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Sample records for berkeley nuclear engineering

  1. Nuclear Medicine at Berkeley Lab: From Pioneering Beginnings to Today (LBNL Summer Lecture Series)

    International Nuclear Information System (INIS)

    Summer Lecture Series 2006: Thomas Budinger, head of Berkeley Lab's Center for Functional Imaging, discusses Berkeley Lab's rich history pioneering the field of nuclear medicine, from radioisotopes to medical imaging.

  2. U.C. Berkeley Nuclear Engineering curriculum and research enhancement. Final report for award DE-FG03-94ER-76010 and progress report for award DE-FG03-95NE-38105, February 15, 1993--September 29, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Kastenberg, W.; Peterson, P.F.

    1996-10-24

    This report discusses the progress achieved during the multi-year program for curriculum and research enhancement for the Department of Nuclear Engineering at the University of California, Berkeley. Due to its declining utility for research, six years ago the department decommissioned the TRIGA research reactor, to make the space available for an accelerator-driven rotating target neutron source for fusion studies. The DOE has traditionally supported these university reactors, in part because they provide a vital educational experience for undergraduate students in reactor operations. Thus in 1993 the department was determined to use its DOE award to replace the undergraduate education that the research reactor formerly provided with an equal or superior educational experience. As this progress report indicates, they can now make a compelling argument that the effort has been successful. Students now have the opportunity to spend a full week at the Diablo Canyon Nuclear Power Plant, after spending two weeks full time at Berkeley studying plant operations. The students spend a full day operating the plant using the full-scale simulator, spend a day each individually and in small groups with operations and engineering personnel, and by the end of the week are intimately familiar with the basics of nuclear power plant operations, at a depth that can not be achieved with a university research reactor. A primary mission for nuclear engineering departments will remain the education of the engineers who will be responsible for the safe operation of the nation`s existing nuclear power plants. In the past, university research reactors have provided a crucial element in that education. As more research reactors are decommissioned in response to evolving research needs, the program developed may serve as a useful model for other nuclear engineering departments.

  3. Nuclear engineering introduction

    International Nuclear Information System (INIS)

    This book describes nuclear engineering introducing nuclear energy and its utilization, nuclear engineering basics, nuclear reactor and nuclear reaction, nuclear steam system, thermal output and reactor physics, transient reactor, radiation management, safety in nuclear power plant and nuclear economy. It explains the technical terms of nuclear engineering in detail.

  4. Follow the Money: Engineering at Stanford and UC Berkeley during the Rise of Silicon Valley

    Science.gov (United States)

    Adams, Stephen B.

    2009-01-01

    A comparison of the engineering schools at UC Berkeley and Stanford during the 1940s and 1950s shows that having an excellent academic program is necessary but not sufficient to make a university entrepreneurial (an engine of economic development). Key factors that made Stanford more entrepreneurial than Cal during this period were superior…

  5. Searching the "Nuclear Science Abstracts" Data Base by Use of the Berkeley Mass Storage System

    Science.gov (United States)

    Herr, J. Joanne; Smith, Gloria L.

    1972-01-01

    Advantages of the Berkeley Mass Storage System (MSS) for information retrieval other than its size are: high serial-read rate, archival data storage; and random-access capability. By use of this device, the search cost in an SDI system based on the Nuclear Science Abstracts" data base was reduced by 20 percent. (6 references) (Author/NH)

  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. An advanced educational program for nuclear professionals with social scientific literacy. A collaborative initiative by UC Berkeley and Univ. of Tokyo on the Fukushima accident

    International Nuclear Information System (INIS)

    The authors have collaborated for over three years in developing an advanced educational program to cultivate leading engineers who can productively interact with other stakeholders. The program is organized under a partnership between the Nuclear Engineering Department of University of California, Berkeley (UCBNE) and the Global COE Program 'Nuclear Education and Research Initiative' (GoNERI) of the University of Tokyo, and is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology), Japan. We conducted two 'summer schools' in 2009 and 2010 as trial cases of the educational program. This year, in response to the Fukushima Daiichi nuclear accident, we decided to make our third summer school a venue for preliminary, yet multi-dimensional learning from that event. This school was held in Berkeley, CA, in the first week of August, with 12 lecturers and 18 students from various fields and countries. In this paper, we will explain the concept, aim, and design of our program; do a preliminary assessment of its effectiveness; introduce a couple of intriguing discussions held by participants; and discuss the program's implications for the post-Fukushima nuclear context. (author)

  8. News of nuclear engineering

    International Nuclear Information System (INIS)

    Data on news of nuclear engineering in Bulgaria, Pakistan, Serbia, USA, South Africa, South Korea and Japan are presented. Problems of reactor safety, construction of new nuclear units at existing sites, highly enriched uranium removal are treated. Companies performing jobs on designing, manufacture of different nuclear reactor components are named. Questions of environment protection, timely information on accidents at NPP and qualified maintenance are discussed

  9. Nuclear rocket engine reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lanin, Anatoly

    2013-07-01

    Covers a new technology of nuclear reactors and the related materials aspects. Integrates physics, materials science and engineering Serves as a basic book for nuclear engineers and nuclear physicists. 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.

  10. Welding in nuclear engineering

    International Nuclear Information System (INIS)

    The 3rd international conference 'Welding in nuclear engineering', organized in 1978 by the Deutscher Verband fuer Schweisstechnik e.V., was, like the two foregoing conferences in 1970 and 1974, an absolute success. The noteworthy echo to this meeting in the international technical world - the number of 650 participants from 26 countries is self-evidence - and this fact, was for the Deutscher Verband fuer Schweisstechnik e.V. occasion and at the same time an obligation now to follow in the same way, the meeting that was started 12 years ago, by organizing the international conference 'Welding in nuclear engineering'. The conference this year offers in addition to the two plenary session lectures, 34 short reports and a further 28 single contributions in the form of two poster-sessions. Unfortunately, it was again not possible to accept all the papers submitted because the conference was limited to 2 days only. Nevertheless, the papers will offer a representative cross-section through the total range of welding engineering. In particular, the poster session, which take place for the first time within the scope of a meeting organized by the Working Group 'Welding in Nuclear Engineering', should contribute to the aim that this time again the discussions will form the main point of the conference. (orig./RW)

  11. 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)

  12. 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.

  13. A High Intensity Multi-Purpose D-D Neutron Generator for Nuclear Engineering Laboratories

    International Nuclear Information System (INIS)

    This NEER project involves the design, construction and testing of a low-cost high intensity D-D neutron generator for teaching nuclear engineering students in a laboratory environment without radioisotopes or a nuclear reactor. The neutron generator was designed, fabricated and tested at Lawrence Berkeley National Laboratory (LBNL)

  14. Bishop Berkeley

    OpenAIRE

    Bindon, Francis (Irish artist, 1690-1765)

    2008-01-01

    'Berkeley was born at his family home, Dysart Castle, near Thomastown, County Kilkenny, Ireland, the eldest son of William Berkeley, a cadet of the noble family of Berkeley. He was educated at Kilkenny College and attended Trinity College, Dublin, completing a Master's degree in 1707. He remained at Trinity College after completion of his degree as a tutor and Greek lecturer.' (en.wikipedia.org)

  15. 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.

  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 science annual report, July 1, 1977-June 30, 1978. [Lawrence Berkeley Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, L.S.; Gough, R.A.; Nurmia, M.J. (eds.)

    1978-01-01

    Activities for the period July 1, 1977, through June 30, 1978, are reported in the following areas: experimental research (nuclear structure; nuclear reactions and scattering; relativistic heavy ions - projectile and target fragmentation, central collisions; the Table of Isotopes Project, atomic physics, and magnetic monopoles), theory of nuclear collisions (microscopic, macroscopic, relativistic), and apparatus (accelerator operations and development, nuclear instrumentation). Also included are thesis abstracts, publications lists, and an author index. Individual abstracts were prepared for 33 of the reports in this volume. (RWR)

  18. Introduction to nuclear facilities engineering

    International Nuclear Information System (INIS)

    Engineering, or 'engineer's art', aims at transforming simple principle schemes into operational facilities often complex especially when they concern the nuclear industry. This transformation requires various knowledge and skills: in nuclear sciences and technologies (nuclear physics, neutronics, thermal-hydraulics, material properties, radiation protection..), as well as in non-nuclear sciences and technologies (civil engineering, mechanics, electricity, computer sciences, instrumentation and control..), and in the regulatory, legal, contractual and financial domains. This book explains how this huge body of knowledge and skills must be organized and coordinated to create a reliable, exploitable, available, profitable and long-lasting facility, together with respecting extremely high safety, quality, and environmental impact requirements. Each aspect of the problem is approached through the commented presentation of nuclear engineering macro-processes: legal procedures and administrative authorizations, nuclear safety/radiation protection/security approach, design and detailed studies, purchase of equipments, on-site construction, bringing into operation, financing, legal, contractual and logistic aspects, all under the global control of a project management. The 'hyper-complexness' of such an approach leads to hard points and unexpected events. The author identifies the most common ones and proposes some possible solutions to avoid, mitigate or deal with them. In a more general way, he proposes some thoughts about the performance factors of a nuclear engineering process

  19. ENEN - European nuclear engineering network

    International Nuclear Information System (INIS)

    The paper presents the main objectives and expected results of European Project FP5 - ENEN - 'European Nuclear Engineering Network'. The underlying objective of the work is safeguarding the nuclear knowledge and expertise through the preservation of higher nuclear engineering education. Co-operation between universities and universities and research centres, will entail a better use of dwindling teaching capacity, scientific equipment and research infrastructure. 'Today, the priorities of the scientific community regarding basic research lie elsewhere than in nuclear sciences. Taken together, these circumstances create a significantly different situation from three to four decades ago when much of the present competence base was in fact generated. In addition, many of the highly competent engineers and scientists, who helped create the present nuclear industry, and its regulatory structure, are approaching retirement age. These competence issues need to be addressed at Community level and a well designed Community research and training programme should play a role that is more important than ever before. This is an area where the concept of an European research area should be further explored'. The outcome from this project should be a clear road map for the way ahead in nuclear engineering education in Europe. The underlying objective of the concerted action is the preservation of nuclear knowledge and expertise through the preservation of higher nuclear engineering education. 'Many diverse technologies, currently serving nations world-wide, would be affected by an inadequate number of future nuclear scientists and engineers. Nuclear technology is widespread and multidisciplinary: nuclear and reactor physics, thermal hydraulics and mechanics, material science, chemistry, health science, information technology and a variety of other areas. Yet the advancement of this technology, with all its associated benefits, will be threatened if not curtailed unless the

  20. 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.

  1. Accreditation of nuclear engineering programs

    International Nuclear Information System (INIS)

    The American Nuclear Society (ANS) Professional Development and Accreditation Committee (PDAC) has the responsibility for accreditation of engineering and technology programs for nuclear and similarly named programs. This committee provides society liaison with the Accreditation Board for Engineering and Technology (ABET), is responsible for the appointment and training of accreditation visitors, nomination of members for the ABET Board and Accreditation Commissions, and review of the criteria for accreditation of nuclear-related programs. The committee is composed of 21 members representing academia and industry. The ABET consists of 19 participating bodies, primarily professional societies, and 4 affiliate bodies. Representation on ABET is determined by the size of the professional society and the number of programs accredited. The ANS, as a participating body, has one member on the ABET board, two members on the Engineering Accreditation Commission, and one on the Technology Accreditation Commission. The ABET board sets ABET policy and the commissions are responsible for accreditation visits

  2. Introduction to nuclear test engineering

    International Nuclear Information System (INIS)

    The basic information in this report is from a vu-graph presentation prepared to acquaint new or prospective employees with the Nuclear Test Engineering Division (NTED). Additional information has been added here to enhance a reader's understanding when reviewing the material after hearing the presentation, or in lieu of attending a presentation

  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. The Berkeley TRIGA Mark III research reactor

    International Nuclear Information System (INIS)

    The Berkeley Research Reactor went critical on August 10, 1966, and achieved licensed operating power of 1000 kW shortly thereafter. Since then, the reactor has operated, by and large, trouble free on a one-shift basis. The major use of the reactor is in service irradiations, and many scientific programs are accommodated, both on and off campus. The principal off-campus user is the Lawrence Radiation Laboratory at Berkeley. The reactor is also an important instructional tool in the Nuclear Engineering Department reactor experiments laboratory course, and as a source of radioisotopes for two other laboratory courses given by the Department. Finally, the reactor is used in several research programs conducted within the Department, involving studies with neutron beams and in reactor kinetics

  5. Proceedings of the international conference on nuclear physics, August 24-30, 1980, Berkeley, California. Volume 1. Abstracts. [Berkeley, California, August 24-30, 1980 (abstracts only)

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This volume contains all abstracts (931) received by the conference organizers before June 20, 1980. The abstracts are grouped according to the following topics: nucleon-nucleon interactions, free and in nuclei; distribution of matter, charge, and magnetism; exotic nuclei and exotic probes; giant resonances and other high-lying excitations; applications of nuclear science; nuclei with large angular momentum and deformation; heavy-ion reactions and relaxation phenomena; new techniques and instruments; pion absorption and scattering by nuclei; and miscellaneous. Some of these one-page abstracts contain data. A complete author index is provided. (RWR)

  6. Nuclear engineering enrollments and degrees, 1994: Appendixes

    International Nuclear Information System (INIS)

    This survey is designed to include those programs sponsored by the Department of Energy. The survey is designed to include those programs offering a major in nuclear engineering or course work equivalent to a major in other engineering disciplines that prepare the graduates to perform as nuclear engineers. This survey provides data on nuclear engineering enrollments and degrees for use in labor market analyses, information on education programs for students, and information on new graduates to employers, government agencies, academia and professional societies

  7. Engineering and science education for nuclear power

    International Nuclear Information System (INIS)

    The Guidebook contains detailed information on curricula which would provide the professional technical education qualifications which have been established for nuclear power programme personnel. The core of the Guidebook consists of model curricula in engineering and science, including relevant practical work. Curricula are provided for specialization, undergraduate, and postgraduate programmes in nuclear-oriented mechanical, chemical, electrical, and electronics engineering, as well as nuclear engineering and radiation health physics. Basic nuclear science and engineering laboratory work is presented together with a list of basic experiments and the nuclear equipment needed to perform them. Useful measures for implementing and improving engineering and science education and training capabilities for nuclear power personnel are presented. Valuable information on the national experiences of IAEA Member States in engineering and science education for nuclear power, as well as examples of such education from various Member States, have been included

  8. Data mining in nuclear engineering

    International Nuclear Information System (INIS)

    Data mining (DM) is a process to find the useful and interesting information in huge data. Support Vector Machine (SVM) is a new technique in data mining, but Support Vector Regression (SVR) is the applying of SM in regression . Compared with the traditional regression methods, SVR has not been specified beforehand, and is fitted directly from the inner relationship of data, thus the simulation results are more accurate. This paper introduces the mathematical theory of SVR and uses SVR to process the data of the moving characteristics of molten metal droplets in serious nuclear engineering accidents. (authors)

  9. US Nuclear Engineering Education: Status and prospects

    International Nuclear Information System (INIS)

    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, as described in this report 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 ageing 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., 24 figs., 49 tabs

  10. 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.

  11. Engineers call for US nuclear safety fix

    Science.gov (United States)

    Gwynne, Peter

    2016-04-01

    Seven Nuclear Regulatory Commission (NRC) engineers have called on the commission to force the owners of US nuclear reactors to repair a design flaw that could affect the safe operation of emergency core cooling systems.

  12. Catalog of research projects at Lawrence Berkeley Laboratory, 1985

    International Nuclear Information System (INIS)

    This Catalog has been created to aid in the transfer of technology from the Lawrence Berkeley Laboratory to potential users in industry, government, universities, and the public. The projects are listed for the following LBL groups: Accelerator and Fusion Research Division, Applied Science Division, Biology and Medicine Division, Center for Advanced Materials, Chemical Biodynamics Division, Computing Division, Earth Sciences Division, Engineering and Technical Services Division, Materials and Molecular Research Division, Nuclear Science Division, and Physics Division

  13. Catalog of research projects at Lawrence Berkeley Laboratory, 1985

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    This Catalog has been created to aid in the transfer of technology from the Lawrence Berkeley Laboratory to potential users in industry, government, universities, and the public. The projects are listed for the following LBL groups: Accelerator and Fusion Research Division, Applied Science Division, Biology and Medicine Division, Center for Advanced Materials, Chemical Biodynamics Division, Computing Division, Earth Sciences Division, Engineering and Technical Services Division, Materials and Molecular Research Division, Nuclear Science Division, and Physics Division.

  14. Nuclear engineering education in the USA revitalization

    International Nuclear Information System (INIS)

    Nuclear engineering education in the U.S. had been in decline for nearly two decades into the mid 1990's and the number of next generation nuclear engineers needed to replace those reaching retirement age appeared woefully inadequate. Sensing this, the U.S. Department of Energy's Office of Nuclear Energy, Science and Technology and others in the nuclear community committed themselves to a revitalization of the nuclear engineering infrastructure in the U.S. New programs were initiated, cooperation was fostered, more funding was provided and steps were undertaken to improve communications among the key players including, universities, utilities, the private sector and government allowing the nuclear community to speak with one voice, work together and be heard. Almost simultaneously, nuclear energy was being given a another look by several energy dependent countries and the developing countries were in the midst of embracing nuclear energy as one of their primary sources to foster industrial development. Today, while no new plants have been ordered in the U.S. to date, the nuclear engineering infrastructure in much improved, the interest in nuclear at the academic level is high and awareness of the benefits of nuclear energy and science are now being communicated to the next generation of students. While continued success in the U.S. is not yet assured, it is important that the U.S. institutions work together with the international community to further strengthen the worldwide nuclear infrastructure. While much has been done domestically and some steps have been taken internationally, others need to be. This presentation will show where the U.S. has been, where it is today and where it is headed in support of nuclear engineering education. (author)

  15. A preliminary assessment of individual doses in the environs of Berkeley, Gloucestershire, following the Chernobyl nuclear reactor accident

    International Nuclear Information System (INIS)

    A preliminary assessment has been made of the individual doses to critical group members of the public in the environs of Berkeley arising from fallout resulting from the Chernobyl accident. The assessment was based on measurements of airborne radionuclide concentrations, ground deposition and nuclide concentrations in rainwater, tapwater, grass, milk and green vegetables. The committed effective dose-equivalent was found to be as follows:- Adult - 200 μSv, 1 year old child - 500 μSv, the 10 year old child receiving a dose intermediate between these two values. The estimate accounts only for the nuclides measured and the specific exposure routes considered namely ingestion of milk and vegetables, inhalation and external exposure. However, it is believed that the inclusion of a range of other nuclides of potential significance, which may have been present but not measured, and potential intakes from additional routes is unlikely to increase the above estimates by more than a factor of 2. (author)

  16. Nuclear engineering in the National Polytechnic Institute

    International Nuclear Information System (INIS)

    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

  17. 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.

  18. Development of nuclear engineering education in Jordan

    International Nuclear Information System (INIS)

    Full text: The establishment of a Nuclear Engineering program is another step in Jordan's efforts to develop its nuclear infrastructure, and to introduce nuclear power as part of its energy mix. Nuclear energy offers a promising approach to meeting Jordan's energy needs - an approach that would reduce our dependence on oil imports, create jobs, raise the standard of living, and alleviate the burden on the national budget. Nuclear energy will also be required to provide electricity to fulfil growing electrical demands, water desalination, and hydrogen production. The Nuclear Engineering department at Jordan University of Science and Technology (JUST), is the first and only such department/program in Jordan. The university it self is a scientific university with more than 17000 undergraduate students and 1000 graduates, including more than 3000 international students from 41 different countries. Approximately 6,000 students are enrolled in the college of engineering. Our goal is to establish a world class department, which will enhance nuclear knowledge in Jordan, and will graduate qualified engineers that will help in the design, building and running of Jordan's first nuclear power plant. It is also our goal to serve as Jordan's leading nuclear research center. The department is planning to start accepting students in the next academic year (2007/2008), which starts in September 2007, it will accept students both in the freshman and sophomore levels (first and second year). Thus graduating its first class in 2011, this is the period that Jordan will be in the building phase of its first nuclear power plant. Consequently nuclear knowledge transfer from nuclear suppliers and contractors of developed nations to our graduates working with them will be more realistic. The objectives of the nuclear engineering program are to educate students in the fundamental subjects necessary for a career in nuclear engineering, and in the basics of nuclear technology, radiation

  19. Laboratory instruction for nuclear engineering application experiments

    International Nuclear Information System (INIS)

    This report contains several laboratory instruction texts for 'Nuclear Engineering Application Experiments', which has been offered to Graduate students of Graduate School of Engineering at Kyoto University from 1970's. These experiments have been carried out by using experimental facilities; a research reactor, a critical assembly, accelerators, and a hot laboratory at Kyoto University Research Institute. (author)

  20. 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...

  1. 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.

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

    International Nuclear Information System (INIS)

    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.

  3. A nuclear engineer's ethical responsibility to society

    International Nuclear Information System (INIS)

    Chernobyl notwithstanding, this paper seeks to illustrate why, on numerous fronts, nuclear technology provides the safest, cleanest and most effective method of base-load power generation. In particular it seeks to demonstrate that, despite the strident rhetoric and media exposure given to the anti-nuclear lobby, the technology is fundamental to the quality of life and the equitable sharing of energy by the year 2000. Therefore, the safety and technological superiority of the nuclear fuel cycle together with its high technology peripheral benefits both societal and fiscal are viewed as an ever increasing challenge and motivation which constitutes a major part of the nuclear engineer's ethical responsibility to society

  4. New directions in university nuclear engineering support

    International Nuclear Information System (INIS)

    Full text: The Office of Nuclear Energy has supported university nuclear engineering education for over a decade within a program typically known as University Programs. Prior to the mid 1990's support for nuclear engineering education could be found not only in the Office of Nuclear Energy but also in the Office of Energy Research, now the Office of Science. Although some of the current programs were present in those two offices, there was little coordination between the offices and the Department of Energy did not speak with one voice when interacting with university engineering and science departments engaged in nuclear education. By the middle of the 1990's, the Office of Energy Research had terminated its involvement in nuclear engineering education and the Office of Nuclear Energy assumed responsibility for programs such as Reactor Sharing, Reactor Instrumentation, Fellowships and Scholarships and Nuclear Engineering and Education Research. Previously in 1992-1993, the Office of Nuclear Energy had introduced a new program, Matching Grants, in concert with Commonwealth Edison (Exelon) where the private sector matched the Department's funding contribution up to a predetermined ceiling. By the late 1990's, surveys of universities demonstrated that nuclear engineering undergraduate and graduate programs were severely under-populated and were experiencing yearly declines in their student population. Clearly, more had to be done not only in terms of new programs to attract students to nuclear engineering but to educate the public, especially students, about the need for nuclear engineers and the promising careers offered in the nuclear field from the standpoint of technical challenge and remuneration. It was at this point in the late 1990's and early 2000's that DOE assumed a more active role in assisting the universities in attracting more students. Various methods were employed to accomplish this including: funding outreach by the American Nuclear Society

  5. Engineering and science education for nuclear power

    International Nuclear Information System (INIS)

    Experience has shown that one of the critical conditions for the successful introduction of a nuclear power programme is the availability of sufficient numbers of personnel having the required education and experience qualifications. For this reason, the introduction of nuclear power should be preceded by a thorough assessment of the relevant capabilities of the industrial and education/training infrastructures of the country involved. The IAEA assists its Member States in a variety of ways in the development of infrastructures and capabilities for engineering and science education for nuclear power. Types of assistance provided by the IAEA to Member States include: Providing information in connection with the establishment or upgrading of academic and non-academic engineering and science education programmes for nuclear power (on the basis of curricula recommended in the Agency's Guidebook on engineering and science education for nuclear power); Expert assistance in setting up or upgrading laboratories and other teaching facilities; Assessing the capabilities and interest of Member States and their institutions/organizations for technical co-operation among countries, especially developing ones, in engineering and science education, as well as its feasibility and usefulness; Preparing and conducting nuclear specialization courses (e.g. on radiation protection) in various Member States

  6. European Master of Science in Nuclear Engineering

    International Nuclear Information System (INIS)

    The need to preserve, enhance or strengthen nuclear knowledge is worldwide recognised since a couple of years. It appears that within the European university education and training network, nuclear engineering is presently sufficiently covered, although somewhat fragmented. To take up the challenges of offering top quality, new, attractive and relevant curricula, higher education institutions should cooperate with industry, regulatory bodies and research centres, and more appropriate funding a.o. from public and private is to be re-established. More, European nuclear education and training should benefit from links with international organisations like IAEA, OECD-NEA and others, and should include world-wide cooperation with academic institutions and research centres. The European master in nuclear engineering guarantees a high quality nuclear education in Europe by means of stimulating student and instructor exchange, through mutual checks of the quality of the programmes offered, by close collaboration with renowned nuclear-research groups at universities and laboratories. The concept for a nuclear master programme consists of a solid basket of recommended basic nuclear science and engineering courses, but also contains advanced courses as well as practical training. Some of the advanced courses also serve as part of the curricula for doctoral programmes. A second important issue identified is Continued Professional Development. In order to achieve the objectives and practical goals described above, the ENEN association was formed. This international, non-profit association is be considered as a step towards a virtual European Nuclear University symbolising the active collaboration between various national institutions pursuing nuclear education. (author)

  7. Nuclear engineering education initiative at Ibaraki University

    International Nuclear Information System (INIS)

    With the help of a grant from the Ministry of Education, Culture, Sports, Science and Technology, Ibaraki University has been engaging for six years in the development and preparation of educational environment on nuclear engineering for each of graduate and undergraduate. Core faculty conducts general services including the design and implementation of curriculum, operational improvement, and implementation of lectures. 'Beginner-friendly introduction for nuclear power education' is provided at the Faculty of Engineering, and 'nuclear engineering education program' at the Graduate School of Science and Engineering. All the students who have interest or concern in the accidents at nuclear power plants or the future of nuclear power engineering have opportunities to learn actively. This university participates in the alliance or association with other universities, builds industry - government - academia cooperation with neighboring institutions such as the Japan Atomic Energy Agency, and makes efforts to promote the learning and development of applied skills related to nuclear engineering through training and study tours at each facility. For example, it established the Frontier Applied Atomic Science Center to analyze the structure and function of materials using the strong neutron source of J-PARC. As the efforts after the earthquake accident, it carried out a radiation survey work in Fukushima Prefecture. In addition, it proposed and practiced the projects such as 'development of methods for the evaluation of transfer/fixation properties and decontamination of radioactive substances,' and 'structure analysis of radioactive substances remaining in soil, litter, and polluted water and its application to the decontamination.' (A.O.)

  8. The world nuclear power engineering. 1998 year

    International Nuclear Information System (INIS)

    The purpose of this article consists in the analysis of the state and prospects of the world nuclear power engineering development. The data on the ratio and value of electrical energy obtained at the NPPs in the world in 1998, the specific capital expenditures on the NPPs construction by 2005, the forecast for the capacity of all NPPs by 2020 are presented. The progress in developing nuclear power engineering conditioned by improvement of the NPPs operation, optimization of their life-cycle and developing of new NPPs projects is noted

  9. Nuclear engineering enrollments and degrees, 1981

    International Nuclear Information System (INIS)

    This report presents data on the number of students enrolled and the degrees awarded in academic year 1980-81 from 73 US institutions offering degree programs in nuclear engineering or nuclear options within other engineering fields. Presented here are historical data for the last decade, which provide information such as trends by degree level, foreign national student participation, female and minority student participation, and placement of graduates. Also included is a listing of the universities by type of program and number of students

  10. Education in nuclear engineering in Slovakia

    International Nuclear Information System (INIS)

    Slovak University of Technology is the largest and also the oldest university of technology in Slovakia. Surely more than 50% of high-educated technicians who work nowadays in nuclear industry have graduated from this university. The Department of Nuclear Physics and Technology of the Faculty of Electrical Engineering and Information Technology as a one of seven faculties of this University feels responsibility for proper engineering education and training for Slovak NPP operating staff. The education process is realised via undergraduate (Bc.), graduate (MSc.) and postgraduate (PhD..) study as well as via specialised training courses in a frame of continuous education system. (author)

  11. Corrosion Engineers and Nuclear Waste Disposition

    International Nuclear Information System (INIS)

    More and more articles appear in the press daily about the renaissance of nuclear energy. Even many former opponents of nuclear energy are now convinced that nuclear energy is more environmentally friendly than burning fossil fuels. Nuclear energy does not release carbon dioxide to the atmosphere and therefore does not contribute to the global warming problem. But nuclear energy produces spent fuel or nuclear waste. Spent fuel is radioactive and requires thousands of years of isolation from plants, animals and humans. Every country currently studying the option for disposing of high-level nuclear waste has selected deep geologic formations to be the primary barrier for accomplishing this isolation. It is postulated that by the very nature of these geological sites, they will contain the waste for long time, limiting the spread of radionuclides, for example, through water flow. The release of radionuclides to the environment can also be delayed by the construction of engineered barrier systems between the waste and the geologic formation. Corrosion engineers are participating in the design and the performance prediction of the engineered barriers. The principal engineered component in this multibarrier approach is the container for the waste. Beyond the metallic containers, other engineered barriers could be added to attenuate the impact of the emplacement environment on the containers. The containers will probably be concentric double walled vessels of dissimilar metals. Each vessel would have a specific function. For example, the inner container may be designed to shield radiation and provide structural support to facilitate the safe handling and emplacement operations. This inner container may be over-packed with a corrosion-resistant outer layer. The design of the different containers for nuclear waste would vary according to the nature of the geologic formation at the site of the repository. The most common host rocks for nuclear waste repositories in the world

  12. Eugene Wigner, The First Nuclear Reactor Engineer

    Science.gov (United States)

    Weinberg, Alvin M.

    2002-04-01

    All physicists recognize Eugene Wigner as a theoretical physicist of the very first rank. Yet Wigner's only advanced degree was in Chemical Engineering. His physics was largely self-taught. During WWII, Wigner brilliantly returned to his original occupation as an engineer. He led the small team of theoretical physicists and engineers who designed, in remarkable detail, the original graphite-moderated, water-cooled Hanford reactor, which produced the Pu239 of the Trinity and Nagasaki bombs. With his unparalleled understanding of chain reactors (matched only by Fermi) and his skill and liking for engineering, Wigner can properly be called the Founder of Nuclear Engineering. The evidence for this is demonstrated by a summary of his 37 Patents on various chain reacting systems.

  13. Proceedings of the international conference on nuclear physics, August 24-30, 1980, Berkeley, California. Volume 1. Abstracts

    International Nuclear Information System (INIS)

    This volume contains all abstracts (931) received by the conference organizers before June 20, 1980. The abstracts are grouped according to the following topics: nucleon-nucleon interactions, free and in nuclei; distribution of matter, charge, and magnetism; exotic nuclei and exotic probes; giant resonances and other high-lying excitations; applications of nuclear science; nuclei with large angular momentum and deformation; heavy-ion reactions and relaxation phenomena; new techniques and instruments; pion absorption and scattering by nuclei; and miscellaneous. Some of these one-page abstracts contain data. A complete author index is provided

  14. Midwest Nuclear Science and Engineering Consortium

    International Nuclear Information System (INIS)

    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.

  15. 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.

  16. 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.

  17. Environmental research at Berkeley

    CERN Document Server

    1973-01-01

    The information concerning the Energy and Environment Programme at the Lawrence Berkeley Laboratory is based on a talk given at CERN by A.M. Sessler, one of the initiators of the Programme. (Dr. Sessler has been appointed Director of the Lawrence Berkeley Laboratory, in succession to Prof. E. M. McMillan, from 1 November.) Many of the topics mentioned merit an extended story in themselves but the purpose of this article is simply to give a sketch of what is happening.

  18. NUKEM. Innovative solutions for nuclear engineering

    International Nuclear Information System (INIS)

    Management of radioactive waste, handling spent fuel elements, decommissioning of nuclear facilities, and engineering and consulting activities are services associated with the name of NUKEM all over the world. The company's scientists and engineers develop solution concepts combining the latest technologies with proven techniques and many years of experience. The company;s history and the services offered to the nuclear industry began more than 5 decades ago. The predecessor, NUKEM Nuklear-Chemie-Metallurgie, was founded in 1960 as one of the earliest nuclear companies in Germany. Originally, the firm produced fuel elements for a variety of reactor lines. As early as in the 1970s, logical extensions of these business activities were nuclear engineering and plant construction. In the meantime, NUKEM Technologies GmbH has developed a worldwide reputation for its activities. Numerous reference projects bear witness to optimum project management and customer satisfaction. Since 2009, NUKEM Technologies has been a wholly owned subsidiary of the Russian Atomstroyexport. NUKEM Technologies operates sales and project offices outside Germany, e.g. in Russia, China, Lithuania, France, and Bulgaria. In this way, the company is present in its target markets of Russia, Western and Eastern Europe as well as Asia, offering customers and partners fast and direct contacts. (orig.)

  19. Nuclear industry - challenges in chemical engineering

    International Nuclear Information System (INIS)

    Chemical engineering processes and operations are closely involved in every step of the nuclear fuel cycle. Starting from mining and milling of the ore through the production of fuel and other materials and their use in nuclear reactors, fuel reprocessing, fissile material recycle and treatment and disposal of fission product wastes, each step presents a challenge to the chemical engineer to evolve and innovate processes and techniques for more efficient utilization of the energy in the atom. The requirement of high recovery of the desired components at high purity levels is in itself a challenge. ''Nuclear Grade'' specifications for materials put a requirement which very few industries can satisfy. Recovery of uranium and thorium from low grade ores, of heavy water from raw water, etc. are examples. Economical and large scale separation of isotopes particularly those of heavy elements is a task for which processess are under various stages of development. Further design of chemical plants such as fuel reprocessing plants and high level waste treatment plants, which are to be operated and maintained remotely due to the high levels of radio-activity call for engineering skills which are being continually evolved. In the reactor, analysis of the fluid mechanics and optimum design of heat removal system are other examples where a chemical engineer can play a useful role. In addition to the above, the activities in the nuclear industry cover a very wide range of chemical engineering applications, such as desalination and other energy intensive processes, radioisotope and radiation applications in industry, medicine and agriculture. (auth.)

  20. Final Technical Report and management: NUCLEAR ENGINEERING RECRUITMENT EFFORT

    International Nuclear Information System (INIS)

    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; and Objective 6--Nuclear engineering enrollment survey at universities

  1. European master of science in nuclear engineering

    International Nuclear Information System (INIS)

    Full text: The need to preserve, enhance or strengthen nuclear knowledge is worldwide recognised since a couple of years. Among others, 'networking to maintain nuclear competence through education and training', was recommended in 2001 by an expert panel to the European Commission. (EUR 19150 EN). It appears that within the European university education and training framework, nuclear engineering is presently still sufficiently covered, although somewhat fragmented. However it has been observed that several areas are at risk in the very near future including safety relevant fields such as reactor physics and nuclear thermal-hydraulics. Furthermore, in some countries deficiencies have been identified in areas such as the back-end of the nuclear fuel cycle, waste management and decommissioning. To overcome these risks and deficiencies, it is of very high importance that European countries work more closely together. Harmonisation and improvement of the nuclear education and training have to take place at an international level in order to maintain the knowledge properly and to transfer it throughout Europe for the safe and economic design, operation and dismantling of present and future nuclear systems. To take up the challenges of offering top quality, new, attractive and relevant curricula, higher education institutions should cooperate with industry, regulatory bodies and research centres, and more appropriate funding from public and private sources. In addition, European nuclear education and training should benefit from links with international organisations like IAEA, OECD-NEA and others, and should include world-wide cooperation with academic institutions and research centres. The first and central issue is to establish a European Master of Science in Nuclear Engineering. The concept envisaged is compatible with the projected harmonised European architecture for higher education defining Bachelors and Masters degrees. The basic goal is to guarantee a high

  2. European Master of Science in Nuclear Engineering

    International Nuclear Information System (INIS)

    The need to preserve, enhance or strengthen nuclear knowledge is worldwide recognised since a couple of years. Among others, 'networking to maintain nuclear competence through education and training', was recommended in 2001 by an expert panel to the European Commission [EUR, 19150 EN, Strategic issues related to a 6th Euratom Framework Programme (2002-2006). Scientific and Technical Committee Euratom, pp. 14]. It appears that within the European University education and training framework, nuclear engineering is presently still sufficiently covered, although somewhat fragmented. However, it has been observed that several areas are at risk in the very near future including safety relevant fields such as reactor physics and nuclear thermal-hydraulics. Furthermore, in some countries deficiencies have been identified in areas such as the back-end of the nuclear fuel cycle, waste management and decommissioning. To overcome these risks and deficiencies, it is of very high importance that European countries work more closely together. Harmonisation and improvement of the nuclear education and training have to take place at an international level in order to maintain the knowledge properly and to transfer it throughout Europe for the safe and economic design, operation and dismantling of present and future nuclear systems. To take up the challenges of offering top quality, new, attractive and relevant curricula, higher education institutions should cooperate with industry, regulatory bodies and research centres, and more appropriate funding from public and private sources. In addition, European nuclear education and training should benefit from links with international organisations like IAEA, OECD-NEA and others, and should include worldwide cooperation with academic institutions and research centres. The first and central issue is to establish a European Master of Science in Nuclear Engineering. The concept envisaged is compatible with the projected harmonised European

  3. Nuclear Engineering Academic Programs Survey, 2003

    International Nuclear Information System (INIS)

    The survey includes degrees granted between September 1, 2002 and August 31, 2003. Thirty-three academic programs reported having nuclear engineering programs during the survey time period and all responded (100% response rate). Three of the programs included in last year's report were discontinued or out-of-scope in 2003. One new program has been added to the list. This year the survey data include U.S. citizenship, gender, and race/ethnicity by degree level

  4. El idealismo de Berkeley

    Directory of Open Access Journals (Sweden)

    David Sobrevilla

    1995-12-01

    Full Text Available En esta conferencia se examina en qué consiste el idealismo de Berkeley. Para ello se sigue el mismo camino propuesto por G .J. Warnock: se indaga contra qué se opone Berkeley, el materialismo, y cómo lo entiende, y por qué está en contra del mismo. A continuación se reexamina el idealismo berkeleyano, y en la consideración final se juzgan sus virtudes y defectos: algunas de las críticas fundadas que se le han formulado y la visión de la ciencia que se desprende de los escritos de Berkeley. A este respecto se pone en conexión las ideas del autor con algunos planteamientos del último Husserl y con una interpretación de Popper sobre la sorprendente modernidad de algunas de las ideas berkeleyanas sobre la ciencia.

  5. Life sciences: Lawrence Berkeley Laboratory, 1988

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    Life Sciences Research at LBL has both a long history and a new visibility. The physics technologies pioneered in the days of Ernest O. Lawrence found almost immediate application in the medical research conducted by Ernest's brother, John Lawrence. And the tradition of nuclear medicine continues today, largely uninterrupted for more than 50 years. Until recently, though, life sciences research has been a secondary force at the Lawrence Berkeley Laboratory (LBL). Today, a true multi-program laboratory has emerged, in which the life sciences participate as a full partner. The LBL Human Genome Center is a contribution to the growing international effort to map the human genome. Its achievements represent LBL divisions, including Engineering, Materials and Chemical Sciences, and Information and Computing Sciences, along with Cell and Molecular Biology and Chemical Biodynamics. The Advanced Light Source Life Sciences Center will comprise not only beamlines and experimental end stations, but also supporting laboratories and office space for scientists from across the US. This effort reflects a confluence of scientific disciplines --- this time represented by individuals from the life sciences divisions and by engineers and physicists associated with the Advanced Light Source project. And finally, this report itself, the first summarizing the efforts of all four life sciences divisions, suggests a new spirit of cooperation. 30 figs.

  6. Life sciences: Lawrence Berkeley Laboratory, 1988

    International Nuclear Information System (INIS)

    Life Sciences Research at LBL has both a long history and a new visibility. The physics technologies pioneered in the days of Ernest O. Lawrence found almost immediate application in the medical research conducted by Ernest's brother, John Lawrence. And the tradition of nuclear medicine continues today, largely uninterrupted for more than 50 years. Until recently, though, life sciences research has been a secondary force at the Lawrence Berkeley Laboratory (LBL). Today, a true multi-program laboratory has emerged, in which the life sciences participate as a full partner. The LBL Human Genome Center is a contribution to the growing international effort to map the human genome. Its achievements represent LBL divisions, including Engineering, Materials and Chemical Sciences, and Information and Computing Sciences, along with Cell and Molecular Biology and Chemical Biodynamics. The Advanced Light Source Life Sciences Center will comprise not only beamlines and experimental end stations, but also supporting laboratories and office space for scientists from across the US. This effort reflects a confluence of scientific disciplines --- this time represented by individuals from the life sciences divisions and by engineers and physicists associated with the Advanced Light Source project. And finally, this report itself, the first summarizing the efforts of all four life sciences divisions, suggests a new spirit of cooperation. 30 figs

  7. Berkeley mini-collider

    International Nuclear Information System (INIS)

    The Berkeley Mini-Collider, a heavy-ion collider being planned to provide uranium-uranium collisions at T/sub cm/ less than or equal to 4 GeV/nucleon, is described. The central physics to be studied at these energies and our early ideas for a collider detector are presented

  8. Nuclear power engineering problems as the political and economical problems

    International Nuclear Information System (INIS)

    The political and economic aspects of nuclear power engineering status in the countries of the former USSR nowadays are considered. The factors, which lead to the nuclear power crisis, are analyzed. It is shown that the state monopoly for developing the problems of nuclear power engineering and NPP operation plays the main part. The ways for possible crisis overcoming are suggested

  9. Malignant pleural mesothelioma in a nuclear engineer

    International Nuclear Information System (INIS)

    Malignant pleural mesothelioma accounts for a large proportion of deaths among occupational cohorts exposed to asbestos. Of particular interest are recent reports of a high risk of mesothelioma among occupational groups previously thought to be at low risk for developing this neoplasm. In the present report we present a case of pleural mesothelioma associated with bystander exposure to asbestos in a nuclear engineer. To our knowledge, this is the first report of the disease occurring in a member of this occupational group after work related exposure to asbestos. (author)

  10. The Nuclear Review: the Institution of Nuclear Engineers' response to the Review of Nuclear Power

    International Nuclear Information System (INIS)

    The United Kingdom Government's Nuclear Review currently underway, addresses whether and in what form nuclear power should continue to be part of the country's power generation capability. This article sets out the response of the Institution of Nuclear Engineers to the Nuclear Review. This pro-nuclear group emphasises the benefits to be gained from diversity of generation in the energy supply industry. The environmentally benign nature of nuclear power is emphasised, in terms of gaseous emissions. The industry's excellent safety record also argues in favour of nuclear power. Finally, as power demand increases globally, a health U.K. nuclear industry could generate British wealth through power exports and via the construction industry. The Institution's view on radioactive waste management is also set out. (UK)

  11. 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

  12. Do nuclear engineering educators have a special responsibility

    International Nuclear Information System (INIS)

    Each 1000 MW(e) reactor in equilibrium contains 15 x 109 Ci of radioactivity. To handle this material safety requires an extremely high level of expertise and commitment - in many respects, an expertise that goes beyond what is demanded of any other technology. If one grants that nuclear engineering is more demanding than other engineering because the price of failure is greater, one must ask how can we inculcate into the coming generations of nuclear engineers a full sense of the responsibility they bear in practising their profession. Clearly a first requirement is that all elements of the nuclear community -utility executives, equipment engineers, operating engineers, nuclear engineers, administrators - must recognize and accept the idea that nuclear energy is something special, and that therefore its practitioners must be special. This sense must be instilled into young nuclear engineers during their education. A special responsibility therefore devolves upon nuclear engineering educators: first, to recognize the special character of their profession, and second, to convey this sense to their students. The possibility of institutionalizing this sense of responsibility by establishing a nuclear Hippocratic Oath or special canon of ethics for nuclear engineers ought to be discussed within the nuclear community. (author)

  13. Human Factors in Nuclear Power Engineering in Polish Conditions

    OpenAIRE

    Agnieszka Kaczmarek-Kacprzak; Martin Catlow

    2014-01-01

    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 p...

  14. Centre for nuclear engineering University of Toronto annual report 1984

    International Nuclear Information System (INIS)

    The annual report of the Centre for Nuclear Engineering, University of Toronto covers the following subjects: message from the Dean; Chairman's message; origins of the centre; formation of the centre; new nuclear appointments; and activities of the centre, 1984

  15. Role of the biomedical engineer in nuclear medicine.

    Science.gov (United States)

    Llaurado, J G

    1981-01-01

    Throughout the short history of the development of radioactivity applied in the biomedical field, there have been many contributions made by engineers. With the advent of Nuclear Medicine as a well systematized specialty and its mushrooming in hospitals, the opportunities for biomedical engineers have increased. This article is written from the viewpoint of historic perspective in order to display the different aspects and situations where engineers, and particularly biomedical and clinical engineers, can participate in Nuclear Medicine. Finally, a more detailed survey is made of the activities of biomedical engineers in the nuclear medicine department.

  16. Berkeley Low Background Facility

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, K. J.; Norman, E. B. [Department of Nuclear Engineering, University of California-Berkeley, CA 94720 (United States); Nuclear Science Division, Lawrence Berkeley National Laboratory, CA 94720 (United States); Smith, A. R.; Poon, A. W. P.; Chan, Y. D. [Nuclear Science Division, Lawrence Berkeley National Laboratory, CA 94720 (United States); Lesko, K. T. [Physics Division, Lawrence Berkeley National Laboratory, CA 94720 (United States)

    2015-08-17

    The Berkeley Low Background Facility (BLBF) at Lawrence Berkeley National Laboratory (LBNL) in Berkeley, California provides low background gamma spectroscopy services to a wide array of experiments and projects. The analysis of samples takes place within two unique facilities; locally within a carefully-constructed, low background laboratory on the surface at LBNL and at the Sanford Underground Research Facility (SURF) in Lead, SD. These facilities provide a variety of gamma spectroscopy services to low background experiments primarily in the form of passive material screening for primordial radioisotopes (U, Th, K) or common cosmogenic/anthropogenic products; active screening via neutron activation analysis for U,Th, and K as well as a variety of stable isotopes; and neutron flux/beam characterization measurements through the use of monitors. A general overview of the facilities, services, and sensitivities will be presented. Recent activities and upgrades will also be described including an overview of the recently installed counting system at SURF (recently relocated from Oroville, CA in 2014), the installation of a second underground counting station at SURF in 2015, and future plans. The BLBF is open to any users for counting services or collaboration on a wide variety of experiments and projects.

  17. Berkeley Low Background Facility

    International Nuclear Information System (INIS)

    The Berkeley Low Background Facility (BLBF) at Lawrence Berkeley National Laboratory (LBNL) in Berkeley, California provides low background gamma spectroscopy services to a wide array of experiments and projects. The analysis of samples takes place within two unique facilities; locally within a carefully-constructed, low background laboratory on the surface at LBNL and at the Sanford Underground Research Facility (SURF) in Lead, SD. These facilities provide a variety of gamma spectroscopy services to low background experiments primarily in the form of passive material screening for primordial radioisotopes (U, Th, K) or common cosmogenic/anthropogenic products; active screening via neutron activation analysis for U,Th, and K as well as a variety of stable isotopes; and neutron flux/beam characterization measurements through the use of monitors. A general overview of the facilities, services, and sensitivities will be presented. Recent activities and upgrades will also be described including an overview of the recently installed counting system at SURF (recently relocated from Oroville, CA in 2014), the installation of a second underground counting station at SURF in 2015, and future plans. The BLBF is open to any users for counting services or collaboration on a wide variety of experiments and projects

  18. 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.

  19. C. Judson King of UC Berkeley

    Energy Technology Data Exchange (ETDEWEB)

    Prausnitz, John

    2005-06-01

    In the middle of the UC Berkeley campus, next to the Main Library, South Hall is the last surviving building from the original campus, founded about 135 years ago. A tiny tree-shaded appendix to this venerated classical building houses Berkeley's Center for Studies in Higher Education, directed by C. Judson King, former Provost and Senior Vice President--Academic Affairs of the ten-campus University of California and long-time Professor of Chemical Engineering at Berkeley. Jud came to Berkeley in 1963 as assistant professor of chemical engineering, following receipt of a doctor's degree from MIT and a subsequent short appointment as director of the MIT chemical engineering practice school station at what was then Esso (now Exxon) in New Jersey. His undergraduate degree is from Yale. Starting with his MIT doctoral dissertation on gas absorption, Jud has devoted much of his professional career to separation processes. His teaching and research activities have been primarily concerned with separation of mixtures with emphasis on liquid-liquid extraction and drying. As a consultant to Procter and Gamble, he contributed to the technology of making instant coffee. His life-long activities in hiking and camping stimulated Jud's interest in the manufacture of freeze-dried foods (e.g. turkey meat) to minimize the weight of his hiking back-pack. Jud is internationally known not only for his many research publications but even more, for his acclaimed textbook ''Separation Processses'' (McGraw-Hill, second edition 1980) that is used in standard chemical engineering courses in the US and abroad.

  20. Introducing Knowledge Management in Study Program of Nuclear Engineering

    International Nuclear Information System (INIS)

    Nuclear engineering is the branch of engineering concerning application of the fission as well as the fusion of atomic nuclei, and the application of other sub-atomic physics, based on the principles of nuclear physics. In the sub-field of nuclear fission there are many investigations of interactions and maintaining of systems and components like nuclear reactors and nuclear power plants. The field also includes the study of different applications of ionizing radiation (medicine, agriculture...), nuclear safety, the problems of thermodynamics transport, nuclear materials and nuclear fuels, and other related technologies like radioactive waste management. In the area of nuclear science and engineering a big amount of knowledge has been accumulated over the last decades. Different levels of nuclear knowledge were considered in different ways and they were taught to different parts of population as a general human culture and as a general scientific-technical-technological culture (high schools, nuclear information centres, training centres, universities...). An advanced level of nuclear knowledge has been accumulated by many experienced workers, specialists and experts in all nuclear and nuclear-related fields and applications. In the last 20 years knowledge management has established itself as a discipline of enabling individuals, teams and whole organizations to create, share and apply knowledge collectively and systematically, with goal to better achieve their objectives. Also, knowledge management became key strategic approach for management of intellectual assets and knowledge that can improve safety, efficiency and innovation, and lead to preserve and enhance current knowledge. Knowledge management could be applied in education, training, networking, human resource development and capacity building, sharing, pooling and transferring knowledge form centres of knowledge to centres of growth. Considering the critical importance of nuclear knowledge it is important

  1. Labor market trends for nuclear engineers through 2005

    International Nuclear Information System (INIS)

    Between 1983 and 1989, employment of nuclear engineers in the nuclear energy field increased almost 40 percent while the annual number of nuclear engineering degrees awarded decreased by almost one-fourth. There were, on average, more job openings for new graduates than there were new graduates available to fill the jobs during the 1980s. This trend reversed in the l990s as nuclear engineering employment in the nuclear energy field decreased from 11,500 in 1991 to 9,400 in 1995. During roughly the same period, the annual number of nuclear engineering degrees increased by 11 percent. As a result, from 1990 through 1995, the number of new graduate nuclear engineers available in the labor supply far exceeded the number of job openings for new graduates in the nuclear energy field. This oversupply of new graduates was particularly acute for 1993 through 1995. During 1996--1997, a relative improvement is expected in job opportunities in the nuclear energy field for new graduates; however, a large oversupply is still expected (almost twice as many graduates available for employment as there are job openings). For 1998 through 2000, some improvement is expected in the relative number of job opportunities for new graduates in the nuclear energy field. Nuclear engineering jobs in the nuclear energy field are expected to decrease only slightly (by less than 150) during this period. Also a 10--15% decrease in the annual number of degrees and available supply of new graduates is expected. Overall, an oversupply is expected (140 graduates available per 100 job openings for new graduates in the nuclear energy field), but this is still a substantial improvement over the current period. For 2001 through 2005, if enrollments and degrees continue to decline, the labor market for new graduates is expected to be approximately balanced. This assumes, however, that the number of degrees and the available supply of new graduates will decrease by 25% from 1995 levels

  2. Finally, nuclear engineering textbooks with a Canadian flavour!

    International Nuclear Information System (INIS)

    The need for nuclear engineering textbooks more appropriate to the Canadian nuclear industry context and the CANDU nuclear reactor program has long been felt not only among the universities offering nuclear engineering programs at the graduate level, but also within the Canadian nuclear industry itself. Coverage of the CANDU reactor system in the textbooks presently supporting teaching is limited to a brief description of the concept. Course instructors usually complement these textbooks with course notes written from their personal experience from past employment within the nuclear industry and from their research interests In the last ten years, the Canadian nuclear industry has been involved on an increasing basis with the issue of the technology transfer to foreign countries which have purchased CANDU reactors or have been in the process of purchasing one or several CANDUs. For some of these countries, the 'turn key' approach is required, in which the Canadian nuclear industry looks after everything up to the commissioning of the nuclear power plant, including the education and training of local nuclear engineers and plant personnel. Atomic Energy of Canada Limited (AECL) in particular has dispatched some personnel tasked to prepare and give short courses on some specific aspects of CANDU design and operation, but a lack of consistency was observed as different persons prepared and gave the courses rather independently. To address the many problems tied with nuclear engineering education, the CANTEACH program was set up involving major partners of the Canadian nuclear industry. Parts of the activities foreseen by CANTEACH consist in the writing of nuclear engineering textbooks and associated computer-based pedagogical material. The present paper discusses the main parts of two textbooks being produced, one in reactor physics at steady state and the other on nuclear fuel management. (author)

  3. 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.

  4. 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.

  5. 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.

  6. Brief 66 Nuclear Engineering Enrollments and Degrees Survey, 2009 Data

    International Nuclear Information System (INIS)

    The survey includes degrees granted between September 1, 2008 and August 31, 2009, and fall 2009 enrollments. Thirty-two academic programs reported having nuclear engineering programs during 2009, and data was obtained from all thirty-two.

  7. Nuclear Engineering Enrollments and Degrees Survey, 2008 Data

    Energy Technology Data Exchange (ETDEWEB)

    Analysis and Evaluation, Science Education Programs

    2009-03-30

    The survey includes degrees granted between September 1, 2007, and August 31, 2008, and fall 2008 enrollments. Thirty-one academic programs reported having nuclear engineering programs during 2008, and data was provided by all thirty-one programs.

  8. 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)

  9. Status of nuclear engineering education in the United States

    International Nuclear Information System (INIS)

    Nuclear engineering education in the United States is reflective of the perceived health of the nuclear electric power industry within the country. Just as new commercial reactor orders have vanished and some power plants have shut down, so too have university enrollments shrunk and research reactors closed. This decline in nuclear trained specialists and the disappearance of the nuclear infrastructure is a trend that must be arrested and reversed if the United States is to have a workforce capable of caring for a nuclear power industry to not only meet future electric demand but to ensure that the over 100 existing plants, their supporting facilities and their legacy in the form of high level waste and facility clean-up are addressed. Additionally, the United States has an obligation to support and maintain its nuclear navy and other defence needs. And, lastly, if the United States is to have a meaningful role in the international use of nuclear power with regard to safety, non-proliferation and the environment, then it is imperative that the country continues to produce world-class nuclear engineers and scientists by supporting nuclear engineering education at its universities. The continued support of the federal government. and industry for university nuclear engineering and nuclear energy research and development is essential to sustain the nuclear infrastructure in the United States. Even with this support, and the continued excellent operation of the existing fleet of nuclear electric power plants, it is conceivable that nuclear engineering as an academic discipline may fall victim to poor communications and a tarnished public image. What is needed is a combination of federal and industrial support along with the creativity of the universities to expand their offerings to include more than power production. The objective is a positive message on careers in nuclear related fields, and recognition of the important role of nuclear energy in meeting the country

  10. Master on Nuclear Engineering and Applications (MINA): instrument of knowledge management in the nuclear sector

    International Nuclear Information System (INIS)

    Knowledge Management in nuclear industry is indespensable 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 occured 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)

  11. 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.

  12. German nuclear engineering is high tech

    International Nuclear Information System (INIS)

    Despite the political decision of Germany to opt out of electricity production from nuclear power, know-how in nuclear technology will continue to be needed not only for demolition of nuclear plants and final storage of radioactive waste, but especially in the field of safety technology. ''For decades after the last nuclear power plant in Germany has been shut down we will continue to need know-how in nuclear technology, innovative solutions, and well-trained personnel to do the job'', said Dr. Ralf Gueldner, President of DAtF. ''Nuclear technology in this country is more than just electricity generation'', Gueldner continued. At the ''Energy in a Dialog'' event organized in Berlin on March 12, 2013, these were topics of debate. Hans-Christoph Pape of the German Federal Ministry of Economics and Technology and Stefan vom Scheidt, Technical Manager and Spokesman of the Board of Management of Areva GmbH, offered comments and explained the status and perspectives.

  13. Innovation on multi-project nuclear power engineering management

    International Nuclear Information System (INIS)

    The paper introduces the nuclear power development in China. Referring to foreign nuclear power engineering mode, innovations on the traditional line functional management are proposed to improve the organizational adaptability; to perfect project team management and keep mechanism flexibility; to build multi-project management platform and realize refined operation. (author)

  14. Annual technical report - 1987 - Nuclear Engineering Institute - Dept. of Physics

    International Nuclear Information System (INIS)

    The research reports carried out in the Physics Department of Nuclear Engineering Institute/Brazilian CNEN, in nuclear physics, isotope production and hazards by irradiation using the CV-28 cyclotron capable to accelerate protons, deuterons, helium and alpha particles with maximum energies of 24, 14, 36 and 28 MeV, respectively, are presented. (M.C.K.)

  15. 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.

  16. Nuclear engineering career - Phase 2 Argentina. Final report

    International Nuclear Information System (INIS)

    The objective of the project was to consolidate and extend the conditions necessary for the development of nuclear technology, and to observe the problems posed by the application of the nuclear energy through the increase and improvement of the scientific and technical infrastructure. The immediate objective of the project was to complete the advancement of research and development activities in nuclear engineering at the Centro Atomico Bariloche and Instituto Balseiro

  17. Nuclear criticality safety engineer qualification program utilizing SAT

    Energy Technology Data Exchange (ETDEWEB)

    Baltimore, C.J.; Dean, J.C.; Henson, T.L. [Lockheed Martin Utility Services, Inc., Paducah, KY (United States)

    1996-12-31

    As part of the privatization process of the U.S. uranium enrichment plants, the Paducah Gaseous Diffusion Plant (PGDP) and the Portsmouth Gaseous Diffusion Plant (PORTS) have been in transition from U.S. Department of Energy (DOE) regulatory oversight to U.S. Nuclear Regulatory Commission (NRC) oversight since July 1993. One of the focus areas of this transition has been training and qualification of plant personnel who perform tasks important to nuclear safety, such as nuclear criticality safety (NCS) engineers.

  18. Engineering blasting and vibration monitor near nuclear power station

    International Nuclear Information System (INIS)

    The record of earth and stone work blasting test near the Daya bay nuclear power station is presented. Through the test, the schemes of earth and stone work blasting excavation and vibration monitor are gained, ensuring not only the safe operation of Daya bay nuclear power station but also the progress of Lingao nuclear power station engineering. Practice indicates that the two schemes are feasible

  19. Rover nuclear rocket engine program: Overview of rover engine tests

    Science.gov (United States)

    Finseth, J. L.

    1991-01-01

    The results of nuclear rocket development activities from the inception of the ROVER program in 1955 through the termination of activities on January 5, 1973 are summarized. This report discusses the nuclear reactor test configurations (non cold flow) along with the nuclear furnace demonstrated during this time frame. Included in the report are brief descriptions of the propulsion systems, test objectives, accomplishments, technical issues, and relevant test results for the various reactor tests. Additionally, this document is specifically aimed at reporting performance data and their relationship to fuel element development with little or no emphasis on other (important) items.

  20. Exploratory Research and Development Fund, FY 1990. Report on Lawrence Berkeley Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1992-05-01

    The Lawrence Berkeley Laboratory Exploratory R&D Fund FY 1990 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the projects supported and summarizes their accomplishments. It constitutes a part of an Exploratory R&D Fund (ERF) planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The research areas covered in this report are: Accelerator and fusion research; applied science; cell and molecular biology; chemical biodynamics; chemical sciences; earth sciences; engineering; information and computing sciences; materials sciences; nuclear science; physics and research medicine and radiation biophysics.

  1. Reconstruction of nuclear science and engineering harmonized with human society

    International Nuclear Information System (INIS)

    At the beginning of the 21th century, the use of nuclear power has assumed very serious dimensions, because there are many problems not only safety technologies but also action of technical expert. The situation and problems of nuclear power are explained. It consists of six chapter as followings; introduction, history and R and D of nuclear power, paradigm change of nuclear science and engineering, energy science, investigation of micro world, how to research and development and education and training of special talent. The improvement plans and five proposals are stated as followings; 1) a scholar and engineer related to nuclear power have to understand ethics and build up closer connection with person in the various fields. 2) Nuclear power generation and nuclear fuel cycle are important in future, so that they have to be accepted by the society by means of opening to the public. Safety science, anti-pollution measurements, treatment and disposal of radioactive waste and development of new reactor and fusion reactor should be carried out. 3) It is necessary that the original researches of quantum beam and isotope have to step up. 4) The education of nuclear science and technology and upbringing special talent has to be reconstructed. New educational system such as 'nuclear engineering course crossing with many universities' is established. 5) Cooperation among industry, academic world and government. (S.Y.)

  2. Educational experiments of radiochemistry in the nuclear engineering school

    International Nuclear Information System (INIS)

    Educational experiments of radiochemistry are described. They were an improvement of educational experiment of burn-up measurement as well as experiments on a solvent extraction, a cation exchange behavior of 60Co, liquid scintillation spectrometry and half-life determination of 87Rb, and determination of 137Cs in sea water. Two or one of the experiments were ordinarily studied, depending the occasional situations, by the students of the general course or of the nuclear engineering course in the Nuclear Engineering School, Nuclear Education Center, JAERI from 1976 to 1994. (author)

  3. Foundations of nuclear power engineering safety

    International Nuclear Information System (INIS)

    Report is devoted to justification of nuclear power industry safety. The maximum improvement of safety may be ensured by accident prevention in one of reactor functional units. One presents four basic physical principles ensuring the limiting safety and economical expedience of nuclear power industry

  4. Chaos and fractals. Applications to nuclear engineering

    International Nuclear Information System (INIS)

    This work presents a description of the research lines carried out by the authors on chaos and fractal theories, oriented to the nuclear field. The possibilities that appear in the nuclear security branch where the information deriving from chaos and fractal techniques may help to the development of better criteria and more reliable designs, are of special importance. (Author)

  5. 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.

  6. 2009 SCDNR Berkeley County Lidar

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Sanborn Map Company completed the original classification of the multiple return LiDAR of Berkeley County, South Carolina in 2009. In 2013, Dewberry was tasked with...

  7. Qualified nuclear engineer certification program at Commonwealth Edison

    International Nuclear Information System (INIS)

    Commonwealth Edison (CECo) has utilized a nuclear engineer training and certification program called the Qualified Nuclear Engineer (QNE) Program for many years to ensure that on-site nuclear engineers are ready to assume critical responsibilities in support of reactor operations and reactivity management. Review of this program is significant now because it effectively implements and exceeds the guidance provided by the Institute of Nuclear Power Operations in ACAD 91-017, open-quotes Guidelines for Training and Qualification of Engineering Support Personnelclose quotes for position-specific training of reactor engineers. The CECo QNE program was initiated for boiling water reactor (BWR) station nuclear engineers after reactivity management events occurred in the early 1970s. In 1974 and 1975, two major fuel-failure events occurred in CECo BWR cores caused, in part, by control rod manipulations inappropriate for the original 7 x 7 fuel, which was very susceptible to pellet-clad interaction. In the 1980s pressurized water reactor (PWR) stations across the nation also had a significant number of reactivity management events. From these events, it was apparent that PWR as well as BWR nuclear engineers needed more specialized training to protect the fuel and a PWR QNE program was implemented at CECo. The major purpose of the QNE program is to provide engineers with the proper training and experience to enable them to make good decisions and recommendations regarding core reactivity and fuel performance. The duties that a QNE can be expected to perform after certification include (a) providing reactivity management guidance to operations personnel during normal and abnormal conditions and (b) reviewing special tests, procedures, and modifications that affect reactivity management

  8. The midwest workshop on preparing nuclear engineering professionals

    International Nuclear Information System (INIS)

    Personnel training and education are activities of major importance for nuclear utilities and represent fruitful areas for possible cooperation between utilities and educational institutions. Utility personnel have a need for continuing education through advanced and undergraduate degree programs and special courses. Nuclear engineering departments are in a position to meet at least some of these needs. The purpose of the workshop described in this paper was to explore ways to increase the dialogue between utilities and universities and to bring faculty and utility personnel together to discuss the educational needs of nuclear utilities. The workshop was held May 25-27, 1988, at Iowa State University. Planning for the workshop was coordinated by a steering committee with representation from the Department of Nuclear Engineering at Iowa State University, Iowa Electric Light and Power Company (IEL ampersand P), and Kirkwood Community College at Cedar Rapids, Iowa. Participants represented nuclear utilities, nuclear engineering departments, 2- and 4-yr colleges, a nuclear training organization, and the Institute of Nuclear Power Operations

  9. Nuclear engineering career path - Past, present and future in Europe

    International Nuclear Information System (INIS)

    Full text: Today's nuclear workforce is growing older. The nuclear industry is at a turning point, mainly when we try to evaluate future needs. The paper tries to explore what is the present status of nuclear engineering career in Europe and which are the future trends. Today's students are either unaware of, or indifferent to, nuclear power. But it is not their fault - after all, an entire generation has grown to adulthood since the Three Miles Island and Chernobyl accidents. If their parents' views about nuclear power have been changed after these unhappy accidents, today's teens appear to be almost ambivalent toward it. What could be done to attract younger to the nuclear field in Europe? Probably the main key is in education and even more in a positive image-making of nuclear industry. Creation of more possibilities for gaining work experience and an improvement of economical situation and successful completion of reforms in the industry could attract young people. Political viewpoint is very important, if we consider that people in general thinks that nuclear will be phased out within a short future. A good advertising about job opportunities to come is another factor that plays a role in information of young generation. The paper provides information about university programmes in nuclear engineering in European countries. (authors)

  10. Labor market trends for nuclear engineers through 2000

    International Nuclear Information System (INIS)

    Throughout most of the 1980s, both private organizations and government agencies were concerned about the availability of an adequate supply of qualified nuclear engineers. This concern was primarily the result of a number of nuclear engineering academic programs being eliminated coupled with a continuous decline in graduate and undergraduate enrollments and degrees. By the early 1990s, the number of degrees and available supply had declined to new lows, but cutbacks in funding for the nuclear weapons program and nuclear energy R ampersand D, and in hiring by the electric utility industry, offset in large measure the declining supply. Recently, concerns about environment and waste management and about nuclear safety have again generated questions about the adequacy of supply of qualified personnel for nuclear energy activities. This report briefly examines the nuclear engineering labor market. Trends in employment, new graduates, job openings, and salaries are reviewed as a basis for understanding the current labor market. This review is then used as a basis for assessing future employment needs and new graduate supply to provide an outlook for future labor market conditions through 2000

  11. Nuclear power engineering in the 21 century

    International Nuclear Information System (INIS)

    Analysis and main aspects of comprehending the role and structure of nuclear power (NP) in solution of crucial problems in power generation of the new century are presented briefly. The following problems are considered, in particular: requirements for future NP; optimal structure and major elements of future NP; solution of nuclear weapons nonproliferation problem; main tasks and anticipated results of the international project implemented for providing solutions to vital problems of NP, suggested by president of the RF; arrangement of collaboration in the framework of the international project

  12. Graduate nuclear engineering programmes motivate educational and research activities

    International Nuclear Information System (INIS)

    Some fifteen years ago the University of Ljubljana, Faculty for Mathematics and Physics together with the national research organisation the J. Stefan jointly established a Graduate programme of Nuclear Engineering. From the onset, the programme focused on nuclear technology, nuclear safety, and reactor physics and environment protection. Over the years this graduate programme has became the focal point of nuclear related, research and educational activities in Slovenia. It has grown into a meeting ground for recognised national and distinguished foreign educators and experienced professionals from the industry. In conjunction with an important national project, supported by the Slovenian government, entitled 'Jung Researcher' it also enhances the knowledge transfer to the next generation. Since the programme was introduced, the interest for this programme has been steadily growing. Accordingly, a number of PhD and MS degrees in NE have been awarded. The graduates of this programme have encountered very good job opportunities in nuclear as well as in non-nuclear sector. (author)

  13. Ernest Orlando Berkeley National Laboratory - Fundamental and applied research on lean premixed combustion

    International Nuclear Information System (INIS)

    Ernest Orland Lawrence Berkeley National Laboratory (Berkeley Lab) is the oldest of America's national laboratories and has been a leader in science and engineering technology for more than 65 years, serving as a powerful resource to meet Us national needs. As a multi-program Department of Energy laboratory, Berkeley Lab is dedicated to performing leading edge research in the biological, physical, materials, chemical, energy, environmental and computing sciences. Ernest Orlando Lawrence, the Lab's founder and the first of its nine Nobel prize winners, invented the cyclotron, which led to a Golden Age of particle physics and revolutionary discoveries about the nature of the universe. To this day, the Lab remains a world center for accelerator and detector innovation and design. The Lab is the birthplace of nuclear medicine and the cradle of invention for medical imaging. In the field of heart disease, Lab researchers were the first to isolate lipoproteins and the first to determine that the ratio of high density to low density lipoproteins is a strong indicator of heart disease risk. The demise of the dinosaurs--the revelation that they had been killed off by a massive comet or asteroid that had slammed into the Earth--was a theory developed here. The invention of the chemical laser, the unlocking of the secrets of photosynthesis--this is a short preview of the legacy of this Laboratory

  14. Ernest Orlando Berkeley National Laboratory - Fundamental and applied research on lean premixed combustion

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, Robert K.

    1999-07-07

    Ernest Orland Lawrence Berkeley National Laboratory (Berkeley Lab) is the oldest of America's national laboratories and has been a leader in science and engineering technology for more than 65 years, serving as a powerful resource to meet Us national needs. As a multi-program Department of Energy laboratory, Berkeley Lab is dedicated to performing leading edge research in the biological, physical, materials, chemical, energy, environmental and computing sciences. Ernest Orlando Lawrence, the Lab's founder and the first of its nine Nobel prize winners, invented the cyclotron, which led to a Golden Age of particle physics and revolutionary discoveries about the nature of the universe. To this day, the Lab remains a world center for accelerator and detector innovation and design. The Lab is the birthplace of nuclear medicine and the cradle of invention for medical imaging. In the field of heart disease, Lab researchers were the first to isolate lipoproteins and the first to determine that the ratio of high density to low density lipoproteins is a strong indicator of heart disease risk. The demise of the dinosaurs--the revelation that they had been killed off by a massive comet or asteroid that had slammed into the Earth--was a theory developed here. The invention of the chemical laser, the unlocking of the secrets of photosynthesis--this is a short preview of the legacy of this Laboratory.

  15. 76 FR 37650 - Safety Zone; 4th of July Festival Berkeley Marina Fireworks Display Berkeley, CA

    Science.gov (United States)

    2011-06-28

    ... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zone; 4th of July Festival Berkeley Marina... Berkeley Pier, Berkeley, CA in support of the 4th of July Festival Berkeley Marina Fireworks Display... used in the fireworks display. Background and Purpose The City of Berkeley Marina will sponsor the...

  16. 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.

  17. 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.)

  18. Expert systems and CAD/CAM technology in nuclear research and nuclear engineering

    International Nuclear Information System (INIS)

    The development of expert systems for the peaceful uses of atomic energy, especially nuclear energetics, isotope technique and radiation technology, as well as the interrelation between expert systems used in nuclear research and engineering, and CAD/CAM technology are dealt with. (orig.)

  19. Development of System Engineering Technology for Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    This report is aims to establish design requirements for constructing mock-up system of pyroprocess by 2011 to realize long-term goal of nuclear energy promotion comprehensive plan, which is construction of engineering scale pyroprocess integrated process demonstration facility. The development of efficient process for spent fuel and establishment of system engineering technology to demonstrate the process are required to develop nuclear energy continuously. The detailed contents of research for these are as follows; - Design of Mock-up facility for demonstrate pyroprocess, Construction, Approval, Trial run, Performance test - Development of nuclear material accountancy technology for unit processes of pyroprocess and design of safeguards system - Remote operation of demonstrating pyroprocess / Development of maintenance technology and equipment - Establishment of transportation system and evaluation of pre-safety for interim storage system - Deriving and implementation of a method to improve nuclear transparency for commercialization proliferation resistance nuclear fuel cycle Spent fuel which is the most important pending problem of nuclear power development would be reduced and recycled by developing the system engineering technology of pyroprocess facility by 2010. This technology would contribute to obtain JD for the use of spent fuel between the ROK-US and to amend the ROK-US Atomic Energy Agreement scheduled in 2014

  20. Nuclear science and engineering in China

    International Nuclear Information System (INIS)

    A brief review of the development of nuclear science and technology in China is given. It is stated that the change of leadership in China has brought about a radical revision of the attitude towards the science and technology. In the plan of the development of nuclear science and technology adopted in 1973 a great emphasis is laid on investigations in the field of high energy physics. For instance, it is planned to construct, before 1983, a 30-50 GeV proton accelerator. A brief description is given of main nuclear research institutes in Phangshan, Peking and Shanghai which are shown to Western visitors. It is indicated that at these institutes there are the only two in China research reactors, a 3.5-MW LWR and 10 MW HWR, two cyclotrons and a 90-cm tokamak. These institutes also conduct investigations on the solid-state physics, low-temperature physics, high-pressure physics, lasers, radiation biology, radiation chemistry and others

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-05-15

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

  2. 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.

  3. 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.

  4. Prevent recurrence of nuclear disaster (3). Agenda on nuclear safety from earthquake engineering

    International Nuclear Information System (INIS)

    Based on results of activities of committee on seismic safety of nuclear power plants (NPPs) of Japan Association for Earthquake Engineering, which started activities after Chuetsu-oki earthquake and then experienced Great East Japan Earthquake, (under close collaboration with the committee of Atomic Energy Society of Japan started activities simultaneously), and taking account of further development of concept, agenda on nuclear safety were proposed from earthquake engineering. In order to prevent recurrence of nuclear disaster, individual technical issues of earthquake engineering and comprehensive issues of integration technology, multidisciplinary collaboration and establishment of technology governance based on them were of prime importance. This article described important problems to be solved; (1) technical issues and mission of seismic safety of NPPs, (2) decision making based on risk assessment - basis of technical governance, (3) framework of risk, design and regulation - framework of required technology governance, (4) technical issues of earthquake engineering for nuclear safety, (5) role of earthquake engineering in nuclear power risk communication and (6) importance of multidisciplinary collaboration. Responsibility of engineering would be attributed to establishment of technology governance, cultivation of individual technology and integration technology, and social communications. (T. Tanaka)

  5. Qualitative knowledge engineering for nuclear applications

    International Nuclear Information System (INIS)

    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

  6. 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.

  7. Qualitative knowledge engineering for nuclear applications

    International Nuclear Information System (INIS)

    After the TMI nuclear power plant accident, plant safety and operational efficiency became more important areas of artificial intelligence. They need to build artificial intelligence systems which can predict and explain plant behaviors in earlier phases. We have a 3-year plan to develop hybrid modeling technology of artificial intelligence and related prototype subsystems. After concept design of autonomous power plant in the first year, basic and essential AI technologies were studied and applied to nuclear power plant subsystems, such as the underwater bubble detection subsystem and the eddy current test (ECT) subsystem this year. We developed diagnostic algorithm and experimented it on a testbed we prepared. The testbed system consists of ultrasonic sensor arrays and signal processors, which generates bubble image data and ultrasonic signal distribution data. The essential algorithm to guess the bubble image and its position was studied and developed using two different technologies: the neural network technology and the ultrasonic tomography technology. We developed diagnostic algorithms through ECT data analysis and applied it on an ECT subsystem. During the analysis of ECT data, we concentrated on structure analysis of physical data and internal data, and especially on segmentation scheme of ECT data. The diagnostic algorithm was studied and developed using two different technologies: Fourier descriptors technology and neural network technology. In order to verify the diagnostic algorithms, we have developed the prototype diagnostic programs which proved its good performance. (author). 15 refs., 5 tabs., 25 figs

  8. Training the next generation of nuclear engineers in safety culture

    International Nuclear Information System (INIS)

    This paper presents how undergraduate and graduate nuclear engineering students at the PennsyIvania State University are trained to develop a safety ethic or 'culture' during their coursework. This safety culture is instilled in terms of nuclear safety analysis, design, and licensing issues. various aspects of reactor safety are described either directly or indirectly in each Penn State nuclear engineering course by the development of particular theory and practical applications. A graduate level reactor safety course serves to tie in all the student's previous knowledge into a focused study of safety analysis, licensing, and accident scenarios. With each Penn State nuclear engineering course, there is a focus, and an expected level of understanding of the impact of analysis and design on reactor safety. Foundational to all courses is the knowledge of atomic, health, and reactor physics, mathematics, and general engineering principles. This paper describes the progression of courses related to reactor safety in the Penn State curriculum. The objectives for each course is given in terms of its importance in reactor safety. A detailed description of the graduate level reactor safety course is given to demonstrate how to assemble safety topics into a course that directly addresses safety, licensing, and accident analyses. This safety course serves to provide students with an comprehension of the current 'safety culture' in the United States, and hopefully, instills a proper understanding of safety issues and ethics. (author)

  9. 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…

  10. Selecting and using materials for a nuclear rocket engine reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lanin, Anatolii G; Fedik, Ivan I [' Luch' Research and Production Association, Podol' sk, Moscow region (Russian Federation)

    2011-03-31

    This paper provides a historical account of how the nuclear rocket engine reactor was created and discusses the problem of selecting materials for a gas environment at a temperature of up to 3100 K and energy release of 30 MW per liter. (from the history of physics)

  11. 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.

  12. Broadening of nuclear engineering programs: An engineering physics approach at Rensselaer

    International Nuclear Information System (INIS)

    With the maturing of nuclear engineering as an academic discipline and the uncertainty surrounding the nuclear industry, attention is being increasingly turned to ways in which the base of traditional nuclear engineering programs in universities can be broadened to make them more attractively useful to a wider class of potential students and employers while maintaining the strengths in mainstream areas of nuclear technology. An approach that seems to provide a natural evolution combining the existing programmatic strengths, infrastructure, and resources with the trending needs of a broad segment of diversified industries is the development and initiation of an engineering physics degree program as an adjunct to an established nuclear engineering curriculum. In line with these developments, a new comprehensive academic program offering baccalaureate, master's, and doctoral degrees in engineering physics has been developed and formally instituted at Rensselaer Polytechnic Institute (RPI). It provides a valuable opportunity for students to pursue education and research that cuts across traditional disciplinary lines, leading to a wide variety of career opportunities in industry, government, national research and defense laboratories, and academia

  13. 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.

  14. Communicating and conserving digital data from nuclear science and engineering

    International Nuclear Information System (INIS)

    Digital data from nuclear science and engineering has to be communicated between many different computer systems in the supply chain during the design and build sequences and conserved in a computer understandable form for many years, effectively for ever, even after the original software systems are no longer available. The development of ISO standards for the computer representation of this data independently from proprietary software provides the resources to achieve these requirements. The fundamental basis for the global success of these standards is outlined and the results of applying one of these standards, ISO 10303-235: ‘Engineering properties for product design’, to some of the requirements of a new engineering code for nuclear components are described

  15. Practical reliability engineering applications to nuclear safety

    International Nuclear Information System (INIS)

    PRA studies have been successful in providing a quantitative perspective on the important contributions to risk and on the relative impact of potential hardware modifications and procedural changes in reducing public risk. They have also been successful in some applications in demonstrating that certain modifications or requirements can be deferred or eliminated with no significant safety impact and with a positive effect on cost or plant availability. This paper considers the applications being made by utilities using PRA models and data, that will improve safety in operation and lead to a continuing demonstration that nuclear plants are achieving acceptably low risks. Topics discussed are: systems reliability analysis and technology transfer; Sequoyah demonstration study; standardized modular GO subsystem models; reliability-centered maintenance; analysis of technical specifications; and reliability analysis program with integral data

  16. Developing engineering capabilities as a support to a nuclear program

    International Nuclear Information System (INIS)

    The performance of a nuclear program needs a quite substantial and diversified volume of technological resources. Its integrated management is one of the basic aspects to be settled. In this regard, the creation of strong engineering organizations with the ability to develop management of the project technical activities as a whole has had success in various countries. These organizations should be provided with suitable means to rapidly assimilate the technology and should serve as a channel and support to local industry in general. The development of a nuclear program also requires the collaboration of other institutions, such as universities and research and development centers. In this sense, engineer and technician training necessities are important both in number and technological qualification, as is the availability of capacities in such different areas as simulation and advanced calculation, geology and soil mechanics, materials, fabrication processes, test laboratories, etc. The volume of technological activities to be developed in relation to a stable, although not necessarily large, nuclear program justifies in itself the assigning of important resources to all the above mentioned activities. However, it should be noted that it has been proved that the nuclear industry is completely pervious as regards other fields of activity. In fact, the more stringent quality requirements are quickly transmitted to other industrial processes, and the engineers trained in this area undergo a far from contemptible turnover towards non-nuclear activities. The basic research area in the nuclear field is not in itself a requirement that has to be in parallel with the development of a nuclear program. However, on medium and long-term bases, it may be interesting for a well balanced commercial program that research activities be established realistically and sensibly, even though short-term practical applications are not necessarily derived from this

  17. Romanian knowledge transfer network in nuclear physics and engineering - REFIN

    International Nuclear Information System (INIS)

    According to the requirements of the Romanian Nuclear Programme regarding the education and training of the skilled personnel for the nuclear facilities, a knowledge transfer network named REFIN (in Romanian: Retea Educationala in Fizica si Ingineria Nucleara) was developed since 2005. The knowledge target field is nuclear physics and engineering. The Polytechnic University of Bucharest is the coordinator of this programme and other involved partners are University of Bucharest, University of Pitesti, University Babes Bolyai of Cluj-Napoca, University of Constanta, Institute for Nuclear Research Pitesti, Institute for Physics and Nuclear Engineering from Bucharest and the Training Center for Nuclear Units of Cernavoda NPP. The main objective of this network is to develop an effective, flexible and modern educational system in the nuclear physics and engineering area that could meet the requirements of all the known types of nuclear facility and therewith be redundant with the perspectives of the European Research Area (FP7, EURATOM). The first stage in this work was to gather information about the present status in the mentioned nuclear area in Romania, to assimilate and put this information in a data base on the program web-site (www.refin.pub.ro). Based on this data base a global strategy was proposed in order to harmonize the curricula between the network faculties, to implement pilot modern teaching programs (courses/ modules), to introduce advanced learning methods (as Systematic Approach to Training, e-learning and distance-learning), to strengthen and better use of existing research infrastructure of the research institutes in network. The second stage is the investigation of the training stage in other European countries related to the present status and the development trends of education in nuclear field. In the next future the English version will also be available and so REFIN will be easily accessed and used by the interested users. These facilities

  18. 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.

  19. 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.).

  20. Romanian knowledge transfer network in nuclear physics and engineering - REFIN

    International Nuclear Information System (INIS)

    According to the requirements of the Romanian Nuclear Programme regarding the education and training of the skilled personnel for the nuclear facilities, a knowledge transfer network named REFIN (in Romanian: Retea Educationala in Fizica si Ingineria Nucleara) was developed since 2005. The knowledge target field is nuclear physics and engineering. The main objective of this network is to develop an effective, flexible and modern educational system in the nuclear physics and engineering area which could meet the requirements of all known types of nuclear facilities and therewith be redundant with the perspectives of the European Research Area (FP7, EURATOM). A global strategy was proposed in order to harmonize the curricula between the network facilities to implement pilot modern teaching programs (courses/modules), to introduce advanced learning methods (as Systematic Approach to Training, e-learning and distance-learning), to strengthen and better use the existing research infrastructures of the research institutes in network. The education and training strategy is divided into several topics: university engineering , master, post-graduate, Ph.D. degree, post-doctoral activity, training for industry, improvement. For the first time in our country, a modular scheme is used allowing staff with different technical background to participate at different levels. In this respect, the European system with transferable credits (ECTS) is used. Based on this strategy, courses in 'Radioactive Waste Management' and 'Numerical and Experimental Methods in Reactor Physics' for both MS students and for industry. This way the training activity which a student attends will allow him or her to be involved, depending on specific professional needs, into a flexible educational scheme. This scheme will ensure competence and enhancement and also the possibility of qualification development and a better mobility on labour market. This kind of activity is already in progress in the

  1. Lawrence Berkeley Laboratory Institutional Plan FY 1987-1992

    Energy Technology Data Exchange (ETDEWEB)

    Various

    1986-12-01

    The Lawrence Berkeley Laboratory, operated by the University of California for the Department of Energy, provides national scientific leadership and supports technological innovation through its mission to: (1) Perform leading multidisciplinary research in general sciences and energy sciences; (2) Develop and operate unique national experimental facilities for use by qualified investigators; (3) Educate and train future generations of scientists and engineers; and (4) Foster productive relationships between LBL research programs and industry. The following areas of research excellence implement this mission and provide current focus for achieving DOE goals. GENERAL SCIENCES--(1) Accelerator and Fusion Research--accelerator design and operation, advanced accelerator technology development, accelerator and ion source research for heavy-ion fusion and magnetic fusion, and x-ray optics; (2) Nuclear Science--relativistic heavy-ion physics, medium- and low-energy nuclear physics, nuclear theory, nuclear astrophysics, nuclear chemistry, transuranium elements studies, nuclear data evaluation, and detector development; (3) Physics--experimental and theoretical particle physics, detector development, astrophysics, and applied mathematics. ENERGY SCIENCES--(1) Applied Science--building energy efficiency, solar for building systems, fossil energy conversion, energy storage, and atmospheric effects of combustion; (2) Biology and Medicine--molecular and cellular biology, diagnostic imaging, radiation biophysics, therapy and radiosurgery, mutagenesis and carcinogenesis, lipoproteins, cardiovascular disease, and hemopoiesis research; (3) Center for Advanced Materials--catalysts, electronic materials, ceramic and metal interfaces, polymer research, instrumentation, and metallic alloys; (4) Chemical Biodynamics--molecular biology of nucleic acids and proteins, genetics of photosynthesis, and photochemistry; (5) Earth Sciences--continental lithosphere properties, structures and

  2. Bachelor of science degree in nuclear engineering technology

    International Nuclear Information System (INIS)

    The American Technical Institute is a nonprofit educational institution chartered for the purpose of promoting the transfer of technology to industry through education and research. The institute is governed by a board of trustees comprised of utility executives who sponsor its programs and leading educators from the academic community. In compliance with this objective, the institute offers a Bachelor of Science in Nuclear Engineering Technology (BSNET) degree for employees at nuclear power facilities. Over 400 students have been admitted to the institute. Programs are in operation at River Bend Nuclear Station for Gulf States Utilities, Grand Gulf Nuclear Station for Systems Energy Resources, Inc., and at the E.I. Hatch and Vogtle generating stations for Georgia Power Company. Programs were initiated during the summer of 1985, and seven students graduated with the BSNET degree in December 1988. The purpose of the BSNET degree is to upgrade the engineering expertise of licensed operators, thereby strengthening the cadre of experienced operators qualified to meet requirements of the US Nuclear Regulatory Commission for senior operator, shift supervisor, and shift technical advisor

  3. 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)

  4. 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.

  5. 78 FR 29022 - Safety Zone; Fourth of July Fireworks, Berkeley Marina, Berkeley, CA

    Science.gov (United States)

    2013-05-17

    ... SECURITY Coast Guard 33 CFR Part 165 Safety Zone; Fourth of July Fireworks, Berkeley Marina, Berkeley, CA... enforce the safety zone for the Berkeley Marina Fourth of July Fireworks display in the Captain of the...'19'' W (NAD 83) for the Berkeley Marina Fourth of July Fireworks display listed in 33 CFR...

  6. Application of plasma technology to nuclear engineering fields

    International Nuclear Information System (INIS)

    In order to discuss about the application of the plasma technology to nuclear engineering fields, we mention two subjects, the oxygenation of metal chloride waste by oxygen plasma and the characterization of fine particles generated in the plasma process. Through the experimental results of two subjects, both of the advantage and the disadvantage of the plasma technology and their characteristics are shown and discussed. The following conclusions are obtained. The reactive plasma is effective to oxygenate the chloride wastes. The particle generation which is one of the disadvantages must not be specialized and its characteristics can be estimated. Consequently, the plasma technology should be applicable to nuclear engineering fields adopting its advantage and overcoming its disadvantage. (author)

  7. Human engineering guide for enhancing nuclear control rooms

    International Nuclear Information System (INIS)

    The primary objective of this project was to develop near-term human engineering approaches, that is, those which can be implemented while the plant is operating or during a planned shutdown, for enhancing existing nuclear control rooms. Primary data for the Guide was collected during site visits to four pressurized water reactor (PWR) plants representing a mix of Nuclear Steam Supply System (NSSS) vendors and architects/engineers. Structured interviews, checklists, walkthroughs/talkthroughs, surveys, and task analyses were used. Data on boiling water reactors (BWRs) were collected in a meeting with representatives of the BWR Owners Group. All enhancement approaches were reviewed extensively with cognizant industry representatives for feasibility and acceptability before being including in the Guide

  8. Nuclear quantum state engineering in ion channeling regime

    Directory of Open Access Journals (Sweden)

    Berec Vesna

    2015-01-01

    Full Text Available A key challenge in quantum state engineering is to identify coherent quantum mechanical systems that can be precisely manipulated and scaled, but at the same time to allow decoupling from unwanted interactions. Such systems, once realized, would represent an efficient tool for characterization of quantum behavior reflected in the properties of matter with prerequisites for meeting dissipation constraints imposed in the nuclear physics as well in the quantum information theory. Using the pure29Si nanocrystal system we present a novel high resolution method for initialization of single electron polarized spin interaction and control of nuclear spin qubits. The presented study fuses field of particle channeling in MeV energy regime with quantum state engineering utilized via entanglement as an essential quantum property. Its aim is to bring focus on new theoretical proposals testing the quantum mechanical models for systems producible at particle accelerator facilities.

  9. Building an integrated nuclear engineering and nuclear science human resources pipeline at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Full text: In 2002, the US Department of Energy (US DOE) transferred sponsorship of the INEEL and ANL-W to the DOE Office of Nuclear Energy, Science and Technology and designated the INEEL and ANL-W as the nation's lead laboratories for nuclear reactor and nuclear fuel cycle research and development. This transfer acknowledged the laboratories' history, infrastructure, expertise and commitment to collaborate broadly in order to fulfill its assigned role as the nation's center for nuclear energy research and development. Key to this role is the availability of well-educated and trained nuclear engineers, professionals from other disciplines of engineering, nuclear scientists, and others with advanced degrees in supporting disciplines such as physics, chemistry, and math. In 2005 the INEEL and ANL-W will be combined into the Idaho National Laboratory (INL). One of US DOE's objectives for the INL will be for it to take a strong role in the revitalization of nuclear engineering and nuclear science education in the US. Responding to this objective for the INL and the national need to rejuvenate nuclear engineering and nuclear science research and education, ISU, University of Idaho (UI), Boise State University, the INEEL, and ANL-W are all supporting a new Institute of Nuclear Science and Engineering (INSE), initially proposed by and to be administered by ISU. The Institute will rely on the resources of both universities and the INL to create a US center for reactor and fuel cycle research to development and attract outstanding faculty and students to Idaho and to the INL. The Institute and other university based education development efforts represent only one component of a viable Human Resources Pipeline from university to leading edge laboratory researcher. Another critical component is the successful integration of new graduates into the laboratory research environment, the transfer of knowledge from senior researchers, and the development of these individuals into

  10. Annual report of Radiation Laboratory Department of Nuclear Engineering Faculty of Engineering, Kyoto University

    International Nuclear Information System (INIS)

    This publication is the collection of the papers presented research activities of Radiation laboratory, Department of Nuclear Engineering, Kyoto University during the 1992 academic/fiscal year (April, 1992 - March, 1993). The 48 of the presented papers are indexed individually. (J.P.N.)

  11. Catalog of Research Abstracts, 1993: Partnership opportunities at Lawrence Berkeley Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    The 1993 edition of Lawrence Berkeley Laboratory`s Catalog of Research Abstracts is a comprehensive listing of ongoing research projects in LBL`s ten research divisions. Lawrence Berkeley Laboratory (LBL) is a major multi-program national laboratory managed by the University of California for the US Department of Energy (DOE). LBL has more than 3000 employees, including over 1000 scientists and engineers. With an annual budget of approximately $250 million, LBL conducts a wide range of research activities, many that address the long-term needs of American industry and have the potential for a positive impact on US competitiveness. LBL actively seeks to share its expertise with the private sector to increase US competitiveness in world markets. LBL has transferable expertise in conservation and renewable energy, environmental remediation, materials sciences, computing sciences, and biotechnology, which includes fundamental genetic research and nuclear medicine. This catalog gives an excellent overview of LBL`s expertise, and is a good resource for those seeking partnerships with national laboratories. Such partnerships allow private enterprise access to the exceptional scientific and engineering capabilities of the federal laboratory systems. Such arrangements also leverage the research and development resources of the private partner. Most importantly, they are a means of accessing the cutting-edge technologies and innovations being discovered every day in our federal laboratories.

  12. Computerized engineering logic for nuclear procurement and dedication processes

    International Nuclear Information System (INIS)

    In an attempt to better meet the needs of operations and maintenance organizations, many nuclear utility procurement engineering groups have simplified their procedures, developed on-line tools for performing the specification of replacement items, and developed relational databases containing part-level information necessary to automate the procurement process. Although these improvements have helped to reduce the engineering necessary to properly specify and accept/dedicate items for nuclear safety-related applications, a number of utilities have recognized that additional long-term savings can be realized by integrating a computerized logic to assist technical procurement engineering personnel. The most commonly used logic follows the generic processes contained in Electric Power Research Institute (EPRI) published guidelines. The processes are typically customized to some extent to accommodate each utility's organizational structure, operating procedures, and strategic goals. This paper will discuss a typical logic that integrates the technical evaluation, acceptance, and receipt inspection and testing processes. The logic this paper will describe has been successfully integrated at a growing number of nuclear utilities and has produced numerous positive results. The application of the logic ensures that utility-wide standards or procedures, common among multi-site utilities, are followed

  13. Application of bulk material commodity code in nuclear engineering

    International Nuclear Information System (INIS)

    The text details the signification and current status and difficulty of commodity code in the nuclear power engineering. By the applying condition of Ling Ao Phrase 2 Nuclear Power Plant there are several ways to create commodity code. Detail how to make commodity code structure and commodity code rule. And define material style, commodity code prefix, size and thickness etc. Then create commodity code. The other way is by user define to create commodity code. Next register specification in VPRM, make size range, thickness and branch fitting consolidation in the specification, select commodity code to create part number. And introduce how the interface of VPRM and PDMS, how import the weight data, and how make owner part number press in the drawing conveniently. The part numbers are applied in the drawings of LingAo Phrase 2 Nuclear Power Plant, owner accepts them. (authors)

  14. 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.

  15. Development of Nuclear ship Engineering Simulation SYstem (NESSY)

    Energy Technology Data Exchange (ETDEWEB)

    Kusunoki, Tsuyoshi; Kyouya, Masahiko; Takahashi, Teruo; Kobayashi, Hideo; Ochiai, Masa-aki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Hashidate, Kouji

    1993-11-01

    NESSY has been developed for design studies of advanced marine reactors as a part of nuclear ship research and development since 1987. Engineering simulation model of the Mutsu, which is the first nuclear ship in Japan, was completed in March of 1993. In this report we concentration on detail description of softwares for Mutsu modeling. The aims of development of NESSY are as follows; (1) Assessment and confirmation on plant performance of an advanced marine reactor in each step of nuclear ship design (2) Development of abnormality diagnosis system and operator support system as a part of enhanced automization study, and study of human interface with hardware The characteristics of NESSY are the followings. (1) Total engineering simulation system simulate simultaneously ship motions, propulsion system behavior, and nuclear plant behavior under given weather and sea conditions. (2) Models based on physical theory as far as possible. (3) The simulator has high extensibility and flexibility. It is able to apply to other reactors, as the simulation model consists of the part of basic model and the part of plant data which are easy to change. After completion of Mutsu modeling, we are planning to utilize this system as one of design tools for an advanced marine reactor. (author).

  16. University and national laboratory roles in nuclear engineering

    International Nuclear Information System (INIS)

    Nuclear engineering education is being significantly challenged in the US. The decline in enrollment generally and the reduction of the number of nuclear engineering departments has been well documented. These declines parallel a lack of new construction for nuclear power plants and a decline in research and development to support new plant design. Precisely at a time when innovation is needed to deal with the many issues facing nuclear power, the number of qualified people to do so is being reduced. It is important that the university and national laboratory communities cooperate to address these issues. To be drawn into the technology, the best students must see a future, a need, and must identify challenges to meet. The university community can provide that vision with help from the national laboratories. It has been a major goal within the reactor development program at Argonne National Laboratory to establish the kind of program that can help accomplish this. The integral fast reactor (IFR) program represents opportunities for joint research in fuel technology, fuel reprocessing, and waste handling, reactor-plant design to emphasize passive response to upsets, development and testing of advanced diagnostic and control-system technology core designs to enhance breeding while minimizing sodium void effects and reducing the magnitude of reactivity changes with burnup, development of approaches to the probabilistic risk assessment that fully integrate passive responses, and many others. To involve students and faculty, they have established the IFR fellows program

  17. Feasibility study of a contained pulsed nuclear propulsion engine

    Energy Technology Data Exchange (ETDEWEB)

    Parlos, A.G.; Metzger, J.D. (Texas A M Univ., College Station, TX (United States))

    1994-03-01

    The result of a feasibility analysis of a contained pulsed nuclear propulsion (CPNP) engine concept utilizing the enormously dense energy generated by small nuclear detonations is presented in this article. This concept was initially proposed and studied in the 1950s and 1960s under the program name HELIOS. The current feasibility of the concept is based upon materials technology that has advanced to a state that allows the design of pressure vessels required to contain the blast associated with small nuclear detonations. The impulsive nature of the energy source provides the means for circumventing the materials thermal barriers that are inherent in steady-state nuclear propulsion concepts. The rapid energy transfer to the propellant results in high thrust levels for times less than 1 s following the detonation. The preliminary feasibility analysis using off-the-shelf materials technology appears to indicate that the CPNP concept can have thrust-to-weight ratios on the order of 1 or greater. Though the specific impulse is not a good indicator for impulsive engines, an operating-cycle averaged specific impulse of approximately 1000 or greater seconds was calculated. 16 refs.

  18. Knowledge engineering and its applications to nuclear technology

    International Nuclear Information System (INIS)

    The application of knowledge engineering to nuclear technology is rapidly advancing over wide ranges. For the problems which have been solved so far by empirical laws and know-hows, the knowledge engineering offers new approach, and its potential is very large. In this report, this technology is explained about the various actual examples of application, and its future perspective is given. The reports of the research on the application of knowledge engineering presented to the Atomic Energy Society of Japan have increased very much. The fields of the object of application were initially abnormality diagnosis and operation guidance, but recently, alarm dealing, the planning of fuel exchange, the layout of machinery and equipment, the routing of pipings, the forecast of machinery and equipment life, maintenance planning and so on have been included. As the concrete examples of application, the description and analysis of the networks related to phenomena, the diagnosis of nuclear power plants, qualitative inference and the acquirement of the knowledge for diagnosis, the planning of fuel movement and others are described. The expression of knowledge and the mechanism of inference, and the problems of knowledge engineering hereafter are discussed. (Kako, I.)

  19. 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.

  20. 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

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

    International Nuclear Information System (INIS)

    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

  2. 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

  3. Environmental Survey preliminary report, Lawrence Berkeley Laboratory, Berkeley, California

    Energy Technology Data Exchange (ETDEWEB)

    1988-07-01

    The purpose of this report is to present the preliminary findings made during the Environmental Survey, February 22--29, 1988, at the US Department of Energy (DOE) Lawrence Berkeley Laboratory (LBL) in Berkeley, California. The University of California operates the LBL facility for DOE. The LBL Survey is part of the larger DOE-wide Environmental Survey announced by Secretary John S. Herrington on September 18, 1985. The purpose of this effort is to identify, via no fault'' baseline Surveys, existing environmental problems and areas of environmental risk at DOE facilities, and to rank them on a DOE wide basis. This ranking will enable DOE to more effectively establish priorities for addressing environmental problems and allocate the resources necessary to correct them. Because the Survey is no fault'' and is not an audit,'' it is not designed to identify specific isolated incidents of noncompliance or to analyze environmental management practices. Such incidents and/or management practices will, however, be used in the Survey as a means of identifying existing and potential environmental problems. The LBL Survey was conducted by a multidisciplinary team of technical specialists headed and managed by a Team Leader and Assistant Team Leader from DOE's Office of Environmental Audit. A complete list of the LBL Survey participants and their affiliations is provided in Appendix A. 80 refs., 27 figs., 37 tabs.

  4. Environmental Survey preliminary report, Lawrence Berkeley Laboratory, Berkeley, California

    International Nuclear Information System (INIS)

    The purpose of this report is to present the preliminary findings made during the Environmental Survey, February 22--29, 1988, at the US Department of Energy (DOE) Lawrence Berkeley Laboratory (LBL) in Berkeley, California. The University of California operates the LBL facility for DOE. The LBL Survey is part of the larger DOE-wide Environmental Survey announced by Secretary John S. Herrington on September 18, 1985. The purpose of this effort is to identify, via ''no fault'' baseline Surveys, existing environmental problems and areas of environmental risk at DOE facilities, and to rank them on a DOE wide basis. This ranking will enable DOE to more effectively establish priorities for addressing environmental problems and allocate the resources necessary to correct them. Because the Survey is ''no fault'' and is not an ''audit,'' it is not designed to identify specific isolated incidents of noncompliance or to analyze environmental management practices. Such incidents and/or management practices will, however, be used in the Survey as a means of identifying existing and potential environmental problems. The LBL Survey was conducted by a multidisciplinary team of technical specialists headed and managed by a Team Leader and Assistant Team Leader from DOE's Office of Environmental Audit. A complete list of the LBL Survey participants and their affiliations is provided in Appendix A. 80 refs., 27 figs., 37 tabs

  5. Nuclear Power Engineering Education Program, University of Illinois

    International Nuclear Information System (INIS)

    The DOE/CECo Nuclear Power Engineering Education Program at the University of Illinois in its first year has significantly impacted the quality of the power education which our students receive. It has contributed to: the recently completed upgrade of the console of our Advanced TRIGA reactor which increases the reactor's utility for training, the procurement of new equipment to upgrade and refurbish several of the undergraduate laboratory set-ups, and the procurement of computational workstations in support of the instructional computing laboratory. In addition, smaller amounts of funds were used for the recruitment and retention of top quality graduate students, the support of faculty to visit other institutions to attract top students into the discipline, and to provide funds for faculty to participate in short courses to improve their skills and background in the power area. These items and activities have helped elevate in the student's perspective the role of nuclear power in the discipline. We feel this is having a favorable impact on student career selection and on ensuring the continued supply of well educated nuclear engineering graduates

  6. 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.

  7. CAE - nuclear engineering analysis on work-station computers

    International Nuclear Information System (INIS)

    Emergence of the inexpensive and widely available 32-bit-work-station computer is revolutionizing the scientific and engineering computing environment. These systems reach or exceed threshold for many midscale nuclear applications and bridge the gap between the era of expensive computing: cheap people and the era of cheap computing: expensive people. Experience at the Idaho National Engineering Laboratory (INEL) has demonstrated the efficacy of this new computer technology. For the past 1 1/2 yr, a Hewlett-Packard 9000/540 32-bit multi-user microcomputer has been used to perform many calculations typical of a nuclear design effort. This system is similar with respect to performance and memory to such work stations as the SUN-3, HP-9000/32, or the Apollo DN-3000 that are available for under $20,000 for a fully configured single-user station. The system is being used for code development, model setup and checkout, and a full range of nuclear applications. Various one- and two-dimensional discrete ordinates transport codes are used on a routine basis. These include the well-known ANISN code as well as locally developed transport models. Typical one-dimensional multigroup calculations can be executed in clock times <10 min

  8. Quantity and quality in nuclear engineering professional skills needed by the nuclear power industry

    International Nuclear Information System (INIS)

    This paper examines the challenge of work force requirements in the context of the full range of issues facing the nuclear power industry. The supply of skilled managers and workers may be a more serious problem if nuclear power fades away than if it is reborn in a new generation. An even greater concern, however, is the quality of education that the industry needs in all its future professionals. Both government and industry should be helping universities adapt their curricula to the needs of the future. This means building a closer relationship with schools that educate nuclear professionals, that is, providing adequate scholarships and funding for research and development programs, offering in-kind services, and encouraging internships and other opportunities for hands-on experience. The goal should not be just state-of-the-art engineering practices, but the broad range of knowledge, issues, and skills that will be required of the nuclear leadership of the twenty-first century

  9. Two amateur astronomers at Berkeley

    CERN Document Server

    Sparavigna, Amelia Carolina

    2012-01-01

    The book on Mechanics of the Physics at Berkeley, by C. Kittel, W.D. Knight and M.A. Ruderman, is proposing at the end of its first chapter some problems of simple astronomy within the solar system. The discussion begins with two amateur astronomers who set for themselves the goal of determining the diameter and mass of the Sun. Here we discuss the problems proposed by the book and some other matters on ancient and modern astronomical studies of the solar system.

  10. A brief history of graduate distance education in nuclear engineering at Penn State Univ

    International Nuclear Information System (INIS)

    The Pennsylvania State University Nuclear Engineering Distance Education Program has a twenty year history of providing graduate level distance education in Nuclear Engineering. The Distance Education Program was initiated as a specific program which was developed for the Westinghouse Energy Systems Divisions in Pittsburgh. In 1983, Carnegie-Mellon University (CMU) decided to terminate its small Nuclear Engineering Program. Up until that time, Westinghouse employees could enroll at CMU for graduate classes in Nuclear Engineering as well as other engineering disciplines and could obtain a masters degree or if desired, could continue for a Ph.D. degree. (authors)

  11. Human Factors Engineering Review Model for advanced nuclear power reactors

    Energy Technology Data Exchange (ETDEWEB)

    O`Hara, J.; Higgins, J. [Brookhaven National Lab., Upton, NY (United States); Goodman, C.; Galletti, G.: Eckenrode, R. [Nuclear Regulatory Commission, Rockville, MD (United States)

    1993-05-01

    One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model`s rationale, scope, objectives, development, general characteristics. and application.

  12. Nuclear engineering of diagnostic port plugs on ITER

    Energy Technology Data Exchange (ETDEWEB)

    Pitcher, C.S., E-mail: spencer.pitcher@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Barnsley, R. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Feder, R. [Princeton Plasma Physics Lab, Princeton, NJ (United States); Hu, Q. [Institute of Plasma Physics, Chinese Academy of Sciences (China); Loesser, G.D. [Princeton Plasma Physics Lab, Princeton, NJ (United States); Lyublin, B. [Efremov, St. Petersburg (Russian Federation); Padasalagi, S. [Institute for Plasma Research, Gandhinagar, Gujarat (India); Pak, S. [National Fusion Research Institute, Daejeon (Korea, Republic of); Reichle, R. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Sato, K. [Japan Atomic Energy Agency, Naka, Ibaraki (Japan); Udintsev, V.S.; Walker, C.; Walsh, M. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Zhai, Y. [Princeton Plasma Physics Lab, Princeton, NJ (United States)

    2012-08-15

    The nuclear engineering infrastructure of port-based diagnostics on ITER is presented, including the equatorial and upper port plug generic designs, the adopted modular concept, the loads and associated load response and the remote handling. A modular approach is adopted for the internal shielding modules as this helps to reduce the dominant electromagnetic loads, reduces interfaces and accelerates remote handling. Extensive use of gun-drilling is employed to produce water channels in the stainless steel plate and forgings used to construct the port plugs and modules. The French Nuclear Code RCC-MR (2007) is employed in the design and the manufacturing. An integrated remote handling scheme is described, including a description of maintenance operations in the Hot Cell Facility.

  13. Upgrades to the NESS (Nuclear Engine System Simulation) Code

    Science.gov (United States)

    Fittje, James E.

    2007-01-01

    In support of the President's Vision for Space Exploration, the Nuclear Thermal Rocket (NTR) concept is being evaluated as a potential propulsion technology for human expeditions to the moon and Mars. The need for exceptional propulsion system performance in these missions has been documented in numerous studies, and was the primary focus of a considerable effort undertaken during the 1960's and 1970's. The NASA Glenn Research Center is leveraging this past NTR investment in their vehicle concepts and mission analysis studies with the aid of the Nuclear Engine System Simulation (NESS) code. This paper presents the additional capabilities and upgrades made to this code in order to perform higher fidelity NTR propulsion system analysis and design.

  14. Symposium on engineering with nuclear explosives. Proceedings. Vol. 1

    International Nuclear Information System (INIS)

    This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. These proceedings are the record of the symposium

  15. Dismantling of nuclear facilities. From a structural engineering perspective

    International Nuclear Information System (INIS)

    The paper summarizes some important aspects, requirements and technical boundary conditions that need to be considered in dismantling projects in the nuclear sector from a structural engineering perspective. Besides general requirements regarding radiation protection, occupational safety, efficiency and cost effectiveness it is important to take into account other conditions which have a direct impact on technical details and the structural assessment of the dismantling project. These are the main aspects highlighted in this paper: - The structural assessment of dismantling projects has to be based on the as-built situation. - The limitations in terms of available equipment and space have to be taken into account. - The structural assessments are often non-standardized engineering evaluations. A selection of five dismantling projects illustrates the various structural aspects. (orig.)

  16. Symposium on engineering with nuclear explosives. Proceedings. Volume 2

    International Nuclear Information System (INIS)

    This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. This proceedings is the record of the symposium

  17. 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…

  18. Grain boundary engineering for structure materials of nuclear reactors

    Science.gov (United States)

    Tan, L.; Allen, T. R.; Busby, J. T.

    2013-10-01

    Grain boundary engineering (GBE), primarily implemented by thermomechanical processing, is an effective and economical method of enhancing the properties of polycrystalline materials. Among the factors affecting grain boundary character distribution, literature data showed definitive effect of grain size and texture. GBE is more effective for austenitic stainless steels and Ni-base alloys compared to other structural materials of nuclear reactors, such as refractory metals, ferritic and ferritic-martensitic steels, and Zr alloys. GBE has shown beneficial effects on improving the strength, creep strength, and resistance to stress corrosion cracking and oxidation of austenitic stainless steels and Ni-base alloys.

  19. Public information and acceptance of nuclear engineering studies at the faculty of nuclear sciences and physical engineering of CTU Prague

    International Nuclear Information System (INIS)

    The Faculty of Nuclear Sciences and Physical Engineering was founded in 1955, when the nuclear program in Czechoslovakia has been launched. In approximately the same time also some nuclear research institutes were founded, as, e.g., the Institute of Nuclear Research and the Research Institute of Nuclear Instruments, etc., extensive plans of development of nuclear power production were drafted, and everybody was very enthusiastic for this new branch of science and technology. The present status of nuclear technology and the new trends in applied hard sciences have resulted in widening the profile of the Faculty, because the staff has intended to preserve it as a modern and advanced part of the University. It means that now nuclear sciences represent about one third of the programme and the structure of its responsibilities. What is the public acceptance of the Faculty nowadays? Two unfavourable trends act against the interest to enrol at the Faculty. The first one is general - a decreasing interest of the young in engineering, given probably by both higher work-load in comparison with, e.g., social sciences, and a not very high social status of engineering graduates in the former socialist society. The second trend is given by a strong antinuclear opposition and campaigns in the past few years, relatively latent between the Chernobyl accident and 1989, because the former regime had not allow any discussions about this subject, and clearly apparent after the 1989 November revolution. These antinuclear tendencies were also fuelled by the effective Greenpeace campaign in 1990, imported mostly from Austria, and, unfortunately, unfounded from the scientific point of view. How can the Faculty resist this ebb of interest? First of all this can be achieved by suitable modification of curricula towards 'computerisation' and ecologisation. Among other activities priority is given to cooperation with mass media as the press, TV etc. Direct contacts with high and grammar

  20. The Belgian nuclear higher education network: the evolution of an academic programme in nuclear engineering

    International Nuclear Information System (INIS)

    The master-after-master in nuclear engineering provided by the Belgian Nuclear higher Education Network (BNEN) is a one-year, 60 ECTS programme which combines the expertise of six Belgian universities and SCK.CEN, the Belgian Nuclear Research Centre, which participates through its Academy for Nuclear Science and Technology. It was created in close collaboration with representatives of academia, research centres, industry and other nuclear stakeholders. The BNEN consortium Due to its modular programme, BNEN is accessible for both full-time students (mainly young engineering graduates) as well as young professionals already employed in the nuclear industry. The programme is offered in English to facilitate the participation of international students. One of the important aspects of the BNEN programme is the fact that exercises and hands-on sessions in the specialised laboratories of SCK.CEN complement the theoretical classes to bring the students into contact with all facets of nuclear energy. Several of SCK.CEN's researchers provide valuable contributions to the programme through seminars and practical exercises. From their daily practices and responsibilities they give an expert view on the subjects that are being taught. In 2012, in the framework of an official accreditation process all aspects of the BNEN programme were audited by an international visitation panel. The most important outcome of this process is the current reform of the academic programme, which will be implemented in the academic year 2014-2015, taking into account the recommendations by the visitation panel. In this paper, the history of the BNEN programme will be discussed, the new BNEN programme will be presented as well as the process that has led to its implementation. (authors)

  1. An engineer-constructor's view of nuclear power plant safety

    International Nuclear Information System (INIS)

    At SWEC we have been involved in the development of safety features of nuclear power plants ever since we served as the engineer-constructur for the first commerical nuclear power station at Shippingport, Pennsylvania, in the 1950s. Our personnel have pioneered a number of safety innovations and improvements. Among these innovations is the subatmospheric containment for pressurized water reactor (PWR) power plants. This type of containment is designed so that leakage will terminate within 1 to 2 hours of the worst postulated loss of coolant accident. Other notable contributions include first use of reinforced-concrete atmospheric containments for PWR power plants and of reinforced-concrete, vapor-suppression containments for boiling water reactor (BWR) power plants. Both concepts meet rigorous U.S. safety requirements. SWEC has performed a substantial amount of work on developing standardized plant designs and has developed standardized engineering and construction techniques and procedures. Standardization concepts are being developed in Canada, France, USSR, and Germany, as well as in the United States. The West German convoy concept, which involves developing a number of standardized plants in a common effort, has been quite successful. We believe standardization contributes to safety in a number of ways. Use of standardized designs, procedures, techniques, equipment, and methods increases efficiency and results in higher quality. Standardization also reduces the design variations with which plant operators, emergency teams, and regulatory personnel must be familiar, thus increasing operator capability, and permits specialized talents to be focused on important safety considerations. (orig./RW)

  2. 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.

  3. 77 FR 37604 - Safety Zone; Fourth of July Fireworks, Berkeley Marina, Berkeley, CA

    Science.gov (United States)

    2012-06-22

    ... SECURITY Coast Guard 33 CFR Part 165 Safety Zone; Fourth of July Fireworks, Berkeley Marina, Berkeley, CA... enforce the safety zone for the Berkeley Marina Fourth of July Fireworks display in the Captain of the... Marina Fourth of July Fireworks display in 33 CFR 165.1191. This safety zone will be in effect from...

  4. The function of specialized organization in work safety engineering for nuclear installations

    International Nuclear Information System (INIS)

    The attributions of Brazilian CNEN in the licensing procedures of any nuclear installation are discussed. It is shown that the work safety engineering and industrial safety constitute important functions for nuclear safety. (M.C.K.)

  5. Texas A and M University student/professional nuclear science and engineering conference

    International Nuclear Information System (INIS)

    Abstracts of papers presented at the meeting are included. Topics discussed include: reactor engineering; space nuclear power systems; health physics and dosimetry; fusion engineering and physics; and reactor physics and theory

  6. Berkeley High-Resolution Ball

    International Nuclear Information System (INIS)

    Criteria for a high-resolution γ-ray system are discussed. Desirable properties are high resolution, good response function, and moderate solid angle so as to achieve not only double- but triple-coincidences with good statistics. The Berkeley High-Resolution Ball involved the first use of bismuth germanate (BGO) for anti-Compton shield for Ge detectors. The resulting compact shield permitted rather close packing of 21 detectors around a target. In addition, a small central BGO ball gives the total γ-ray energy and multiplicity, as well as the angular pattern of the γ rays. The 21-detector array is nearly complete, and the central ball has been designed, but not yet constructed. First results taken with 9 detector modules are shown for the nucleus 156Er. The complex decay scheme indicates a transition from collective rotation (prolate shape) to single- particle states (possibly oblate) near spin 30 h, and has other interesting features

  7. A Program for Cultivating Nuclear Talent at Engineering Educational Institute in a Remote Area from Nuclear Power Plants

    Science.gov (United States)

    Takahashi, Tsuyoshi

    Recently, in Japan, the number of students who hope for finding employment at the nuclear power company has decreased as students‧ concern for the nuclear power industry decreases. To improve the situation, Ministry of Education, Culture, Sports, Science and Technology launched the program of cultivating talent for nuclear power which supports research and education of nuclear power in the academic year of 2007. Supported by the program, Kushiro College of Technology conducted several activities concerning nuclear power for about a year. The students came to be interested in nuclear engineering through these activities and its results.

  8. Artificial neural networks in the nuclear engineering (Part 2)

    International Nuclear Information System (INIS)

    The field of Artificial Neural Networks (ANN), one of the branches of Artificial Intelligence has been waking up a lot of interest in the Nuclear Engineering (NE). ANN can be used to solve problems of difficult modeling, when the data are fail or incomplete and in high complexity problems of control. The first part of this work began a discussion with feed-forward neural networks in back-propagation. In this part of the work, the Multi-synaptic neural networks is applied to control problems. Also, the self-organized maps is presented in a typical pattern classification problem: transients classification. The main purpose of the work is to show that ANN can be successfully used in NE if a carefully choice of its type is done: the application sets this choice. (author)

  9. The disposal of Canada's nuclear fuel waste: engineered barriers alternatives

    International Nuclear Information System (INIS)

    The concept for disposal of Canada's nuclear fuel waste involves emplacing the waste in a vault excavated at a depth of 500 to 1000 m in plutonic rock of the Canadian Shield. The solid waste would be isolated from the biosphere by a multibarrier system consisting of engineered barriers, including long-lived containers and clay and cement-based sealing materials, and the natural barrier provided by the massive geological formation. The technical feasibility of this concept and its impact on the environment and human health are being documented in an Environmental Impact Statement (EIS), which will be submitted for review under the federal Environmental Assessment and Review Process. This report, one of nine EIS primary references, describes the various alternative designs and materials for engineered barriers that have been considered during the development of the Canadian disposal concept and summarizes engineered barrier concepts being evaluated in other countries. The basis for the selection of a reference engineered barrier system for the EIS is presented. This reference system involves placing used CANDU (Canada Deuterium Uranium) fuel bundles in titanium containers, which would then be emplaced in boreholes drilled in the floor of disposal rooms. Clay-based sealing materials would be used to fill both the space between the containers and the rock and the remaining excavations. In the section on waste forms, the properties of both used-fuel bundles and solidified high-level wastes, which would be produced by treating wastes resulting from the reprocessing of used fuel, are discussed. Methods of solidifying the wastes and the chemical durability of the solidified waste under disposal conditions are reviewed. Various alternative container designs are reviewed, ranging from preliminary conceptual designs to designs that have received extensive prototype testing. Results of structural performance, welding and inspection studies are also summarized. The corrosion of

  10. Performance evaluation of nuclear ship engineering simulation system

    Energy Technology Data Exchange (ETDEWEB)

    Kyouya, Masahiko; Ochiai, Masa-aki; Kusunoki, Takeshi; Takahashi, Teruo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Uematsu, Haruki

    1994-06-01

    Nuclear Ship Engineering Simulation System (NESSY) has been developed for an efficient design study of an advanced marine reactor, Marine Reactor X (MRX). This time, the performance evaluation of NESSY was carried out by comparing predictions which were computed on NESSY with measurements which were got from experimental voyage of the nuclear ship `Mutsu`. This report writes the way of evaluation and the results. The aims of the performance evaluation is to find out differences between predictions and measurements, to make their causes on the side of simulator clear and to verify the applicable range of NESSY. As a result, it shows that NESSY has a sufficient performance to simulate the `Mutsu` and further is applicable to MRX except for the part of a helical-type once-through steam generator and a water-filled containment vessel which are introduced into it. After this, we are planning to utilize this system effectively as one of design tools for design study of MRX by adding functions of MRX. (author).

  11. 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.

  12. Challenges faced by engineering services group in meeting nuclear power project targets

    International Nuclear Information System (INIS)

    Nuclear Power Corporation of India Ltd. (NPCIL) is an organisation building and operating nuclear power stations for which a number of different types of engineering services/activities are necessary. All these services are provided by Engineering Services Group of NPCIL. The activities and responsibilities of the group are discussed

  13. The Romanian educational system in nuclear engineering field - experience and new approaches

    International Nuclear Information System (INIS)

    In this paper we would like to present the actual status of the education in the nuclear engineering field at 'Pantholic' University Bucharest, Romania, Power Engineering Faculty, Nuclear Power Plant Department, and also the efforts of integration of the educational system of Romania into the international system and the development of new concepts concerning the education of the new specialists generation. (authors)

  14. Nuclear Science and Engineering education at the Delft University of Technology

    International Nuclear Information System (INIS)

    There is a national awareness in the Netherlands for strengthening education in the nuclear sciences, because of the ageing workforce, and to ensure competence as acceptability increases of nuclear power as an option for diversification of the energy supply. This may be reflected by the rapidly increasing number of students at the Delft University of Technology with interest in nuclear science oriented courses, and related bachelor and MSc graduation projects. These considerations formed the basis of the Nuclear Science and Engineering concentration, effectively starting in 2009. The programme can be taken as focus of the Research and Development Specialisation within the Master Programme in Applied Physics or as a Specialisation within the Master's Programme in Chemical Engineering. Both programmes require successful completion of a total of 120 ECTS study points, consisting of two academic years of 60 ECTS (1680 hours of study). Of that total, 100 ECTS are in the field of Nuclear Science and Engineering, depending on students choices within the programme, including a (industrial) internship, to be taken in companies all over the world. In Chemical Engineering, there is a compulsory design project during which a product or process should be developed. Both programmes also require a final graduation project. In both curricula, Nuclear Science and Engineering comprises compulsory and elective courses, which allow students to focus on either health or energy. Examples of courses include Nuclear Science, Nuclear Chemistry, Nuclear Engineering, Reactor Physics, Chemistry of the Nuclear Fuel Cycle, Medical Physics and Radiation Technology and Radiological Health Physics. (Author)

  15. Lessons Learned on University Education Programs of Chemical Engineering Principles for Nuclear Plant Operations - 13588

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Jun-hyung [Department of Nuclear and Energy System, Dongguk University, Gyeongju Campus, Gyeongju, 780-714 (Korea, Republic of)

    2013-07-01

    University education aims to supply qualified human resources for industries. In complex large scale engineering systems such as nuclear power plants, the importance of qualified human resources cannot be underestimated. The corresponding education program should involve many topics systematically. Recently a nuclear engineering program has been initiated in Dongguk University, South Korea. The current education program focuses on undergraduate level nuclear engineering students. Our main objective is to provide industries fresh engineers with the understanding on the interconnection of local parts and the entire systems of nuclear power plants and the associated systems. From the experience there is a huge opportunity for chemical engineering disciple in the context of giving macroscopic overview on nuclear power plant and waste treatment management by strengthening the analyzing capability of fundamental situations. (authors)

  16. Lessons Learned on University Education Programs of Chemical Engineering Principles for Nuclear Plant Operations - 13588

    International Nuclear Information System (INIS)

    University education aims to supply qualified human resources for industries. In complex large scale engineering systems such as nuclear power plants, the importance of qualified human resources cannot be underestimated. The corresponding education program should involve many topics systematically. Recently a nuclear engineering program has been initiated in Dongguk University, South Korea. The current education program focuses on undergraduate level nuclear engineering students. Our main objective is to provide industries fresh engineers with the understanding on the interconnection of local parts and the entire systems of nuclear power plants and the associated systems. From the experience there is a huge opportunity for chemical engineering disciple in the context of giving macroscopic overview on nuclear power plant and waste treatment management by strengthening the analyzing capability of fundamental situations. (authors)

  17. The anticentre old open clusters Berkeley 27, Berkeley 34, and Berkeley 36: new additions to the BOCCE project

    CERN Document Server

    Donati, P; Cignoni, M; Cocozza, G; Tosi, M

    2012-01-01

    In this paper we present the investigation of the evolutionary status of three open clusters: Berkeley 27, Berkeley 34, and Berkeley 36, all located in the Galactic anti-centre direction. All of them were observed with SUSI2@NTT using the Bessel B, V, and I filters. The cluster parameters have been obtained using the synthetic colour-magnitude diagram (CMD) method i.e. the direct comparison of the observational CMDs with a library of synthetic CMDs generated with different evolutionary sets (Padova, FRANEC, and FST). This analysis shows that Berkeley 27 has an age between 1.5 and 1.7 Gyr, a reddening E(B-V) in the range 0.40 and 0.50, and a distance modulus (m-M)_0 between 13.1 and 13.3; Berkeley 34 is older with an age in the range 2.1 and 2.5 Gyr, E(B-V) between 0.57 and 0.64, and (m-M)_0 between 14.1 and 14.3; Berkeley 36, with an age between 7.0 and 7.5 Gyr, has a reddening E(B-V)~0.50 and a distance modulus (m-M)_0 between 13.1 and 13.2. For all the clusters our analysis suggests a sub-solar metallicity ...

  18. Computer aided training in nuclear power engineering at the Gdansk Technical University

    International Nuclear Information System (INIS)

    The Faculty of Electrical Engineering of the Gdansk Technical University has organized post-graduate studies in nuclear power engineering in cooperation with the Institute of Nuclear Research at Swierk since 1973. Post-graduate courses in nuclear power plant construction and design were organized twice. Between 1986 and 1990, prototype software was developed for aiding lectures, self-teaching and knowledge testing in the following fields: 1) dynamics and control of nuclear reactors; 2) simulators of nuclear power plant basic systems (reactor, steam generator, steam turbine, and synchronous generator). (Z.S.) 2 refs

  19. 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;…

  20. Evaluating physical protection systems of licensed nuclear facilities using systems engineered inspection guidance

    International Nuclear Information System (INIS)

    The Lawrence Livermore National Laboratory (LLNL) and the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) have applied a systems engineering approach to provide the NRC Office of Inspection and Enforcement (IE) with improved methods and guidance for evaluating the physical protection systems of licensed nuclear facilities

  1. The Berkeley Digital Seismic Network

    Science.gov (United States)

    Romanowicz, B.; Dreger, D.; Neuhauser, D.; Karavas, W.; Hellweg, M.; Uhrhammer, R.; Lombard, P.; Friday, J.; Lellinger, R.; Gardner, J.; McKenzie, M. R.; Bresloff, C.

    2007-05-01

    Since it began monitoring earthquakes in northern California 120 years ago, the Berkeley Seismological Laboratory (BSL) has been striving to produce the highest quality and most complete seismic data possible in the most modern way. This goal has influenced choices in instrumentation, installation and telemetry, as well as the investment in expertise and manpower. Since the transition to broadband (BB) instrumentation in the mid- 1980s and to a fully digitally telemetered network in the early 1990s, we have continued these efforts. Each of our 25 BB installations includes three component BB seismometers (STS-1s or STS-2) and digital accelerometers to capture the full range of ground motion from distant teleseisms to large, nearby earthquakes (almost 250 dB). The ground motion is recorded on-site by 24 bit dataloggers. Additional environmental parameters, such as temperature and pressure, are also monitored continuously. Many stations record also C-GPS data that is transmitted continuously to the BSL via shared real-time telemetry. The BDSN's first stations were installed in abandoned mines. In the last 15 years, we developed installations using buried shipping containers to reduce environmental noise and provide security and easy access to the equipment. Data are transmitted in real-time at several sampling rates to one or more processing centers, using frame relay, radio, microwave, and/or satellite. Each site has 7-30 days of onsite data storage to guard against data loss during telemetry outages. Each station is supplied with backup batteries to provide power for 3 days. The BDSN real-time data acquisition, earthquake analysis and archiving computers are housed in a building built to "emergency grade" seismic standards, with air conditioning and power backed up by a UPS and a large generator. Data latency and power are monitored by automated processes that alert staff via pager and email. Data completeness and timing quality are automatically assessed on a daily

  2. Aspects of consolidation of engineering capability related to nuclear power plants

    International Nuclear Information System (INIS)

    A major interest of countries launching nuclear program is to consolidate an engineering capability for Nuclear Power Plants design by performing part of the engineering services locally. A decade of nuclear power plant engineering and construction has exposed Brazilian architect-engineers to this new challenge. To cope with it, technology sources were identified, agreements were made and transfer is going on between foreign and local companies. Services performed by Brazilian architect-engineers are summarized. Foreign technology must be judiciously examined before implementation in a different environment. The receiver has to be prepared to develop his own capabilities and absorb the know-how being offered, taking into consideration the local engineering experience and construction practices. Some of the problems faced are outlined herein. The performed efforts brought Brazilian architect-engineers to a consolidated level of experience. (Author)

  3. Berkeley Lab Laser Accelerator (BELLA) facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Berkeley Lab Laser Accelerator (BELLA) facility (formerly LOASIS) develops advanced accelerators and radiation sources. High gradient (1-100 GV/m) laser-plasma...

  4. 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.

  5. 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.

  6. Generating human resources in nuclear engineering in India: need of the hour

    International Nuclear Information System (INIS)

    With the fast growth of energy requirement scenario, particularly, in India with limited dependence on fossil power and increased emphasis on green power we have lots of nuclear power plant and associated projects in pipeline. This requires enormous human resources trained and qualified in nuclear engineering who will be engaged in all aspects of nuclear plant projects right from conceptualization, design, construction, development, operation, maintenance till decommissioning. As on today, Department of Atomic Energy (DAE) in Government of India is almost the only agency catering to this need. DAE grooms graduate engineers from various disciplines and postgraduates from sciences, specially, Physics and Chemistry. But, it takes enough financial resources and full 1-year duration past graduation from Indian Government. Even after imparting training to these freshly recruited DAE employees, sizeable chunk of the population quit DAE for better prospect such as higher studies abroad, management studies, IT profession etc. Also, the people trained in nuclear engineering are fewer in number than required and the gap would be increasingly large as time progresses and increasing number of nuclear plants would be constructed/operational. Comparatively larger number of engineering graduates currently produced in India are in Computer Engineering/Information Technology rather than in conventional disciplines like Civil, Mechanical, Electrical, Electronics and Telecommunications Engineering. This poses another problem of orienting/motivating the manpower in nuclear fields. Considering these problems the author proposes to produce and develop nuclear engineering graduates directly in the academic institutions which will help the nation in reducing the gap between the increasing demand of manpower in view of large number of nuclear plants in the pipeline and the availability of the nuclear engineers. Even large number of industries related to manufacturing and consultancy also

  7. 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

  8. 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.

  9. 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)

  10. Proposal of experimental facilities for studies of nuclear data and radiation engineering in the Intense Proton Accelerator Project

    CERN Document Server

    Baba, M; Nagai, Y; Ishibashi, K

    2003-01-01

    A proposal is given on the facilities and experiments in the Intense Proton Accelerator Project (J-PARC) relevant to the nuclear data and radiation engineering, nuclear astrophysics, nuclear transmutation, accelerator technology and space technology and so on. (3 refs).

  11. Application of integrated computer-aided engineering for design, construction and operation of nuclear power plant

    International Nuclear Information System (INIS)

    Computer-aided-engineering (CAE) is an essential tool for modern nuclear power plant engineering. It greatly varies in definition, application, and technology from project to project and company to company. Despite the fast growing technologies and applications of CAE, its complexty and variety have thrown aonther puzzle to management of a nuclear project. Without due consideration of an integrated CAE system in early planning stage, the overall efficiency of a nuclear project would slow down due to the inefficiency in data flow. In this paper, practices and perspectives of CAE appliation are discussed under the Korea Power Engineering Company (KOPEC) philosophy in CAE approach. (author)

  12. The fifth conference on nuclear science and engineering in Australia, 2003. Conference handbook

    International Nuclear Information System (INIS)

    The theme of the fifth Nuclear Science and Engineering in Australia conference was 'Building on 100 years of Nuclear Science and Technology'. During the six main sessions the following topics were presented: Nuclear research and progress on major nuclear facilities, including the ANSTO Research Replacement Reactor, the Australian synchrotron and irradiation facilities; Uranium and waste management; Radiation Protection and Nuclear safety; Safeguards and Security; Nuclear Power in the Asia/Pacific region and prospects for Australia. The opening address, given by Mr Peter McGauran, Minister for Science was followed by Dr Robin Batterham, Australian Chief Scientist's introductory address. Papers included in the handbook were separately indexed

  13. Review on the application of system engineer model in nuclear power plant

    International Nuclear Information System (INIS)

    system engineer was adopted deeply and play important roles in nuclear power plants in United States and Canada, the plant performance indicates that system engineer mode is a good practice. Qinshan CANDU nuclear power plant, established the system engineer mode since commissioning, as a core, system engineer took charge of the preparation of commissioning procedures, organization, coordination and guidance of commissioning execution. Unit 1 was put into commercial operation 43 days in advance and 112 days ahead of schedule for Unit 2 with excellent quality. Commissioning period are just 10.5 and 7.8 months for both Units respectively. Which is the shortest record in the history of CANDU nuclear power plant commissioning up to now. During operation, systems engineer has strength in routine operating and units reliability improvement. Based on the practice of Qinshan CANDU nuclear power plant commissioning and production technical management, the main form of the article in the era of knowledge: its characteristics and advantage and operating mode of the system engineer mode. System engineer is different from project engineer, he act as the master of systems and takes full responsibility for systems technical management. System engineer should do many jobs and improvement schedule to ensure his system in health status. System health monitor is a basic tool in system management, which is useful for equipment performance improvement. At last, the author made a forecast and comment on the prospects for the system engineer in the future. (author)

  14. The nuclear engineering programmes at the Royal Military College of Canada. Part I

    International Nuclear Information System (INIS)

    The last years have been eventful for the staff and students in the nuclear engineering programmes at the Royal Military College of Canada (RMC) in Kingston, Ontario. Among the several changes is the accessibility of the graduate programmes to civilian (Canadian citizens) students, a fact that is little known outside RMC since, in the past, these graduate programmes were intended only for military personnel. Another major event is the accreditation of the graduate programmes offered by the Department of Chemistry and Chemical Engineering(chemical, nuclear and environmental science and engineering) by the Ontario Council of Graduate Studies. The teaching and research staff share the following research areas: radiochemistry and neutron activation analysis, radiation effects on materials, radiation processing of polymers, neutron radiography, nuclear reactor simulation, analysis and design, CANDU fuel bundle optimal design, nuclear fuel cycles and management, nuclear fuel engineering and behaviour, including fission product release modelling, artificial intelligence applications to nuclear systems, nuclear accident response, nuclear radiation detection and measurement, health physics, dosimetry and radiation protection and nuclear reactor control

  15. Developing of database on nuclear power engineering and purchase of ORACLE system

    International Nuclear Information System (INIS)

    This paper presents a point of view according development of database on the nuclear power engineering and performance of ORACLE database manager system. ORACLE system is a practical database system for purchasing

  16. Importance of Research Reactors in Human Capacity Building in Nuclear Science and Engineering

    International Nuclear Information System (INIS)

    This oral presentation describes the robust utilization program of a university reactor in the United States, particularly through agreements for human capacity building in nuclear engineering and reactor operation. (author)

  17. Brief 68.1 Nuclear Engineering Enrollments and Degrees Survey, 2010 Data

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Don Johnson, Analysis and Evaluation, Science Education Programs

    2011-07-28

    The survey includes degrees granted between September 1, 2009 and August 31, 2010, and fall 2010 enrollments. Thirty-two academic programs reported having nuclear engineering programs during 2010, and data was obtained from all thirty-two.

  18. 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.

  19. ''Perspectives in nuclear technology'': recruiting young scientists and engineers

    International Nuclear Information System (INIS)

    Securing competence in nuclear technology is a topic of great interest especially because the preservation and promotion of scientific and technical know-how in Germany are particularly important under conditions of an opt-out of the use of nuclear power. In the light of decreasing numbers of graduates from courses in nuclear science and technology, positive action is indicated. For the first time, the Deutsches Atomforum e.V., together with major partners in cooperation, therefore organized a colloquy last year on 'Perspectives in Nuclear Technology'. Young students of various disciplines were given an opportunity to obtain in-depth information about nuclear power as part of the entire field of energy supply by attending lectures, round-table discussions, and on-site events. Because of the positive response elicited by that first event, another 'Perspectives in Nuclear Technology' colloquy will be held in 2003. (orig.)

  20. The application and developments for the artificial intelligence in the nuclear engineering

    International Nuclear Information System (INIS)

    The general situations of the research developing artificial intelligence in the nuclear engineering are introduced, and the expert systems and its developing direction which include the failure diagnosis, control and operation, maintenance, alarm and display, accident management for nuclear reactors and the robots are briefly discussed

  1. 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.

  2. Program plan for US Department of Energy support for nuclear engineering education

    International Nuclear Information System (INIS)

    This document describes the plan developed to address the growing concern for the continued deterioration of nuclear engineering education in the United States and its ability to meet the manpower demands for this Nation's work force requiring nuclear related talent in the foreseeable future

  3. Your Career and Nuclear Weapons: A Guide for Young Scientists and Engineers.

    Science.gov (United States)

    Albrecht, Andreas; And Others

    This four-part booklet examines various issues related to nuclear weapons and how they will affect an individual working as a scientist or engineer. It provides information about the history of nuclear weapons, about the weapons industry which produces them, and about new weapons programs. Issues are raised so that new or future graduates may make…

  4. Annual Technical Report - Nuclear Engineering Institute/ Dept. of Physics (IEN/DEFI) 1988

    International Nuclear Information System (INIS)

    The researches carried out by physics department of Nuclear Engineering Institute(IEN)/Brazilian CNEN are presented. The researches in nuclear physics, isotope production and irradiation damages using CV-28 cyclotron which accelerates protons, deuterons, helium and alpha particles with maximum energies of 24, 14, 36 and 28 MeV, respectively are described. (M.C.K.)

  5. The romanian educational system in nuclear engineering field - experience and new approaches

    International Nuclear Information System (INIS)

    In this paper we would like to present the actual status of the education in the nuclear engineering field at 'POLITEHNICA' University Bucharest, Nuclear Power Plant Department, and also the efforts of integration of the educational system of Romania into the international system and the development of new concepts concerning the education of the new specialists generation. (authors)

  6. Development and application of the ultrasonic technologies in nuclear engineering

    International Nuclear Information System (INIS)

    Efficiency of some traditional chemical technologies in different areas could be significantly increased by adding ultrasonic treatment. For example, ultrasonic treatment was found to improve make-up water systems, decontamination procedures, etc. Improvement of traditional chemical technologies with implementation of ultrasonic treatment has allowed to significantly reducing water waste, including harmful species and radioactive products. The report shows the examples of the recent ultrasonic technology development and application in Russian nuclear engineering. They are as follows: - Preliminary cleaning of surfaces of in-pile parts (e.g. control sensors) prior to their assemblage and welding - Decontamination of grounds and metal surfaces of components with a complex structure -Decrease in sliding friction between fuel rods and grids during VVER reactor fuel assembly manufacturing -Removal of deposits from reactor fuel surfaces in VVER-440s -Increasing the density and strength of pressed sintered items while making fuel pellets and fuel elements, especially mixed-oxide fuel Surface cleanness is very important for the fuel assembly manufacturing, especially prior to welding. An ultrasonic technology for surface cleaning (from graphite and other lubricants, oxides etc.) was developed and implemented. The ultrasonic cleaning is applicable to the parts having both simple shape and different holes. Ultrasonic technology has allowed to improve the surface quality and environmental safety. Ultrasonic treatment appears to be expedient to intensify the chemical decontamination of solid radioactive waste from grounds of different fractions to metallic components. Ultrasonic treatment reduces the decontamination process duration up to 100 times as much. Excellent decontamination factor was received even for the ground fractions below 1 mm. It should be noted that alternative decontamination techniques (e.g. hydraulic separation) are poorly applicable for such ground

  7. Nuclear engineering, health physics, and radioactive waste management fellowship program: Summary of program activities: Nuclear engineering and health physics fellowship, 1985-1986

    International Nuclear Information System (INIS)

    Progress is reported in the nuclear engineering and health physics elements of the fellowship program. Statistics are given on numbers of student applications and new appointments, the degree areas of applicants, GPA and GRE score averages of the fellows, and employment of completed fellows

  8. Berkeley Foundation for Opportunities in Information Technology: A Decade of Broadening Participation

    Science.gov (United States)

    Crutchfield, Orpheus S. L.; Harrison, Christopher D.; Haas, Guy; Garcia, Daniel D.; Humphreys, Sheila M.; Lewis, Colleen M.; Khooshabeh, Peter

    2011-01-01

    The Berkeley Foundation for Opportunities in Information Technology is a decade-old endeavor to expose pre-college young women and underrepresented racial and ethnic minorities to the fields of computer science and engineering, and prepare them for rigorous, university-level study. We have served more than 150 students, and graduated more than 65…

  9. Applications of engineering simulators in the nuclear power industry

    International Nuclear Information System (INIS)

    Full-scope replica operator training simulators, when designed and built to conserve the plant design database, can provide ideal testbeds for the growing number of Information Technology systems being proposed for nuclear power stations. An appropriate simulator design philosophy and some sample applications used during the Torness nuclear power station commissioning are described. (author)

  10. Introduction to digital instrumentation and control techniques used in nuclear engineering

    International Nuclear Information System (INIS)

    For the past 8 yr, the nuclear engineering department at Pennsylvania State University has been teaching a digital interfacing class at the undergraduate (senior) level. With the ever-increasing use of computers in the nuclear engineering area (such as in the use of automated data acquisition systems) and the complexity of control instrumentation, more than a cursory introduction into electronics and computer controls is needed. Because of the ever-increasing popularity, and hence importance, of IBM-PC compatible microcomputers in the engineering fields, the program has been adapted to the Intel 8086 microprocessor. Courses such as this one are helpful in ensuring the students have an adequate design and practice base as required by accrediting groups. The course, is composed of three parts: (1) machine code/assembly language, (2) interfacing, and (3) final project. Experience demonstrates that a course of this inherent complexity can successfully be taught within a nuclear engineering curriculum without extensive prerequisites. The important ingredient is to treat nuclear engineering students for exactly what they are, engineers. By having them use their creativity and adaptability, they can successfully integrate the digital interfacing techniques now routinely used in the nuclear industry

  11. Status of University of Cincinnati reactor-site nuclear engineering graduate programs

    International Nuclear Information System (INIS)

    The University of Cincinnati (UC) nuclear engineering program faculty has now had 12 yr of experience in delivering reactor-site educational programs to nuclear power plant technical personnel. Currently, with the sponsorship of the Toledo-Edison Company (TED), we are conducting a multiyear on-site graduate program with more than 30 participants at the Davis-Besse nuclear power plant. The program enables TED employees with the proper academic background to earn a master of science (MS) degree in nuclear engineering (mechanical engineering option). This paper presents a brief history of tile evolution of UC reactor-site educational programs together with a description of the progress of the current program

  12. Recent developments in on-site nuclear engineering graduate programs at the University of Cincinnati

    International Nuclear Information System (INIS)

    The University of Cincinnati (UC) Department of Mechanical, Industrial, and Nuclear Engineering with the sponsorship of the Toledo-Edison Company (TED) has undertaken a new multiyear on-site graduate program at the Davis-Besse nuclear power plant. The program enables TED employees with the proper academic background to earn a master of science (MS) degree in nuclear engineering (mechanical engineering option). In addition, with management approval, selected individual courses may be taken without enrolling in the overall program. One objective of the program is to enhance the understanding and engineering skills of the participants so that this knowledge may be applied to their professional positions. To this end, appropriate plant-specific examples and problems are incorporated into each course, enhancing the technical staff's understanding of the practical applications of the principles presented

  13. An Historical Perspective of the NERVA Nuclear Rocket Engine Technology Program

    Science.gov (United States)

    Robbins, W. H.; Finger, H. B.

    1991-01-01

    Nuclear rocket research and development was initiated in the United States in 1955 and is still being pursued to a limited extent. The major technology emphasis occurred in the decade of the 1960s and was primarily associated with the Rover/NERVA Program where the technology for a nuclear rocket engine system for space application was developed and demonstrated. The NERVA (Nuclear Engine for Rocket Vehicle Application) technology developed twenty years ago provides a comprehensive and viable propulsion technology base that can be applied and will prove to be valuable for application to the NASA Space Exploration Initiative (SEI). This paper, which is historical in scope, provides an overview of the conduct of the NERVA Engine Program, its organization and management, development philosophy, the engine configuration, and significant accomplishments.

  14. Nuclear engineering education in the United States: The first 50 years

    International Nuclear Information System (INIS)

    This paper will discuss recent trends in the nuclear engineering education infrastructure in the United States. In the last several years political, economic and technical issues have been addressed and nuclear technology appears poised to resume growing again. In order to understand the current situation it is important to give a brief historical perspective covering the six decades since 1954. There was an understandable optimistic outlook. In only a few years demonstration nuclear power plants were built. In the following decade much progress was made and commercial plant orders increased substantially in number and in size. There were going to LWRs, GCRs, LMFBRs, reprocessing, waste buried in salt mines. The first nuclear engineering academic programs and university research reactors were established in the 1950s. Academic expertise was primarily in the areas of physics and in mechanical and chemical engineering. The government supported these university programs. The American Nuclear Society was established as the professional society for the dissemination of scholarly work. This picture changed dramatically in the 1970's and in the following decades. Most significantly, the oil crises of the 1970's sent the country into a deep recession. All this led to a tremendous over supply of planned power plants and resulted in delays, cancellations, and attendant cost increases. The technological issues unveiled by the Three Mile Island accident compounded these political and economic issues. Students stopped selecting nuclear as a major field of study. Nuclear programs and research reactors were being closed. From a high of 70 reactors, there are now only 23, and from over 50 nuclear academic programs there remain only about 24. Undergraduate enrollments, which once peaked at nearly 2000, fell to only a few hundred. This paper will provide statistical information quantifying the aforementioned trends. It will summarize the various efforts of the DOE, the Institute for

  15. Proceedings of the Nuclear Engineering Science and Technology - NESTeT 2008 Transactions

    International Nuclear Information System (INIS)

    This important European Nuclear Society (ENS) conference is dedicated to networking in nuclear education and training across the fields of engineering, science and technology. An OECD study in 2000, 'Nuclear Education and Training: Cause for Concern?' recommended the following: -Governments have a strategic role to play in energy planning. Governments should contribute to, if not take responsibility for, integrated planning to ensure that necessary human resources are available. There should also be adequate resources for vibrant nuclear research and development programmes including modernisation of facilities; -The provision of basic and attractive educational programmes at university level is among the challenges of revitalising nuclear education; -Rigorous training programmes are needed to meet specific needs and exciting research projects should also be developed to attract quality students and employees to research institutes; -Industry, research institutes and universities need to work together to better co-ordinate efforts to encourage the younger generation and develop and promote a programme of collaboration in nuclear education and training. There should also be mechanisms for sharing best practices in promoting nuclear courses. The world is responding. From the Americas to Europe and Asia networks have been established to maintain nuclear knowledge and to ensure there is a suitably qualified nuclear workforce for the future. NESTet 2008 is designed to facilitate an exchange of information, collaboration and the sharing of best practices in nuclear education and training in engineering science and technology. (authors)

  16. 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)

  17. 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.

  18. 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.

  19. Nuclear EMP: ingredients of an EMP protection engineering methodology

    International Nuclear Information System (INIS)

    A fundamental methodology of electromagnetic pulse (EMP) protection engineering is described. Operations performed within the framework of this methodology are discussed. These operations, along with problem constraints and data, constitute the essential ingredients needed to implement the overall engineering methodology. Basic definitions and descriptions of these essential ingredients are provided. The issues discussed represent the first step in developing a methodology for protecting systems against EMP effects

  20. 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.

  1. The third conference on nuclear science and engineering in Australia, 1999. Conference handbook

    International Nuclear Information System (INIS)

    The Australian Nuclear Association has organised this third Conference in a biennial series with the theme: 'A Nuclear Renaissance'. The theme is based on our perception that nuclear science and technology is on the threshold of a major expansion after a period which many thought was the onset of the Dark Ages after the old Australian Atomic Energy Commission was abolished in 1987. Fortunately, nuclear science and technology was not abolished and the AAEC was replaced by the government with ANSTO, which the government has continued to support strongly. The most recent expression of this support has been the approval of nearly $300 millions in investment in a major Replacement Research Reactor to be operational in about 2005, and the establishment of the new regulatory body ARPANSA. The conference aims to review all of the major nuclear issues of importance to Australia as we enter the 21st Century. These include: uranium mining and upgrading; the management of nuclear waste; the plans for the future by the government's major nuclear research laboratory, operated by ANSTO, including plans for constructing a major Replacement Research Reactor at Lucas Heights, the status of safeguards and nuclear regulation in Australia now that the government has set up the Australian Radiation Protection and Nuclear Safety Agency, and the many and varied applications of nuclear science in Australia. The conference also presents the plans for nuclear research by the universities through the Australian Institute of Nuclear Science and Engineering, and features in particular the work at the Australian National University in Canberra

  2. Key methods for sustaining quality engineering data in nuclear power plants

    International Nuclear Information System (INIS)

    This paper discusses key methods for sustaining quality engineering data, the fundamental principles that these methods are based on, and the methods for supporting the performance of nuclear power plants by the provision of quality engineering data at all times. The concept of an 'engineering data foundation', and a Configuration Management data model are developed. The concepts and methods for managing the integrity of engineering data across many different databases and document systems are developed, including the key concepts of data-positions and data-values, Master Data and Copy Data, and the concept of a 'partnership between people and technology'. (author). 7 refs., 1 tab., 2 figs

  3. Development of EDG Engine Condition Diagnosis Logic in Korean Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byoung Oh; Choi, Kwang Hee; Lee, Sang Guk [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2012-05-15

    Through benchmarking using the excellent record of the nuclear power plants under operation in the United States and Europe and with the continuous development of nuclear-related technology, the Korea Hydro and Nuclear Power Co., LTD (KHNP) reached an average planned preventive maintenance period of 29.6 days in 2009. In addition, KHNP plans to reduce the planned preventive maintenance period at Korea standard nuclear plants (KSNPs) from 29.6 days to less than 21 days by 2014 through a combination of domestic research and development (R and D) and the introduction of the technical know-how applied in the very best overseas nuclear power plants (NPPs). Accordingly, it is necessary to reduce the inspection and maintenance periods of an emergency diesel generator (EDG), which are currently set in the planned preventive maintenance period. If the condition-based predictive maintenance (CBM) technology is applied to EDG engines, the maintenance period of an EDG will be shortened because engine maintenance is accomplished according to the engine condition under this plan. In this study, in the series of CBM program developments which will be applied to EDG engines, the development results of condition diagnosis logic to be applied to EDG engines for exiting domestic NPPs are introduced

  4. Politics and engineering in nuclear-energy installations

    International Nuclear Information System (INIS)

    The author gives a summarising report on the 1977 Reactor Conference where the review lectures gave information on the present social-political and polito-economic questions at issue on nuclear energy, such as the attitude of politicians in the democracy; the effects of zero growth and subdivision; indpendence of energy supply due to a national waste-disposal centre, and adaption of the economy to the changing requirements of the people. By statements on leasing and export finance, the necessity for state promotion and international cooperation in building up a reactor industry, as well as transfer of nuclear technology, he demonstrates the interlinking between political economy and the nuclear industry. He also reports on the state of the work in Germany on studying risks from nuclear power stations having pressure-water reactors; ensuring reliability of output and of the system; the tightening of high-temperature reactor development; the competitive position of nuclear energy, and the energy research programme in the Federal Republic of Germany. (orig.)

  5. Construction of a bibliographic information database for the nuclear engineering

    International Nuclear Information System (INIS)

    The major goal of the project is to develop a nuclear science database of materials that have been published in Korea and to establish a network system that will give relevant information to people in the nuclear industry by linking this system with the proposed National Science Technical Information Network. This project aims to establish a database consisted of about 1,000 research reports that were prepared by KAERI from 1979 to 1990. The contents of the project are as follows: 1. Materials Selection and Collection 2. Index and Abstract Preparation 3. Data Input and Transmission. This project is intended to achieve the goal of maximum utilization of nuclear information in Korea. (Author)

  6. THE YOUNG OPEN CLUSTER BERKELEY 55

    Energy Technology Data Exchange (ETDEWEB)

    Negueruela, Ignacio; Marco, Amparo, E-mail: ignacio.negueruela@ua.es, E-mail: amparo.marco@ua.es [Departamento de Fisica, Ingenieria de Sistemas y Teoria de la Senal, Universidad de Alicante, Apdo. 99, E-03080 Alicante (Spain)

    2012-02-15

    We present UBV photometry of the highly reddened and poorly studied open cluster Berkeley 55, revealing an important population of B-type stars and several evolved stars of high luminosity. Intermediate-resolution far-red spectra of several candidate members confirm the presence of one F-type supergiant and six late supergiants or bright giants. The brightest blue stars are mid-B giants. Spectroscopic and photometric analyses indicate an age 50 {+-} 10 Myr. The cluster is located at a distance d Almost-Equal-To 4 kpc, consistent with other tracers of the Perseus Arm in this direction. Berkeley 55 is thus a moderately young open cluster with a sizable population of candidate red (super)giant members, which can provide valuable information about the evolution of intermediate-mass stars.

  7. Political-social reactor problems at Berkeley

    International Nuclear Information System (INIS)

    For better than ten years there was little public notice of the TRIGA reactor at UC-Berkeley. Then: a) A non-student persuaded the Student and Senate to pass a resolution to request Campus Administration to stop operation of the reactor and remove it from campus. b) Presence of the reactor became a campaign-issue in a City Mayoral election. c) Two local residents reported adverse physical reactions before, during, and after a routine tour of the reactor facility. d) The Berkeley City Council began a study of problems associated with radioactive material within the city. e) Friends Of The Earth formally petitioned the NRC to terminate the reactor's license. Campus personnel have expended many man-hours and many pounds of paper in responding to these happenings. Some of the details are of interest, and may be of use to other reactor facilities. (author)

  8. Lawrence Berkeley Laboratory 1993 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    This annual Site Environmental Report summarizes Lawrence Berkeley Laboratory`s (LBL`s) environmental activities in calendar year (CY) 1993. The purpose of this report is to characterize site environmental management performance, confirm compliance status with environmental standards and requirements, and highlight significant programs and efforts. Its format and content are consistent with the requirements of the US Department of Energy (DOE) Order 5400.1, General Environmental Protection Program.

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

    International Nuclear Information System (INIS)

    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.

  10. 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...

  11. The interaction between basic science and engineering technology in the nuclear power field

    International Nuclear Information System (INIS)

    This paper explores the interaction between basic science and its application in engineering technology in the context of the author's experience in the nuclear power field. Popular and professional differences in the images of the scientist and engineer are first noted and their significance assessed. The problems and benefits of combining expertise from diverse backgrounds in major projects are then outlined with examples from the development of nuclear power. Interactions in measurement science are also discussed and finally suggestions are made for changes in the education of technical specialists which, it is hoped, would improve their responsiveness to the needs of society. (author)

  12. Post TMI-2 view on the responsibilities of nuclear engineering educators

    International Nuclear Information System (INIS)

    The Three Mile Island (TMI) accident of March 28, 1979 was the result of a complex set of interactions involving design deficiencies, equipment failure and human error. Nuclear engineering educators may need to accept responsibility for some of the underlying, industry-wide causes leading to the event. The many detailed investigations and recommendations following the accident are certain to have a significant impact on nuclear engineering education. Areas of impact include changes in curricula, increased demand for graduates, heavier involvement in utility staff training and education, and new approaches to university, industry, and societal interactions

  13. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    International Nuclear Information System (INIS)

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  14. Education and training of future nuclear engineers through the use of an interactive plant simulator

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) sponsors the development of nuclear reactor simulators for education, or arranges the supply of such simulation programs. Aware of this, the Department of Nuclear Engineering of the Universidad Politecnica de Madrid was provided in 2008 with the Interactive Graphical Simulator of the Spanish nuclear power plant Jose Cabrera, whose operation ceased definitively in 2006. According with the IAEA-TECDOC- 1411, the simulator is a Graphical Simulator, used for training of main control room personnel, technical support engineers, and operations management. This paper presents all the work performed at the Department to turn the simulator into a teaching/learning tool, to be use in the nuclear engineering studies following guidance found in: Shtub, A. Parush, T.T. Hewett 'The use of simulation in learning and teaching' (Int. J. Eng. Educ., 25(2), 2009, pp. 206-208). The experience obtained so far with the use of the simulator has been very successful. The graduate students involved in the development of the projects, practices and documents related with the simulator show a great interest for the work that they are doing making that the laboratory where the simulator is installed to be busy place. Regarding the undergraduate students, the practices in the simulator encourage them to follow the Nuclear Energy studies in the Engineering Schools, what is very rewarding for the Department professors. The simulator has proved to be an optimal tool to transfer the knowledge of the physical phenomena that are involved in the nuclear power plants, from the nuclear reactor to the whole set of systems and equipments on a nuclear power plant. It is also a relevant tool for motivation of the students, and to complete the theoretical lessons. This use of the simulator in the learning-teaching process meats also the criteria recommended for the Bologna adapted studies, as it helps to increase the private hands-on work of the student, and

  15. Education and training of future nuclear engineers through the use of an interactive plant simulator

    Energy Technology Data Exchange (ETDEWEB)

    Ahnert, C.; Cuervo, D.; Garcia-Herranz, N.; Aragones, J.M.; Cabellos, O.; Gallego, E.; Minguez, E.; Lorente, A.; Piedra, D. [Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid, Jose Gutierrez Abascal 2, 28006 Madrid (Spain); Rebollo, L.; Blanco, J. [Gas Natural-Union FENOSA, Avda. de San Luis 77, 28033 Madrid (Spain)

    2010-07-01

    The International Atomic Energy Agency (IAEA) sponsors the development of nuclear reactor simulators for education, or arranges the supply of such simulation programs. Aware of this, the Department of Nuclear Engineering of the Universidad Politecnica de Madrid was provided in 2008 with the Interactive Graphical Simulator of the Spanish nuclear power plant Jose Cabrera, whose operation ceased definitively in 2006. According with the IAEA-TECDOC- 1411, the simulator is a Graphical Simulator, used for training of main control room personnel, technical support engineers, and operations management. This paper presents all the work performed at the Department to turn the simulator into a teaching/learning tool, to be use in the nuclear engineering studies following guidance found in: Shtub, A. Parush, T.T. Hewett 'The use of simulation in learning and teaching' (Int. J. Eng. Educ., 25(2), 2009, pp. 206-208). The experience obtained so far with the use of the simulator has been very successful. The graduate students involved in the development of the projects, practices and documents related with the simulator show a great interest for the work that they are doing making that the laboratory where the simulator is installed to be busy place. Regarding the undergraduate students, the practices in the simulator encourage them to follow the Nuclear Energy studies in the Engineering Schools, what is very rewarding for the Department professors. The simulator has proved to be an optimal tool to transfer the knowledge of the physical phenomena that are involved in the nuclear power plants, from the nuclear reactor to the whole set of systems and equipments on a nuclear power plant. It is also a relevant tool for motivation of the students, and to complete the theoretical lessons. This use of the simulator in the learning-teaching process meats also the criteria recommended for the Bologna adapted studies, as it helps to increase the private hands-on work of the

  16. Engineer, procure, construct (EPC) for nuclear projects in OPG

    International Nuclear Information System (INIS)

    OPG is exploring the use of EPC contracts for Nuclear Plant Design Modifications. Although OPG has used EPC outside of the nuclear island, this new initiative will begin to use EPC inside the plant, including upgrades to existing stations and mid-life refurbishment of Darlington. Benchmarking has shown that apart from new build, nuclear utilities rarely use this method inside the plant so OPG is using a step-by-step approach starting with projects with low complexity and low plant impact. The expected benefits are reduced interfaces and a simplified accountability model leading to schedule and cost improvements and lower rework. Design packages that incorporate construction input before issue will be a significant improvement. OPG's early challenges in moving to EPC include clearly defining roles, responsibilities and interfaces between the vendors and OPG, and modifying governance to match the new model. OPG intends to oversee the work while holding the vendor accountable for needs skill development on both sides. Vendors are expected to establish an engaged organization with complete knowledge of plant conditions, processes and streamlined methods to gain operations input. Vendors are also expected to identify and fix any quality issues before the modifications are commissioned and to have an in-house corrective action program to continuously improve. Vendors' early challenges include presenting one face to OPG rather than a collection of joint venture partners. This presentation describes OPG's plans and early feedback on this exciting new initiative.

  17. Applying system engineering methods to site characterization research for nuclear waste repositories

    International Nuclear Information System (INIS)

    Nuclear research and engineering projects can benefit from the use of system engineering methods. This paper is brief overview illustrating how system engineering methods could be applied in structuring a site characterization effort for a candidate nuclear waste repository. System engineering is simply an orderly process that has been widely used to transform a recognized need into a fully defined system. Such a system may be physical or abstract, natural or man-made, hardware or procedural, as is appropriate to the system's need or objective. It is a way of mentally visualizing all the constituent elements and their relationships necessary to fulfill a need, and doing so compliant with all constraining requirements attendant to that need. Such a system approach provides completeness, order, clarity, and direction. Admittedly, system engineering can be burdensome and inappropriate for those project objectives having simple and familiar solutions that are easily held and controlled mentally. However, some type of documented and structured approach is needed for those objectives that dictate extensive, unique, or complex programs, and/or creation of state-of-the-art machines and facilities. System engineering methods have been used extensively and successfully in these cases. The scientific methods has served well in ordering countless technical undertakings that address a specific question. Similarly, conventional construction and engineering job methods will continue to be quite adequate to organize routine building projects. Nuclear waste repository site characterization projects involve multiple complex research questions and regulatory requirements that interface with each other and with advanced engineering and subsurface construction techniques. There is little doubt that system engineering is an appropriate orchestrating process to structure such diverse elements into a cohesive, well defied project

  18. Engineering Safety Aspects of the Protection of Nuclear Power Plants Against Sabotage (Chinese Edition)

    International Nuclear Information System (INIS)

    The IAEA helps to identify threats and vulnerabilities related to the security of nuclear and other radioactive material. However, it is the responsibility of States to provide for the physical protection of nuclear and other radioactive material and the associated facilities, to ensure the security of such material in transport, and to combat illicit trafficking and the inadvertent movement of radioactive material. This publication provides guidelines for the assessment of the engineering safety aspects of the protection of nuclear power plants against sabotage, including standoff attacks. This publication is the result of extensive dialogue between safety and security specialists within and outside the IAEA. It also takes into account feedback from regulatory agencies and design organizations. It expands on more general concepts concerning the physical protection of nuclear material and nuclear facilities against sabotage

  19. Framatome, from the nuclear engineering office to the international group

    International Nuclear Information System (INIS)

    A simple office of studies by its inceptions, Framatome became during 30 years an international and diversified group, a world nuclear leader, as designer-manufacturer, fuel supplier and servicing provider. It asserts itself also as a foreground actor in the industrial equipment and connections. This book not only presents an exciting and capital episode of the history of nuclear energy in France but it demonstrate also how an company with a little bit of chance, a lot of endeavour, a plenty of talent and a huge firmness succeeded in becoming an incontestable reference authority in its sector. Staking on technological choices, although different from the creeds inspiring the French decision makers, Framatome has obtained its first orders ahead other French companies, much more powerful and prestigious at the time. The impressive Framatome evolution is presented along six chapters entitled as follows: 1. Beginning of nuclear power; 2. Technological challenge; 3. Industrial challenge; 4. Sectorial challenge; 5. Management challenge; 6. Future. The following four witness' papers are inserted with in the main text: 1. Beginning of Framatome (by P. Boulin); 2. The difficult choice for the PWR system (by M. Boiteux); 3. Impossibly is not French (by A. Giraud); 4. A fabulous common effort (by M. Hug). The book is addressed to the public at large but aims also at the Company's personnel, both the people witnessing the Company's beginning and the newcomers who should know the social body they have chosen to join and to the effort of which they have to contribute with their inventiveness and dynamism

  20. Verification of structural analysis computer codes in nuclear engineering

    International Nuclear Information System (INIS)

    Sources of potential errors, which can take place during use of finite element method based computer programs, are described in the paper. The magnitude of errors was defined as acceptance criteria for those programs. Error sources are described as they are treated by 'National Agency for Finite Element Methods and Standards (NAFEMS)'. Specific verification examples are used from literature of Nuclear Regulatory Commission (NRC). Example of verification is made on PAFEC-FE computer code for seismic response analyses of piping systems by response spectrum method. (author)

  1. Quality and Reliability Aspects in Nuclear Power Reactor Fuel Engineering

    International Nuclear Information System (INIS)

    In order to decrease costs and increase competitiveness, nuclear utilities use more challenging operational conditions, longer fuel cycles and higher burnups, which require modifications in fuel designs and materials. Different aspects of quality assurance and control, as well as analysis of fuel performance have been considered in a number of specialized publications. The present publication provides a concise but comprehensive overview of all interconnected quality and reliability issues in fuel fabrication, design and operation. It jointly tackles technical, safety and organizational aspects, and contains examples of state of the art developments and good practices of coordinated work of fuel designers, vendors and reactor operators

  2. Effect of nuclear power technology on development of engineering geodesy

    International Nuclear Information System (INIS)

    The role is described of geodesy in the sphere of nuclear power plant safety, the GAU, i.e., maximum acceptable accident concept is briefly explained and three basic conditions (redundancy, diversity, fail-safe operation) are listed for safety facilities. The necesity of systematic measurement of changes in the geometrical properties of an object is shown on an example of a failure consisting of a sudden double breakage of the cooling pipe in the reactor primary coolant circuit. Theoretical relations are shown for calculating redundancy from measured values. (E.J.). 1 fig., 1 tab., 4 refs

  3. The Nuclear Department, Royal Naval School of Marine Engineering - Provision of nuclear education and training to the naval nuclear propulsion programme and beyond

    International Nuclear Information System (INIS)

    Full text: The Nuclear Department (ND) of the Royal Naval School of Marine Engineering was formed within HMS SULTAN on 1 April 2001, following the integration of SULTAN's existing Nuclear Training Group and the Department of Nuclear Science and Technology, relocated from the (old) Royal Naval College Greenwich, London in October 1998. Both groups have a distinguished history with officers courses established at Greenwich in 1959 and ratings training established at HMS SULTAN in 1963. This collocation of nuclear systems' training, academics, and research placed, for the first time, the majority of Naval Nuclear Propulsion Programme (NNPP) shore based education and training on the one site. As systems training and education in nuclear reactor technology are integral to most courses offered by the Department, the integration enhanced aspirations to establish a centre of excellence in nuclear engineering within the Royal Navy School of Marine Engineering, which is part of the Naval Recruiting and Training Agency. The ND is also an Associated Institution of the University of Surrey with which it has had an alliance for almost 20 years. The Department's primary purpose is to provide education and training for all naval and civilian personnel appointed to the NNPP and its secondary purpose is to provide research, consultancy and expert advice in support of the Programme. With over 40 years proven experience in the provision of high quality nuclear education and systems training the ND presently offers over 45 scheduled courses in all key disciplines, from 'cradle to grave', to a broad group of key customers. Five academic courses attract post-graduate qualifications, that are validated by the University of Surrey, whilst the majority of ND's NNPP systems training courses are necessary prerequisites for both officers and ratings in order to qualify as nuclear submarine reactor and propulsion plant watch-keepers. The ND has a number of facilities and equipments that support

  4. 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.

  5. Strategy and main directions of the Russian nuclear power engineering development in the first half of the 21-st century

    International Nuclear Information System (INIS)

    The directions of the state policy of Russia on nuclear power engineering development in the 21-st century are considered. The conclusion is made, that the state energy policy, in realization, whereof the nuclear power engineering should play the key role, as the factor of energy supply stability, is necessary for assuring the energy security of Russia

  6. Construction and engineering report for advanced nuclear fuel development facility

    International Nuclear Information System (INIS)

    The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m2, basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

  7. Construction and engineering report for advanced nuclear fuel development facility

    Energy Technology Data Exchange (ETDEWEB)

    Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H

    2003-09-01

    The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m{sup 2}, basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc.

  8. 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.

  9. Annual Technical Report - Nuclear Engineering Institute/Dept. of Physics (IEN/DEFI) 1985

    International Nuclear Information System (INIS)

    The annual technical report of the Dept. of Physics of the Nuclear Engineering Institut (IEN/DEFI) is presented. The report describes the scientific and technical activities developed at this Institute, such as research, projects, development, personnel involved, support to research and the publications issued in 1985. (M.I.)

  10. Annual report of Radiation Laboratory Department of Nuclear Engineering Kyoto University for fiscal 1993

    International Nuclear Information System (INIS)

    This publication is the collection of the papers presented research activities of Radiation Laboratory, Department of Nuclear Engineering, Kyoto University during the 1993 academic/fiscal year (April, 1993 - March, 1994). The 47 of the presented papers are indexed individually. (J.P.N.)

  11. The RA nuclear research reactor at VINCA Institute as an engineering and scientific challenge

    International Nuclear Information System (INIS)

    The RA nuclear research at the Vinca Institute of Nuclear Sciences is the largest nuclear research facility in Yugoslavia and belongs to that generation of research reactors which have had an important contribution to nuclear technology development. As these older reactors were generally not built to specific nuclear standards, new safety systems had to be installed at the RA reactor for a renewal of its operating licence in 1984 and it was shut down, after 25 years of operation. Although all the required and several additional systems were built for the restart of the RA reactor, a disruption of foreign delivery of new control equipment caused its conversion to a 'dormant' facility, and it is still out of operation. Therefore, the future status of the RA reactor presents an engineering and scientific challenge to the engineers and scientists from Yugoslavia and other countries that may be interested to participate. To attract their attention on the subject, principal features of the RA reactor and its present status are described in detail, based on a recent engineering economic and safety evaluation. A comparative review of the world research reactors is also presented.(author)

  12. 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.

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

    International Nuclear Information System (INIS)

    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

  14. Evaluation of Recent Upgrades to the NESS (Nuclear Engine System Simulation) Code

    Science.gov (United States)

    Fittje, James E.; Schnitzler, Bruce G.

    2008-01-01

    The Nuclear Thermal Rocket (NTR) concept is being evaluated as a potential propulsion technology for exploratory expeditions to the moon, Mars, and beyond. The need for exceptional propulsion system performance in these missions has been documented in numerous studies, and was the primary focus of a considerable effort undertaken during the Rover/NERVA program from 1955 to 1973. The NASA Glenn Research Center is leveraging this past NTR investment in their vehicle concepts and mission analysis studies with the aid of the Nuclear Engine System Simulation (NESS) code. This paper presents the additional capabilities and upgrades made to this code in order to perform higher fidelity NTR propulsion system analysis and design, and a comparison of its results to the Small Nuclear Rocket Engine (SNRE) design.

  15. 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.

  16. 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.

  17. Lawrence Berkeley Laboratory 1994 site environmental report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    The 1994 Site Environmental Report summarizes environmental activities at Lawrence Berkeley Laboratory (LBL) for the calendar year (CY) 1994. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the Laboratory`s environmental management programs when measured against regulatory standards and DOE requirements. The report also discusses significant highlight and planning efforts of these programs. The format and content of the report are consistent with the requirements of the U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program.

  18. Lawrence Berkeley Laboratory 1994 site environmental report

    International Nuclear Information System (INIS)

    The 1994 Site Environmental Report summarizes environmental activities at Lawrence Berkeley Laboratory (LBL) for the calendar year (CY) 1994. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the Laboratory's environmental management programs when measured against regulatory standards and DOE requirements. The report also discusses significant highlight and planning efforts of these programs. The format and content of the report are consistent with the requirements of the U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program

  19. 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.

  20. Non-linear nuclear engineering models as genetic programming application

    International Nuclear Information System (INIS)

    This work presents a Genetic Programming paradigm and a nuclear application. A field of Artificial Intelligence, based on the concepts of Species Evolution and Natural Selection, can be understood as a self-programming process where the computer is the main agent responsible for the discovery of a program able to solve a given problem. In the present case, the problem was to find a mathematical expression in symbolic form, able to express the existent relation between equivalent ratio of a fuel cell, the enrichment of fuel elements and the multiplication factor. Such expression would avoid repeatedly reactor physics codes execution for core optimization. The results were compared with those obtained by different techniques such as Neural Networks and Linear Multiple Regression. Genetic Programming has shown to present a performance as good as, and under some features superior to Neural Network and Linear Multiple Regression. (author). 10 refs., 8 figs., 1 tabs

  1. 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.

  2. Role of the Vinca Institute in nuclear engineering and radiation protection education

    International Nuclear Information System (INIS)

    Education programmes in nuclear engineering and radiation protection in former Yugoslavia have been supported by comprehensive research and development and pertinent training of experts and students in the Vinca (former Boris Kidric) Institute of nuclear sciences and abroad. Two research reactors were constructed and operated in the Vinca Institute since 1958. Adopted law on ban for NPP construction, isolation of the country due to the UN sanctions and weak economical situation deteriorated considerably the nuclear expertise in Serbia after 1989. Nuclear courses at the University were revoked, major research programmes were cancelled, RA research reactor in the Vinca Institute was shut down and many experts left the country. A novel nuclear programme related to remedial of nuclear and radiation safety in the Vinca Institute has been launched in 2003. This paper emphasizes the need for nuclear expertise, the lack of nuclear professionals to carry out the new programme, the experience gained so far and point out a possible future creative role of the Vinca Institute in education of new experts in the country and abroad. (author)

  3. Three new bricks in the wall: Berkeley 23, Berkeley 31, and King 8

    CERN Document Server

    Cignoni, Michele; Bragaglia, Angela; Tosi, Monica

    2011-01-01

    A comprehensive census of Galactic open cluster properties places unique constraints on the Galactic disc structure and evolution. In this framework we investigate the evolutionary status of three poorly-studied open clusters, Berkeley 31, Berkeley 23 and King 8, all located in the Galactic anti-centre direction. To this aim, we make use of deep LBT observations, reaching more than 6 mag below the main sequence Turn- Off. To determine the cluster parameters, namely age, metallicity, distance, reddening and binary fraction, we compare the observational colour-magnitude diagrams (CMDs) with a library of synthetic CMDs generated with different evolutionary sets (Padova, FRANEC and FST) and metallicities. We find that Berkeley 31 is relatively old, with an age between 2.3 and 2.9 Gyr, and rather high above the Galactic plane, at about 700 pc. Berkeley 23 and King 8 are younger, with best fitting ages in the range 1.1-1.3 Gyr and 0.8-1.3 Gyr, respectively. The position above the Galactic plane is about 500- 600 pc...

  4. Careers in Data Science: A Berkeley Perspective

    Science.gov (United States)

    Koy, K.

    2015-12-01

    Last year, I took on an amazing opportunity to serve as the Executive Director of the new Berkeley Institute for Data Science (BIDS). After a 15-year career working with geospatial data to advance our understanding of the environment, I have been presented with a unique opportunity through BIDS to work with talented researchers from a wide variety of backgrounds. Founded in 2013, BIDS is a central hub of research and education at UC Berkeley designed to facilitate and nurture data-intensive science. We are building a community centered on a cohort of talented data science fellows and senior fellows who are representative of the world-class researchers from across our campus and are leading the data science revolution within their disciplines. Our initiatives are designed to bring together broad constituents of the data science community, including domain experts from the life, social, and physical sciences and methodological experts from computer science, statistics, and applied mathematics. While many of these individuals rarely cross professional paths, BIDS actively seeks new and creative ways to engage and foster collaboration across these different research fields. In this presentation, I will share my own story, along with some insights into how BIDS is supporting the careers of data scientists, including graduate students, postdocs, faculty, and research staff. I will also describe how these individuals we are helping support are working to address a number of data science-related challenges in scientific research.

  5. Research Programs in the Field of Nuclear Power Engineering and Technologies in the Republic of Kazakhstan

    International Nuclear Information System (INIS)

    In 1991 the Semipalatinsk Test Site (STS) was closed under the decree of President of the Republic of Kazakhstan, N.A. Nazarbayev. Later, the National Nuclear Center of the Republic of Kazakhstan (NNC RK) was established under President's decree 779 dated May 15 1992. A range of NNC RK activity was specified in the decree: ' To create National Nuclear Center of the Republic of Kazakhstan on the basis of the former Semipalatinsk Test Site and appropriate scientific organizations and facilities situated in the Republic of Kazakhstan with a view to conduct work on radiation safety and ecology, investigation of problems related to utilization and radioactive waste disposal, development work in the field of nuclear technology and nuclear power engineering'. Tasks outlined in this decree, later on, became the work program of NNC RK

  6. Ground Test Facility for Propulsion and Power Modes of Nuclear Engine Operation

    Energy Technology Data Exchange (ETDEWEB)

    Michael, WILLIAMS

    2004-11-22

    Existing DOE Ground Test Facilities have not been used to support nuclear propulsion testing since the Rover/NERVA programs of the 1960's. Unlike the Rover/NERVA programs, DOE Ground Test facilities for space exploration enabling nuclear technologies can no longer be vented to the open atmosphere. The optimal selection of DOE facilities and accompanying modifications for confinement and treatment of exhaust gases will permit the safe testing of NASA Nuclear Propulsion and Power devices involving variable size and source nuclear engines for NASA Jupiter Icy Moon Orbiter (JIMO) and Commercial Space Exploration Missions with minimal cost, schedule and environmental impact. NASA site selection criteria and testing requirements are presented.

  7. Main research results in the field of nuclear power engineering of the Nuclear Reactors and Thermal Physics Institute in 2014

    International Nuclear Information System (INIS)

    The main results of scientific and technological activities for last years of the Nuclear Reactors and Thermal Physics Institute FSUE SSC RF - IPPE in solving problems of nuclear power engineering are presented. The work have been carried out on the following problems: justification of research and development solutions and safety of NPPs with fast reactors of new generation with sodium (BN-1200, MBIR) and lead (BREST-OD-300) coolants, justification of safety of operating and advanced NPPs with WWER reactor facilities (WWER-1000, AEhS 2006, WWER-TOI), development and benchmarking of computational codes, research and development support of Beloyarsk-3 (BN-600) and Bilibino (BN-800) NPPs operation, decommissioning of AM and BR-10 research reactors, pilot scientific studies (WWER-SKD, ITER), international scientific and technical cooperation. Problems for further investigations are charted

  8. Nuclear disasters at Chornobyl NPP, Fukushima NPP and nuclear power engineering in the 21- century

    International Nuclear Information System (INIS)

    The article presents a brief analysis of nuclear accidents at the Chornobyl NPP 91986) and Fukushima NPP (2011), discusses causes and scenarios of the accidents. The radioactive contamination of the environment resulting from the disasters is characterized, and top-priority actions for mitigation of the consequences and protection of public are discussed

  9. Construction of a bibliographic information database and a web directory for the nuclear science and engineering

    International Nuclear Information System (INIS)

    The objective of this project is to construct the bibliographic information database and the web directory in the nuclear field. Its construction is very timely and important. Because nuclear science and technology has an considerable effect all over the other sciences and technologies due to its property of giant and complex engineering. We aimed to firmly build up a basis of efficient management of the bibliographic information database and the web directory in the nuclear field. The results of this project that we achieved in this year are as follows : first, construction of the bibliographic information database in the nuclear field(the target title: 1,500 titles ; research report: 1,000 titles, full-text report: 250 titles, full-text article: 250 titles). Second, completion of construction of the web directory in the nuclear field by using SWING (the total figure achieved : 2,613 titles). We plan that we will positively give more information to the general public interested in the nuclear field and to the experts of the field through this bibliographic information database on KAERI's home page, KAERI's electronic library and other related sites as well as participation at various seminars and meetings related to the nuclear field

  10. Research-based learning for nuclear engineering education in Gadjah Mada University

    International Nuclear Information System (INIS)

    Nuclear engineering education in Gadjah Mada University has been operated since 1977 in order to prepare Indonesian people facing up nuclear era in Indonesia. Until 1995, most of the alumni work in National Nuclear Energy Board, but recently many of them have been taking advanced study abroad. To improve our quality of education, since the last 3 years Gadjah Mada University has implemented Research-Based Learning (RBL). RBL for nuclear engineering student is conducted by providing challenges to the student related to the critical issues in public acceptance of nuclear power plant (NPP) in Indonesia that is waste management. Students should join in a group to complete the assignment. Within the group, they discuss and produce new idea in order to manage radioactive waste of new generation NPP. So, they are stimulated to think the future based on the state of the art of waste technology. This method could increase student's knowledge and soft skills, simultaneously. Some students also continue to explore and to refine the task as their thesis topic. Therefore, implementation of RBL also succeeds in increasing student's efficiency study. (author)

  11. Proceedings of the Nuclear Engineering Science and Technology - NESTeT 2011 Transactions

    International Nuclear Information System (INIS)

    This important European Nuclear Society (ENS) conference is dedicated to networking in nuclear education and training across the fields of engineering, science and technology. It is organised as a back-to-back event with the European Nuclear Young Generation Forum (ENYGF) which will attract over 150 Young Professionals from all over Europe. Exchange of information on available expertise, capacity, infrastructure and needs, together with networking and collaboration between all stakeholders involved is crucial for the development of an efficient education and training system that is able to provide adequately skilled workforce for a dynamically evolving sector. NESTet is designed to facilitate an exchange of information, collaboration and the sharing of best practices in nuclear education and training in engineering science and technology. It is an important networking opportunity for better co-ordination and collaboration between different stakeholders. The conference is targeted at all stakeholders responsible for human resources and skills development and stakeholders responsible for the development of education and training programmes in the nuclear sector. (authors)

  12. Nuclear power engineering development on the basis of new conceptions of nuclear reactor and fuel cycle

    International Nuclear Information System (INIS)

    One analyzes the status of nuclear power industry (NPI) and lists the excuses explaining the modest progress of NPI in contrast to the predicted one. It is shown that progress of NPI equivalent to the expansion of power consumers may be ensured by construction of large breeder NPPs. One lists the requirements for reactor and for fuel cycle technologies. The design of the BREST fast UN-PuN fuel and lead-cooling reactor enables to meet the listed requirements

  13. Lawrence Berkeley Laboratory Affirmative Action Program. Revised

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Lawrence Berkeley Laboratory`s Affirmative Action Program (AAP) serves as a working document that describes current policies, practices, and results in the area of affirmative action. It represents the Laboratory`s framework for an affirmative approach to increasing the representation of people of color and women in segments of our work force where they have been underrepresented and taking action to increase the employment of persons with disabilities and special disabled and Vietnam era veterans. The AAP describes the hierarchy of responsibility for Laboratory affirmative action, the mechanisms that exist for full Laboratory participation in the AAP, the policies and procedures governing recruitment at all levels, the Laboratory`s plan for monitoring, reporting, and evaluating affirmative action progress, and a description of special affirmative action programs and plans the Laboratory has used and will use in its efforts to increase the representation and retention of groups historically underrepresented in our work force.

  14. The Berkeley gas-filled separator

    CERN Document Server

    Ninov, V; McGrath, C A

    1998-01-01

    The BGS is being constructed at the 88-Inch Cyclotron at LBNL in Berkeley. The magnetic configuration of the BGS will allow a large angular acceptance and good suppression of primary beam particles. BGS operates as a mass spectrometer with a A/ Delta A approximately =200 and as a gas filled separator at pressures between 0.1-50 hPa. The reaction products recoiling off a thin target will be collected with efficiencies from 10-80at the focal plane. A Monte Carlo simulation program of the ion transport through the gas-filled magnets in combination of 3-dimensional TOSCA field maps has been developed and reproduces closely the experimental behavior of BGS. (9 refs).

  15. Application of integrated computer-aided engineering for design, construction and operation of nuclear power plant: practice and prospects

    International Nuclear Information System (INIS)

    Computer-aided-engineering (CAE) is an essential tool for modern nuclear power plant engineering. It greatly varies in definition, application, and technology from project to project and company to company. Despite the fast growing technologies and applications of CAE, its complexity and variety have thrown another puzzle to management of a nuclear project. Without due consideration of an integrated CAE system in early planning stage, the overall efficiency of a nuclear project would slow down due to the inefficiency in data flow. In this application are discussed under the Korea Power engineering Company philosophy in CAE approach

  16. 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.

  17. The role of the Iowa State University research reactor in nuclear engineering education

    International Nuclear Information System (INIS)

    On October 19, 1959, the Iowa State University Research Reactor (ISURR) was made critical for the first time. In the 29 yr since then, the reactor has been an integral part of the nuclear engineering program. Throughout its history, the major use of the ISURR has been as an educational tool. The reactor is currently used in both the undergraduate and graduate programs at ISU. The paper provides the reactor description and discusses reactor experiments for undergraduates and reactor use in graduate education

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

    International Nuclear Information System (INIS)

    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

  19. Junior High Schools of Berkeley, California. Bulletin, 1923, No. 4

    Science.gov (United States)

    Preston, James T.; Clark, W. B.; Glessner, H. H.; Hennessey, D. L.

    1923-01-01

    This bulletin demonstrates that Berkeley, California's educational problem is and has been that of meeting the varied needs of a population such as may be found in any typical American city. The varied population needs, together with the rapid growth, have brought many difficult problems to Berkeley, just has they have to other cities. Based on…

  20. Minimum requirements for safety-relevant computers in railway and nuclear engineering

    International Nuclear Information System (INIS)

    Safety-relevant computers basically have to satisfy the requirements of their field of application. These requirements are based on the respectively valid regulation also governing laws and standards. The two fields of application, railway and nuclear engineering, require separate regulations. For this reason, the requirements for these two fields of application are handled separately. Four safety classes were introduced for the nuclear engineering applications within the research project 210 (see also chapter 2, partial TUeV (Technical Surveyance Association) report, TUeV, northern Germany). Regulations valid in railway engineering and also common-day praxis do not allow safety classes to be subdivided. As far as an application is considered relevant in regard to safety, the technical signal safety must be guaranteed for this application. From the safety level, this includes safety-relevant applications of the railway engineering, basically in safety class 1 of the classification mentioned above. Note, however, that the requirements explicitly stated in the regulation are always to be satisfied. Essential aspects of computers used in safety applications are independent of the field of application. This especially applies for the application areas of railway and nuclear engineering, since computer applications with the highest safety class occur in these two fields of application. This was also the reason for VdTUeV Research Project 210 to handle the two fields of application jointly, when possible. In regard to this application-independent section, the two report volumes of TUeV northern Germany and TUeV Rhineland refer to the differences which reflect a corresponding division of work in Research Group 210. The partial report of TUeV northern Germany covers the theme in complete detail with the depths limited by the research material. (orig.)

  1. Building of Nuclear Ship Engineering Simulation System development of the simulator for the integral type reactor

    International Nuclear Information System (INIS)

    JAERI had carried out the design study of a light-weight and compact integral type reactor of power 100 MWth with passive safety as a power source for the future nuclear ships, and completed an engineering design. To confirm the design and operation performance and to utilize the study of automation of the operations of reactor, we developed a real-time simulator for the integral type reactor. This simulator is a part of Nuclear Ship Engineering Simulation System (NESSY) and on the same hardware as 'Mutsu' simulator which was developed to simulate the first Japanese nuclear ship Mutsu'. Simulation accuracy of 'Mutsu' simulator was verified by comparing the simulation results With data got in the experimental voyage of 'Mutsu'. The simulator for the integral type reactor uses the same programs which were used in 'Mutsu' simulator for the separate type PWR, and the simulated results are approximately consistent with the calculated values using RELAP5/MOD2 (The later points are reported separately). Therefore simulation accuracy of the simulator for the integral type reactor is also expected to be reasonable, though it is necessary to verify by comparing with the real plant data or experimental data in future. We can get the perspectives to use as a real-time engineering simulator and to achieve the above-mentioned aims. This is a report on development of the simulator for the integral type reactor mainly focused on the contents of the analytical programs expressed the structural features of reactor. (author)

  2. Berkeley UPC编译技术分析%Analysis of the Berkeley UPC Compile Technique

    Institute of Scientific and Technical Information of China (English)

    文延华; 黄传信; 漆锋滨

    2004-01-01

    UPC是一种可以在多种体系结构的并行系统上进行移植的基于全局地址空间(GAS)访问的并行编程语言.本文主要介绍了Berkeley UPC编译器的结构特点,分析了它对文本的支持程度和对并行的实现效率.

  3. 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.

  4. 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)

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

    International Nuclear Information System (INIS)

    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)

  6. Project-based learning in the Master’s degree in Nuclear Engineering at BarcelonaTECH. Experience gained in the area of Management of Nuclear Power Plants

    OpenAIRE

    Reventós Puigjaner, Francesc Josep; Vives Laflor, Eugeni; Brunet, Antoni; Sabaté, Ramon; Calviño Tavares, Francisco; Batet Miracle, Lluís

    2014-01-01

    From its first edition, that took place in 2011-2012, the Master’s degree in Nuclear Engineering from BarcelonaTECH has been using techniques of Project-Based Learning to fulfil 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 E...

  7. Systems analysis of nuclear solid-core engines for cis-lunar trajectories

    International Nuclear Information System (INIS)

    This report summarizes the result of a comprehensive study about the use of nuclear engines in cis-lunar space. The nuclear space transportation system elements were defined and the restrictions imposed on the nuclear ferries by the chemical Earth-to-LEO transportation system were analyzed. Operating conditions are met best by tungsten-water-moderated reactors due to a high specific impulse and long durability. Specific transportation cost for LEO-to-GEO and LEO-to-lunar orbit flights were calculated for a transportation system life of 50 years. Average transportation cost were estimated to be about 141 $/kg. No difference was made for both routes mentioned above. An additional analysis of smaller and larger flight units showed only small cost reductions by employing larger ferries but a significant cost increase in case smaller flight units would be used. (orig.)

  8. High energy nucleus--nucleus studies at the Berkeley Bevalac. [Survey

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, L.S.

    1976-09-01

    A survey of high-energy nucleus--nucleus experiments performed at the Berkeley Bevalac Facility is presented. Experimental results are divided into the general areas of peripheral and central collisions. Results on projectile and target fragmentation, total cross-section measurements, pion and photon production, and charged-particle multiplicities are stressed. Recently, there have been theoretical predictions concerning the possibility of observing new phenomena such as shock waves, pion condensates, or collapsed nuclear matter. Existing data relevant to some of these speculations are discussed. A brief discussion of future developments with high-energy nuclear beams is also presented. 27 figures, 1 table.

  9. Organization and management of heterogeneous, dispersed data bases in nuclear engineering

    International Nuclear Information System (INIS)

    Large, complex, multiperson engineering projects in many areas, nuclear, aerospace, electronics, and manufacturing, have inherent needs for coordination, control, and management of the related engineering data. Taken in the abstract, the notion of an integrated engineering data base (IED) for such projects is attractive. The potential capabilities of an (IED) are that all data are managed in a coordinated way, are made accessible to all users who need it, allow relations between all parts of the data to be tracked and managed, provide backup, recovery, audit trails, security and access control, and allow overall project status to be monitored and managed. Common data accessing schemes and user interfaces to applications are also part of an IED. This paper describes a new software product that allows incremental realization of many of the capabilities of an IED, without the massive disruption and risk

  10. 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.)

  11. 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.

  12. Developments in the Nuclear Safeguards and Security Engineering Degree Program at Tomsk Polytechnic University

    International Nuclear Information System (INIS)

    Over the last six years, Tomsk Polytechnic University (TPU) has developed a 5 1/2 year engineering degree program in the field of Material Protection Control and Accounting (MPC and A). In 2009 the first students graduated with this new degree. There were 25 job offers from nuclear fuel cycle enterprises of Russia and Kazakhstan for 17 graduates of the program. Due to the rather wide selection of workplaces, all graduates have obtained positions at nuclear enterprises. The program was developed within the Applied Physics and Engineering Department (APED). The laboratory and methodological base has been created taking into consideration the experience of the similar program at the Moscow Engineering Physics Institute (MEPhI). However, the TPU program has some distinguishing features such as the inclusion of special courses pertaining to fuel enrichment and reprocessing. During the last two years, three MPC and A laboratories have been established at APED. This was made possible due to several factors such as establishment of the State innovative educational program at TPU, assistance of the U.S. Department of Energy through Pacific Northwest National Laboratory and Los Alamos National Laboratory, and the financial support of the Swedish Radiation Safety Authority and some Russian private companies. All three of the MPC and A laboratories are part of the Innovative Educational Center 'Nuclear Technologies and Non-Proliferation,' which deals with many topics including research activities, development of new curricula for experts training and retraining, and training of master's students. In 2008, TPU developed a relationship with the International Atomic Energy Agency (IAEA), which was familiarized with APED's current resources and activities. The IAEA has shown interest in creation of a master's degree educational program in the field of nuclear security at TPU. A future objective is to acquaint nuclear fuel cycle enterprises with new APED capabilities and involve

  13. Radiation dose assessment in nuclear plants through virtual simulations using a game engine

    International Nuclear Information System (INIS)

    Full text: This paper reports an R and D which has the purpose of performing dose assessment of workers in nuclear plants, through virtual simulations using a game engine. The main objective of this R and D is to support the planning of operational and maintenance routines in nuclear plants, aiming to reduce the dose received by workers. Game engine is the core of a computer game, that is usually made independent of both the scenarios and the original applications, and thus can be adapted for any other purposes, including scientific or technological ones. Computer games have experienced a great development in the last years, regarding computer graphics, 3D image rendering and the representation of the physics needed for the virtual simulations, such as gravity effect and collision among virtual components within the games. Thus, researchers do not need to develop an entire platform for virtual simulations, what would be a hard work itself, but they can rather take advantage of such well developed platforms, adapting them for their own applications. The game engine used in this R and D is part of a computer game widely used, Unreal, that has its source code partially open, and can be pursued for low cost. A nuclear plant in our Institution, Argonauta research reactor, has been virtually modeled in 3D, and trainees can navigate virtually through it, with realistic walking velocity, and experiencing collision. The modified game engine computes and displays in real-time the dose received by a virtual person, the avatar, as it walks through the plant, from the radiation dose rate distribution assigned to the virtual environment. In the beginning of this R and D, radiation dose rate measurements were previously collected by the radiological protection service, and input off-line to the game engine. Currently, on-line measurements can be also input to it, by taking advantage of the game's networking capabilities. A real radiation monitor has been used to collect real

  14. Meeting report of the consultancy meeting on comparison of curricula in nuclear engineering within the ANENT countries

    International Nuclear Information System (INIS)

    The participants of the Meeting have agreed to conclude: 1. The participants have been acquainted with the following: a. Curricula on nuclear science and nuclear engineering of the host country - Russia, as well as of the Republic of Korea, India and Vietnam; b. Nuclear education activities of the World Nuclear University (WNU); c. Nuclear education facilities at Moscow Engineering Physics Institute (MEPhI). 2. Discussions and analysis were made on the curricula in nuclear engineering education in the Region. 3. Main efforts were focused on developing a draft of the ANENT Reference Curricula for Master's Degree in Nuclear Engineering. The skeleton of the first draft of the Reference Curricula was created. 4. The idea about the ANENT Master's Degree in Nuclear Engineering (ANENT MDNE) was discussed. Realization of such degree would strongly and directly enhance and heighten the regional educational level in nuclear engineering in the near future. It is also expected to facilitate credit transfer and mutual recognition of degrees within the ANENT member countries in line with the ANENT's long term goals. 5. It was suggested to conduct an intensive exchange of opinions between experts and educators in the ANENT member countries to develop the ANENT MDNE further based on the skeleton of the draft. 6. It was preferable to start more extensive discussion about the idea of the ANENT MDNE and how to realize it effectively and reasonably as soon as possible. 7. The ANENT members were encouraged to discuss about ANENT Activity 4 at the next Meeting of the ANENT Coordination Committee. 8. The participants expressed their heartfelt thanks to the collective of Moscow Engineering Physics Institute (MEPhI) - the Host Organization - and to all the members of the Local Organizing Committee of the Meeting, as well as to the ANENT Scientific Secretary, for the warm atmosphere and perfect conditions provided for the success of the Meeting

  15. Engineering assessment of inactive uranium mill tailings: Phillips/United Nuclear site, Ambrosia Lake, New Mexico

    International Nuclear Information System (INIS)

    Ford, Bacon and Davis Utah, Inc., has reevaluated the Phillips/United Nuclear site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Ambrosia Lake, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from 2.6 million dry tons of tailings at the Phillips/United Nuclear site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The four alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material, to removal of the tailings to remote disposal sites and decontamination of the tailings site. Cost estimates for the four options range from about $21,500,000 for stabilization in-place, to about $45,200,000 for disposal at a distance of about 15 mi. Three principal alternatives for the reprocessing of the Phillips/United Nuclear tailings were examined: heap leaching; treatment at an existing mill; and reprocessing at a new conventional mill constructed for tailings reprocessing.The cost of the uranium recovered would be about $87/lb of U3O8 by either heap leach or conventional plant process. The spot market price for uranium was $25/lb early in 1981. Reprocessing the Phillips/United Nuclear tailings for uranium recovery does not appear to be economically attractive under present or foreseeable market conditions

  16. 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 ...

  17. Safety culture of complex risky systems: the Nuclear Engineering Institute case study

    International Nuclear Information System (INIS)

    Analysis of industrial accidents have demonstrated that safe and reliable operation of complex industrial processes that use risky technology and/or hazard material depends not only on technical factors but on human and organizational factors as well. After the Chernobyl nuclear accident in 1986, the International Atomic Energy Agency established the safety culture concept and started a safety culture enhancement program within nuclear organizations worldwide. The Nuclear Engineering Institute, IEN, is a research and technological development unit of the Brazilian Nuclear Energy Commission, CNEN, characterized as a nuclear and radioactive installation where processes presenting risks to operators and to the environment are executed. In 1999, IEN started a management change program, aiming to achieve excellence of performance, based on the Model of Excellence of the National Quality Award. IEN's safety culture project is based on IAEA methodology and has been incorporated to the organizational management process. This work presents IEN's safety culture project; the results obtained on the initial safety culture assessment and the following project actions. (author)

  18. Annual cooperative research report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This is FY 1995 annual report of research results of the Yayoi research group and the high speed neutron science group as well as the cooperative application research results of reactor `Yayoi` application, related to reactor `Yayoi` and of accelerator Linac. The reactor was also operated smoothly in FY 1995, and its application and related research reached to 25 themes. The research using Linac reduced apparently to 7 themes from 14 in FY 1994, which showed apparent reduction because of integration of the cooperative research theme but showed more results in general. in particular, it was a wonderful result to success the formation of sub-pico second pulsed beam in world wide area. The Yayoi research group reported 13 researches which was two more than these in last fiscal year, all of which were the most advanced discussions in the field related to nuclear engineering. The high speed neutron science group started in FY 1993 aiming at construction of new research field on application of the high speed neutron as a quantum beam with excellent nuclear transfer and transmittance, to manifestation and control of new material function and design and creation of intelligent material. In FY 1995, the group began his full scale operation and reported on 8 themes. (G.K.)

  19. 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.

  20. 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…

  1. Study of the effects of a tornado on a nuclear plant(from the point of view of civil engineering)

    International Nuclear Information System (INIS)

    is to analyze the applicability of Regulatory Guide 1.76 design basis Tornado and Tornado Missiles for Nuclear Power Plants, assessing the guide / standard compliance of a nuclear facility with respect to it, identifying the actions required for the compliance if applicable and valuation, with engineering judgment, the benefits for the plant would total or partial implantation of the guide.

  2. Radioactive ion beam development in Berkeley

    CERN Document Server

    Wutte, D C; Leitner, M A; Xie, Z Q

    1999-01-01

    Two radioactive ion beam projects are under development at the 88" Cyclotron, BEARS (Berkeley Experiment with accelerated radioactive species) and the 14O experiment. The projects are initially focused on the production of 11C and 14O, but it is planned to expand the program to 17F, 18F, 13N and 76Kr. For the BEARS project, the radioactivity is produced in form of either CO2 or N2O in a small medical 10 MeV proton cyclotron. The activity is then transported through a 300 m long He-jet line to the 88" cyclotron building, injected into the AECR-U ion source and accelerated through the 88" cyclotron to energies between 1 to 30 MeV/ nucleon. The 14O experiment is a new experiment at the 88" cyclotron to measure the energy-shape of the beta decay spectrum. For this purpose, a target transfer line and a radioactive ion beam test stand has been constructed. The radioactivity is produced in form of CO in a hot carbon target with a 20 MeV 3He from the 88" Cyclotron. The activity diffuses through an 8m long stainless s...

  3. 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)

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

    International Nuclear Information System (INIS)

    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)

  5. Innovations in nuclear engineering distance education at the University of Tennessee

    International Nuclear Information System (INIS)

    The Univ. of Tennessee Dept. of Nuclear Engineering (UTNE) offers both graduate and undergraduate internet-based courses that support a Master of Science (MS) degree and several certificate programs. In particular a MS degree can be conveniently obtained through distance classes. In addition certificates in Nuclear Criticality Safety and in Maintenance and Reliability can be obtained by completing a subset of courses offered for the MS degree. Students enrolled in these courses are predominately located in East Tennessee, but many live throughout the United States and in several foreign countries. An innovation of significant benefit to the UTNE undergraduate program is the implementation of reactor and laboratory experiments that are conducted over the Internet on the PULSTAR reactor at North Carolina State Univ. (NCSU). These experiments are conducted live with video, audio, and data transmission, and to date experiments involving approach to critical, rod calibration using incremental and inverse kinetics methods, thermal calibration of neutron detectors, and reactivity coefficients have been conducted. Neutron scattering experiments are planned for remote control by students. The use of internet-based education has enhanced the undergraduate program at the UTNE, and it has created opportunities for students with Internet access to obtain a quality education in Nuclear Engineering. (authors)

  6. 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.)

  7. Blended-mode pedagogical model fosters nuclear engineering education in Southern Africa

    Energy Technology Data Exchange (ETDEWEB)

    Kruger, J.H.; Fick, J.I.J. [Postgraduate School for Nuclear Science and Engineering, North-West University, Potchefstroom Campus, 11 Hoffman Street, 2531 Potchefstroom (South Africa)

    2010-07-01

    Social upliftment requires access to energy. Especially in the Southern Africa region, affordable energy gives communities access to improved living conditions, potable water and life-changing educational opportunities. Distributed nuclear power generation can make a significant difference in a continent where communities are geographically widely dispersed and where technology centres are few and far between. Unfortunately, for a country to obtain a nuclear capability and be part of the renaissance, it needs a skilled and educated workforce - a workforce that must be trained through an educational system facing the same challenges of dispersed human resources and lack of infrastructure as the community it serves. The blended-mode pedagogical model developed by the Postgraduate School for Nuclear Science and Engineering at the North-West University (NWU) in South Africa represents one manner in which the problem of dispersed resources can be addressed. As a matter of national policy, South Africa has embarked on a drive to not only innovate in terms of reactor technology, but to also develop and sustain a skilled workforce in the nuclear engineering field. Due to a severe shortage of personnel in the local nuclear community, the NWU devised a blended-mode teaching system to link overseas lecturers with local students to expand the local workforce through training and human capital development. The blended-mode delivery takes place through the online Sakai system that uses powerful learning management tools to achieve the learning outcomes. Students are guided in distance self-study for the larger part of the course and a contact session is then used to contextualize and integrate the knowledge. In this manner, a virtual collaborative environment between geographically dispersed faculty members and students is created which provides essential flexibility in terms of time and human resource management. The blended-mode teaching model has already achieved great

  8. Blended-mode pedagogical model fosters nuclear engineering education in Southern Africa

    International Nuclear Information System (INIS)

    Social upliftment requires access to energy. Especially in the Southern Africa region, affordable energy gives communities access to improved living conditions, potable water and life-changing educational opportunities. Distributed nuclear power generation can make a significant difference in a continent where communities are geographically widely dispersed and where technology centres are few and far between. Unfortunately, for a country to obtain a nuclear capability and be part of the renaissance, it needs a skilled and educated workforce - a workforce that must be trained through an educational system facing the same challenges of dispersed human resources and lack of infrastructure as the community it serves. The blended-mode pedagogical model developed by the Postgraduate School for Nuclear Science and Engineering at the North-West University (NWU) in South Africa represents one manner in which the problem of dispersed resources can be addressed. As a matter of national policy, South Africa has embarked on a drive to not only innovate in terms of reactor technology, but to also develop and sustain a skilled workforce in the nuclear engineering field. Due to a severe shortage of personnel in the local nuclear community, the NWU devised a blended-mode teaching system to link overseas lecturers with local students to expand the local workforce through training and human capital development. The blended-mode delivery takes place through the online Sakai system that uses powerful learning management tools to achieve the learning outcomes. Students are guided in distance self-study for the larger part of the course and a contact session is then used to contextualize and integrate the knowledge. In this manner, a virtual collaborative environment between geographically dispersed faculty members and students is created which provides essential flexibility in terms of time and human resource management. The blended-mode teaching model has already achieved great

  9. Building of Nuclear Ship Engineering Simulation System development of the simulator for the integral type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Teruo; Shimazaki, Junya; Yabuuchi, Noriaki; Fukuhara, Yosifumi; Kusunoki, Takeshi; Ochiai, Masaaki [Department of Nuclear Energy Systems, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan); Nakazawa, Toshio [Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute, Oarai, Ibaraki (Japan)

    2000-03-01

    JAERI had carried out the design study of a light-weight and compact integral type reactor of power 100 MW{sub th} with passive safety as a power source for the future nuclear ships, and completed an engineering design. To confirm the design and operation performance and to utilize the study of automation of the operations of reactor, we developed a real-time simulator for the integral type reactor. This simulator is a part of Nuclear Ship Engineering Simulation System (NESSY) and on the same hardware as 'Mutsu' simulator which was developed to simulate the first Japanese nuclear ship Mutsu'. Simulation accuracy of 'Mutsu' simulator was verified by comparing the simulation results With data got in the experimental voyage of 'Mutsu'. The simulator for the integral type reactor uses the same programs which were used in 'Mutsu' simulator for the separate type PWR, and the simulated results are approximately consistent with the calculated values using RELAP5/MOD2 (The later points are reported separately). Therefore simulation accuracy of the simulator for the integral type reactor is also expected to be reasonable, though it is necessary to verify by comparing with the real plant data or experimental data in future. We can get the perspectives to use as a real-time engineering simulator and to achieve the above-mentioned aims. This is a report on development of the simulator for the integral type reactor mainly focused on the contents of the analytical programs expressed the structural features of reactor. (author)

  10. 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. PMID:18348907

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

    Energy Technology Data Exchange (ETDEWEB)

    Taam, I.H. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Caixa Postal 68550, 21945-970 Rio de Janeiro, RJ (Brazil); Rosa, L.A.R. da [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Av. Salvador Allende s/n, Caixa Postal 37760, 22780-160 Rio de Janeiro, RJ (Brazil)], E-mail: lrosa@ird.gov.br; Crispim, V.R. [PEN/COPPE-DNC/POLI/CT/UFRJ, Caixa Postal 68509, 21941-972 Rio de Janeiro, RJ (Brazil)

    2008-09-15

    Since 2003 the Institute of Nuclear Engineering in Rio de Janeiro city, Brazil, operates a new cyclotron, RDS-111, to produce {sup 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.

  12. Evaluation of foreign currency payment ability of China Nuclear Power Engineering Corporate

    International Nuclear Information System (INIS)

    Through this paper, after making a detailed research into the current foreign currency policy of China and the experience of China Nuclear Power Engineering Corporate(CNPEC) during LA2 project, the author evaluates the current ability of foreign currency settlement ability and defines the applicable process in CNPEC, in order to meet the future needs of CNPEC to make foreign currency payment for the multiple nuclear power projects. To ensure the foreign payment can be settled successfully, CNPEC should pay more attention to the import duty, foreign currency loan, clearing method, remittance after verification, as well as the financial risk management of foreign currency loan. On the premise that CNPEC can also get entitlement of import duty and value added tax preference, the author makes the point about how to enhance the capacity of foreign currency payment of CNPEC. (authors)

  13. 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.

  14. 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.

  15. 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.

  16. Meteorological and engineering approach to the regionalization of tornado wind criteria for nuclear power plant design

    International Nuclear Information System (INIS)

    Data on general meteorological factors governing tornado frequency and intensity in various locations throughout the USA are revised. A climatological model of multiple outbreak and long track tornadoes and the relation between the speed of a hurricane and the frequency of tornado occurrence over land and sea are discussed. Data from a structural engineering assessment of tornado damage are summarized and applications of the data for the development of design criteria for buildings and nuclear power plants to minimize tornado damage are suggested. It was concluded that it is very difficult to predict tornado risk and alternate methods and areas of study are presented for consideration

  17. 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.

  18. Former Fermilab boss to lead Lawrence Berkeley National Laboratory

    Science.gov (United States)

    Gwynne, Peter

    2016-03-01

    Particle physicist Michael Witherell - current vice-chancellor for research at the University of California, Santa Barbara (UCSB) - has been appointed the next director of the Lawrence Berkeley National Laboratory (LBL).

  19. Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Schleimer, G.E. (ed.)

    1981-04-01

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory is described. Data on air and water sampling and continuous radiation monitoring for 1980 are presented, and general trends are discussed.

  20. Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1980

    International Nuclear Information System (INIS)

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory is described. Data on air and water sampling and continuous radiation monitoring for 1980 are presented, and general trends are discussed

  1. Annual environmental monitoring report of the Lawrence Berkeley Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Schleimer, G.E.; Pauer, R.O. (eds.)

    1990-08-01

    The Lawrence Berkeley Laboratory (LBL) is a multiprogram national laboratory managed by the University of California (UC) for the US Department of Energy (DOE). LBL's major role is to conduct basic and applied science research that is appropriate for an energy research laboratory. The Environmental Monitoring Program of the Lawrence Berkeley Laboratory is described. Data for 1989 are presented, and general trends are discussed. 17 refs., 12 figs., 23 tabs.

  2. Education of energy and environment engineers in Hokkaido University. Education for nuclear and energy utilization for low-carbon society

    International Nuclear Information System (INIS)

    The Division of Energy and Environmental Systems in Hokkaido University is chasing energy systems contributing to sustain the global environment, such as next-generation nuclear reactor systems, nuclear safety, nuclear fuel cycles, nuclear wastes management, hydrogen fuel cells, advanced engine systems, and fluid energy systems. In these technologies, there exists common science and technology field, that is to say the multiphase flow. The filed of energy and environmental systems are very important not only for human beings but also for all the life on this planet, the Erath. Education and study of nuclear and energy engineering in this division has proved to be quite attractive for students and researchers on the view point of multiphase flow. (author)

  3. 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.

  4. 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

  5. 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

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

    International Nuclear Information System (INIS)

    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 (H2) over the chemical reaction by-products. A NTR uses thermal energy released from a nuclear fission reactor to heat the H2 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 (Isp) which represents the ratio of the thrust over the propellant consumption rate. If the average exhaust H2 temperature of a NTR is around 3,000 K, the Isp 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 NTR engines have continued as

  7. The construction of social identity in newly recruited nuclear engineering staff: A longitudinal study

    International Nuclear Information System (INIS)

    This study examines the process by which newly recruited nuclear engineering and technical staff came to understand, define, think, feel and behave within a distinct group that has a direct contribution to the organization's overall emphasis on a culture of reliability and system safety. In the field of organizational behavior the interactive model of social identity formation has been recently proposed to explain the process by which the internalization of shared norms and values occurs, an element critical in identity formation. Using this rich model of organizational behavior we analyzed multiple sources of data from nine new hires over a period of three years. This was done from the time they were employed to investigate the construction of social identity by new entrants entering into a complex organizational setting reflected in the context of a nuclear facility. Informed by our data analyses, we found support for the interactive model of social identity development and report the unexpected finding that a newly appointed member's age and level of experience appears to influence the manner in which they adapt, and assimilate into their surroundings. This study represents an important contribution to the safety and reliability literature as it provides a rich insight into the way newly recruited employees enact the process by which their identities are formed and hence act, particularly under conditions of duress or significant organizational disruption in complex organizational settings. - Highlights: • We examined how newly recruited nuclear engineer staff develop their social identity. • The study empirically examined the interactive model of social identity formation. • Innovative research strategies were used to capture rich primary data for all case studies. • Age and experience moderated internalization route and the social identity formation process

  8. The disposal of Canada's nuclear fuel waste: engineering for a disposal facility

    International Nuclear Information System (INIS)

    This report presents some general considerations for engineering a nuclear fuel waste disposal facility, alternative disposal-vault concepts and arrangements, and a conceptual design of a used-fuel disposal centre that was used to assess the technical feasibility, costs and potential effects of disposal. The general considerations and alternative disposal-vault arrangements are presented to show that options are available to allow the design to be adapted to actual site conditions. The conceptual design for a used-fuel disposal centre includes descriptions of the two major components of the disposal facility, the Used-Fuel Packaging Plant and the disposal vault; the ancillary facilities and services needed to carry out the operations are also identified. The development of the disposal facility, its operation, its decommissioning, and the reclamation of the site are discussed. The costs, labour requirements and schedules used to assess socioeconomic effects and that may be used to assess the cost burden of waste disposal to the consumer of nuclear energy are estimated. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

  9. 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

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

    International Nuclear Information System (INIS)

    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

  11. 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.

  12. Hybrid particle swarm optimization algorithm and its application in nuclear engineering

    International Nuclear Information System (INIS)

    Highlights: • We propose a hybrid particle swarm optimization algorithm (HPSO). • Modified Nelder–Mead simplex search method is applied in HPSO. • The algorithm has a high search precision and rapidly calculation speed. • HPSO can be used in the nuclear engineering optimization design problems. - Abstract: A hybrid particle swarm optimization algorithm with a feasibility-based rule for solving constrained optimization problems has been developed in this research. Firstly, the global optimal solution zone can be obtained through particle swarm optimization process, and then the refined search of the global optimal solution will be achieved through the modified Nelder–Mead simplex algorithm. Simulations based on two well-studied benchmark problems demonstrate the proposed algorithm will be an efficient alternative to solving constrained optimization problems. The vertical electrical heating pressurizer is one of the key components in reactor coolant system. The mathematical model of pressurizer has been established in steady state. The optimization design of pressurizer weight has been carried out through HPSO algorithm. The results show the pressurizer weight can be reduced by 16.92%. The thermal efficiencies of conventional PWR nuclear power plants are about 31–35% so far, which are much lower than fossil fueled plants based in a steam cycle as PWR. The thermal equilibrium mathematic model for nuclear power plant secondary loop has been established. An optimization case study has been conducted to improve the efficiency of the nuclear power plant with the proposed algorithm. The results show the thermal efficiency is improved by 0.5%

  13. A survey of innovative trains of thoughts for nuclear power fuel cycle engineering of pressurized water reactor

    International Nuclear Information System (INIS)

    Based on achievements in technique innovation of nuclear power fuel cycle engineering of pressurized water reactor since the late 1970's, the progress is sumed up and classified as three trains of innovation thoughts: once-through cycle reprocessing fuel cycle and reprocessing-partitioning-transmutation cycle. From angles of sustainable development of fission nuclear power utilization and development of circuit economy, the necessity is inquired and analyzed to develop the reprocessing-partitioning-transmutation closed circulating. (authors)

  14. Accident analysis in the water loop of the nuclear engineering department of IPEN using the RELAP4 code

    International Nuclear Information System (INIS)

    A thermal-hydraulic analysis to describe the transient behavior in the water loop of the Nuclear Engineering Department of the Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, Brazil, was performed. Postulated accidents such as those resulting from (1) loss of coolant, (2) main pump failure and (3) power excursions, were studied. The computer code RELAP4/Mod.3 was employed as the principal tool of analysis. (Author)

  15. Transfer of nuclear engineering knowledge at Hanoi University of Technology: Lessons learned and challenges

    International Nuclear Information System (INIS)

    Full text: Hanoi University of Technology (HUT) has been being the most important polytechnic education centre of the country for half a century. Nuclear Engineering Education Programme (NEEP) was started at HUT since the year 1970, right after establishment of Department of Nuclear Engineering at the University according to the initiative of the first Minister of Ministry of Higher Education of the country. Since the year 2000 the Department changed its education programme to adapt it to the actual circumstances in the country and renamed as Department of Nuclear Engineering and Environmental Physics (DONEEP). The objectives of the HUT's NEEP are as follows: 1. To train up nuclear technical manpower for development of peaceful uses of atomic energy in Vietnam. 2. To prepare initial nuclear technical human resources for introduction of Nuclear Power into the country. Aiming at these objectives, the Programme achieved remarkable results such as inestimable contributions to introducing and then developing the NDT radiography method in Vietnam, to improving and developing the atomic energy applications in the country, to providing important parts of technical human resources for strengthening the nuclear community of the country. The duration of 37 years of implementation of the Programme may be divided by 3 periods: from 1970 to 1989, 1990-2000 and from the year 2001 up to now. During the first period, the Programme was fully supported by the leadership of the University and the Ministry of Higher Education. The second period was full of difficulties. This was the period of searching the ways for preserving and adapting the Programme to the new circumstances in the country. The present period is the one of searching the ways for developing the NEEP at HUT. The lessons learned from 37-year implementation of the HUT's NEEP are as follows: 1. To establish proper objectives aiming to satisfy the urgent short term and/or long term demands of the country is the most

  16. Statistics for nuclear engineers and scientists. Part 1. Basic statistical inference

    International Nuclear Information System (INIS)

    This report is intended for the use of engineers and scientists working in the nuclear industry, especially at the Bettis Atomic Power Laboratory. It serves as the basis for several Bettis in-house statistics courses. The objectives of the report are to introduce the reader to the language and concepts of statistics and to provide a basic set of techniques to apply to problems of the collection and analysis of data. Part 1 covers subjects of basic inference. The subjects include: descriptive statistics; probability; simple inference for normally distributed populations, and for non-normal populations as well; comparison of two populations; the analysis of variance; quality control procedures; and linear regression analysis

  17. Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination

    Energy Technology Data Exchange (ETDEWEB)

    Jacobson, Victor Levon

    2002-08-01

    U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodiumbearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements.

  18. Development of decommissioning engineering support system (DEXUS) of the Fugen Nuclear Power Station

    International Nuclear Information System (INIS)

    The Fugen Nuclear Power Station (NPS) was shut down permanently in March 2003, and preparatory activities are underway to decommission the Fugen NPS. An engineering system to support the decommissioning is being developed to create a dismantling plan using state-of-art software such as 3-dimensional computer aided design (3D-CAD) and virtual reality (VR). In particular, an exposure dose evaluation system using VR has been developed and tested. The total system can be used to quantify radioactive waste, to visualize radioactive inventory, to simulate the dismantling plan, to evaluate workload in radiation environments and to optimize the decommissioning plan. The system will also be useful for educating and training workers and for gaining public acceptance. (author)

  19. Operator support architecture for monitoring abnormal symptoms of nuclear power plant based on knowledge engineering

    International Nuclear Information System (INIS)

    An architecture to support nuclear power plant operators for monitoring abnormal symptoms has been proposed based on the techniques of knowledge engineering, and the feasibility of a plant monitoring support system was investigated. The purpose of the support system is to present the operators with useful information so that they can make correct judgment at an early and subtle stage of abnormal plant conditions. In the architecture proposed, abductive reasoning is performed to search for causal events and deductive one to predict consequential events using the knowledge representing plant components as frames and those representing causal relations as production rules. A method to deal with uncertainties in each types of reasoning has been adopted, and it is used to rank several hypotheses of causal events and to assess the importance of plant parameters for monitoring. A prototype system was developed, and its usefulness was tested using a case of failure in a recirculation pump of a BWR plant. (author)

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

    Science.gov (United States)

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

    2006-01-01

    The objective of this effort is to develop an efficient and accurate thermo-fluid computational methodology to predict environments for a hypothetical solid-core, nuclear thermal engine thrust chamber. The computational methodology is based on an unstructured-grid, pressure-based computational fluid dynamics methodology. Formulations for heat transfer in solids and porous media were implemented and anchored. A two-pronged approach was employed in this effort: A detailed thermo-fluid analysis on a multi-channel flow element for mid-section corrosion investigation; and a global modeling of the thrust chamber to understand the effect of hydrogen dissociation and recombination on heat transfer and thrust performance. The formulations and preliminary results on both aspects are presented.

  1. Effect of buoyancy on fuel containment in an open-cycle gas-core nuclear rocket engine.

    Science.gov (United States)

    Putre, H. A.

    1971-01-01

    Analysis aimed at determining the scaling laws for the buoyancy effect on fuel containment in an open-cycle gas-core nuclear rocket engine, so conducted that experimental conditions can be related to engine conditions. The fuel volume fraction in a short coaxial flow cavity is calculated with a programmed numerical solution of the steady Navier-Stokes equations for isothermal, variable density fluid mixing. A dimensionless parameter B, called the Buoyancy number, was found to correlate the fuel volume fraction for large accelerations and various density ratios. This parameter has the value B = 0 for zero acceleration, and B = 350 for typical engine conditions.

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. A materials engineering view of license renewal at the US Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    This paper discusses the treatment of license renewal at the US Nuclear Regulatory Commission (NRC) with emphasis on the review process by the staff of the Materials and Chemical Engineering Branch (EMCB). The paper covers the rules governing license renewal, the applications received, the schedule, the approach, and the technical issues. The NRC has a tight schedule of 30-36 months to renew a license. To date, Baltimore Gas and Electric (BG and E) and Duke Power have applied for license renewal. Expecting more applicants, the staff has taken steps to address the public's concern that the effects of aging will be adequately managed and the industry's concern that the reviews will be timely, efficient, and uniform. These steps include identifying aging effects and making the results available in a report and computerized database, approving topical reports and aging management programs for generic use, and reviewing aging management programs according to specific criteria. Materials Engineering staff have a major role because many of the aging issues are materials related. (author)

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

    International Nuclear Information System (INIS)

    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. 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.

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

    International Nuclear Information System (INIS)

    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

  11. BERSAFE: (BERkeley Structural Analysis by Finite Elements)

    International Nuclear Information System (INIS)

    BERSAFE is a well-known finite element system which has been under continuous use and development for over 20 years. The BERSAFE system comprises an inter-compatible set of program modules covering static stress analysis, linear dynamics and thermal analysis. Data generation and results presentation modules are also available, along with special supporting functions including automatic crack growth through a model with adaptive meshing. The functionality of BERSAFE, is nowadays very advanced, both in engineering scope and finite element technology. It has seen many firsts, including the front solution and Virtual Crack Extension methods (VCE). More recent additions which have developed out of the Power Industry's requirements are a finite element computational fluid dynamics code, FEAT, and engineering design assessment procedures. These procedures include R6 and R5 for the assessment of the integrity of structures containing defects below and within the creep regime. To use all this software in a user-friendly manner, a new computational environment has been developed, called 'The Harness' which takes advantage of modern hardware and software philosophies. This provides the tool-kit to undertake complete problems, covering determination of fluid loads, structural analysis and failure assessment. In the following sections we describe briefly various components of the BERSAFE suite. (author)

  12. The fourth conference on nuclear science and engineering in Australia, 2001. Conference handbook

    International Nuclear Information System (INIS)

    This conference, with the theme 'New Nuclear Century' consists of invited papers supported by contributed posters on the following topics: nuclear research and ANSTO's Replacement Research Reactor; Australian uranium resources; radioactive waste management; low-level radiation, radiation protection, nuclear safety, the environment and sustainable development; application of nuclear energy in Nuclear Medicine, non-destructive testing; nuclear science and technology for the future and nuclear education

  13. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1986

    International Nuclear Information System (INIS)

    This book contains a large number of reports of studies made in 1986 through joint utilization of the nuclear reactor 'Yayoi' and electron beam type accelerator which are installed in the Nuclear engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The reports presented deal with 'Behaviors of Neutrons in Fast Reactor Blanket Shield', 'Effect of Fast Neutron Radiation on Organic Materials', 'Production and Recovery of Tritium in Nuclear Fusion Reactor Blanket System', 'Bench Mark Experiment of Effect of Atmospheric Scattering of Neutron', 'Experimental Evaluation of Nuclear Heat Rate', 'Fast Neutron Shielding Experiment', 'Effect of Fast Neutron Radiation on Hot Water', 'Neutron Shielding Experiment', 'Biological and Medical Application of 'Yayoi' Neutron', 'Effect of Fission-Fusion Correlation Radiation on Semiconductors (Si, GaAs)', 'Application of Fast Neutron to Radiography Technology', 'Streaming in Offset Slit', 'Design and Evaluation of New Reactor', 'LET Effect on Organic Material', 'Handling, Separation and Recovery of Transuranium Elements', 'Reactor Operation Support System Using Knowledge Engineering Technique', 'Application of Shape Memory Alloys to Nuclear Reactor Devices', 'Numerical Simulation of Turbulent Hear Transfer', and many other studies. (Nogami, K.)

  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 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.

  15. Studies, Transport and Treatment Concept for Boilers from Berkeley NPP, England - 13599

    International Nuclear Information System (INIS)

    In November 2011 Studsvik was awarded a contract to transport five decommissioned boilers from the Berkeley Nuclear Licensed Site in the UK to the Studsvik Nuclear Site in Sweden for metal treatment and recycling. A key objective of the project was to remove the boilers from the site by 31 March 2012 and this was successfully achieved with all boilers off site by 22 March and delivered to Studsvik on 6 April. Four boilers have been processed and the fifth is planned for completion by end of December 2012.The project had many challenges including a very tight timescale and has been successfully delivered to cost and ahead of the baseline programme. This paper describes the project and the experience gained from treatment of the first four boilers. It is the first UK project to send large components overseas for recycling and provides new insight into the processing of Magnox gas-circuit components. (authors)

  16. Studies, Transport and Treatment Concept for Boilers from Berkeley NPP, England - 13599

    Energy Technology Data Exchange (ETDEWEB)

    Wirendal, Bo [Studsvik Nuclear AB (Sweden); Saul, David; Robinson, Joe; Davidson, Gavin [Studsvik UK Ltd (United Kingdom)

    2013-07-01

    In November 2011 Studsvik was awarded a contract to transport five decommissioned boilers from the Berkeley Nuclear Licensed Site in the UK to the Studsvik Nuclear Site in Sweden for metal treatment and recycling. A key objective of the project was to remove the boilers from the site by 31 March 2012 and this was successfully achieved with all boilers off site by 22 March and delivered to Studsvik on 6 April. Four boilers have been processed and the fifth is planned for completion by end of December 2012.The project had many challenges including a very tight timescale and has been successfully delivered to cost and ahead of the baseline programme. This paper describes the project and the experience gained from treatment of the first four boilers. It is the first UK project to send large components overseas for recycling and provides new insight into the processing of Magnox gas-circuit components. (authors)

  17. 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

    Under contract with the U.S. Department of Energy, the College of Engineering at the University of South Carolina has conducted an assessment of educational needs among engineers working in nuclear fuel cycle related areas. The study was initiated as a regional effort focusing on the concentration of nuclear industry in the Southeast. Educational needs addressed were those at the post-baccalaureate professional level. The project was envisioned as providing base line information for the eventual implementation of a program in line with the needs of the Southeast's nuclear community. Specific objectives were to establish the content of such a program and to determine those specialized features which would make the program most attractive and useful.

  18. Study of advanced professional educational requirements relative to nuclear fuel cycle engineering in industry and government. Final report

    International Nuclear Information System (INIS)

    Under contract with the U.S. Department of Energy, the College of Engineering at the University of South Carolina has conducted an assessment of educational needs among engineers working in nuclear fuel cycle related areas. The study was initiated as a regional effort focusing on the concentration of nuclear industry in the Southeast. Educational needs addressed were those at the post-baccalaureate professional level. The project was envisioned as providing base line information for the eventual implementation of a program in line with the needs of the Southeast's nuclear community. Specific objectives were to establish the content of such a program and to determine those specialized features which would make the program most attractive and useful

  19. Networking of institutions in India to promote research and education in nuclear science and engineering

    International Nuclear Information System (INIS)

    Full text: The Programme of Nuclear Energy and its Applications (NEA) is knowledge intensive requiring engineers and scientists having special education and training for its implementation. The paucity of manpower in managing this programme is partly due to limitations of the university system in catering to the needs of the nuclear industry. Those limitations arise due to several reasons, like, regulatory requirements which make it difficult to set up nuclear facilities in university environment, capital intensive nature of nuclear set-ups, paucity of teaching staff having hands-on experience and limited employment opportunities making nuclear option unattractive for talented youngsters. The Department of Atomic Energy of India (DAE) established in 1954 for shaping and managing the Indian NEA programme realized those limitations and opted for an in-house education and training programme leading to assured employment for young Engineering Graduates and Science Post Graduates. Called the Bhabha Atomic Research Centre (BARC) Training School Programme, it is in place since 1957. The Indian NEA programme is thus fortunate to be supported by a visionary human resource development (HRD) programme in nuclear science and technology practically right since its inception. The success of HRD programme of DAE lies in its broader outlook based on the premise that technology development and basic research go hand-in-hand. This outlook is reflected also in the way DAE has been managing the implementation of its programme in that on one hand it has set up centres for technological Research and Development and, on the other, it is providing Grant-in-Aid to several Institutes for carrying basic research. Moreover, DAE has not lost sight of the fact that success of its initiatives lies as much in the vibrant university system as in its own training and educational efforts. It has, therefore, created avenues for extra-mural funding for supporting research activities in universities in

  20. Unique approaches in emphasizing the role of reactor laboratories and facilities for training and education of future nuclear engineers 'without the borders'

    International Nuclear Information System (INIS)

    The 21st century brings numerous challenges into daily lives of nuclear engineers worldwide, such as at nuclear power plants (facing new safety paradigm influenced by 2011-unfortunate Japanese Fukushima incident), at the universities in educating and training new generations of nuclear engineers in capturing new expectations of safety standards, and in reaching out to countries that are interested to develop new or revitalize their decades-old education and training programs as pertaining to nuclear engineering and science. In this paper we present two novel aspects we have developed: (a) the establishment of novel educational approaches pertaining to training and practices of nuclear safety culture in university curricula, and (b) development of novel digital-type class focused on the basic aspects of nuclear science and engineering shared between a class in the State of Utah (USA) and Uruguay. (author)

  1. A transdisciplinary approach to education and training in radiological protection and nuclear engineering

    International Nuclear Information System (INIS)

    Full text: This paper aims at developing an argumentation for an approach to education and training in radiological protection (RP) and nuclear engineering that is broader than the 'classical' acquiring of factual knowledge related to physics and regulation. As for most other areas where applications of a technology are connected to a certain risk, the complexity of applications of radioactivity and nuclear technology has generally technical as well as social dimensions. As well the nuclear worker as the policy maker, or any other person working within an application field of ionising radiation, could face situations requiring action where, apparently, the available factual knowledge does not lead unambiguously to a way forward that is 'justified enough' in relation to the potential risk. And if the solution would be justified for him/her, it could be that others involved have different opinions. Having this in mind, it is clear that education and training in RP - seen as a continuous learning process - should elaborate on as well the socio-technical complexity of 'risk assessment' as on the conditions and methodologies to 'find a way out'. Rather than dwelling on methodologies for the organisation of this 'broader' education and training, this paper will analyse elements of complex problem solving and make a link to ethical aspects in order to found the argumentation for this broader approach. We will highlight how the key ideas related to complex problem solving have been translated already in specific methodologies in socio-political science and epistemology. Based on the philosophical reasoning and on the related (existing) methodologies, we will then argue that the theory and practice of RP could and should develop as a systematic and interactive practice of a diversity of disciplines and skills, and that RP, in this sense, has the potential to serve as a key example of a transdisciplinary interaction of science with society. The paper then looks at the

  2. 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.

  3. Pass-Fail Grading at Berkeley: Facts and Opinions.

    Science.gov (United States)

    Suslow, Sidney

    The facts and opinions regarding pass/no pass grading at Berkeley discussed in this report are based on three sources of information. These sources include a survey of faculty conducted in the spring quarter 1970, a survey of undergraduate students in the winter quarter 1971, and the records routinely generated in the Registrar's Office for the…

  4. UC-Berkeley-area citizens decry waste transfer from lab.

    CERN Multimedia

    Nakasato, L

    2002-01-01

    Residents are working to stop the transfer of potentially hazardous and radioactive material from Lawrence Berkeley National Laboratory. The lab has begun to dismantle the Bevatron which has been shut down since 1993 and says eight trucks per day will move material offsite (1 page).

  5. Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1986

    Energy Technology Data Exchange (ETDEWEB)

    Schleimer, G.E. (ed.)

    1987-04-01

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory is described. Data for 1986 are presented and general trends are discussed. Topics include radiation monitoring, wastewater discharge monitoring, dose distribution estimates, and ground water monitoring. 9 refs., 8 figs., 20 tabs.

  6. Integration Defended: Berkeley Unified's Strategy to Maintain School Diversity

    Science.gov (United States)

    Chavez, Lisa; Frankenberg, Erica

    2009-01-01

    In June 2007, the Supreme Court limited the tools that school districts could use to voluntarily integrate schools. In the aftermath of the decision, educators around the country have sought models of successful plans that would also be legal. One such model may be Berkeley Unified School District's (BUSD) plan. Earlier this year, the California…

  7. Lawrence Berkeley Laboratory Institutional Plan FY 1995--2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    This report presents the details of the mission and strategic plan for Lawrence Berkeley Laboratory during the fiscal years of 1995--2000. It presents summaries of current programs and potential changes; critical success factors such as human resources; management practices; budgetary allowances; and technical and administrative initiatives.

  8. Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1986

    International Nuclear Information System (INIS)

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory is described. Data for 1986 are presented and general trends are discussed. Topics include radiation monitoring, wastewater discharge monitoring, dose distribution estimates, and ground water monitoring. 9 refs., 8 figs., 20 tabs

  9. Materials Science and Technology - Nuclear Materials, Advanced Course - Kon-67.5100 Postgraduate Seminar on Engineering Materials - Seminar papers 8 October, 2015

    OpenAIRE

    Hänninen, Hannu; Kiesi, Timo (editor); Lindqvist, Sebastian; Leskelä, Esa; Lindroos, Vesa; POHJA Rami; Rantanen, Ville; Salenius, Elina; Sarikka, Teemu

    2015-01-01

    The Engineering materials research group of Department of Engineering Design and Production of Aalto University arranged a postgraduate course on nuclear materials. The course consisted of three day long lecture session given in April 20-22, 2015. Lectures were given by professionals from nuclear power related research institutes (Aalto and VTT), nuclear industry and authority. The course also included a seminar session held October 8, 2015. The seminar session was targeted to postgraduate st...

  10. Hydrogeology and tritium transport in Chicken Creek Canyon,Lawrence Berkeley National Laboratory, Berkeley, California

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, Preston D.; Javandel, Iraj

    2007-10-31

    This study of the hydrogeology of Chicken Creek Canyon wasconducted by the Environmental Restoration Program (ERP) at LawrenceBerkeley National Laboratory (LBNL). This canyon extends downhill fromBuilding 31 at LBNL to Centennial Road below. The leading edge of agroundwater tritium plume at LBNL is located at the top of the canyon.Tritium activities measured in this portion of the plume during thisstudy were approximately 3,000 picocuries/liter (pCi/L), which issignificantly less than the maximum contaminant level (MCL) for drinkingwaterof 20,000 pCi/L established by the Environmental ProtectionAgency.There are three main pathways for tritium migration beyond theLaboratory s boundary: air, surface water and groundwater flow. Thepurpose of this report is to evaluate the groundwater pathway.Hydrogeologic investigation commenced with review of historicalgeotechnical reports including 35 bore logs and 27 test pit/trench logsas well as existing ERP information from 9 bore logs. This was followedby field mapping of bedrock outcrops along Chicken Creek as well asbedrock exposures in road cuts on the north and east walls of the canyon.Water levels and tritium activities from 6 wells were also considered.Electrical-resistivity profiles and cone penetration test (CPT) data werecollected to investigate the extent of an interpreted alluvial sandencountered in one of the wells drilled in this area. Subsequent loggingof 7 additional borings indicated that this sand was actually anunusually well-sorted and typically deeply weathered sandstone of theOrinda Formation. Wells were installed in 6 of the new borings to allowwater level measurement and analysis of groundwater tritium activity. Aslug test and pumping tests were also performed in the wellfield.

  11. Infrastructures Development Strategy in Energy Engineering Education and Research: a Bonus to Introduce a Safe and Secure Nuclear Power Program

    International Nuclear Information System (INIS)

    In the area of Energy Engineering, high education programs including nuclear activities are currently running in collaboration with the employment sector to provide skills oriented profiles; the available packages are thus characterized by a limited size and a low impact in enhancing power technology teaching and industrial partnerships. However, ongoing nuclear applications activities are undertaken through strong legal and institutional infrastructures as Morocco has joined a large number of international conventions and agreements trusted by the IAEA. The introduction of nuclear power is subject to a close attention today to investigate if it is an alternative solution to meet the increasing energy needs. For a country not much industrialized and characterized by a medium electricity grid, the decision on the recourse to nuclear power needs to carry up early a training, R and D federative program on behalf of the engineering sector and the international cooperation. As the challenges associated to develop a successful nuclear power program requires an important effort directed toward increasing capacity, new education and training programs in the field of Energy Sciences and Engineering are presently targeted in several high education institutions prior to the goals of the education and research national reform. The preparation of a new master and engineer diploma at ENIM 'Power Systems Engineering and Management' is in process: the curricula introduces innovative concepts bringing together academic teachers, researchers and stakeholders to establish new discipline-based teaching and learning tools: what is mainly focused is to increase competency profile in consultation with the industry sector and to attract high quality students to ensure availability of human resources at the right time in the field of power technology utilization including nuclear power. A coordinated approach joining national and international partnership to implement oriented R and D

  12. Application of AI Technology for some design problems in nuclear engineering

    International Nuclear Information System (INIS)

    We have been engaged in the research and development on advanced computer application such as artificial intelligence in the field of instrumentation, control and systems analysis of nuclear engineering, for a long period since early 80a. Since then, our research activities have covered the following areas: reactor diagnostic methods and systems, post-trip plant analyzer. module-based simulation system for NPP dynamic simulation, various intelligent support methods for light water reactor two-phase flow analysis, intelligent CAD/CAE system for conceptual design of advanced reactor, human cognitive experiment on man-machine interface and the related bio cybernetic measurement, and man-machine system design evaluation methodology development. In this paper, we will start by brief historical reviews on our past progress in the aforementioned research items to. Then, we will proceed to introduce on-going two topics and, concerning methodological development of object-oriented intelligent CAD/CAE model for conceptual design of advanced reactor, and realtime human cognitive state estimator by means of bio cybernetic measurement

  13. Parallel computing in cluster of GPU applied to a problem of nuclear engineering

    International Nuclear Information System (INIS)

    Cluster computing has been widely used as a low cost alternative for parallel processing in scientific applications. With the use of Message-Passing Interface (MPI) protocol development became even more accessible and widespread in the scientific community. A more recent trend is the use of Graphic Processing Unit (GPU), which is a powerful co-processor able to perform hundreds of instructions in parallel, reaching a capacity of hundreds of times the processing of a CPU. However, a standard PC does not allow, in general, more than two GPUs. Hence, it is proposed in this work development and evaluation of a hybrid low cost parallel approach to the solution to a nuclear engineering typical problem. The idea is to use clusters parallelism technology (MPI) together with GPU programming techniques (CUDA - Compute Unified Device Architecture) to simulate neutron transport through a slab using Monte Carlo method. By using a cluster comprised by four quad-core computers with 2 GPU each, it has been developed programs using MPI and CUDA technologies. Experiments, applying different configurations, from 1 to 8 GPUs has been performed and results were compared with the sequential (non-parallel) version. A speed up of about 2.000 times has been observed when comparing the 8-GPU with the sequential version. Results here presented are discussed and analyzed with the objective of outlining gains and possible limitations of the proposed approach. (author)

  14. 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 o...... 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.......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...... - 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...

  15. Karlsruhe Nuclear Research Center, Institute of Neutron Physics and Reactor Engineering. Progress report on research and development work in 1993

    International Nuclear Information System (INIS)

    The Institute of Neutron Physics and Reactor Engineering is concerned with research work in the field of nuclear engineering related to the safety of thermal reactors as well as with specific problems of fusion reactor technology. Under the project of nuclear safety research, the Institute works on concepts designed to drastically improve reactor safety. Apart from that, methods to estimate and minimize the radiological consequences of reactor accidents are developed. Under the fusion technology project, the Institute deals with neutron physics and technological questions of the breeding blanket. Basic research covers technico-physical questions of the interaction between light ion radiation of a high energy density and matter. In addition and to a small extent, questions of employing hydrogen in the transport area are studied. (orig.)

  16. Calibration of the Berkeley EUV Airglow Rocket Spectrometer

    Science.gov (United States)

    Cotton, Daniel M.; Chakrabarti, Supriya; Siegmund, Oswald

    1989-01-01

    The Berkeley Extreme-ultraviolet Airglow Rocket Spectrometer (BEARS), a multiinstrument sounding rocket payload, made comprehensive measurements of the earth's dayglow. The primary instruments consisted of two near-normal Rowland mount spectrometers: one channel to measure several atomic oxygen features at high spectral resolution (about 1.5 A) in the band passes 980-1040 and 1300-1360 A, and the other to measure EUV dayglow and the solar EUV simultaneously in a much broader bandpass (250-1150 A) at moderate resolution (about 10 A). The payload also included a hydrogen Lyman-alpha photometer to monitor the solar irradiance and goecoronal emissions. The instrument was calibrated at the EUV calibration facility at the University of California at Berkeley, and was subsequently launched successfully on September 30, 1988 aboard a four-stage experimental sounding rocket, Black Brant XII flight 12.041 WT. The calibration procedure and resulting data are presented.

  17. Annual site environmental report of the Lawrence Berkeley Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Schleimer, G.E.; Pauer, R.O. (eds.)

    1991-05-01

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory is described. Data for 1990 are presented, and general trends are discussed. The report is organized under the following topics: Environmental Program Overview; Environmental Permits; Environmental Assessments; Environmental Activities; Penetrating Radiation; Airborne Radionuclides; Waterborne Radionuclides; Public Doses Resulting from LBL Operations; Trends -- LBL Environmental Impact; Waterborne Pollutants; Airborne Pollutants; Groundwater Protection; and Quality Assurance. 20 refs., 26 figs., 23 tabs.

  18. 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

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

    International Nuclear Information System (INIS)

    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. 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)

  1. Collaborative Russian-US work in nuclear material protection, control and accounting at the Institute of Physics and Power Engineering

    International Nuclear Information System (INIS)

    The Institute of Physics and Power Engineering (IPPE) is a leading research center under the Ministry of Atomic Energy of the Russian Federation. IPPE encompasses many installations and many specialists who perform fundamental and applied investigations in nuclear power and technology for the national nuclear program. IPPE has a key role in the national nuclear material protection, control, and accounting (MPC ampersand A) system both as a nuclear facility and also as a training center for MPC ampersand A. As a participant in the US-Russian Laboratory-to-Laboratory Cooperative Program in MPC ampersand A, IPPE is conducting several tasks in collaboration with US Department of Energy national laboratories. The main goal of these tasks is the rapid improvement of MPC ampersand A at one of the most sensitive operating IPPE installations, the BFS critical facility, which has large numbers of fuel items containing highly enriched uranium and weapons-grade plutonium. After the completion of several test, evaluation, and demonstration tasks, it is hoped that the tested and adopted methods and procedures can be applied not only to the entire population of BFS fuel items, but also to other facilities at IPPE and other Russian nuclear institutes and operating facilities. The collaborative tasks cover seven areas: computerized nuclear material accounting, entry control and portals, item control and inventory, design evaluation and analysis, gamma and neutron assay, an integrated demonstration, and physical protection elements and test bed

  2. Long-term lining performance - Civil engineering problem of potential retrieval of buried spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Vasicek, Radek, E-mail: radek.vasicek@fsv.cvut.c [Czech Technical University in Prague, Faculty of Civil Engineering, Centre of Experimental Geotechnics, Thakurova 7, 16629 Prague 6 (Czech Republic); Svoboda, Jiri, E-mail: jiri.svoboda@seznam.c [Czech Technical University in Prague, Faculty of Civil Engineering, Centre of Experimental Geotechnics, Thakurova 7, 16629 Prague 6 (Czech Republic)

    2011-04-15

    The current solution for the spent fuel, high-level and long-lived radioactive waste is to store them at surface facilities from which they will be subsequently moved to a deep repository. No such repositories are in operation currently but several such facilities are close to the construction phase. A deep repository can be situated in several types of geological conditions including clay formations, salt sediments, argillites and tuffitic and granitic rocks. The character of the host rock is the key factor determining the design and specific requirements of individual components of such a facility. The future potential retrieval of canisters containing nuclear waste from the repository is a further influential factor. The reason for retrieval of containers lies in the development of fast reactors and increased interest for spent fuel reprocessing. Naturally, the decision as to whether retrievability is technically feasible must be made before finalising the design and construction process of the repository. If the decision is made to retrieve, a design which will include all the relevant safety aspects for the potential retrieval of canisters must be determined. The lay-out of the repository, the materials to be used and the design of the various structures of the facility (e.g. access tunnels, disposal shafts, buffer and backfill) are not the only issues to be addressed. The long-term stability of the system as a whole, i.e. of all the components, is crucial. Depending on the disposal concept chosen, the thermal load generated by the waste in the disposal container, saturation by water from the surrounding environment and the loading of the host rock massif will constitute the main processes which will affect the behaviour, safety and future functioning of the repository from the civil engineering point of view. The long-term stability of the lining of disposal galleries is a basic precondition for the safe removal of spent nuclear waste from deep underground

  3. Innovation and practice on assessment of nuclear power engineering management procedures

    International Nuclear Information System (INIS)

    This article has introduced the innovative implementation method and process adopted by Shandong Nuclear Power Company in procedure management for AP1000 nuclear power project, summarized its effects, and also analyzed advantages and disadvantages of this management method. (authors)

  4. Nuclear Science Division 1992 annual report

    International Nuclear Information System (INIS)

    This report contains short papers from research conducted at Lawrence Berkeley Laboratory in Nuclear Physics. The categories of these papers are: Low-Energy Research Program; Bevalac Research Program; Relativistic Nuclear Collisions Program; Nuclear Theory Program; Nuclear Data Evaluation Program; and 88-Inch Cyclotron Operations

  5. Maintenance practices for emergency diesel generator engines onboard United States Navy Los Angeles class nuclear submarines

    OpenAIRE

    Hawks, Matthew Arthur

    2006-01-01

    CIVINS The United States Navy has recognized the rising age of its nuclear reactors. With this increasing age comes increasing importance of backup generators. In addition to the need for decay heat removal common to all (naval and commercial) nuclear reactors, naval vessels with nuclear reactors also require a backup means of propulsion. All underway Navy nuclear reactors are operated with diesel generators as a backup power system, able to provide emergency electric power for reactor dec...

  6. Strengthening the fission reactor nuclear science and engineering program at UCLA. Final technical report

    International Nuclear Information System (INIS)

    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. 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.

  8. 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.

  9. Emerging nuclear energy and transmutation systems: Core physics and engineering aspects

    International Nuclear Information System (INIS)

    The Technical Committee Meeting (TCM) on Core Physics and Engineering Aspects of Emerging Nuclear Energy Systems for Energy Generation and Transmutation held in December 2000, was convened by the IAEA on the recommendation of its Technical Working Group on Fast Reactors (TWG-FR). The objectives of this TCM were threefold: to review the status of Research and Development activities in the area of hybrid systems for energy generation and transmutation, to discuss specific scientific and technical issues covering the different R and D topics of these systems; and to recommend to the IAEA activities that would be specifically targeted to the needs of the Member States performing R and D in this field. The TCM had not called for broad overview papers of the various R and D fields. Apart from a rather brief presentation by each delegation of the general issues and the status of the R and D in the respective country, the IAEA had called for in-depth technical papers addressing one or more of the following topics: accelerator driven systems (ADS) concepts, requirements and features of ADS accelerators, target development, experiments and validation, sub-critical core studies, technology of heavy liquid metals, fuel and fuel processes development, and fuel cycle studies. Forty-five participants from eleven countries and one international organization attended the TCM, and thirty papers were presented. The status information presented in the delegates' general statements and in some of the papers is as of the time of the TCM. Thus, other later material should also be referenced for more current information. One such source of information is the Web Site of IAEA's project on Technology Advances in Fast Reactors and Accelerator Driven Systems for Actinide and Long lived Fission Product Transmutation (http://www.iaea.org/inis/aws/fnss/). However, the technical information provided in the papers, representing the bulk of the information presented, remains valid

  10. 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)

  11. Closing remarks at the American Nuclear Society-Atomic Energy Commission sponsored Symposium on engineering with nuclear explosives

    International Nuclear Information System (INIS)

    All 112 papers have been presented, at the 17 technical sessions. The technical highlights are divided into three parts: the highlights of the data from nuclear events, highlights from the broader research papers, and a discussion of some of the application papers

  12. Preliminary Thermo-hydraulic Core Design Analysis of Korea Advanced Nuclear Thermal Engine Rocket for Space Application

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-05-15

    Nclear rockets improve the propellant efficiency more than twice compared to CRs and thus significantly reduce the propellant requirement. The superior efficiency of nuclear rockets is due to the combination of the huge energy density and a single low molecular weight propellant utilization. Nuclear Thermal Rockets (NTRs) are particularly suitable for manned missions to Mars because it satisfies a relatively high thrust as well as a high propellant efficiency. NTRs use thermal energy released from a nuclear fission reactor to heat a single low molecular weight propellant, i. e., Hydrogen (H{sub 2}) and then exhausted the extremely heated propellant through a thermodynamic nozzle to produce thrust. A propellant efficiency parameter of rocket engines is specific impulse (I{sub sp}) which represents the ratio of the thrust over the rate of propellant consumption. The difference of I{sub sp} makes over three times propellant savings of NTRs for a manned Mars mission compared to CRs. NTRs can also be configured to operate bimodally by converting the surplus nuclear energy to auxiliary electric power required for the operation of a spacecraft. Moreover, the concept and technology of NTRs are very simple, already proven, and safe. Thus, NTRs can be applied to various space missions such as solar system exploration, International Space Station (ISS) transport support, Near Earth Objects (NEOs) interception, etc. Nuclear propulsion is the most promising and viable option to achieve challenging deep space missions. Particularly, the attractions of a NTR include excellent thrust and propellant efficiency, bimodal capability, proven technology, and safe and reliable performance. The ROK has also begun the research for space nuclear systems as a volunteer of the international space race and a major world nuclear energy country. KANUTER is one of the advanced NTR engines currently under development at KAIST. This bimodal engine is operated in two modes of propulsion with 100 MW

  13. Summary of the engineering assessment of inactive uranium mill tailings: Phillips/United Nuclear site, Ambrosia Lake, New Mexico

    International Nuclear Information System (INIS)

    Ford, Bacon and Davis Utah, Inc., has reevaluated the Phillips/United Nuclear site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Ambrosia Lake, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 2.6 million dry tons of tailings at the Phillips/United Nuclear site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The four alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material, to removal of the tailings to remote disposal sites and decontamination of the tailings site. Cost estimates for the four options range from about $21,500,000 for stabilization in-place, to about $45,200,000 for disposal at a distance of about 15 mi. Three principal alternatives for the reprocessing of the Phillips/United Nuclear tailings were examined: heap leaching; treatment at an existing mill; reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovered would be about $87/lb of U3O8 by either heap leach or conventional plant process. The spot market price for uranium was $25/lb early in 1981. Reprocessing the Phillips/United Nuclear tailings for uranium recovery does not appear to be economically attractive under present or foreseeable market conditions

  14. MITEE-B: A Compact Ultra Lightweight Bi-Modal Nuclear Propulsion Engine for Robotic Planetary Science Missions

    Science.gov (United States)

    Powell, James; Maise, George; Paniagua, John; Borowski, Stanley

    2003-01-01

    Nuclear thermal propulsion (NTP) enables unique new robotic planetary science missions that are impossible with chemical or nuclear electric propulsion systems. A compact and ultra lightweight bi-modal nuclear engine, termed MITEE-B (MInature ReacTor EnginE - Bi-Modal) can deliver 1000's of kilograms of propulsive thrust when it operates in the NTP mode, and many kilowatts of continuous electric power when it operates in the electric generation mode. The high propulsive thrust NTP mode enables spacecraft to land and takeoff from the surface of a planet or moon, to hop to multiple widely separated sites on the surface, and virtually unlimited flight in planetary atmospheres. The continuous electric generation mode enables a spacecraft to replenish its propellant by processing in-situ resources, provide power for controls, instruments, and communications while in space and on the surface, and operate electric propulsion units. Six examples of unique and important missions enabled by the MITEE-B engine are described, including: (1) Pluto lander and sample return; (2) Europa lander and ocean explorer; (3) Mars Hopper; (4) Jupiter atmospheric flyer; (5) SunBurn hypervelocity spacecraft; and (6) He3 mining from Uranus. Many additional important missions are enabled by MITEE-B. A strong technology base for MITEE-B already exists. With a vigorous development program, it could be ready for initial robotic science and exploration missions by 2010 AD. Potential mission benefits include much shorter in-space times, reduced IMLEO requirements, and replenishment of supplies from in-situ resources.

  15. 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.

  16. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    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

  17. Results of a monitoring programme in the environs of Berkeley aimed at collecting Chernobyl data for foodchain model validation

    International Nuclear Information System (INIS)

    The results of a fallout measurement programme which was carried out in the environs of Berkeley Nuclear Laboratory in the United Kingdom following the Chernobyl reactor accident in April 1986 are presented in this report. The programme was aimed at establishing a time-dependent data base of concentrations of Chernobyl fallout radionuclides in selected agricultural products. Results were obtained for milk, grass, silage, soil and wheat over an eighteen month period from May 1986. It is intended to use the data to validate the CEGB's dynamic foodchain model, which is incorporated in the FOODWEB module of the NECTAR environmental code. (author)

  18. A case for the expansion of effort and the adoption of a modified approach in Australia to education and research on the engineering and technology of nuclear power

    International Nuclear Information System (INIS)

    A positive initiative needs to be taken to place more emphasis on undergraduate education in the field of nuclear engineering in Australia. Excellent facilities exist at the AAEC to aid tertiary institutions. Many excellent opportunities also exist for developing post-graduate research projects in nuclear technology

  19. Radiological protection and nuclear engineering studies in multi-MW target systems

    OpenAIRE

    Luís, Raul Fernandes, 1984-

    2014-01-01

    Tese de doutoramento, Física, Universidade de Lisboa, Faculdade de Ciências, 2014 Several innovative projects involving nuclear technology have emerged around the world in recent years, for applications such as spallation neutron sources, accelerator-driven systems for the transmutation of nuclear waste and radioactive ion beam (RIB) production. While the available neutron Wuxes from nuclear reactors did not increase substantially in intensity over the past three decades, the i...

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

    International Nuclear Information System (INIS)

    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

  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. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement, Volume 1, Appendix C

    OpenAIRE

    United States Department of Energy

    1995-01-01

    The U.S. Department of Energy (DOE) is engaged in two related decisionmaking 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 tw...

  3. 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.

  4. 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

  5. Mid-Term Direction of JAEA Nuclear Fuel Cycle Engineering Laboratories

    International Nuclear Information System (INIS)

    1. Introduction Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) has sufficient experience and ability through its 50 year operation to establish the next generation closed cycle. It strives to become a world-class Center Of Excellence. 2. Current activity in NCL: 1) - Recycling of MOX fuel: The Tokai Reprocessing Plant has reprocessed 29 tons of MOX fuel from the ATR Fugenh as a part of 1140 tons of cumulative spent fuel reprocessed. JAEA has supported the pre-operation of the Rokkasho Reprocessing Plant. An innovative MOX pellet fabrication process has been developed in the Plutonium Fuel Development Center, and a part of products obtained by the development are used as a fuel for core confirmation test for re-startup of the FBR Monjuh. Characterization of MOX containing Am and Np has been studied and a new data such as melting point and thermal conductivity were reported. In the Chemical Processing Facility, a hot lab., an advanced aqueous reprocessing technology has been tested for TRU recovery, economical improvement, etc., using irradiated MOX fuel from the FR Joyoh. 2) - Supporting Activity: JAEA has improved the effectiveness and efficiency of existing safeguards activities. The Integrated Safeguards approach for all facilities in NCL has been implemented since August, 2008, as a pioneer and a good example in the world. To reduce anxiety among local residents, NCL has explained its operation plans and exchanged information and opinions with them concerning potential risks to health and environment. Recently, stake-holder participation in the management of NCL was started from the view point of Corporate Social Responsibility. In April, 2008, the agreement was signed with Idaho National Laboratory for cooperation of personnel training in fuel cycle area. 3. Mid-Term Direction: In Japan, feasibility and direction of the transition period from the LWR era to the FBR era should be discussed for the next several years. Study

  6. Community Relations Plan for Lawrence Berkeley Laboratory. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    The Lawrence Berkeley Laboratory (LBL) has applied to the California Environmental Protection Agency, Department of Toxic Substances Control (DTSC), for renewal of its Hazardous Waste Handling Facility Permit. A permit is required under Resource Conservation and Recovery Act (RCRA) regulations. The permit will allow LBL to continue using its current hazardous waste handling facility, upgrade the existing facility, and construct a replacement facility. The new facility is scheduled for completion in 1995. The existing facility will be closed under RCRA guidelines by 1996. As part of the permitting process, LBL is required to investigate areas of soil and groundwater contamination at its main site in the Berkeley Hills. The investigations are being conducted by LBL`s Environmental Restoration Program and are overseen by a number of regulatory agencies. The regulatory agencies working with LBL include the California Environmental Protection Agency`s Department of Toxic Substances Control, the California Regional Water Quality Control Board, the Bay Area Air Quality Management District, the East Bay Municipal Utilities District, and the Berkeley Department of Environmental Health. RCRA requires that the public be informed of LBL`s investigations and site cleanup, and that opportunities be available for the public to participate in making decisions about how LBL will address contamination issues. LBL has prepared this Community Relations Plan (CRP) to describe activities that LBL will use to keep the community informed of environmental restoration progress and to provide for an open dialogue with the public on issues of importance. The CRP documents the community`s current concerns about LBL`s Environmental Restoration Program. Interviews conducted between February and April 1993 with elected officials, agency staff, environmental organizations, businesses, site neighbors, and LBL employees form the basis for the information contained in this document.

  7. Lawrence Berkeley National Laboratory 1995 site environmental report

    Energy Technology Data Exchange (ETDEWEB)

    Balgobin, D.; Javandel, I.; Lackner, G.; Smith, C.; Thorson, P.; Tran, H.

    1996-07-01

    The 1995 Site Environmental Report summarizes environmental activities at the Ernest Orlando Lawrence Berkeley National Laboratory (LBNL) for the 1995 calendar year. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the environmental management programs. The report also discusses significant highlights and plans of these programs. Topics discussed include: environmental monitoring, environmental compliance programs, air quality, water quality, ground water protection, sanitary sewer monitoring, soil and sediment quality, vegetation and foodstuffs monitoring, and special studies which include preoperational monitoring of building 85 and 1995 sampling results, radiological dose assessment, and quality assessment.

  8. Assembly Manual for the Berkeley Lab Cosmic Ray Detector

    CERN Document Server

    Collier, M

    2002-01-01

    The Berkeley Lab Cosmic Ray Detector consists of 3 main components that must be prepared separately before they can be assembled. These components are the scintillator, circuit board, and casing. They are described in the main sections of this report, which may be completed in any order. Preparing the scintillator paddles involves several steps--cutting the scintillator material to the appropriate size and shape, preparing and attaching Lucite cookies (optional), polishing the edges, gluing the end to the photomultiplier tube (optional), and wrapping the scintillator. Since the detector has 2 paddles, each of the sections needs to be repeated for the other paddle.

  9. Lawrence Berkeley National Laboratory 1995 site environmental report

    International Nuclear Information System (INIS)

    The 1995 Site Environmental Report summarizes environmental activities at the Ernest Orlando Lawrence Berkeley National Laboratory (LBNL) for the 1995 calendar year. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the environmental management programs. The report also discusses significant highlights and plans of these programs. Topics discussed include: environmental monitoring, environmental compliance programs, air quality, water quality, ground water protection, sanitary sewer monitoring, soil and sediment quality, vegetation and foodstuffs monitoring, and special studies which include preoperational monitoring of building 85 and 1995 sampling results, radiological dose assessment, and quality assessment

  10. Annual environmental monitoring report of the Lawrence Berkeley Laboratory

    International Nuclear Information System (INIS)

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory (LBL) is described. Data for 1988 are presented and general trends are discussed. In order to establish whether LBL research activities produced any impact on the population surrounding the laboratory, a program of environmental air and water sampling and continuous radiation monitoring was carried on throughout the year. For 1988, as in the previous several years, dose equivalents attributable to LBL radiological operations were a small fraction of both the relevant radiation protection guidelines (RPG) and of the natural radiation background. 16 refs., 7 figs., 21 tabs

  11. Assembly Manual for the Berkeley Lab Cosmic Ray Detector

    International Nuclear Information System (INIS)

    The Berkeley Lab Cosmic Ray Detector consists of 3 main components that must be prepared separately before they can be assembled. These components are the scintillator, circuit board, and casing. They are described in the main sections of this report, which may be completed in any order. Preparing the scintillator paddles involves several steps--cutting the scintillator material to the appropriate size and shape, preparing and attaching Lucite cookies (optional), polishing the edges, gluing the end to the photomultiplier tube (optional), and wrapping the scintillator. Since the detector has 2 paddles, each of the sections needs to be repeated for the other paddle

  12. Stability of the Zagreb Carnegie-Mellon-Berkeley model

    CERN Document Server

    Osmanović, H; Švarc, A; Hadžimehmedović, M; Stahov, J

    2011-01-01

    In ref. [1] we have used the Zagreb realization of Carnegie-Melon-Berkeley coupled-channel, unitary model as a tool for extracting pole positions from the world collection of partial wave data, with the aim of eliminating model dependence in pole-search procedures. In order that the method is sensible, we in this paper discuss the stability of the method with respect to the strong variation of different model ingredients. We show that the Zagreb CMB procedure is very stable with strong variation of the model assumptions, and that it can reliably predict the pole positions of the fitted partial wave amplitudes.

  13. Annual environmental monitoring report of the Lawrence Berkeley Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Schleimer, G.E. (ed.)

    1989-06-01

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory (LBL) is described. Data for 1988 are presented and general trends are discussed. In order to establish whether LBL research activities produced any impact on the population surrounding the laboratory, a program of environmental air and water sampling and continuous radiation monitoring was carried on throughout the year. For 1988, as in the previous several years, dose equivalents attributable to LBL radiological operations were a small fraction of both the relevant radiation protection guidelines (RPG) and of the natural radiation background. 16 refs., 7 figs., 21 tabs.

  14. USING DOE-2.1 AT LAWRENCE BERKELEY LABORATORY

    Energy Technology Data Exchange (ETDEWEB)

    Building Energy Analysis Group.; Authors, Various

    1980-09-01

    The purpose of this manual is to assist the DOE-2 user to run DOE-2 and its utility programs at Lawrence Berkeley Laboratory (LBL). It is organized to reflect the facts that every DOE-2 job run at LBL requires certain steps, and that there are options related to DOE-2 job runs available to any DOE-2 user. The standard steps for running a DOE-2 job are as follows: 1. Prepare a job deck 2. Process a job deck 3. Obtain standard output reports.

  15. Assembly Manual for the Berkeley Lab Cosmic Ray Detector

    Energy Technology Data Exchange (ETDEWEB)

    Collier, Michael

    2002-12-17

    The Berkeley Lab Cosmic Ray Detector consists of 3 main components that must be prepared separately before they can be assembled. These components are the scintillator, circuit board, and casing. They are described in the main sections of this report, which may be completed in any order. Preparing the scintillator paddles involves several steps--cutting the scintillator material to the appropriate size and shape, preparing and attaching Lucite cookies (optional), polishing the edges, gluing the end to the photomultiplier tube (optional), and wrapping the scintillator. Since the detector has 2 paddles, each of the sections needs to be repeated for the other paddle.

  16. Lipoprotein subclasses in genetic studies: The Berkeley Data Set

    Energy Technology Data Exchange (ETDEWEB)

    Krauss, R.M.; Williams, P.T.; Blanche, P.J.; Cavanaugh, A.; Holl, L.G. [Lawrence Berkeley Lab., CA (United States); Austin, M.A. [Washington Univ., Seattle, WA (United States). Dept. of Epidemiology

    1992-10-01

    Data from the Berkeley Data Set was used to investigate familial correlations of HDL-subclasses. Analysis of the sibling intraclass correlation coefficient by HDL particle diameter showed that sibling HDL levels were significantly correlated for HDL{sub 2b}, HDL{sub 3a} and HDL{sub 3b} subclasses. The percentage of the offsprings` variance explained by their two parents. Our finding that parents and offspring-have the highest correlation for HDL{sub 2b} is consistent with published reports that show higher heritability estimates for HDL{sub 2} compared with HDL{sub 3}{minus} cholesterol.

  17. 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.

  18. Nuclear power facility siting with respect to geological and seismic engineering surveys

    Energy Technology Data Exchange (ETDEWEB)

    Simunek, P. (Energoprojekt, Prague (Czechoslovakia))

    1983-09-01

    The basic geological and seismological factors are defined considered in the site selection for a nuclear power plant: earthquakes, seismic waves, seismic hazard, magnitude, earthquake intensity, accelerogram, response spectrum, fault, design-basis earthquake and maximum hypothetical earthquake. The tasks are determined of geological surveys and the criteria set for evaluating the site with regard to the construction of a nuclear power plant.

  19. The Yankee approach to engineering support of operating nuclear power plants

    International Nuclear Information System (INIS)

    Although there has been a recent movement of engineering to plant sites in the hopes of improving engineering feedback and efficiency, the most critical aspect of success is not the location of the engineering staff but the working relationship between the Engineering Department and the plant staff. Both can be on the same site, but if the organizational structure restricts communication and diffuses responsibility and accountability, problems will result. At Yankee the author has found that the key ingredients to successful engineering and design integrity is a clear assignment of responsibility and accountability, free access to plant staff at all levels in design process, a minimization of bureaucracy and an environment that nurtures a close cooperative working relationship. This task is not easy, but it is a primary responsibility of management

  20. 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.

  1. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1982

    International Nuclear Information System (INIS)

    The results of the research carried out in fiscal 1982 commonly using the facilities in the Nuclear Engineering Research Laboratory, University of Tokyo, are summarized in this report. In the utilization of the nuclear reactor, the maximum output was limited to 500W, because it was necessary to examine the growth of the abnormal protrusion having arisen on fuel cladding. The linear accelerator was utilized almost perfectly. The total number of those who commonly utilized the facilities was 2,468, suggesting the importance of the role of common utilization. The summaries of the results of 12 on-pile researches, 11 off-pile researches and 18 researches using the linear accelerator are collected. The committee meetings held in fiscal 1982 are listed. The names of the members of various committees and the names of those in charge of various experiments are given. (Kako, I.)

  2. Implementation of Eugene Wigner Training Course at University 'Politehnica' of Bucharest Power Engineering Faculty Nuclear Power Plant Department

    International Nuclear Information System (INIS)

    Full text: 'Eugene Wigner Course' Training Course for Reactor Physics Experiments has been supported by the 5th Framework Programme of the European Commission, and it has been integrated in the ENEN (European Nuclear Engineering Network) program. This project has been prepared for the future European Nuclear Education schemes and degrees. Starting from a general presentation of the course this paper presents my opinion as a former student about the course impact. Presented is my opinion about the following: The content of theoretical courses; The usefulness of the textbook; The content of the practical experiments; The usefulness of the textbook for the practical experiments, and evaluations. Moreover, parts of this course were implemented to my seminars. Results and also expectations and conclusions about the usefulness of the course are presented. (author)

  3. Study of advanced professional educational requirements relative to nuclear fuel cycle engineering in industry and government. Final report

    International Nuclear Information System (INIS)

    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

  4. 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.

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

    International Nuclear Information System (INIS)

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

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

  7. 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.

  8. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.; 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.

  10. Berkeley extreme-ultraviolet airglow rocket spectrometer: BEARS.

    Science.gov (United States)

    Cotton, D M; Chakrabarti, S

    1992-09-20

    We describe the Berkeley extreme-UV airglow rocket spectrometer, which is a payload designed to test several thermospheric remote-sensing concepts by measuring the terrestrial O I far-UV and extreme-UV dayglow and the solar extreme-UV spectrum simultaneously. The instrument consisted of two near-normal Rowland mount spectrometers and a Lyman-alpha photometer. The dayglow spectrometer covered two spectral regions from 980 to 1040 A and from 1300 to 1360 A with 1.5-A resolution. The solar spectrometer had a bandpass of 250-1150 A with an ~ 10-A resolution. All three spectra were accumulated by using a icrochannel-plate-intensified, two-dimensional imaging detector with three separate wedge-and strip anode readouts. The hydrogen Lyman-alpha photometer was included to monitor the solar Lyman-alpha irradiance and geocoronal Lyman-alpha emissions. The instrument was designed, fabricated, and calibrated at the University of California, Berkeley and was successfully launched on 30 September 1988 aboard the first test flight of a four-stage sounding rocket, Black Brant XII. PMID:20733778

  11. Lawrence Berkeley National Laboratory 1997 Site Environmental Report Vol. I

    International Nuclear Information System (INIS)

    Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of U.S. Department of Energy Order 231.1. The Site Environmental Report for 1997 is intended to summarize Berkeley Lab's compliance with environmental standards and requirements, characterize environmental management efforts through surveillance and monitoring activities, and highlight significant programs and efforts for calendar year 1997. This report is structured into three basic areas that cover a general overview of the Laboratory, the status of environmental programs, and the results of the surveillance and monitoring activities, including air quality, surface water, groundwater, sanitary sewer, soil and sediment, vegetation and foodstuffs, radiation dose assessment, and quality assurance. The report is separated into two volumes. Volume I contains the body of the report, a list of references, a list of acronyms and abbreviations, a glossary, Appendix A (NESHAPS annual report), and Appendix B (distribution list for volume I). Volume II contains Appendix C, the individual data results from monitoring programs. Each chapter in volume I begins with an outline of the sections that follow

  12. Artificial neural networks in the nuclear engineering (Part 1); Redes neurais artificiais na engenharia nuclear (Parte 1)

    Energy Technology Data Exchange (ETDEWEB)

    Baptista Filho, Benedito Dias [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    2002-07-01

    Artificial Neural Networks (ANN) can be defined as 'parallel systems composed of layers of simple processing units highly interconnected and inspired in the human brain.' ANN can be used to solve problems of difficult modeling, when the data are fail or incomplete and in problems of control of high complexity. Several problems related with network training and generalization are to be solved to a safe utilization in nuclear plants systems. This work, divided into two parts, intends to begin a discussion on three ANN concepts: feed-forward neural networks, Self-Organized Maps (SOM), and multi-synaptic neural networks. The discussion will cover control applications, approximation of functions and pattern recognition. A few set of samples are commented. This first part focus on feed-forward neural networks with the back-propagation algorithm. (author)

  13. Seismic Protection of Laboratory Contents: The UC Berkeley Science Building Case Study

    OpenAIRE

    Comerio, Mary C.

    2003-01-01

    The research described in this report is a part of the Disaster Resistant University (DRU) initiative funded by the Federal Emergency Management Agency (FEMA) and the University of California, Berkeley. The first phase of the Disaster Resistant University initiative produced a study of potential earthquake losses at UC Berkeley together with an analysis of the economic impacts. In that report, Comerio (2000) found that despite the extraordinary building retrofit program, the UC Berkeley cam...

  14. The outlook for application of powerful nuclear thermionic reactor -powered space electric jet propulsion engines

    International Nuclear Information System (INIS)

    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)

  15. 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)

  16. Proceeding of the Seminar Nuclear Instrumentation Management and Technician of Engineering Research

    International Nuclear Information System (INIS)

    The proceeding is result of research activity report from researcher Center for Development of Nuclear Ores. The research paper include about Exploration; Geology; Processing Technology and Safety. The articles is indexing separately

  17. Nuclear

    International Nuclear Information System (INIS)

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  18. Support of nuclear engineering education and research at the University of Michigan

    International Nuclear Information System (INIS)

    This report describes progress on four different projects in the fission reactor area that have been supported by the grant during the past year. These projects are: Accelerator transmutation of nuclear waste (Steve Pearson); neutronic analysis of the Ford Nuclear Reactor (Brent Renkema); developing Monte Carlo benchmarks for commercial LWR configurations (Jie Du); Monte Carlo depletion capability for massively parallel processors (Amit Majumdar); these tasks are briefly described and progress to date is presented

  19. State of the art of earthquake engineering in nuclear power plant design

    International Nuclear Information System (INIS)

    A brief outline of definitions based on the USNRC, Seismic and Geologic Siting Criteria for Nuclear Power Plants, and on the plate tectonics and earthquake terminology is given. An introduction into plate tectonics and the associated earthquake phenomena is then presented. Ground motion characteristics are described in connection with the selection of design earthquakes. Mathematical methods of dynamic structural analyses are discussed for linear and nonlinear systems. Response analysis techniques for nuclear power plants are explained considering soil-structure interaction effects. (Auth.)

  20. 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.

  1. System engineering in the Nuclear Regulatory Commission licensing process: Program architecture process and structure

    International Nuclear Information System (INIS)

    In October 1987, the U.S. Nuclear Regulatory Commission (NRC) established the Center for Nuclear Waste Regulatory Analyses at Southwest Research Institute in San Antonio, Texas. The overall mission of the center is to provide a sustained level of high-quality research and technical assistance in support of NRC regulatory responsibilities under the Nuclear Waste Policy Act (NWPA). A key part of that mission is to assist the NRC in the development of the program architecture - the systems approach to regulatory analysis for the NRC high-level waste repository licensing process - and the development and implementation of the computer-based Program Architecture Support System (PASS). This paper describes the concept of program architecture, summarizes the process and basic structure of the PASS relational data base, and describes the applications of the system

  2. Early History of Heavy Isotope Research at Berkeley

    Energy Technology Data Exchange (ETDEWEB)

    Glenn T. Seaborg

    1976-06-01

    I have had the idea for some time that it would be interesting and worthwhile to put together an account of the early work on heavy isotopes at Berkeley. Of a special interest is the discovery of plutonium (atomic number 94) and the isotope U{sup 233}, and the demonstration of their fission with slow neutrons. This work served as a prelude to the subsequent Plutonium Project (Metallurgical Project) centered at the University of Chicago, in connection with which I have also had the idea of putting together a history of the work of my chemistry group. I have decided that it would be an interesting challenge to write this account on a day-to-day basis in a style that would be consistent with the entries having been written at the end of each day. The aim would be to make this history as accurate as possible by going back to the original records and using them with meticulous care.

  3. BVI photometry of the very old open cluster Berkeley 17

    CERN Document Server

    Bragaglia, A; Marconi, G; Tosi, M; Andreuzzi, Gloria; Bragaglia, Angela; Marconi, Gianni; Tosi, Monica

    2006-01-01

    We have obtained BVI CCD imaging of Berkeley 17, an anticentre open cluster that competes with NGC 6791 as the oldest known open cluster. Using the synthetic colour magnitude diagrams (CMD) technique with three sets of evolutionary tracks we have determined that its age is 8.5 - 9.0 Gyr, it distance modulus is (m-M)_0 = 12.2, with a reddening of E(B-V) = 0.62 - 0.60. Differential reddening, if present, is at the 5 % level. All these values have been obtained using models with metallicity about half of solar (Z=0.008 or Z=0.01 depending on the stellar evolution tracks), which allows us to reproduce the features of the cluster CMD better than other metallicities. Finally, from the analysis of a nearby comparison field we think to have intercepted a portion of the disrupting Canis Major dwarf galaxy.

  4. Berkeley Program Offers New Option for Financing Residential PV Systems

    Energy Technology Data Exchange (ETDEWEB)

    Bolinger, Mark A

    2008-07-06

    Readily accessible credit has often been cited as a necessary ingredient to open up the market for residential photovoltaic (PV) systems. Though financing does not reduce the high up-front cost of PV, by spreading that cost over some portion of the system's life, financing can certainly make PV systems more affordable. As a result, a number of states have, in the past, set up special residential loan programs targeting the installation of renewable energy systems and/or energy-efficiency improvements and often featuring low interest rates, longer terms and no-hassle application requirements. Historically, these loan programs have had mixed success (particularly for PV), for a variety of reasons, including a historical lack of homeowner interest in PV, a lack of program awareness, a reduced appeal in a low-interest-rate environment, and a tendency for early PV adopters to be wealthy and not in need of financing. Some of these barriers have begun to fade. Most notably, homeowner interest in PV has grown in some states, particularly those that offer solar rebates. The passage of the Energy Policy Act of 2005 (EPAct 2005), however, introduced one additional roadblock to the success of low-interest PV loan programs: a residential solar investment tax credit (ITC), subject to the Federal government's 'anti-double-dipping' rules. Specifically, the residential solar ITC--equal to 30% of the system's tax basis, capped at $2000--will be reduced or offset if the system also benefits from what is known as 'subsidized energy financing', which is likely to include most government-sponsored low-interest loan programs. Within this context, it has been interesting to note the recent flurry of announcements from a number of U.S cities concerning a new type of PV financing program. Led by the city of Berkeley, Calif., these cities propose to offer their residents the ability to finance the installation of a PV system using increased property tax

  5. Costs of delays in German nuclear power plant engineering - an attempted economic assessment

    International Nuclear Information System (INIS)

    Since 1975, all nuclear power plant projects in West Germany have been delayed as a result of more rigid requirements for construction permits, interruptions of construction, and failures to be granted the first part-construction permit which is required for the starting of construction. The total delays for all commercial nuclear power plants amount to 1160 months since 1974. The author investigates the direct and indirect costs of these delays. 23 commercial power plants are investigated which were started up in 1974 or later. (orig./UA)

  6. 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.

  7. Report 1986/1987. Department of Nuclear Engineering and Applied Research

    International Nuclear Information System (INIS)

    The objective of the Department of Applied Research is to carry out research on fields of physics, materials sciences, chemistry and engineering. Some branches of research can be mentioned: high Tc superconductors, hydrogen storage in metallic hydrides, extractive metallurgy of strategic minerals and others. In the first case, both the Development Division and the Thermodynamics group in the Metallurgy Division, have actively participated

  8. Long-term security of electrical and control engineering equipment in nuclear power stations to withstand a loss of coolant accident

    International Nuclear Information System (INIS)

    Electrical and control engineering equipment, which has to function even after many years of operation in the event of a fault in a saturated steam atmosphere of 160 C maximum, is essential in nuclear power stations in order to control a loss of coolant accident. The nuclear power station operators have, for this purpose, developed verification strategies for groups of components, by means of which it is ensured that the electrical and control engineering components are capable of dealing with a loss of coolant accident even at the end of their planned operating life. (orig.)

  9. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement, Summary

    OpenAIRE

    United States Department of Energy

    1995-01-01

    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 U.S. 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. F...

  10. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement, Volume 2, Part A

    OpenAIRE

    United States Department of Energy

    1995-01-01

    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 U.S. 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...

  11. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement, Volume 3, Part A

    OpenAIRE

    United States Department of Energy

    1995-01-01

    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 U.S. 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...

  12. 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.

  13. Table-top natural uranium subcritical assembly for nuclear engineering education

    International Nuclear Information System (INIS)

    A small water-moderated, natural uranium, table-top subcritical assembly has been used in teaching basic concepts of neutron diffusion, scattering, absorption, and multiplication in nuclear reactors. The assembly consists of a transparent Plexiglas tank, 0.7 m in height and 0.6 m in diameter. It contains a Plexiglas grid plate with positions for 60 aluminum-clad natural uranium metal fuel slugs, a central 253CF or PuBe neutron source, and a BF3 thermal neutron detector. Pieces of common materials encountered in nuclear reactors are used to illustrate different neutron absorption and scattering properties. The tank is portable with the water removed, and can be set up in a laboratory or classroom in a short time

  14. Dismantling of civilian nuclear powered fleet technical support vessels. engineering solutions - 59386

    International Nuclear Information System (INIS)

    At the present time six nuclear technical support vessels are operated and maintained by Atomflot. Two of them (Volodarsky FTB (floating technical base) and Lepse FTB) were taken out of service for decommissioning and are stored afloat. One more vessel Lotta FTB should be decommissioned during next two years. The nuclear technological support ships carrying spent nuclear fuel (SNF), liquid and solid radioactive wastes (LRW and SRW) appear to be a possible radiation contamination of Murmansk region and Kola Bay because the Ship long-term storage afloat has the negative effect on hull's structures technical condition. As a result of this in the context of the Federal Program 'Nuclear and Radiation Safety' (2008-2015) NIPTB Onega OAO was engaged by state corporation Rosatom to develop the dismantling procedure for Volodarsky FTB and Lotta FTB. Before developing of nuclear technological support ships decommissioning projects the technical and economic assessment of decommissioning/dismantling was carried out. The following options were examined: - formation of module as one-piece Ship's hull for long-term storage at Saida Bay; - formation of separated modules for long-term storage at Saida Bay; - complete dismantling of hull's structures, systems and equipment with packing all generated SRW into certified long-term storage containers. This paper contains description of options, research procedure, comparative analysis of options of decommissioning and dismantling (D and D) of nuclear technological support ships and its difference with dismantling of nuclear submarine. On the basis of the technical and economic assessment of FTB D and D options the least expensive on the first D and D stage and the least duration option is the option 1 (Formation of module as one-piece Ship's hull for long-term storage at Saida Bay). By the implementation of the given option there will be the need of large areas for modules storage at Saida Bay. It was not considered while working out

  15. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    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

  16. 10 CFR Appendix S to Part 50 - Earthquake Engineering Criteria for Nuclear Power Plants

    Science.gov (United States)

    2010-01-01

    ... criteria in Section VI of appendix A to 10 CFR part 100 continue to apply. Paragraphs IV.a.1.i, IV.a.1.ii... license, design approval, or manufacturing license is required by §§ 50.34(a)(12), 50.34(b)(10), or 10 CFR... final standard design for a nuclear power reactor of the type described in 10 CFR 50.22....

  17. Ion engine propelled Earth-Mars cycler with nuclear thermal propelled transfer vehicle, volume 2

    Science.gov (United States)

    Meyer, Rudolf X.; Baker, Myles; Melko, Joseph

    1994-01-01

    The goal of this project was to perform a preliminary design of a long term, reusable transportation system between earth and Mars which would be capable of providing both artificial gravity and shelter from solar flare radiation. The heart of this system was assumed to be a Cycler spacecraft propelled by an ion propulsion system. The crew transfer vehicle was designed to be propelled by a nuclear-thermal propulsion system. Several Mars transportation system architectures and their associated space vehicles were designed.

  18. Engineering works for increasing earthquake resistance of Hamaoka nuclear power plant

    International Nuclear Information System (INIS)

    The improvement works of the ground of outdoor piping and duct system of Hamaoka-3, one of engineering works for increasing earthquake resistance of the plant, are reported. The movable outdoor piping systems were moved. SJ method, one of the high-pressure jet mixing method, improved the ground between the duct and the unmoved light oil tank on the western side, and the environmental ground. The other places were improved by the concrete replacement works. The results of ground treated by SJ method showed the high quality of stiffness and continuity. Outline of engineering works, execution of concrete replacement works, the high-pressure jet mixing method, SJ method, the quality control and treatment of the generated mud by SJ method are reported. A seismic response analysis, execution facilities, construction planning, working diagram, improvement work conditions of three methods, and steps of SJ method are illustrated. (S.Y.)

  19. 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.

  20. Nuclear physics accelerator facilities

    International Nuclear Information System (INIS)

    This paper describes many of the nuclear physics heavy-ion accelerator facilities in the US and the research programs being conducted. The accelerators described are: Argonne National Laboratory--ATLAS; Brookhaven National Laboratory--Tandem/AGS Heavy Ion Facility; Brookhaven National Laboratory--Relativistic Heavy Ion Collider (RHIC) (Proposed); Continuous Electron Beam Accelerator Facility; Lawrence Berkeley Laboratory--Bevalac; Lawrence Berkeley Laboratory--88-Inch Cyclotron; Los Alamos National Laboratory--Clinton P. Anderson Meson Physics Facility (LAMPF); Massachusetts Institute of Technology--Bates Linear Accelerator Center; Oak Ridge National Laboratory--Holifield Heavy Ion Research Facility; Oak Ridge National Laboratory--Oak Ridge Electron Linear Accelerator; Stanford Linear Accelerator Center--Nuclear Physics Injector; Texas AandM University--Texas AandM Cyclotron; Triangle Universities Nuclear Laboratory (TUNL); University of Washington--Tandem/Superconducting Booster; and Yale University--Tandem Van de Graaff

  1. 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.

  2. 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

    International Nuclear Information System (INIS)

    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

  3. Prospects of international collaboration and knowledge transfer on project management and public relations in nuclear power engineering (economic aspect)

    International Nuclear Information System (INIS)

    In this paper author deals with public consultations of the State Scientific Engineering Center of Control Systems and Emergency Response, Kiev. The following conclusions should be made: - Public consultations support and strengthen the positive image of nuclear energy projects, also by youth. - The public relations work which includes only occasional meetings or discussions of some problems is not effective. - Effective are the following facilities: - press releases in popular scientific and technical issues (now there are a few of such issues because of lack of financing) - career-guidance at all phases of education (to begin with secondary schools to post-graduate courses). It is well known that the economic situation in a country influences the functioning of electric energy market and efficiency of energy companies. The aim of our research is to find out the ways of further development of energy branch and what economic consequences the different changes in legislation and taxation systems can bring about. Great attention is paid to the activities of the producers of nuclear energy and regional energy supplying companies and the state of payments in electric energy market. Current research is being carried out to find out the ways of enlarging current assets, decreasing debts, also optimal equipment depreciation normative and main dependencies between some economic indexes and existing tariffs. All these tasks can be effectively solved using the. (author)

  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. Instrumentation and control engineering at ENACE (Argentine Nuclear Enterprise of Electric Power Plants S.A.)

    International Nuclear Information System (INIS)

    This paper describes the techniques used in the project of instrumentation and control for the Atucha II nuclear power plant, from the original flow diagram of the system whose instrumentation and control is requested to the functional binary diagrams and control loops, through measurement sheets and other documentation. An account of the organization and handling of this mass of information is given, using an electronic processing system of data file for the project. A brief description of the task implied in the completing and updating of these files defines the scheme in which all the documentation development associated with a given process is included. (Author)

  6. 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.

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

    International Nuclear Information System (INIS)

    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)

  8. 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)

  9. Inherent safety of advanced nuclear engineering based on BN-800 - type fast reactors

    International Nuclear Information System (INIS)

    Considerations based on the prolonged experience of fast reactor operations exhibiting outlook application of reactors on a basis of BN-800 with sodium coolant are given. Reliability and safety of the block are supported by the probability analysis of safety in the content of engineering project. Conversion on the reactor core with nitride fuel will significantly raise a possibility to conform to safety and nonproliferation of fission materials needs. The suggested optimum variant for reactor core on a basis of nitride fuel is advanced

  10. Design, Analysis, and Evaluation of the UC-Berkeley Wave-Energy Extractor

    KAUST Repository

    Yeung, Ronald W.

    2012-01-01

    This paper evaluates the technical feasibility and performance characteristics of an ocean-wave energy to electrical energy conversion device that is based on a moving linear generator. The UC-Berkeley design consists of a cylindrical floater, acting as a rotor, which drives a stator consisting of two banks of wound coils. The performance of such a device in waves depends on the hydrodynamics of the floater, the motion of which is strongly coupled to the electromagnetic properties of the generator. Mathematical models are developed to reveal the critical hurdles that can affect the efficiency of the design. A working physical unit is also constructed. The linear generator is first tested in a dry environment to quantify its performance. The complete physical floater and generator system is then tested in a wave tank with a computer-controlled wavemaker. Measurements are compared with theoretical predictions to allow an assessment of the viability of the design and the future directions for improvements. © 2012 American Society of Mechanical Engineers.

  11. 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)

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

    International Nuclear Information System (INIS)

    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)

  13. 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.

  14. Tiger Team assessment of the Lawrence Berkeley Laboratory, Washington, DC

    Energy Technology Data Exchange (ETDEWEB)

    1991-02-01

    This report documents the results of the Department of Energy's (DOE's) Tiger Team Assessment of the Lawrence Berkeley Laboratory (LBL) conducted from January 14 through February 15, 1991. The purpose of the assessment was to provide the Secretary of Energy with the status of environment, safety, and health (ES H) programs at LBL. The Tiger Team concluded that curtailment of cessation of any operations at LBL is not warranted. However, the number and breadth of findings and concerns from this assessment reflect a serious condition at this site. In spite of its late start, LBL has recently made progress in increasing ES H awareness at all staff levels and in identifying ES H deficiencies. Corrective action plans are inadequate, however, many compensatory actions are underway. Also, LBL does not have the technical expertise or training programs nor the tracking and followup to effectively direct and control sitewide guidance and oversight by DOE of ES H activities at LBL. As a result of these deficiencies, the Tiger Team has reservations about LBL's ability to implement effective actions in a timely manner and, thereby, achieve excellence in their ES H program. 4 figs., 24 tabs.

  15. Status of the UC-Berkeley SETI Efforts

    CERN Document Server

    Korpela, Eric J; Bankay, Robert; Cobb, Jeff; Howard, Andrew; Lebofsky, Matt; Siemion, Andrew P V; von Korff, Joshua; Werthimer, Dan

    2011-01-01

    We summarize radio and optical SETI programs based at the University of California, Berkeley. The SEVENDIP optical pulse search looks for ns time scale pulses at visible wavelengths using an automated 30 inch telescope. The ongoing SERENDIP V.v sky survey searches for radio signals at the 300 meter Arecibo Observatory. The currently installed configuration supports 128 million channels over a 200 MHz bandwidth with ~1.6 Hz spectral resolution. SETI@home uses the desktop computers of volunteers to analyze over 160 TB of data at taken at Arecibo looking for two types of continuous wave signals and two types of pulsed signals. A version to be released this summer adds autocorrelation analysis to look for complex wave forms that have been repeated (and overlayed) after a short delay. SETI@home will soon be processing data of Kepler exoplanet systems collected at the GBT. The Astropulse project is the first SETI search for $\\mu$s time scale dispersed pulses in the radio spectrum. We recently reobserved 114 sky loc...

  16. Berkeley lab checkpoint/restart (BLCR) for Linux clusters

    Science.gov (United States)

    Hargrove, Paul H.; Duell, Jason C.

    2006-09-01

    This article describes the motivation, design and implementation of Berkeley Lab Checkpoint/Restart (BLCR), a system-level checkpoint/restart implementation for Linux clusters that targets the space of typical High Performance Computing applications, including MPI. Application-level solutions, including both checkpointing and fault-tolerant algorithms, are recognized as more time and space efficient than system-level checkpoints, which cannot make use of any application-specific knowledge. However, system-level checkpointing allows for preemption, making it suitable for responding to ''fault precursors'' (for instance, elevated error rates from ECC memory or network CRCs, or elevated temperature from sensors). Preemption can also increase the efficiency of batch scheduling; for instance reducing idle cycles (by allowing for shutdown without any queue draining period or reallocation of resources to eliminate idle nodes when better fitting jobs are queued), and reducing the average queued time (by limiting large jobs to running during off-peak hours, without the need to limit the length of such jobs). Each of these potential uses makes BLCR a valuable tool for efficient resource management in Linux clusters.

  17. Tiger Team assessment of the Lawrence Berkeley Laboratory, Washington, DC

    International Nuclear Information System (INIS)

    This report documents the results of the Department of Energy's (DOE's) Tiger Team Assessment of the Lawrence Berkeley Laboratory (LBL) conducted from January 14 through February 15, 1991. The purpose of the assessment was to provide the Secretary of Energy with the status of environment, safety, and health (ES ampersand H) programs at LBL. The Tiger Team concluded that curtailment of cessation of any operations at LBL is not warranted. However, the number and breadth of findings and concerns from this assessment reflect a serious condition at this site. In spite of its late start, LBL has recently made progress in increasing ES ampersand H awareness at all staff levels and in identifying ES ampersand H deficiencies. Corrective action plans are inadequate, however, many compensatory actions are underway. Also, LBL does not have the technical expertise or training programs nor the tracking and followup to effectively direct and control sitewide guidance and oversight by DOE of ES ampersand H activities at LBL. As a result of these deficiencies, the Tiger Team has reservations about LBL's ability to implement effective actions in a timely manner and, thereby, achieve excellence in their ES ampersand H program. 4 figs., 24 tabs

  18. Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, L.D. (ed.)

    1978-03-01

    The data obtained from the Environmental Monitoring Program of the Lawrence Berkeley Laboratory for the Calendar year 1977 are described and general trends are discussed. The general trend of decreasing radiation levels at our site boundary due to accelerator operation during past years has leveled off during 1977 and in some areas shows a slight but not statistically significant increase as predicted in last year's summary. There were changes in both ion beams as well as current which have resulted in shifts in maxima at the monitoring stations. The gamma levels are once again reported as zero. There is only one period of detectable gamma radiation due to accelerator operation. The annual dose equivalent are reported from the environmental monitoring stations since they have been established. Radiation levels at the Olympus Gate Station have shown a steady decline since 1959 when estimates were first made. The Olympus Gate Station is in direct view of the Bevatron and most directly influenced by that accelerator. Over the past several years the atmospheric sampling program has, with the exception of occasional known releases, yielded data which are within the range of normal background. The surface water program always yields results within the range of normal background. As no substantial changes in the quantities of radionuclides used are anticipated, no changes are expected in these observations.

  19. A study of the old galactic star cluster Berkeley 32

    CERN Document Server

    Richtler, T; Richtler, Tom; Sagar, Ram

    2001-01-01

    We present new CCD photometry of the distant old open star cluster Berkeley 32 in Johnson V and Cousins I passbands. A total of about 3200 stars have been observed in a field of 13X13 arcmin**2. The colour-magnitude diagram in V, (V-I) has been generated down to V = 22 mag. A broad but well defined main sequence is clearly visible. Some blue stragglers, a well developed subgiant branch and a Red Clump are also seen. By fitting isochrones to this CMD as well as to other CMDs available in the literature, and using the Red Clump location, the reddening, distance and age of the star cluster have been determined. The cluster has a distance of 3.3 kpc, its radius is about 2.4 pc; the reddening E(B-V) is 0.08 mag and the age is 6.3 Gyr. By comparison with theoretical isochrones, a metallicity of [Fe/H]= -0.2 dex has been estimated. We find a much flatter mass function than what has been found for young clusters. If the mass function is a power law dN/dm = const.*m**alpha, then we get alpha = -0.5+-0.3 in the mass ra...

  20. Berkeley lab checkpoint/restart (BLCR) for Linux clusters

    International Nuclear Information System (INIS)

    This article describes the motivation, design and implementation of Berkeley Lab Checkpoint/Restart (BLCR), a system-level checkpoint/restart implementation for Linux clusters that targets the space of typical High Performance Computing applications, including MPI. Application-level solutions, including both checkpointing and fault-tolerant algorithms, are recognized as more time and space efficient than system-level checkpoints, which cannot make use of any application-specific knowledge. However, system-level checkpointing allows for preemption, making it suitable for responding to ''fault precursors'' (for instance, elevated error rates from ECC memory or network CRCs, or elevated temperature from sensors). Preemption can also increase the efficiency of batch scheduling; for instance reducing idle cycles (by allowing for shutdown without any queue draining period or reallocation of resources to eliminate idle nodes when better fitting jobs are queued), and reducing the average queued time (by limiting large jobs to running during off-peak hours, without the need to limit the length of such jobs). Each of these potential uses makes BLCR a valuable tool for efficient resource management in Linux clusters