxidic HT superconductors was continued, concentrating on the electronic structure and details of the lattice dynamics. New tasks were opened up with studies on the recently discovered boron nitrides of the type LnNi{sub 2}B{sub 2}C (Ln=Y,Lu,..) with superconducting transition temperatures of up to T{sub c}{approx}23K. Good progress was achieved in the preparation of MPMG superconducting bulk specimens intended for use in self-stabilising magnetic bearings. A prototype flywheel power storage system was developed for demonstrating the technological feasibility. Application-oriented studies were concerned with the growth of epitactic thin films on application-relevant substrates and including suitable buffer layers, and with the examination of the high-frequency performance of these films. Fullerene research continued with studies into the solid-state physics of crystalline fullerenes or fullerene compounds, and the preparation and characterisation of endofullerenes such as La C{sub 82}. The remaining approximately 10 percent of the Institute`s research activities covered experimental and theoretical work on the physics of surfaces and boundary surfaces, and the physics of mesoscopic systems. (orig./MM) [Deutsch] Das Institut fuer Nukleare Festkoerperphysik lag im Berichtsjahr mit etwa 90% seiner Aktivitaeten im Arbeitsschwerpunkt Supraleitung. Bei oxidischen Hochtemperatursupraleitern wurden im Bereich der Grundlagenforschung vor allem die elektronische Struktur und gitterdynamische Details untersucht. Neu aufgegriffen wurden die juengst entdeckten Boronitride vom Typ LnNi{sub 2}B{sub 2}C (Ln=Y, Lu,...) mit supraleitenden Uebergangstemperaturen bis T{sub c}{approx}23 K. Grosse Fortschritte gab es auch bei der Herstellung schmelztexturierter HTSL-Volumenproben, wie sie in

  9. The popularization of the nuclear sciences and its impact in the public opinion. Strategies of institutional communication; La divulgacion de las ciencias nucleares y su impacto en la opinion publica. Estrategias de comunicacion institucional

    Energy Technology Data Exchange (ETDEWEB)

    Ortega E, J.M. [ININ, Centro Nuclear ' Dr. Nabor Carrillo Flores' 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: jortega@nuclear.inin.mx

    2007-07-01

    A continuous concern that is presented among those responsible for the exercise of the science and the technology in the Westerner entire world is to give to know the chore of their institutions and individuals. As in the case of several Mexican institutions, and particularly of the National Institute of Nuclear Research (ININ), one of their rector axes are to diffuse their achievements among the different social actors. A suitable vehicle to impact positively to the public opinion on the advances and tendencies of the nuclear energy it is the popularization of the science. The purpose of the popularization is to place accessible information in hands of the public and, by this, it requires of the use of talkative techniques derived of the journalism and of the public relationships, mainly, besides a basic knowledge of the scientific activity. In simple terms, it is not possible to achieve a positive image of the incomprehensible thing. By this cause, the correct understanding of the current administration of the nuclear energy represents the success or the failure of a strategy of institutional communication. Additionally, it is necessary a deep knowledge of the public opinion, in order to classify it and to have the option of to diversify the messages, of agreement with the characteristics of each segment of the public. Nevertheless their competition, the scientific popularization is centered in the construction of texts and other talkative tools, for that its acting frequently doesn't reach the effective dissemination of the messages. In this context, the use of a strategy of institutional communication represents the multi-functional option: on one hand and derived of the strategic planning, it will establish objectives, the periods of realization of the actions and the form of evaluating their efficiency; and on the other hand, it will allow the incorporation of creative solutions according with the nature of the origin institution, the space

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  11. 1 April 2011 - Indian Saha Institute of Nuclear Physics Director M. K. Sanyal in CERN Control Centre with Head of Operation M. Lamont and Adviser R. Voss; signing the guest book with CERN Director-General R. Heuer.

    CERN Multimedia

    Maximilien Brice

    2011-01-01

    1 April 2011 - Indian Saha Institute of Nuclear Physics Director M. K. Sanyal in CERN Control Centre with Head of Operation M. Lamont and Adviser R. Voss; signing the guest book with CERN Director-General R. Heuer.

  12. Mr Bikash Sinha, Director of SAHA & VECC and Prof. Rolf Heuer, Director general of CERN, sign a collaboration agreements between SAHA (Saha Institute of Nuclear Physics), VECC (Variable Energy Cyclotron Centre), India and CERN ISOLDE.

    CERN Multimedia

    Maximilien Brice

    2009-01-01

    Mr Bikash Sinha, Director of SAHA & VECC and Prof. Rolf Heuer, Director general of CERN, sign a collaboration agreements between SAHA (Saha Institute of Nuclear Physics), VECC (Variable Energy Cyclotron Centre), India and CERN ISOLDE.

  13. Signature of a Collaboration Agreement between The Andrzej Soltan Institute for Nuclear Studies (IPJ) and CERN, by Prof. Grzegorz Wrochna, Director and CERN Director-General, concerning Collaboration in the LHC upgrade.

    CERN Multimedia

    Maximilien Brice

    2011-01-01

    Signature of a Collaboration Agreement between The Andrzej Soltan Institute for Nuclear Studies (IPJ) and CERN, by Prof. Grzegorz Wrochna, Director and CERN Director-General, concerning Collaboration in the LHC upgrade.

  14. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement. Volume 1, Appendix D: Part A, Naval Spent Nuclear Fuel Management

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.

  15. Site Earthquake Characteristics and Dynamic Parameter Test of Phase Ⅲ Qinshan Nuclear Power Engineering

    Institute of Scientific and Technical Information of China (English)

    ZHOV Nian-qing; ZHAO Zai-li; QIN Min

    2009-01-01

    The earthquake characteristics and geological structure of the site to sitting the Qinshan Nuclear Power Station are closely related. According to site investigation drilling, sampling, seismic sound logging wave test in single-hole and cross-hole, laboratory wave velocity test of intact rock, together with analysis of the site geological conditions, the seismic wave test results of the site between strata lithology and the geologic structure were studied. The relationships of seismic waves with the site lithology and the geologic structure were set up.The dynamic parameters of different grades of weathering profile were deduced. The results assist the seismic design of Phase Ⅲ Qinshan Nuclear Power Plant, China.

  16. Measurement of Sedimentary Interbed Hydraulic Properties and Their Hydrologic Influence near the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory

    Science.gov (United States)

    Perkins, Kim S.

    2003-01-01

    Disposal of wastewater to unlined infiltration ponds near the Idaho Nuclear Technology and Engineering Center (INTEC), formerly known as the Idaho Chemical Processing Plant, at the Idaho National Engineering and Environmental Laboratory (INEEL) has resulted in the formation of perched water bodies in the unsaturated zone (Cecil and others, 1991). The unsaturated zone at INEEL comprises numerous basalt flows interbedded with thinner layers of coarse- to fine-grained sediments and perched ground-water zones exist at various depths associated with massive basalts, basalt-flow contacts, sedimentary interbeds, and sediment-basalt contacts. Perched ground water is believed to result from large infiltration events such as seasonal flow in the Big Lost River and wastewater discharge to infiltration ponds. Evidence from a large-scale tracer experiment conducted in 1999 near the Radioactive Waste Management Complex (RWMC), approximately 13 km from the INTEC, indicates that rapid lateral flow of perched water in the unsaturated zone may be an important factor in contaminant transport at the INEEL (Nimmo and others, 2002b). Because sedimentary interbeds, and possibly baked-zone alterations at sediment-basalt contacts (Cecil and other, 1991) play an important role in the generation of perched water it is important to assess the hydraulic properties of these units.

  17. Exploring the Academic and Social Experiences of Latino Engineering Community College Transfer Students at a 4-Year Institution: A Qualitative Research Study

    Science.gov (United States)

    Hagler, LaTesha R.

    As the number of historically underrepresented populations transfer from community college to university to pursue baccalaureate degrees in science, technology, engineering, and mathematics (STEM), little research exists about the challenges and successes Latino students experience as they transition from 2-year colleges to 4-year universities. Thus, institutions of higher education have limited insight to inform their policies, practices, and strategic planning in developing effective sources of support, services, and programs for underrepresented students in STEM disciplines. This qualitative research study explored the academic and social experiences of 14 Latino engineering community college transfer students at one university. Specifically, this study examined the lived experiences of minority community college transfer students' transition into and persistence at a 4-year institution. The conceptual framework applied to this study was Schlossberg's Transition Theory, which analyzed the participant's social and academic experiences that led to their successful transition from community college to university. Three themes emerged from the narrative data analysis: (a) Academic Experiences, (b) Social Experiences, and (c) Sources of Support. The findings indicate that engineering community college transfer students experience many challenges in their transition into and persistence at 4-year institutions. Some of the challenges include lack of academic preparedness, environmental challenges, lack of time management skills and faculty serving the role as institutional agents.

  18. The French civilian nuclear: connections and stakes; Le nucleaire civil francais: filieres et enjeux

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This document (18 power point slides) gives an overview of the French civilian nuclear industry and research and development: importance of the nuclear power generation in France, excellence of the education in nuclear sciences, organization of the nuclear connection (CEA, Areva, EDF, IRSN), the role of the French International Nuclear Agency (AFNI), the requirements for a renewal of human resources (French and foreign engineers) in the field of nuclear energy, the degree course for a diploma, examples of engineer and university diplomas, the educational networks in various regions of France, presentation of the Institut National des Sciences et Techniques Nucleaires (Nuclear Sciences and Techniques National Institute) and its master degrees, organization of the French education system in nuclear sciences with strong relations with the research and development programs

  19. Environmental tasks of engineering geology in the construction of nuclear power installations

    Energy Technology Data Exchange (ETDEWEB)

    Hrasna, M. (Komenskeho Univ., Bratislava (Czechoslovakia). Prirodovedecka Fakulta)

    1984-01-01

    A nuclear power installation shoUld be sited in an area without large and intensive geodynamic phenomena such as seismicity, gravitation movement, subsidence, etc., an area with mineral and drinking water resources, deposits of mineral raw materials, quality farmland and protected areas. With regard to demands on the quality of foundation soil and the ground water level it will always be necessary to secure the safe foundation of buildings with possible radioactivity escape. Most such buildings are founded on a solid foundation slab. The definitive siting of the nuclear power facility should be decided upon during the project design preparation stage when most geological surveying is done. During the pre-project stage a quantitative determination is made of all characteristics of rocks on the site. Monitoring and surveillance is conducted during construction.

  20. All-Russia Thermal Engineering Institute experience in using difficult to burn fuels in the power industry

    Science.gov (United States)

    Tugov, A. N.; Ryabov, G. A.; Shtegman, A. V.; Ryzhii, I. A.; Litun, D. S.

    2016-07-01

    This article presents the results of the research carried out at the All-Russia Thermal Engineering Institute (VTI) aimed at using saline coal, municipal solid waste and bark waste, sunflower husk, and nesting/ manure materials from poultry farms. The results of saline coal burning experience in Troitsk and Verkhny Tagil thermal power plants (TPP) show that when switching the boiler to this coal, it is necessary to take into account its operating reliability and environmental safety. Due to increased chlorine content in saline coal, the concentration of hydrogen chloride can make over 500 mg/m3. That this very fact causes the sharp increase of acidity in sludge and the resulting damage of hydraulic ash removal system equipment at these power stations has been proven. High concentration of HCl can trigger damage of the steam superheater due to high-temperature corrosion and result in a danger of low-temperature corrosion of air heating surfaces. Besides, increased HCl emissions worsen the environmental characteristics of the boiler operation on the whole. The data on waste-to-energy research for municipal solid waste (MSW) has been generalized. Based on the results of mastering various technologies of MSW thermal processing at special plants nos. 2 and 4 in Moscow, as well as laboratory, bench, and industrial studies, the principal technical solutions to be implemented in the modern domestic thermal power plant with the installed capacity of 24 MW and MSW as the primary fuel type has been developed. The experience of the VTI in burning various kinds of organic waste—bark waste, sunflower husk, and nesting/manure materials from poultry farms—has been analyzed.

  1. The high-temperature sodium coolant technology in nuclear power installations for hydrogen power engineering

    Science.gov (United States)

    Kozlov, F. A.; Sorokin, A. P.; Alekseev, V. V.; Konovalov, M. A.

    2014-05-01

    In the case of using high-temperature sodium-cooled nuclear power installations for obtaining hydrogen and for other innovative applications (gasification and fluidization of coal, deep petroleum refining, conversion of biomass into liquid fuel, in the chemical industry, metallurgy, food industry, etc.), the sources of hydrogen that enters from the reactor plant tertiary coolant circuit into its secondary coolant circuit have intensity two or three orders of magnitude higher than that of hydrogen sources at a nuclear power plant (NPP) equipped with a BN-600 reactor. Fundamentally new process solutions are proposed for such conditions. The main prerequisite for implementing them is that the hydrogen concentration in sodium coolant is a factor of 100-1000 higher than it is in modern NPPs taken in combination with removal of hydrogen from sodium by subjecting it to vacuum through membranes made of vanadium or niobium. Numerical investigations carried out using a diffusion model showed that, by varying such parameters as fuel rod cladding material, its thickness, and time of operation in developing the fuel rods for high-temperature nuclear power installations (HT NPIs) it is possible to exclude ingress of cesium into sodium through the sealed fuel rod cladding. However, if the fuel rod cladding loses its tightness, operation of the HT NPI with cesium in the sodium will be unavoidable. Under such conditions, measures must be taken for deeply purifying sodium from cesium in order to minimize the diffusion of cesium into the structural materials.

  2. The Swedish radiation protection institute's regulations and general advice on nuclear medicine; issued on April 28, 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-04-01

    These regulations and general advice are applicable to nuclear medicine within human medical care. The regulations are also applicable to activities where radioactive substances are administered to individuals in connection to medical or biomedical research and medical examinations for insurance or legal purposes.

  3. The spatial and urban planning concerns related to nuclear facilities locations: Case study of the Vinča Institute location

    Directory of Open Access Journals (Sweden)

    Stefanović Nebojša D.

    2017-01-01

    Full Text Available The spatial and urban planning is one of the key instruments for the planned formation and development of locations for nuclear facilities, especially in terms of meeting the strict spatial conditionality, as well as in terms of the formation of protection zones in their surroundings. This paper systemizes the international criteria and requirements for the locations of nuclear facilities and analyses the spatial distribution of nuclear facilities in the surrounding countries of the Republic of Serbia. The research was conducted on the example of the location of the Vinča Institute of Nuclear Sciences, within which the fulfilment of spatial requirements, treatment of the location in the existing spatial and urban plans and relationship between other functions in the surrounding area were analysed. The paper proves the starting hypothesis that the general requirements related to both the spatial development of nuclear facilities locations and the protection from radiation have not been met in the Vinča location and its surroundings. It was determined that the spatial and urban plans encompassing the area of Vinča do not contain sufficiently specific planning solutions and that, as such, they do not provide a sufficient planning basis for meeting the necessary requirements and obligations regarding the protection from radiation. The paper also gives recommendations for further spatial development and protection of the Vinča location and its surroundings. The research condcted in this paper indicates the importance and priority of further research so that the necessary planning solutions for further development of the complex in Vinča and for the formation of protection zones could be defined through creating a new planning documentation. In addition, the paper particularly highlights the need for conducting a research to identify a location for permanent disposal of radioactive waste. It also indicates the necessity of considering the aspects

  4. Theoretical determination of the strength characteristics of multilayer materials intended for nuclear and thermonuclear engineering

    Science.gov (United States)

    Vitkovskii, I. V.; Leshukov, A. Yu.; Romashin, S. N.; Shorkin, V. S.

    2015-12-01

    A method is developed to estimate the integrity of multilayer structures. This method is based on the version of the theory of adhesion and cohesion interactions of structure elements that only takes into account their thermomechanical properties. The structures to be studied are the material of the multilayer wall of the liquid-metal thermonuclear reactor blanket and a heat-resistant magnet wire with a bimetallic conductor, which is the base of the windings of the magnetohydrodynamic machines and electric motors intended for operation at high temperatures under ionizing radiation in, e.g., the machines and facilities in nuclear and thermonuclear reactors.

  5. Compulsory Checking of Nuclear Power Engineering Materials by Direct and Eddy Current

    Science.gov (United States)

    Larionov, V. V.; Lider, A. M.; Sednev, D. A.; Xu, Shupeng

    2016-08-01

    The testing technology of copper parts designed for dry storage of spent nuclear fuel with application of direct and eddy current has been developed. Measurements results of flaw quantity caused hydrogenation and oxidation processes are presented. Evolution of copper M 001 flaw structure during hydrogenation from gaseous medium is analyzed. It has been demonstrated that the dependence of copper p electrical resistance on number of flaws in its structure has dome shaped character and changes with eddy current frequency change. Number of flaws formed by hydrogen depends on direction (100) or (200) of the crystal structure of copper lattice.

  6. Why Model-Based Engineering and Manufacturing Makes Sense for the Plants and Laboratories of the Nuclear Weapon Complex

    Energy Technology Data Exchange (ETDEWEB)

    Franklin, K W; Howell, L N; Lewis, D G; Neugebauer, C A; O' Brien, D W; Schilling, S A

    2001-05-15

    The purpose of this White Paper is to outline the benefits we expect to receive from Model-Based Engineering and Manufacturing (MBE/M) for the design, analysis, fabrication, and assembly of nuclear weapons for upcoming Life Extension Programs (LEPs). Industry experiences with model-based approaches and the NNSA/DP investments and experiences, discussed in this paper, indicate that model-based methods can achieve reliable refurbished weapons for the stockpile with less cost and time. In this the paper, we list both general and specific benefits of MBE/M for the upcoming LEPs and the metrics for determining the success of model-based approaches. We also present some outstanding issues and challenges to deploying and achieving long-term benefit from the MBE/M. In conclusion, we argue that successful completion of the upcoming LEPs--with very aggressive schedule and funding restrictions--will depend on electronic model-based methods. We ask for a strong commitment from LEP managers throughout the Nuclear Weapons Complex to support deployment and use of MBE/M systems to meet their program needs.

  7. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix C, Savannah River Site Spent Nuclear Fuel Mangement Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  8. Managing Information for Sparsely Distributed Articles and Readers: The Virtual Journals of the Joint Institute for Nuclear Astrophysics (JINA)

    CERN Document Server

    Cyburt, Richard H; Beers, Timothy C; Estrade, Alfredo; Ferguson, Ryan M; Sakharuk, A; Smith, Karl; Warren, Scott

    2009-01-01

    The research area of nuclear astrophysics is characterized by a need for information published in tens of journals in several fields and an extremely dilute distribution of researchers. For these reasons it is difficult for researchers, especially students, to be adequately informed of the relevant published research. For example, the commonly employed journal club is inefficient for a group consisting of a professor and his two students. In an attempt to address this problem, we have developed a virtual journal (VJ), a process for collecting and distributing a weekly compendium of articles of interest to researchers in nuclear astrophysics. Subscribers are notified of each VJ issue using an email-list server or an RSS feed. The VJ data base is searchable by topics assigned by the editors, or by keywords. There are two related VJs: the Virtual Journal of Nuclear Astrophysics (JINA VJ), and the SEGUE Virtual Journal (SEGUE VJ). The JINA VJ also serves as a source of new experimental and theoretical information...

  9. A preliminary systems-engineering study of an advanced nuclear-electrolytic hydrogen-production facility

    Science.gov (United States)

    Escher, W. J. D.; Donakowski, T. D.; Tison, R. R.

    1975-01-01

    An advanced nuclear-electrolytic hydrogen-production facility concept was synthesized at a conceptual level with the objective of minimizing estimated hydrogen-production costs. The concept is a closely-integrated, fully-dedicated (only hydrogen energy is produced) system whose components and subsystems are predicted on ''1985 technology.'' The principal components are: (1) a high-temperature gas-cooled reactor (HTGR) operating a helium-Brayton/ammonia-Rankine binary cycle with a helium reactor-core exit temperature of 980 C, (2) acyclic d-c generators, (3) high-pressure, high-current-density electrolyzers based on solid-polymer electrolyte technology. Based on an assumed 3,000 MWt HTGR the facility is capable of producing 8.7 million std cu m/day of hydrogen at pipeline conditions, 6,900 kPa. Coproduct oxygen is also available at pipeline conditions at one-half this volume. It has further been shown that the incorporation of advanced technology provides an overall efficiency of about 43 percent, as compared with 25 percent for a contemporary nuclear-electric plant powering close-coupled contemporary industrial electrolyzers.

  10. Increased micronucleus, nucleoplasmic bridge, and nuclear bud frequencies in the peripheral blood lymphocytes of diesel engine exhaust-exposed workers.

    Science.gov (United States)

    Zhang, Xiao; Duan, Huawei; Gao, Feng; Li, Yuanyuan; Huang, Chuanfeng; Niu, Yong; Gao, Weimin; Yu, Shanfa; Zheng, Yuxin

    2015-02-01

    The International Agency for Research on Cancer has recently reclassified diesel engine exhaust (DEE) as a Group 1 carcinogen. Micronucleus (MN), nucleoplasmic bridge (NPB), and nuclear bud (NBUD) frequencies in peripheral blood lymphocytes (PBLs) are associated with cancer risk. However, the impact of DEE exposure on MN frequency has not been thoroughly elucidated due to mixed exposure and its impact on NPB and NBUD frequencies has never been explored in humans. We recruited 117 diesel engine testing workers with exclusive exposure to DEE and 112 non-DEE-exposed workers, and then we measured urinary levels of 4 mono-hydroxylated polycyclic aromatic hydrocarbons (OH-PAHs) using high-performance liquid chromatography-mass spectrometry as well as MN, NPB, and NBUD frequencies in PBLs using cytokinesis-block MN assay. The DEE-exposed workers exhibited significantly higher MN, NPB, and NBUD frequencies than the non-DEE-exposed workers (P frequencies (all P frequencies persisted in DEE-exposed workers (P = 0.001). The percent of MN frequencies increased, on average, by 23.99% (95% confidential interval, 9.64-39.93) per 1-unit increase in ln-transformed 9-OHPh. Our results clearly show that exposure to DEE can induce increases in MN, NPB, and NBUD frequencies in PBLs and suggest that DEE exposure level is associated with MN frequencies.

  11. Statement of work for sytem design and engineering of the spent nuclear fuel multi-cansiter overpack

    Energy Technology Data Exchange (ETDEWEB)

    Smith, K.E., Fluor Daniel Hanford

    1997-03-03

    This Statement of Work (SOW) describes the work scope for the preparation of the Phase 2 (final) design for the Multiple Canister Overpack (MCO) equipment. The MCO is to be used as the radiological containment device for the Spent Nuclear Fuel (SNF) assemblies, currently in wet storage in K East and West Basins, to be transported and stored in the Canister Storage Building (CSB) until final disposal facilities are made available. The engineering services contractor will be requested to provide reports, studies, analyses, engineering, drawings, specifications, estimates and schedules. The overall goal of this task order is to do the following: 1. Prepare a fabrication specification, ASME Code exception report, a packaging, shipping and warehouse plan, and detailed fabrication drawings of the MCO in accordance with the MCO Performance Specification (HNF-S-0426, Rev. 3) for procurement activities by the SNF MCO Subproject. 2. Establish and maintain a comment data base on the comments, resolutions, changes to the design of the MCO. 3. Support fabrication activities through the review of vendor fabrication drawings and shop test reports.

  12. Nuclear reactors and fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Nuclear Fuel Center (CCN) of IPEN produces nuclear fuel for the continuous operation of the IEA-R1 research reactor of IPEN. The serial production started in 1988, when the first nuclear fuel element was delivered for IEA-R1. In 2011, CCN proudly presents the 100{sup th} nuclear fuel element produced. Besides routine production, development of new technologies is also a permanent concern at CCN. In 2005, U{sub 3}O{sub 8} were replaced by U{sub 3}Si{sub 2}-based fuels, and the research of U Mo is currently under investigation. Additionally, the Brazilian Multipurpose Research Reactor (RMB), whose project will rely on the CCN for supplying fuel and uranium targets. Evolving from an annual production from 10 to 70 nuclear fuel elements, plus a thousand uranium targets, is a huge and challenging task. To accomplish it, a new and modern Nuclear Fuel Factory is being concluded, and it will provide not only structure for scaling up, but also a safer and greener production. The Nuclear Engineering Center has shown, along several years, expertise in the field of nuclear, energy systems and correlated areas. Due to the experience obtained during decades in research and technological development at Brazilian Nuclear Program, personnel has been trained and started to actively participate in design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. Along the last two decades, numerous specialized services of engineering for the Brazilian nuclear power plants Angra 1 and Angra 2 have been carried out. The contribution in service, research, training, and teaching in addition to the development of many related technologies applied to nuclear engineering and correlated areas enable the institution to

  13. The calculation and estimation of wastes generated by decommissioning of nuclear facilities. Tokai works and Ningyo-toge Environmental Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S. [Japan Nuclear Cycle Development Inst., Tokai Works, Waste Management and Fuel Cycle Research Center, Tokai, Ibaraki (Japan)

    2001-07-01

    This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)

  14. Dynamic parameters test of Haiyang Nuclear Power Engineering in reactor areas, China

    Science.gov (United States)

    Zhou, N.; Zhao, S.; Sun, L.

    2012-12-01

    Haiyang Nuclear Power Project is located in Haiyang city, China. It consists of 6×1000MW AP1000 Nuclear Power generator sets. The dynamic parameters of the rockmass are essential for the design of the nuclear power plant. No.1 and No.2 reactor area are taken as research target in this paper. Sonic logging, single hole and cross-hole wave velocity are carried out respectively on the site. There are four types of rock lithology within the measured depth. They are siltstone, fine sandstone, shale and allgovite. The total depth of sonic logging is 409.8m and 2049 test points. The sound wave velocity of the rocks are respectively 5521 m/s, 5576m/s, 5318 m/s and 5576 m/s. Accroding to the statistic data, among medium weathered fine sandstone, fairly broken is majority, broken and relatively integrity are second, part of integrity. Medium weathered siltstone, relatively integrity is mojority, fairly broken is second. Medium weathered shale, fairly broken is majority, broken and relatively integrity for the next and part of integrity. Slight weathered fine sandstone, siltstone, shale and allgovite, integrity is the mojority, relatively integrity for the next, part of fairly broken.The single hole wave velocity tests are set in two boreholesin No.1 reactor area and No.2 reactor area respectively. The test depths of two holes are 2-24m, and the others are 2-40m. The wave velocity data are calculated at different depth in each holes and dynamic parameters. According to the test statistic data, the wave velocity and the dynamic parameter values of rockmass are distinctly influenced by the weathering degree. The test results are list in table 1. 3 groups of cross hole wave velocity tests are set for No.1 and 2 reactor area, No.1 reactor area: B16, B16-1, B20(Direction:175°, depth: 100m); B10, B10-1, B11(269°, 40m); B21, B21-1, B17(154°, 40m); with HB16, HB10, HB21 as trigger holes; No.2 reactor area: B47, B47-1, HB51(176°, 100m); B40, B40-1, B41(272°, 40m); B42, B42-1, B

  15. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Summary

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes.

  16. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 2, Part A

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum and maximum treatment, storage, and disposal of US Department of Energy wastes.

  17. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document analyzes at a pregrammatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For pregrammatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes.

  18. Technology Evaluations Related to Mercury, Technetium, and Chloride in Treatment of Wastes at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    C. M. Barnes; D. D. Taylor; S. C. Ashworth; J. B. Bosley; D. R. Haefner

    1999-10-01

    The Idaho High-Level Waste and Facility Disposition Environmental Impact Statement defines alternative for treating and disposing of wastes stored at the Idaho Nuclear Technology and Engineering Center. Development is required for several technologies under consideration for treatment of these wastes. This report contains evaluations of whether specific treatment is needed and if so, by what methods, to remove mercury, technetium, and chlorides in proposed Environmental Impact Statement treatment processes. The evaluations of mercury include a review of regulatory requirements that would apply to mercury wastes in separations processes, an evaluation of the sensitivity of mercury flowrates and concentrations to changes in separations processing schemes and conditions, test results from laboratory-scale experiments of precipitation of mercury by sulfide precipitation agents from the TRUEX carbonate wash effluent, and evaluations of methods to remove mercury from New Waste Calcining Facility liquid and gaseous streams. The evaluation of technetium relates to the need for technetium removal and alternative methods to remove technetium from streams in separations processes. The need for removal of chlorides from New Waste Calcining Facility scrub solution is also evaluated.

  19. 40 Annual Meeting of Spanish Nuclear Society, Oct 1-3, 2014, Valencia, Spain; 40 Reunion Anual Sociedad Nuclear Espanola, 1-3 Octubre 2014, Valencia, Espana

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Spanish Nuclear Society (SNE) is a non-profit association, made up of professionals and institutions in order to promote awareness and dissemination of science and nuclear technology. The 40th meeting of the SNE held in Valencia, analyzes the current situation of nuclear energy and its future challenges, covering different topics from engineering to R and D, nuclear safety, also the impact on health and the environment in the vicinity of a nuclear facility, the experience of Spanish companies in the construction of power and knowledge management in the nuclear sector.

  20. 39 Annual Meeting of Spanish Nuclear Society, September 25-27, 2013, Reus, Spain; 39 Reunion Anual Sociedad Nuclear Espanola, 25-27 Septiembre 2013, Reus, Espana

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

    The Spanish Nuclear Society (SNE) is a non-profit association, made up of professionals and institutions in order to promote awareness and dissemination of science and nuclear technology. The 39th meeting of the SNE held in Reus, analyzes the current situation of nuclear energy and its future challenges, covering different topics from engineering to R and D, nuclear safety, also the impact on health and the environment in the vicinity of a nuclear facility, the experience of Spanish companies in the construction of power and knowledge management in the nuclear sector.

  1. Education and training in the field of nuclear instrumentation and measurement: CEA/INSTN (National Institute for Nuclear Sciences and Technologies) strategy to improve and develop new pedagogical tools and methods

    Energy Technology Data Exchange (ETDEWEB)

    Vitart, Xavier; Foulon, Francois; Bodineau, Jean Christophe; Lescop, Bernard; Massiot, Philippe [CEA/INSTN Centre des Saclay 91191 Gif sur Yvette (France)

    2015-07-01

    Part of the French Alternative Energies and Atomic Energy Commission (CEA), the National Institute for Nuclear Science and Technology (INSTN) is a higher education institution whose mission is to provide students and professionals a high level of scientific and technological qualification in all disciplines related to nuclear energy applications. In this frame, INSTN carries out education and training (E and T) programs in nuclear instrumentation and radioprotection. Its strategy has always been to complete theoretical courses by training courses and laboratory works carried out on an extensive range of training tools that includes a large panel of nuclear instrumentation as well as software applications. Since its creation in 1956, the INSTN has conducted both education and vocational programs on ionizing radiation detection. An extensive range of techniques have commonly been used during practical works with students and employees of companies who need to get the knowledge and specialization in this field. Today, the INSTN is mainly equipped with usual detectors and electronics in large numbers in order to be able to accommodate up to 48 trainees at the same time in two classrooms, with only two trainees for one workstation in order to optimize their learning. In the field of the neutron detection systems, the INSTN has strongly developed its offer taking advantage of the use of research reactors, such as ISIS reactor (700 kW) at Saclay. The implementation of neutron detection systems specific to the courses offers a unique way of observing and analysing the signal coming from neutron detectors, as well as learning how to set the parameters of the detection system in real conditions. Providing the trainees with an extensive overview of each part of the neutron monitoring instrumentation apply to a nuclear reactor, hands-on measurements on the ISIS reactor play a major role in ensuring a practical and comprehensive understanding of the neutron detection system and

  2. Research advances on engineering structural seismic safety of nuclear power plant%核电厂工程结构抗震研究进展

    Institute of Scientific and Technical Information of China (English)

    孔宪京; 林皋

    2013-01-01

      当前以及今后相当长一段时期,核电都将是中国积极发展的能源形式之一,保障核电安全是确保核电工程建设顺利实施和安全运营的关键。然而,中国幅员广阔,地质条件差异大,海域自然条件复杂;同时,中国地震活动范围广、强度大、频度高,基于标准化设计的核电工程结构在建设过程中面临着诸多问题。尤其是2011年日本大地震导致的福岛核电事故的教训,对核电工程的抗震安全提出了新的问题。结合大连理工大学十几年来在解决我国核电工程结构抗震安全中的关键问题,以及在“地震作用下核电厂工程结构的功能失效机理及抗震安全评价”研究中所取得若干进展进行综述性介绍,主要包括核岛地基抗震适应性研究和核岛安全相关工程结构抗震防灾研究。%Nuclear power is one of energy resources that China will vigorously develop for a long term from now on. The issue of nuclear power security guarantee is a key to ensure the smooth implementation and the safe operation of the nuclear power plant construction. However,because of the vast territory of China,the great differences in geological conditions and the complex natural conditions of ocean,as well as a wide range of seis-mic activity,high strength and high frequency of earthquakes in China,nuclear power buildings based on cur-rent standardized design methods are facing problems. Moreover,the lessons of the 2011 Fukushima nuclear ac-cident due to destructive earthquake come out new problems to Chinese seismic safety of nuclear power engineer-ing. In this paper,by combining engineering practice in recent years of nuclear power engineering seismic safety evaluation of the Dalian University of Technology,the key issues and the research methods in the structural seis-mic safety of Chinese nuclear power projects and some progress made by the Dalian University of Technology in the study of

  3. 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).

  4. Decision no. 2011-DC-0216 of the French nuclear safety authority from May 5, 2011, ordering the Laue Langevin Institute to proceed to a complementary safety evaluation of its basic nuclear facility (high flux reactor - INB no. 67) in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0216 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a l'Institut Laue Langevin (ILL) de proceder a une evaluation complementaire de la surete de son installation nucleaire de base (Reacteur a Haut Flux - INB n.67) au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the Laue Langevin Institute, operator of the high flux research reactor (RHF) of Grenoble (France). (J.S.)

  5. Modeling the nuclear magnetic resonance behavior of lung: from electrical engineering to critical care medicine.

    Science.gov (United States)

    Cutillo, A G; Ailion, D C

    1999-01-01

    The present article reviews the basic principles of a new approach to the characterization of pulmonary disease. This approach is based on the unique nuclear magnetic resonance (NMR) properties of the lung and combines experimental measurements (using specially developed NMR techniques) with theoretical simulations. The NMR signal from inflated lungs decays very rapidly compared with the signal from completely collapsed (airless) lungs. This phenomenon is due to the presence of internal magnetic field inhomogeneity produced by the alveolar air-tissue interface (because air and water have different magnetic susceptibilities). The air-tissue interface effects can be detected and quantified by magnetic resonance imaging (MRI) techniques using temporally symmetric and asymmetric spin-echo sequences. Theoretical models developed to explain the internal (tissue-induced) magnetic field inhomogeneity in aerated lungs predict the NMR lung behavior as a function of various technical and physiological factors (e.g., the level of lung inflation) and simulate the effects of various lung disorders (in particular, pulmonary edema) on this behavior. Good agreement has been observed between the predictions obtained from the mathematical models and the results of experimental NMR measurements in normal and diseased lungs. Our theoretical and experimental data have important pathophysiological and clinical implications, especially with respect to the characterization of acute lung disease (e.g., pulmonary edema) and the management of critically ill patients.

  6. High-throughput nuclear magnetic resonance metabolomic footprinting for tissue engineering.

    Science.gov (United States)

    Seagle, Christopher; Christie, Megan A; Winnike, Jason H; McClelland, Randall E; Ludlow, John W; O'Connell, Thomas M; Gamcsik, Michael P; MacDonald, Jeffrey M

    2008-06-01

    We report a high-throughput (HTP) nuclear magnetic resonance (NMR) method for analysis of media components and a metabolic schematic to help easily interpret the data. Spin-lattice relaxation values and concentrations were measured for 19 components and 2 internal referencing agents in pure and 2-day conditioned, hormonally defined media from a 3-dimensional (3D) multicoaxial human bioartificial liver (BAL). The (1)H NMR spectral signal-to-noise ratio is 21 for 0.16 mM alanine in medium and is obtained in 12 min using a 400 MHz NMR spectrometer. For comparison, 2D gel cultures and 3D multicoaxial BALs were batch cultured, with medium changed every day for 15 days after inoculation with human liver cells in Matrigel-collagen type 1 gels. Glutamine consumption was higher by day 8 in the BAL than in 2D culture; lactate production was lower through the 15-day culture period. Alanine was the primary amino acid produced and tracked with lactate or urea production. Glucose and pyruvate consumption were similar in the BAL and 2D cultures. NMR analysis permits quality assurance of the bioreactor by identifying contaminants. Ethanol was observed because of a bioreactor membrane "wetting" procedure. A biochemical scheme is presented illustrating bioreactor metabolomic footprint results and demonstrating how this can be translated to modify bioreactor operational parameters or quality assurance issues.

  7. Implementation of the quality management system in the regulatory body (Peruvian Institute for Nuclear Energy, Lima, Peru); Implementacion del sistema de gestion de calidad en el organo regulador

    Energy Technology Data Exchange (ETDEWEB)

    Medina Gironzini, E., E-mail: medina@ipen.gob.pe [Instituto Peruano de Energia Nuclear (IPEN), Lima (Peru)

    2013-07-01

    One of the functions of the Peruvian Institute of Nuclear Energy (IPEN), Lima, Peru is the control of sources of ionizing radiation. For this, they have the Oficina Tecnica de la Autoridad Nacional (OTAN) which has the necessary infrastructure to issue technical standards, conducting inspections, issuing authorizations and punish according to the existing legislation. OTAN has decided to address this issue and is taking into account the IAEA recommendations, especially the Safety Requirements GS-R-3: Management System facilities and activities and offering advice on the establishment and improvement of integrated management systems, including safety requirements that are not in the ISO 9001 standard and are also considered the requirements of technological safety, security, quality, economic, environmental and health. The working plan is detailed and the activities that are carried out after the scientific visit to a regulator organ, which has experience in the execution of a Quality Management System, consequence of a work initiated for more than four decades ago.

  8. Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant

    Energy Technology Data Exchange (ETDEWEB)

    Latysheva, L. N.; Bergman, A. A.; Sobolevsky, N. M., E-mail: sobolevs@inr.ru [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation); Ilic, R. D. [Vinca Institute of Nuclear Sciences (Serbia)

    2013-04-15

    Lead slowing-down (LSD) spectrometers have a low energy resolution (about 30%), but their luminosity is 10{sup 3} to 10{sup 4} times higher than that of time-of-flight (TOF) spectrometers. A high luminosity of LSD spectrometers makes it possible to use them to measure neutron cross section for samples of mass about several micrograms. These features specify a niche for the application of LSD spectrometers in measuring neutron cross sections for elements hardly available in macroscopic amounts-in particular, for actinides. A mathematical simulation of the parameters of SVZ-100 LSD spectrometer of the Institute for Nuclear Research (INR, Moscow) is performed in the present study on the basis of the MCNPX code. It is found that the moderation constant, which is the main parameter of LSD spectrometers, is highly sensitive to the size and shape of detecting volumes in calculations and, hence, to the real size of experimental channels of the LSD spectrometer.

  9. Focal plane detector for QDD spectrography in Institute of Nuclear Study and detector for SMART 2nd focal plane in RIKEN

    Energy Technology Data Exchange (ETDEWEB)

    Fuchi, Yoshihide [Tokyo Univ., Tanashi (Japan). Inst. for Nuclear Study

    1996-09-01

    The focal plane detector for QDD spectrography in Institute of Nuclear Study was composed of drift space and a proportional counter tube, and the latter is composed of position detector and two delta E detector for recognizing the particles. In this detector, a uniform parallel electric field can be obtained by placing a guard plate at the same height as that of a drift plate outer place of the detector. On the other hand, the detector for SMART 2nd focal plate in RIKEN is composed of drift space and a single wire proportional counter, and has two cathode read out single wire drift counters set so as to hold the focal plane. (G.K.)

  10. Development study on subcriticality monitor. 1. Report under business contract with Japan Nuclear Fuel Cycle Development Institute

    CERN Document Server

    Yamada, S

    2002-01-01

    In this trust fund, we reviewed subcriticality measuring methods and neutron or gamma ray measuring and date transmission systems appropriate for realizing inexpensive on-line criticality surveillance systems, which is required for ensuring the safety of nuclear fuel reprocessing plants. Since the neutron flux level in subcritical systems is fairly low without external neutron sources, it is desirable to use pulse type neutron detectors for subcritical measurement systems. This logically implies that subcriticality measurement methods based on the temporal domain should be used for developing an on-line criticality surveillance system. In the deep subcriticality conditions, a strong external neutron source is needed for eactivity measurement and a D-T tube can be used in order to improve the accuracy of the measurement. A D-T tube is convenient since it is free from Tritium problem since Tritium is sealed in an airtight container and also can be controlled by power supply. Hence, under deep subcritical condit...

  11. Photo-catalytic oxidation of a di-nuclear manganese centre in an engineered bacterioferritin 'reaction centre'.

    Science.gov (United States)

    Conlan, Brendon; Cox, Nicholas; Su, Ji-Hu; Hillier, Warwick; Messinger, Johannes; Lubitz, Wolfgang; Dutton, P Leslie; Wydrzynski, Tom

    2009-09-01

    Photosynthesis involves the conversion of light into chemical energy through a series of electron transfer reactions within membrane-bound pigment/protein complexes. The Photosystem II (PSII) complex in plants, algae and cyanobacteria catalyse the oxidation of water to molecular O2. The complexity of PSII has thus far limited attempts to chemically replicate its function. Here we introduce a reverse engineering approach to build a simple, light-driven photo-catalyst based on the organization and function of the donor side of the PSII reaction centre. We have used bacterioferritin (BFR) (cytochrome b1) from Escherichia coli as the protein scaffold since it has several, inherently useful design features for engineering light-driven electron transport. Among these are: (i.) a di-iron binding site; (ii.) a potentially redox-active tyrosine residue; and (iii.) the ability to dimerise and form an inter-protein heme binding pocket within electron tunnelling distance of the di-iron binding site. Upon replacing the heme with the photoactive zinc-chlorin e6 (ZnCe6) molecule and the di-iron binding site with two manganese ions, we show that the two Mn ions bind as a weakly coupled di-nuclear Mn2II,II centre, and that ZnCe6 binds in stoichiometric amounts of 1:2 with respect to the dimeric form of BFR. Upon illumination the bound ZnCe6 initiates electron transfer, followed by oxidation of the di-nuclear Mn centre possibly via one of the inherent tyrosine residues in the vicinity of the Mn cluster. The light dependent loss of the MnII EPR signals and the formation of low field parallel mode Mn EPR signals are attributed to the formation of MnIII species. The formation of the MnIII is concomitant with consumption of oxygen. Our model is the first artificial reaction centre developed for the photo-catalytic oxidation of a di-metal site within a protein matrix which potentially mimics water oxidation centre (WOC) photo-assembly.

  12. The N4 CAD chain: Another electricite de France breakthrough in nuclear engineering

    Energy Technology Data Exchange (ETDEWEB)

    Cornon, P.; Durey, P. [Electricite de France, Clamart (France)

    1996-12-31

    With the previous pressurized water reactor (PWR) series (1300 MW), Electricite de France (EdF) has experienced the first chain of computer-aided design (CAD) tools from programming drawings to instrumentation and control microprocessor memories. The Engineering and Construction Division of EdF decided to integrate the CAD tools in the design and construction process of its new N4 series (1400-MW PWR). At that time, EdF determined four safety and data quality principles for the human/machine interface of the CAD: 1. Unique data capture: A common alphanumeric database shares all the information used by more than one application, so this information is typed only once and can be verified independently. 2. Intrinsic consistency: Added to the previous principle, data consistency is also ensured by every application that provides ways to enter only allowed data when it is possible. This is completed by some checking facilities. 3. Ergonomy: Making extensive use of windows, buttons, pictures, and wysiwyg facilities, the CAD section develops applications speaking the real language of every designer who is able to understand and verify her/his work. 4. On-line help: For any question, prompted by any application, some on-line help has been written giving the list of allowed answers with explanations and/or examples.

  13. UK Institute of Physics (IOP) President Sir Gareth Roberts (right) at CERN on 9 July with (right to left) IOP council vice-president and distinguished physicist Peter Kalmus, CERN engineer Tim Watson and IOP director of science Peter Cooper

    CERN Multimedia

    Patrice Loiez

    1999-01-01

    UK Institute of Physics (IOP) President Sir Gareth Roberts (right) at CERN on 9 July with (right to left) IOP council vice-president and distinguished physicist Peter Kalmus, CERN engineer Tim Watson and IOP director of science Peter Cooper

  14. Genetic analysis of the Saimiri breeding colony of the Pasteur Institute (French Guiana): development of a molecular typing method using a combination of nuclear and mitochondrial DNA markers.

    Science.gov (United States)

    Lavergne, Anne; Catzeflis, François; Lacôte, Sandra; Barnaud, Antoine; Bordier, Marion; Mercereau-Puijalon, Odile; Contamin, Hugues

    2003-12-01

    Saimiri (Cebidae) groups a complex of species and subspecies, which present a large morphological plasticity. Genetic analysis is complicated by the absence of consensus on classification criteria and the paucity of molecular tools available for the genus. As the squirrel monkey is widely used in biomedical research, breeding centers have been established, but the genetic make up and diversity of many of the existing colonies is unknown precluding a rationale breeding policy. To develop a genetic typing strategy for the Saimiri breeding colony of Pasteur Institute of French Guiana, we have used Cytochrome b, a mitochondrial marker, and nuclear microsatellites. Cytochrome b sequences from wild-caught Saimiri boliviensis, Saimiri sciureus sciureus and S. s. collinsi reference specimens and captive animals identified 11 haplotypes, grouped into three distinct clades. An estimate of genetic variability within each captive morphotype, and of the extent of molecular divergence between the Bolivian, Guyanese and Brazilian breeds was obtained from the analysis of three nuclear microsatellites. Taxon-specific microsatellites enabled typing of F0-F3 animals, but did not differentiate Brazilian from Guyanese animals. Three locus microsatellite analysis of a representative sample from each generation showed no trend for loss of heterozygosity, and identified hybrid animals between Bolivian and the two others sub-species. These data provide novel evidence for taxonomic classification and a rationale strategy to further type the whole colony.

  15. The nuclear in Italy - state of the art; Le nucleaire en Italie - etat des lieux

    Energy Technology Data Exchange (ETDEWEB)

    Schifano, F.; Ziller, T

    2007-02-15

    This report aims to evaluate the italian situation in matter of the nuclear, following the referendum of 1987 which decided to stop the nuclear power plants in the country. The first part is devoted to the historical aspects of the nuclear sector in Italy. The second chapter presents the institutional and legislative framework. The third chapter discusses the today situation and the italian actors of the nuclear, from the radioactive wastes management and the dismantling of nuclear installations to the engineering service realized in other countries. It discusses also the research and development programs. The last chapter proposes perspectives of the debate around a possible restart of the nuclear activity in Italy.

  16. Purgeable organic compounds at or near the Idaho Nuclear Technology and Engineering Center, Idaho National Laboratory, Idaho, 2015

    Science.gov (United States)

    Maimer, Neil V.; Bartholomay, Roy C.

    2016-05-25

    During 2015, the U.S. Geological Survey, in cooperation with the U.S. Department of Energy, collected groundwater samples from 31 wells at or near the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Laboratory for purgeable organic compounds (POCs). The samples were collected and analyzed for the purpose of evaluating whether purge water from wells located inside an areal polygon established downgradient of the INTEC must be treated as a Resource Conservation and Recovery Act listed waste.POC concentrations in water samples from 29 of 31 wells completed in the eastern Snake River Plain aquifer were greater than their detection limit, determined from detection and quantitation calculation software, for at least one to four POCs. Of the 29 wells with concentrations greater than their detection limits, only 20 had concentrations greater than the laboratory reporting limit as calculated with detection and quantitation calculation software. None of the concentrations exceeded any maximum contaminant levels established for public drinking water supplies. Most commonly detected compounds were 1,1,1-trichoroethane, 1,1-dichloroethene, and trichloroethene.

  17. Role of Prognostics in Support of Integrated Risk-based Engineering - A Review in Respect of Nuclear Power Plant Safety

    Directory of Open Access Journals (Sweden)

    Michael G. Pecht

    2012-01-01

    Full Text Available The present approach of plant surveillance employs, on-line monitoring of process parameters, periodic in-service inspection, condition monitoring, etc. To make these program more effective there is growing application of risk-based / risk-informed approach to plant surveillance. However, risk-based approach in the present form is ���static’ in nature, and based on probabilistic methods. It is expected that to cater to real-time challenges the approach should be dynamic in terms on-line monitoring that employing deterministic and probabilistic methods in an integrated manner. The available literature suggests that extensive efforts are being made to upgrade / modify existing condition based approach to prognostic approach. There is a general appreciation of the fact that the prediction capabilities in surveillance programme in general and conditioning monitoring approach in particular can be improved significantly through prognostic approach. This paper reviews prognostics approach that enabled assessment of remaining life of the components in complex engineering systems with a special reference to nuclear plants where safety forms the major objective function.

  18. Improvement of nuclear ship engineering simulation system. Hardware renewal and interface improvement of the integral type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Hiroki; Kyoya, Masahiko; Shimazaki, Junya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kano, Tadashi [KCS, Co., Mito, Ibaraki (Japan); Takahashi, Teruo [Energis, Co., Kobe, Hyogo (Japan)

    2001-10-01

    JAERI had carried out the design study about a lightweight and compact integral type reactor (an advanced marine reactor) with passive safety equipment as a power source for the future nuclear ships, and completed an engineering design. We have developed the simulator for the integral type reactor to confirm the design and operation performance and to utilize the study of automation of the reactor operation. The simulator can be used also for future research and development of a compact reactor. However, the improvement in a performance of hardware and a human machine interface of software of the simulator were needed for future research and development. Therefore, renewal of hardware and improvement of software have been conducted. The operability of the integral-reactor simulator has been improved. Furthermore, this improvement with the hardware and software on the market brought about better versatility, maintainability, extendibility and transfer of the system. This report mainly focuses on contents of the enhancement in a human machine interface, and describes hardware renewal and the interface improvement of the integral type reactor simulator. (author)

  19. Role of Prognostics in Support of Integrated Risk-based Engineering - A Review in Respect of Nuclear Power Plant Safety

    Directory of Open Access Journals (Sweden)

    Prabhakar V. Varde

    2012-12-01

    Full Text Available The present approach of plant surveillance employs, on-line monitoring of process parameters, periodic in-service inspection, condition monitoring, etc. To make these program more effective there is growing application of risk-based / risk-informed approach to plant surveillance. However, risk-based approach in the present form is ‘static’ in nature, and based on probabilistic methods. It is expected that to cater to real-time challenges the approach should be dynamic in terms on-line monitoring that employing deterministic and probabilistic methods in an integrated manner. The available literature suggests that extensive efforts are being made to upgrade / modify existing condition based approach to prognostic approach. There is a general appreciation of the fact that the prediction capabilities in surveillance programm in general and conditioning monitoring approach in particular can be improved significantly through prognostic approach. This paper reviews prognostics approach that enabled assessment of remaining life of the components in complex engineering systems with a special reference to nuclear plants where safety forms the major objective function.

  20. Lunar nuclear power plant design for thermal-hydraulic cooling in nano-scale environment: Nuclear engineering-based interdisciplinary nanotechnology

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Tae Ho [Systemix Global Co. Ltd., Seoul (Korea, Republic of)

    2015-05-15

    The environment of the Moon is nearly vacant, which has very low density of several kinds of gases. It has the molecular level contents of the lunar atmosphere in Table 1, which is recognized that radiation heat transfer is a major cooling method. The coolant of the nuclear power plant (NPP) in the lunar base is the Moon surface soil , which is known as the regolith. The regolith is the layer of loose and heterogeneous material covering the solid rock. For finding the optimized length of the radiator of the coolant in the lunar NPP, the produced power and Moon environmental temperature are needed. This makes the particular heat transfer characteristics in heat transfer in the Moon surface. The radiation is the only heat transfer way due to very weak atmosphere. It is very cold in the night time and very hot in the daytime on the surface of the ground. There are comparisons between lunar high land soil and Earth averages in Table 2. In the historical consideration, Konstantin Tsiolkovsky made a suggestion for the colony on the Moon.. There are a number of ideas for the conceptual design which have been proposed by several scientists. In 1954, Arthur C. Clarke mentioned a lunar base of inflatable modules covered in lunar dust for insulation. John S. Rinehart suggested the structure of the stationary ocean of dust, because there could be a mile-deep dust ocean on the Moon, which gives a safer design. In 1959, the project horizon was launched regarding the U.S. Army's plan to establish a fort on the Moon by 1967. H. H. Koelle, a German rocket engineer of the Army Ballistic Missile Agency, leaded the project (ABMA). There was the first landing in 1965 and 245 tons of cargos were transported to the outpost by 1966. The coolant material of regolith in the Moon is optimized for the NPP. By the simulation, there are some results. The temperature is calculated as the 9 nodals by radiation heat transfer from the potassium coolant to the regolith flow. The high efficiency

  1. Study of social responsibility of the Nuclear and Energy Research Institute of Sao Paulo (IPEN/CNEN-SP); Estudo da responsabilidade social do Instituto de Pesquisas Energeticas e Nucleares de Sao Paulo (IPEN/CNEN-SP)

    Energy Technology Data Exchange (ETDEWEB)

    Mutarelli, Rita de Cassia

    2014-07-01

    Over the years, the socio-environmental concept has grown through programs, conferences and several activities that have been held in Brazil and worldwide. Sustainability and social responsibility are now an integral part of everyday life of organizations The Instituto de Pesquisas Energeticas e Nucleares (IPEN), which is the focus of this research, is committed to the improvement of Brazilian quality of life. Based on IPEN's mission, and due to the lack of tools for assessing socio-environmental actions, this research aims to propose an assessment tool for social responsibility, which may also be a methodological resource committed to the improvement of the Institute. Through indicators and dimensions, a methodology to assess social responsibility and identify both strengths and weaknesses was designed. The methodology was administered to IPEN, and the results demonstrated positive aspects regarding actions towards the internal publics and negative aspects towards the external publics that require improvement. The results obtained were satisfactory. Nevertheless, as the subject of this study is a broad theme, further studies are suggested. IPEN's board may use the results of this research as a tool to help them identify feasible socio-environmental actions to be implemented in the institute. (author)

  2. Analysis of technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla'

    Directory of Open Access Journals (Sweden)

    Grbić Maja

    2014-01-01

    Full Text Available This paper presents an analysis of the technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla' in Belgrade. Calculation of solar irradiation is performed and the conceptual design of the disposition of solar panels on the roof of the building is shown as well as their connections to the inverters. Conditions for connecting the plant to the distribution network are checked and an economic analysis of the project is performed.

  3. Final priority; National Institute on Disability and Rehabilitation Research--Disability and Rehabilitation Research Projects and Centers Program--Rehabilitation Engineering Research Centers. Final priority.

    Science.gov (United States)

    2013-06-14

    The Assistant Secretary for Special Education and Rehabilitative Services announces a priority for a Rehabilitation Engineering Research Center (RERC) on Universal Interfaces and Information Technology Access under the Disability and Rehabilitation Research Projects and Centers Program administered by the National Institute on Disability and Rehabilitation Research (NIDRR). The Assistant Secretary may use this priority for a competition in fiscal year (FY) 2013 and later years. We take this action to focus research attention on areas of national need. We intend to use this priority to improve outcomes for individuals with disabilities.

  4. Final priority; National Institute on Disability and Rehabilitation Research--Disability and Rehabilitation Projects and Centers Program--Rehabilitation Engineering Research Centers. Final priority.

    Science.gov (United States)

    2013-06-19

    The Assistant Secretary for Special Education and Rehabilitative Services announces a priority for a Rehabilitation Engineering Research Center (RERC) on Technologies to Support Successful Aging with Disability under the Disability and Rehabilitation Research Projects and Centers Program administered by the National Institute on Disability and Rehabilitation Research (NIDRR). The Assistant Secretary may use this priority for a competition in fiscal year (FY) 2013 and later years. We take this action to focus research attention on areas of national need. We intend to use this priority to improve outcomes for individuals with disabilities.

  5. White paper on nuclear astrophysics and low energy nuclear physics Part 1: Nuclear astrophysics

    Science.gov (United States)

    Arcones, Almudena; Bardayan, Dan W.; Beers, Timothy C.; Bernstein, Lee A.; Blackmon, Jeffrey C.; Messer, Bronson; Brown, B. Alex; Brown, Edward F.; Brune, Carl R.; Champagne, Art E.; Chieffi, Alessandro; Couture, Aaron J.; Danielewicz, Pawel; Diehl, Roland; El-Eid, Mounib; Escher, Jutta E.; Fields, Brian D.; Fröhlich, Carla; Herwig, Falk; Hix, William Raphael; Iliadis, Christian; Lynch, William G.; McLaughlin, Gail C.; Meyer, Bradley S.; Mezzacappa, Anthony; Nunes, Filomena; O'Shea, Brian W.; Prakash, Madappa; Pritychenko, Boris; Reddy, Sanjay; Rehm, Ernst; Rogachev, Grigory; Rutledge, Robert E.; Schatz, Hendrik; Smith, Michael S.; Stairs, Ingrid H.; Steiner, Andrew W.; Strohmayer, Tod E.; Timmes, F. X.; Townsley, Dean M.; Wiescher, Michael; Zegers, Remco G. T.; Zingale, Michael

    2017-05-01

    This white paper informs the nuclear astrophysics community and funding agencies about the scientific directions and priorities of the field and provides input from this community for the 2015 Nuclear Science Long Range Plan. It summarizes the outcome of the nuclear astrophysics town meeting that was held on August 21-23, 2014 in College Station at the campus of Texas A&M University in preparation of the NSAC Nuclear Science Long Range Plan. It also reflects the outcome of an earlier town meeting of the nuclear astrophysics community organized by the Joint Institute for Nuclear Astrophysics (JINA) on October 9-10, 2012 Detroit, Michigan, with the purpose of developing a vision for nuclear astrophysics in light of the recent NRC decadal surveys in nuclear physics (NP2010) and astronomy (ASTRO2010). The white paper is furthermore informed by the town meeting of the Association of Research at University Nuclear Accelerators (ARUNA) that took place at the University of Notre Dame on June 12-13, 2014. In summary we find that nuclear astrophysics is a modern and vibrant field addressing fundamental science questions at the intersection of nuclear physics and astrophysics. These questions relate to the origin of the elements, the nuclear engines that drive life and death of stars, and the properties of dense matter. A broad range of nuclear accelerator facilities, astronomical observatories, theory efforts, and computational capabilities are needed. With the developments outlined in this white paper, answers to long standing key questions are well within reach in the coming decade.

  6. Thermodynamic Modeling of the Chemical Composition of Calcine at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    C. M. Frazee; J. D. Christian

    2004-02-01

    To send calcine produced at Idaho National Engineering and Environmental Laboratory to the Yucca Mountain Project for disposal, characterization information will be required. To sample calcine from its existing storage location would require extensive personnel exposure. Sufficient analyses of the chemical composition of the calcine would be extremely difficult and very expensive. In support of characterization development, the chemical composition of calcine from Bin 3 of Calcine Solid Storage Facility II was thermodynamic modeled. This calcine was produced in the Waste Calcination Facility during its second processing campaign, operating with indirect heating at 400 C and 0.744 bar (0.734 atm) during processing of aluminum high-level liquid waste (first cycle extraction raffinate from reprocessing aluminum-clad fuels) from tanks WM-180 and -182 from December 27, 1966 through August 26, 1967. The current modeling effort documents the input compositional data (liquid feed and calciner off-gas) for Batches 300 - 620 and a methodology for estimating the calcine chemical composition. The results, along with assumptions and limitations of the thermodynamic calculations, will serve as a basis for benchmarking subsequent calculations. This will be done by comparing the predictions against extensive analytical results that are currently being obtained on representative samples of the modeled calcine. A commercial free-energy minimization program and database, HSC 5.1, was used to perform the thermodynamic calculations. Currently available experimental data and process information on the calcine were used to make judgments about specific phases and compounds to include and eliminate in the thermodynamic calculations. Some off-gas species were eliminated based on kinetics restrictions evidenced by experimental data and other estimates, and some calcine components and off-gas compounds were eliminated as improbable species (unreliable thermodynamic data). The current Yucca

  7. Nuclear Security Education Program at the Pennsylvania State University

    Energy Technology Data Exchange (ETDEWEB)

    Uenlue, Kenan [The Pennsylvania State University, Radiation Science and Engineering Center, University Park, PA 16802-2304 (United States); The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, University Park, PA 16802-2304 (United States); Jovanovic, Igor [The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, University Park, PA 16802-2304 (United States)

    2015-07-01

    The availability of trained and qualified nuclear and radiation security experts worldwide has decreased as those with hands-on experience have retired while the demand for these experts and skills have increased. The U.S. Department of Energy's National Nuclear Security Administration's (NNSA) Global Threat Reduction Initiative (GTRI) has responded to the continued loss of technical and policy expertise amongst personnel and students in the security field by initiating the establishment of a Nuclear Security Education Initiative, in partnership with Pennsylvania State University (PSU), Texas A and M (TAMU), and Massachusetts Institute of Technology (MIT). This collaborative, multi-year initiative forms the basis of specific education programs designed to educate the next generation of personnel who plan on careers in the nonproliferation and security fields with both domestic and international focus. The three universities worked collaboratively to develop five core courses consistent with the GTRI mission, policies, and practices. These courses are the following: Global Nuclear Security Policies, Detectors and Source Technologies, Applications of Detectors/Sensors/Sources for Radiation Detection and Measurements Nuclear Security Laboratory, Threat Analysis and Assessment, and Design and Analysis of Security Systems for Nuclear and Radiological Facilities. The Pennsylvania State University (PSU) Nuclear Engineering Program is a leader in undergraduate and graduate-level nuclear engineering education in the USA. The PSU offers undergraduate and graduate programs in nuclear engineering. The PSU undergraduate program in nuclear engineering is the largest nuclear engineering programs in the USA. The PSU Radiation Science and Engineering Center (RSEC) facilities are being used for most of the nuclear security education program activities. Laboratory space and equipment was made available for this purpose. The RSEC facilities include the Penn State Breazeale

  8. Research Group Introduction : Welfare System Laboratory, Dept.of Electrical, Electronics and Computer Engineering, Chiba Institute of Technology

    Science.gov (United States)

    関, 弘和

    Welfare system laboratory in Chiba Institute of Technology consists of twenty students. The research subjects include the driving control system of electric powered wheelchairs, myoelectric hand control based on EMG signal analysis and non-daily behavior detection monitoring system for elderly people.

  9. EMERGING TECHNOLOGY BULLETIN: DEVELOPMENT OF A PHOTOTHERMAL DETOXIFICATION UNIT - ENVIRONMENTAL SCIENCE AND ENGINEERING GROUP - UNIVERSITY OF DAYTON RESEARCH INSTITUTE

    Science.gov (United States)

    The University of Dayton Research Institute has developed a novel photochemical process embodied in a device called a Photothermal Detoxification Unit (PDU) which offers an efficient means of destroying hazardous organic wastes. The PDU, which overcomes the problems of slow react...

  10. Section 7033 of the America COMPETES Act: Hispanic-Serving Institutions and Science, Technology, Engineering and Mathematics (STEM)

    Science.gov (United States)

    Gartrell, Sandra

    2009-01-01

    On March 1, 2009 from 2 pm to 5 pm at the Madison Hotel in Washington, DC, the National Science Foundation hosted a listening session, requesting input on Section 7033 of the America COMPETES (Creating Opportunities to Meaningfully Promote Excellence in Technology, Education, and Science) Act regarding Hispanic-serving institutions and science,…

  11. The Evaluative State, Institutional Autonomy and Re-engineering Higher Education in Western Europe: The Prince and His Pleasure

    NARCIS (Netherlands)

    Neave, Guy

    2012-01-01

    This vigorous study provides an alternative framework for reflecting on the changes in Western Europe's higher education systems over the past quarter century. Building from two basic concepts – the rise of the evaluative state and the shifts in meaning and definition of positional and institutional

  12. 1996 Department of Energy pre-freshman enrichment program at GMI Engineering and Management Institute, Flint, MI

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This document reports on a summer program to encourage students to pursue scientific or engineering professions. The topics of the report include a description of the recruitment program, selection criteria for participants, workshops, nine follow up activities, research projects and student`s presentation, and field trips. Course descriptions and schedule are included as appendices.

  13. Converting STEM Doctoral Dissertations into Patent Applications: A Study of Chemistry, Physics, Mathematics, and Chemical Engineering Dissertations from CIC Institutions

    Science.gov (United States)

    Butkovich, Nancy J.

    2015-01-01

    Doctoral candidates may request short-term embargoes on the release of their dissertations in order to apply for patents. This study examines how often inventions described in dissertations in chemical engineering, chemistry, physics, and mathematics are converted into U.S. patent applications, as well as the relationship between dissertation…

  14. Converting STEM Doctoral Dissertations into Patent Applications: A Study of Chemistry, Physics, Mathematics, and Chemical Engineering Dissertations from CIC Institutions

    Science.gov (United States)

    Butkovich, Nancy J.

    2015-01-01

    Doctoral candidates may request short-term embargoes on the release of their dissertations in order to apply for patents. This study examines how often inventions described in dissertations in chemical engineering, chemistry, physics, and mathematics are converted into U.S. patent applications, as well as the relationship between dissertation…

  15. MATLAB辅助核反应堆工程专业的教学探索%Exploration of Auxiliary Teaching in Nuclear Reactor Engineering with MATLAB

    Institute of Scientific and Technical Information of China (English)

    何丽华; 于涛; 屈国普; 李小华; 谢金森

    2014-01-01

    MATLAB仿真软件是一套功能强大的数值计算和可视化软件,广泛应用于数值计算、系统的建模、分析和设计中。简要介绍了核反应堆工程专业的课程特点,通过实例重点阐述了MATLAB在课程中的具体应用。实践证明,利用MATLAB辅助教学,有助于学生理解和掌握比较抽象的问题,有效提高教学效果与教学质量。%MATLAB simulation software is a powerful set of numerical computation and visualization software,widely used in the control system modeling,analysis and design. The course' s characteristics of the nuclear reactor engineering were brief introduced. Through examples the specific applications of the MATLAB in nuclear reactor engineering courses were mainly discussed. practice has proved that:MATLAB applied to teaching and research in nuclear reactor engineering cour-ses can help students understand and grasp more abstract issues,and improve teaching effectiveness and the quality of teaching.

  16. Research Progress on Allocation of Clinical Engineering Stafifng in Medical Institutes%医疗机构临床工程人员配置研究进展

    Institute of Scientific and Technical Information of China (English)

    裴智军; 高关心

    2015-01-01

    The concept of clinical engineering staff and the necessity of reasonable allocation of clinical engineering staffing were given firstly. Then this paper reviewed the methods of allocating clinical engineering staff at home and abroad, including staff allocation based on the number of health technicians, operating beds and medical device, the total acquisition cost of medical devices and workload calculation. Several suggestions for allocation of clinical engineering staff were put forward based on the summarization of all the methods, which provided references for formulation of accurate, reliable and feasible methods to allocate clinical engineering staff in medical institutes.%本文介绍了临床工程人员的概念与合理配置临床工程人员的必要性,综述了国内外临床工程人员配置方法,包括以卫生技术人员数量按比例配置、以开放床位数量按比例配置、以医疗设备数量或总值金额按比例配置、以临床工程部门工作量测算配置,并在各类方法总结比较的基础上,提出对临床工程人员现状和配置标准进行系统和深入研究的相关建议,以期为医疗机构制定科学、合理、可操作性强的临床工程人员编配办法提供参考。

  17. Teaching Research on Nuclear Techniques and Nuclear Engineering and Attempts in Training Students' Competence%核技术与核工程课程教学与学生能力培养探索

    Institute of Scientific and Technical Information of China (English)

    郭立平; 刘传胜

    2012-01-01

    文章介绍了笔者在核技术与核工程课程教学与学生能力培养方面的一些经验和尝试。重点介绍了以粒子加速器和核反应堆为代表的大型核科学平台以及在其上建立的应用广泛的重要核技术。在讲授基础知识的同时,突出了当代核技术及应用最新进展。在提高学生能力方面,尝试了课程论文、业余科研和毕业设计三种实践模式,并获得了良好的效果。%The article introduces the author's some experience and try in nuclear technology and engineering curriculum tea- ching and the cultivation of the students' capability, Focused on large nuclear science platform as the representative of particle accelerator and nuclear reactor and widely applied nuclear techniques based on the platform. Contemporary nuclear techni- ques and their up-to-date applications are emphasized, while basic knowledge was taught. In order to improve the students' competence, course thesis, extracurricular academic research as well as graduation design three practical modes are attempted and obtain a good effect.

  18. Spatial variability of sedimentary interbed properties near the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory, Idaho

    Science.gov (United States)

    Winfield, Kari A.

    2003-01-01

    The subsurface at the Idaho National Engineering and Environmental Laboratory (INEEL) is complex, comprised primarily of thick, fractured basalt flows interbedded with thinner sedimentary intervals. The unsaturated zone can be as thick as 200 m in the southwestern part of the INEEL. The Vadose Zone Research Park (VZRP), located approximately 10 km southwest of the Idaho Nuclear Technology and Engineering Center (INTEC), was established in 2001 to study the subsurface of a relatively undisturbed part of the INEEL. Waste percolation ponds for the INTEC were relocated to the VZRP due to concerns that perched water within the vadose zone under the original infiltration ponds (located immediately south of the INTEC) could contribute to migration of contaminants to the Snake River Plain aquifer. Knowledge of the spatial distribution of texture and hydraulic properties is important for developing a better understanding of subsurface flow processes within the interbeds, for example, by identifying low permeability layers that could lead to the formation of perched ground-water zones. Because particle-size distributions are easier to measure than hydraulic properties, particle size serves as an analog for determining how the unsaturated hydraulic properties vary both vertically within particular interbeds and laterally within the VZRP. As part of the characterization program for the subsurface at the VZRP, unsaturated and saturated hydraulic properties were measured on 10 core samples from six boreholes. Bulk properties, including particle size, bulk density, particle density, and specific surface area, were determined on material from the same depth intervals as the core samples, with an additional 66 particle- size distributions measured on bulk samples from the same boreholes. From lithologic logs of the 32 boreholes at the VZRP, three relatively thick interbeds (in places up to 10 m thick) were identified at depths of 35, 45, and 55 m below land surface. The 35-m

  19. 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。

  20. DEFINING ‘PROJECT SUCCESS’ FOR A COMPLEX PROJECT – THE CASE OF A NUCLEAR ENGINEERING DEVELOPMENT

    Directory of Open Access Journals (Sweden)

    S.I. Van Niekerk

    2012-01-01

    Full Text Available

    ENGLISH ABSTRACT: The case of a nuclear engineering project was investigated to establish the relevant success criteria for the development of complex, high-technology systems. The project was first categorised according to an existing scheme, and the Delphi method was used to determine the criteria for project success that apply to this specific case. A framework of project success dimensions was extended to include criteria that are of specific importance for the project under consideration.

    While project efficiency (delivery on time and within budget obviously still needs to be controlled, the results provide empirical evidence for the notion that, for ‘super high tech’ projects, this is relatively less important. The relative importance of the dimensions of success was also evaluated and presented on a timeline stretching from project execution to 10 years after project completion. This provided empirical evidence for certain concepts in the literature.

    AFRIKAANSE OPSOMMING: Die geval van ʼn kern-ingenieursprojek is ondersoek om die relevante kriteria vir sukses vir die ontwikkeling van komplekse hoë-tegnologiesisteme te bepaal. Die projek is eerstens geklassifiseer volgens ʼn bestaande skema, en die Delphi-metode is vervolgens gebruik om die relevante kriteria vir projeksukses vir die betrokke geval te bepaal. ʼn Bestaande raamwerk van dimensies vir projeksukses is uitgebrei om kriteria wat van spesifieke belang vir die betrokke geval in te sluit.

    Terwyl tydige aflewering, binne begroting natuurlik steeds belangrik is, voorsien die resultate empiriese bewys vir die nosie in die literatuur dat hierdie aspekte van relatief minder belang is in die geval van ‘super hoë-tegnologie’-projekte. Die relatiewe belangrikheid van die dimensies van sukses is ook evalueer, en aangedui op ʼn tydlyn wat strek van projekuitvoering tot 10 jaar na die afhandeling van die projek. Dit lewer empiriese bewys vir sekere bewerings in

  1. Environmental concerns regarding a materials test reactor fuel fabrication facility at the Nuclear and Energy Research Institute - IPEN; Atomos para el desarrollo de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Santos, G. R. T.; Durazzo, M.; Carvalho, E. F. U. [IPEN, CNEN-SP, P.O. Box 11049, CEP 05422-970, Sao Paulo (Brazil); Riella, H. G. [Universidade Federal de Santa Catarina, Departamento de Engenharia Quimica, Campus Universitario, Florianopolis, CEP 88040-900 (Brazil)]. e-mail: grsantos@ipen.br

    2008-07-01

    The aim of the industrial activities success, front to a more and more informed and demanding society and to a more and more competitive market demands an environmental administration policy which doesn't limit itself to assist the legislation but anticipate and prevent, in a responsible way, possible damages to the environment. One of the maim programs of the Institute of Energetic and Nuclear Research of the national Commission of Nuclear Energy located in Brazil, through the Center of Nuclear Fuel - CCN - is to manufacture MTR-type fuel elements using low-enrichment uranium (20 wt% {sup 2}35U), to supply its IEA-RI research reactor. Integrated in this program, this work aims at well developing and assuring a methodology to implant an environment, health and safety policy, foreseeing its management with the use of detailed data reports and through the adoption of new tools for improving the management, in order to fulfil the applicable legislation and accomplish all the environmental, operational and works aspects. The applied methodology for the effluents management comprises different aspects, including the specific environmental legislation of a country, main available effluents treatment techniques, process flow analyses from raw materials and intakes to products, generated effluents, residuals and emissions. Data collections were accomplished for points gathering and tests characterization, classification and compatibility of the generated effluents and their eventual environmental impacts. This study aims to implant the Sustainable Concept in order to guarantee access to financial resources, allowing cost reduction, maximizing long-term profits, preventing and reducing environmental accident risks and stimulating both the attraction and the keeping of a motivated manpower. Work on this project has already started and, even though many technical actions have not still ended, the results have being extremely valuable. These results can already give to

  2. Good practices in decommissioning planning and pre-decommissioning activities for the Magurele VVR-S nuclear research reactor

    OpenAIRE

    Dragusin Mitica; Pavelescu Octavian Alexandru; Iorga Ioan

    2011-01-01

    The VVR-S Nuclear Research Reactor at the “Horia Hulubei” National Institute of Physics and Nuclear Engineering in Magurele, Bucharest, will be decommissioned applying the immediate dismantling strategy. The implementation of the decommissioning project started in 2010 and is planned for completion within 11 years. Good practices in decommissioning planning, organization, funding, and logistics are described in this paper.

  3. Nuclear education, training and knowledge management in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Beeley, Phil; Slugen, Vladimir; Kyrki-Rajamaeki, Rita [European Nuclear Society ENS, Brussels (Belgium). ENS High Scientific Council

    2010-04-15

    The situation in the nuclear education today is complex as it relates to nuclear technology for both peaceful and security applications. After more than 20 years period of depression in nuclear facility construction (significant mainly in Europe and USA), there is strong renewed interest in nuclear-generated electricity. Many factors have contributed to ''nuclear renaissance'' including concerns about possible climate changes due to carbon emissions. The Nuclear Energy Agency (OECD/NEA) study in 2000, ''Nuclear Education and Training. Cause for Concern'', highlighted the necessity for a renaissance in nuclear education and training with some recommendations. The European Nuclear Energy Forum (ENEF) identified the nuclear education as one of highest risks in nuclear industry. The nuclear renaissance depends on the increased number of engineers properly educated in wide spectrum of nuclear disciplines. The world has responded. Networks have been established to respond to the necessity to maintain and perpetuate nuclear knowledge in order to provide a suitably qualified workforce for the future operation of nuclear power plants. The quality in Education, Training and Knowledge Management (ETKM) is strongly influenced and supported by development of nuclear research, exploitation of experimental and training facilities, existence of proper education and training networks, software tools, distance and e-learning and a variety of knowledge management activities. The projected global annual requirements for new nuclear engineers over the next 10 years will challenge existing academic and training institutions with respect to capacity and load factors on classrooms, laboratories and other facilities such as basic principles simulators. Additionally, the nuclear academic workforce may need to increase to meet the demand for educating/training the new industrial workforce and this will take time. Within the European context many of the

  4. Pertinence of tests used for conformity assessments of fire resistance of nuclear power plant components. Opinion of several institutions in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Bruynooghe, Christiane [European Commission, DG-JRC, Petten (Netherlands). Inst. for Energy - Nuclear Operation Safety; Hostikka, Simo [VTT Technical Research Centre of Finland (Finland); Maillet, Eric [SUEZ-TRACTEBEL Engineering (GDF SUEZ), Brussels (Belgium); Neugebauer, Wilfried [AREVA NP GmbH, Erlangen (Germany); Richard, Jerome [IRSN, 92 - Fontenay-aux-Roses (France); Roewekamp, Marina [GRS mbH, Koeln (Germany); Zdenek, Tipek [State Office for Nuclear Safety (SUJB), Prague (Czech Republic)

    2010-04-15

    Fire resistance of structures, systems and components (SSC) is widely identified as a fundamental issue for fire risk assessment at nuclear power plants (NPP). It is currently supported by several national or international ambitious experimental programs. Fire risk assessment at NPPs is performed under a series of hypothesis, e.g. the fire load. A problem will arise if tests used for conformity assessment do not appropriately represent the hypothesis selected during the fire risk analysis. In this case, SSCs may possibly be not meeting the expectations related to their fire resistance capacity supposed by the fire risk analysis. Ways of tackling this issue involve a regulatory approach and adapted requirements for components. While the widespread regulatory approach consists in seeking enveloping scenarios and conservative assumptions, a better knowledge of SSCs behaviour under for NPPs typical situations may be also desirable. The Institute for Energy of the European Commission's Joint Research Centre (JRC) at Petten (NL) launched a questionnaire with the aim of gathering opinions of regulatory bodies and their technical support organisations and manufacturers in Europe on this topic. Major goal was to estimate the relevance of the issue according to the perception of the specialists. The present paper collects the answers given by seven entities (AREVA, GRS, iBMB, IRSN, SJUB, SUEZ-TRACTEBEL, and VTT) and makes suggestions for addressing the issues identified by the participants. (orig.)

  5. Annual report 1993 by the Rossendorf Society of Nuclear Engineering and Analysis; Verein fuer Kernverfahrenstechnik und Analytik Rossendorf. Jahresbericht 1993

    Energy Technology Data Exchange (ETDEWEB)

    Haefele, W. [ed.

    1994-03-01

    The second annual report contains, apart from the business report and the organigram, priorities and results achieved in the special fields of nuclear installations (decommissioning and disposal), nuclear waste management (radioactive wastes), nuclear analyses and rehabilitation, radiopharmaceuticals, and safety and radiation protection. (HP) [Deutsch] Der 2. Jahresbericht enthaelt neben dem kaufmaennischen Geschaeftsbericht und dem Organigramm die Schwerpunktaufgaben und erziehlten Ergebnisse der Fachbereiche Kernanlagen (Stillegung und Entsorgung), Nukleare Entsorgungswirtschaft (radioaktive Abfaelle), Nukleare Analytik und Sanierung, Radiopharmaka, und Sicherheit und Strahlenschutz. (HP)

  6. Pengembangan Peta Tiga Dimensi Interaktif Untuk Graha ITS dan UPT Bahasa Institut Teknologi Sepuluh Nopember Menggunakan Unity 3D Engine

    Directory of Open Access Journals (Sweden)

    Fino Nurcahyo Nugrohoadi

    2014-09-01

    Full Text Available Penggunaan teknologi informasi dalam pemetaan digital sudah lama digunakan. Dahulu orang cenderung melakukan pemetaan digital secara 2D untuk memetakan suatu area atau gedung, namun pemetaan secara 2D sendiri tidak memberikan informasi secara mendetail tentang keadaan dan topografi dari area atau gedung tersebut. Seiring dengan perkembangan teknologi informasi penggunaan teknologi 3D pun mulai digunakan dalam pemetaan secara digital agar dapat memberikan informasi yang lebih mendetail tentang keadaan suatu area atau gedung. Untuk membangun sebuah peta 3D dapat dilakukan menggunakan engine 3D yang biasanya digunakan untuk membuat game. Dengan memanfaatkan Unity Engine penulis akan membangun sebuah pemetaan digital secara 3D agar dari pemetaan tersebut dapat memberikan informasi yang akurat dan tepat mengenai keadaan area yang dipetakan sesuai dengan kenyataan. Penulis akan memetakan gedung Graha dan UPT Bahasa ITS. Dengan pemetaan secara 3D ini penulis berharap dapat memberikan informasi yang akurat dan mendetail kepada pengguna peta 3D ini nantinya tentang keadaan dari gedung Graha dan UPT Bahasa ITS

  7. Mechanical Engineering Department technical review

    Energy Technology Data Exchange (ETDEWEB)

    Carr, R.B.; Abrahamson, L.; Denney, R.M.; Dubois, B.E (eds.)

    1982-01-01

    Technical achievements and publication abstracts related to research in the following Divisions of Lawrence Livermore Laboratory are reported in this biannual review: Nuclear Fuel Engineering; Nuclear Explosives Engineering; Weapons Engineering; Energy Systems Engineering; Engineering Sciences; Magnetic Fusion Engineering; and Material Fabrication. (LCL)

  8. PSI Paul Scherrer Institute; PSI Institut Paul Scherrer

    Energy Technology Data Exchange (ETDEWEB)

    Lefrancois, M.; Pladys, D

    2008-05-15

    From research activities focused on civil and military uses of nuclear energy and developed after the second world war, the Paul Scherrer Institute (PSI) has been able to diversify its activities following 2 axis. First, the Gantry proton-therapy that is characterized by a compact equipment and an accurate 3-dimensional treatment of tumors (more than 260 patients have been treated by Gantry from 1996 to 2005). Secondly, new technologies in the fields of energy and transport. Nevertheless, PSI has been able to keep a high of valuation of its staff in nuclear engineering and materials that are the core of its activities. The main equipment of PSI are: -) SLS (Swiss Light Source): a synchrotron radiation source that is both a microscope and an X-ray source; -) SINQ: a neutron source based on spallation reactions; -)S{mu}S: a muon source; and -) the Philips accelerator that is used in radiochemistry and the production of isotopes used for the treatment of eye tumors. PSI has established a large cooperation with French research laboratories on issues like: nuclear reactor safety, synchrotron radiation, the transmutation of nuclear wastes, the design of a source of ultra-cold neutrons, or the development of a hydrogen-fueled light vehicle. The total budget of PSI for 2007 reached 174.2 million euros. (A.C.)

  9. Engineering ceramics

    CERN Document Server

    Bengisu, Murat

    2001-01-01

    This is a comprehensive book applying especially to junior and senior engineering students pursuing Materials Science/ Engineering, Ceramic Engineering and Mechanical Engineering degrees. It is also a reference book for other disciplines such as Chemical Engineering, Biomedical Engineering, Nuclear Engineering and Environmental Engineering. Important properties of most engineering ceramics are given in detailed tables. Many current and possible applications of engineering ceramics are described, which can be used as a guide for materials selection and for potential future research. While covering all relevant information regarding raw materials, processing properties, characterization and applications of engineering ceramics, the book also summarizes most recent innovations and developments in this field as a result of extensive literature search.

  10. Final priorities; National Institute on Disability and Rehabilitation Research--Disability and Rehabilitation Research Projects and Centers Program--Rehabilitation Engineering Research Centers. Final priorities.

    Science.gov (United States)

    2013-06-11

    The Assistant Secretary for Special Education and Rehabilitative Services announces priorities under the Disability and Rehabilitation Research Projects and Centers Program administered by the National Institute on Disability and Rehabilitation Research (NIDRR). Specifically, we announce priorities for a Rehabilitation Engineering Research Center (RERC) on Rehabilitation Strategies, Techniques, and Interventions (Priority 1), Information and Communication Technologies Access (Priority 2), Individual Mobility and Manipulation (Priority 3), and Physical Access and Transportation (Priority 4). The Assistant Secretary may use one or more of these priorities for competitions in fiscal year (FY) 2013 and later years. We take this action to focus research attention on areas of national need. We intend these priorities to improve community living and participation, health and function, and employment outcomes of individuals with disabilities.

  11. National parliaments fighting back? Institutional engineering as a successful means to become active actors in EU affairs

    Directory of Open Access Journals (Sweden)

    Fromage Diane

    2016-12-01

    Full Text Available The European integration process has long been characterised by the predominance of national executive powers. National parliaments were recognised as European actors after several decades only, in the Maastricht Treaty first and to an even larger extent in the Lisbon Treaty. Parliaments were hence long dependent on national constitutional, legal and administrative arrangements to be able to participate in EU affairs. This paper analyses how national parliaments (and their members have reacted to the challenge the European integration process has represented for them while it also takes due account of the role other institutions, such as constitutional courts, have played in this field. It is argued that while these arrangements may have been successful in allowing national parliaments to play a greater role in this field, they should remain temporary for they are characterised by uncertainty and instability and make it generally difficult for citizens to follow up on national parliaments’ actions and to be fully informed.

  12. Feedback from uncertainties propagation research projects conducted in different hydraulic fields: outcomes for engineering projects and nuclear safety assessment.

    Science.gov (United States)

    Bacchi, Vito; Duluc, Claire-Marie; Bertrand, Nathalie; Bardet, Lise

    2017-04-01

    In recent years, in the context of hydraulic risk assessment, much effort has been put into the development of sophisticated numerical model systems able reproducing surface flow field. These numerical models are based on a deterministic approach and the results are presented in terms of measurable quantities (water depths, flow velocities, etc…). However, the modelling of surface flows involves numerous uncertainties associated both to the numerical structure of the model, to the knowledge of the physical parameters which force the system and to the randomness inherent to natural phenomena. As a consequence, dealing with uncertainties can be a difficult task for both modelers and decision-makers [Ioss, 2011]. In the context of nuclear safety, IRSN assesses studies conducted by operators for different reference flood situations (local rain, small or large watershed flooding, sea levels, etc…), that are defined in the guide ASN N°13 [ASN, 2013]. The guide provides some recommendations to deal with uncertainties, by proposing a specific conservative approach to cover hydraulic modelling uncertainties. Depending of the situation, the influencing parameter might be the Strickler coefficient, levee behavior, simplified topographic assumptions, etc. Obviously, identifying the most influencing parameter and giving it a penalizing value is challenging and usually questionable. In this context, IRSN conducted cooperative (Compagnie Nationale du Rhone, I-CiTy laboratory of Polytech'Nice, Atomic Energy Commission, Bureau de Recherches Géologiques et Minières) research activities since 2011 in order to investigate feasibility and benefits of Uncertainties Analysis (UA) and Global Sensitivity Analysis (GSA) when applied to hydraulic modelling. A specific methodology was tested by using the computational environment Promethee, developed by IRSN, which allows carrying out uncertainties propagation study. This methodology was applied with various numerical models and in

  13. Development of human resources through the 2nd WNU Summer Institute

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. J.; Kang, H. K.; Kim, E. S.; Yun, S. K

    2006-10-15

    WNU-SI(World Nuclear University - Summer Institute) is the six-week program designed to develop and inspire future international leaders in the field of nuclear science and technology. In 2006, three Korean young scientists had chances to participate by support of this project. There were three purposes in this project; (1) to motivate young Korean nuclear engineers, (2) to develop the human network with future nuclear leaders in the world, (3) to collect the information for successful WNU-SI 2007 Korea.

  14. Application of complex engineering solutions through advanced composite innovation (for repair of degraded buried pipe at Vandellos II Nuclear Power Plant); Reparacion de tuberias de un sistema de servicios no esenciales con recubrimiento interno de fibra de carbono

    Energy Technology Data Exchange (ETDEWEB)

    Bueno, J. M.; Raji, B. B.

    2011-07-01

    This technical presentation is focused on introducing an engineering solution approach and identification of sensitivity of applications of advanced carbon fiber in a pressurized wet environment: Engineering design, quality assurance of installation, inspection, and a comprehensive testing program to validate and bench mark the design data and compliance with code requirements in nuclear power plants.

  15. HPC Institutional Computing Project: W15_lesreactiveflow KIVA-hpFE Development: A Robust and Accurate Engine Modeling Software

    Energy Technology Data Exchange (ETDEWEB)

    Carrington, David Bradley [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Waters, Jiajia [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-01-05

    KIVA-hpFE is a high performance computer software for solving the physics of multi-species and multiphase turbulent reactive flow in complex geometries having immersed moving parts. The code is written in Fortran 90/95 and can be used on any computer platform with any popular complier. The code is in two versions, a serial version and a parallel version utilizing MPICH2 type Message Passing Interface (MPI or Intel MPI) for solving distributed domains. The parallel version is at least 30x faster than the serial version and much faster than our previous generation of parallel engine modeling software, by many factors. The 5th generation algorithm construction is a Galerkin type Finite Element Method (FEM) solving conservative momentum, species, and energy transport equations along with two-equation turbulent model k-ω Reynolds Averaged Navier-Stokes (RANS) model and a Vreman type dynamic Large Eddy Simulation (LES) method. The LES method is capable modeling transitional flow from laminar to fully turbulent; therefore, this LES method does not require special hybrid or blending to walls. The FEM projection method also uses a Petrov-Galerkin (P-G) stabilization along with pressure stabilization. We employ hierarchical basis sets, constructed on the fly with enrichment in areas associated with relatively larger error as determined by error estimation methods. In addition, when not using the hp-adaptive module, the code employs Lagrangian basis or shape functions. The shape functions are constructed for hexahedral, prismatic and tetrahedral elements. The software is designed to solve many types of reactive flow problems, from burners to internal combustion engines and turbines. In addition, the formulation allows for direct integration of solid bodies (conjugate heat transfer), as in heat transfer through housings, parts, cylinders. It can also easily be extended to stress modeling of solids, used in fluid structure interactions problems, solidification, porous media

  16. Underrepresented Racial/Ethnic Minority Graduate Students in Science, Technology, Engineering, and Math (STEM) Disciplines: A Cross Institutional Analysis of their Experiences

    Science.gov (United States)

    Figueroa, Tanya

    Considering the importance of a diverse science, technology, engineering, and math (STEM) research workforce for our country's future, it is troubling that many underrepresented racial minority (URM) students start graduate STEM programs, but do not finish. However, some institutional contexts better position students for degree completion than others. The purpose of this study was to uncover the academic and social experiences, power dynamics, and programmatic/institutional structures URM students face within their graduate STEM programs that hinder or support degree progression. Using a critical socialization framework applied in a cross-comparative qualitative study, I focused on how issues of race, ethnicity, and underrepresentation within the educational contexts shape students' experiences. Data was collected from focus group interviews involving 53 URM graduate students pursuing STEM disciplines across three institution types -- a Predominately White Institution, a Hispanic-Serving Institution, and a Historically Black University. Results demonstrate that when students' relationships with faculty advisors were characterized by benign neglect, students felt lost, wasted time and energy making avoidable mistakes, had less positive views of their experiences, and had more difficulty progressing through classes or research, which could cause them to delay time to degree completion or to leave with a master's degree. Conversely, faculty empowered students when they helped them navigate difficult processes/milestones with regular check-ins, but also allowed students room to make decisions and solve problems independently. Further, faculty set the tone for the overall interactional culture and helping behavior in the classroom and lab contexts; where faculty modeled collaboration and concern for students, peers were likely to do the same. International peers sometimes excluded domestic students both socially and academically, which had a negative affect on

  17. Evaluation of the aptitude for the service of the pool of the TRIGA Mark III reactor of the National Institute of Nuclear Research of Mexico; Evaluacion de la aptitud para el servicio de la piscina del reactor TRIGA Mark III del Instituto Nacional de Investigaciones Nucleares de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Merino C, J.; Gachuz M, M.; Diaz S, A.; Arganis J, C.; Gonzalez R, C.; Nava G, T.; Medina R, M.J. [Departamento de Sintesis y Caracterizacion de Materiales del ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2001-07-01

    This work describes the evaluation of the structural integrity of the pool of the TRIGA Mark III reactor of the National Institute of Nuclear Research of Mexico, which was realized in July 2001, as an element to determine those actions for preventive and corrective maintenance which owner must do it for a safety and efficient operation of the component in the next years. (Author)

  18. IMPLEMENTATION OF EFQM MODEL IN A GREEK ENGINEERING HIGHER EDUCATION INSTITUTE: A FRAMEWORK AND A CASE STUDY

    Directory of Open Access Journals (Sweden)

    S.Spasos

    2008-03-01

    Full Text Available One of the most effective strategies evolved over the years that have been successfully used by business organizations is total quality management (TQM. TQM is a systems approach to management that aims to enhance value to customer by designing and continually improving organizational processes and systems. In Europe, the EFQM Excellence Model is one of the most widely used organizational TQM frame works and is based on nine criteria. TQM principles incorporated in to the EFQM model are well established in private sector organization but not in education; only a small number of universities, mainly in U.K. have formally adopted the EFQM model as basis for self-assessment. The gap in relative research publications suggest that further research is require on the adaptation of TQM principles and of the EFQM model in the context of Higher Education. The present paper discusses the adaptation of EFQM model in a Department of a Greek Higher Education Institute (HEI. The nine criteria (enablers and results were modified in order to reflect the unique characteristics of a HEI (students a customer, teaching and learning, etc. This process is accordance with recent Greek legislation (Law3374/2005 and Europe an initiatives for a European Higher Education Are a (Bologna process and Bergen report. The implementation of this frame work is, in general, successful. Based on this frame work and on external audit by a UK university, a joint post-graduate program as agreed.

  19. Integrated solutions to SHM problems: an overview of SHM research at the LANL/UCSD engineering institute

    Energy Technology Data Exchange (ETDEWEB)

    Farrar, Charles [Los Alamos National Laboratory; Park, Gyuhae [Los Alamos National Laboratory; Farinholt, Kevin [Los Alamos National Laboratory; Todd, Michael [Los Alamos National Laboratory

    2010-12-08

    This seminar will provide an overview of structural health monitoring (SHM) research that is being undertaken at Los Alamos National Laboratory (LANL). The seminar will begin by stating that SHM should be viewed as an important component of the more comprehensive intelligent life-cycle engineering process. Then LANL's statistical pattern recognition paradigm for addressing SHM problems will be introduced and current research that is focused on each part of the paradigm will be discussed. In th is paradigm, the process can be broken down into four parts: (1) Operational Evaluation, (2) Data Acquisition and Cleansing, (3) Feature Extraction, and (4) Statistical Model Development for Feature Discrimination. When one attempts to apply this paradigm to data from real world structures, it quickly becomes apparent that the ability to cleanse, compress, normalize and fuse data to account for operational and environmental variability is a key implementation issue when addressing Parts 2-4 of this paradigm. This discussion will be followed by the introduction a new project entitled 'Intelligent Wind Turbines' which is the focus of much of our current SHM research . This summary will be followed by a discussion of issues that must be addressed if this technology is to make the transition from research to practice and new research directions that are emerging for SHM.

  20. An improved ARS2-derived nuclear reporter enhances the efficiency and ease of genetic engineering in Chlamydomonas

    DEFF Research Database (Denmark)

    Specht, Elizabeth A; Nour-Eldin, Hussam Hassan; Hoang, Kevin T D

    2015-01-01

    The model alga Chlamydomonas reinhardtii has been used to pioneer genetic engineering techniques for high-value protein and biofuel production from algae. To date, most studies of transgenic Chlamydomonas have utilized the chloroplast genome due to its ease of engineering, with a sizeable suite...