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Sample records for nuclear engineering draft

  1. ANENT reference curricula for Master Degree in Nuclear Engineering (Draft no. 1 = version 19 Feb 2006)

    International Nuclear Information System (INIS)

    Raghunathan, V.S.; Chung, B.J.; Duan, P.V.

    2007-01-01

    Subject contents in the following areas are presented in detail: Advanced Mathematics for Nuclear Engineering; Advanced Numerical Analysis; Advanced Computer Applications; Engineering Physics; Introduction to Nuclear Engineering (Core); Radiation Detection and Measurements (Core); Radiation Safety and Shielding; Power Plant Instrumentation; Nuclear Safety; Nuclear and Reactor Physics; Health Physics; Nuclear Heat Transfer; Nuclear Power Plants Engineering; Materials Science in Nuclear Engineering; Neutron Transport Theory; Reactor Kinetics; Advanced Nuclear Heat Transfer; Nuclear Reactor Numerical Analysis; Nuclear Fuel Cycle and Non-Proliferation; Power Reactor Design (System Engineering); Advanced Nuclear Safety; Probabilistic Safety Analysis; Strategy and Infrastructure for Nuclear Power; NPP Control and Instrumentation; Nuclear Regulation; Nuclear Material Engineering; Radiation Protection and Shielding; Application of Radioisotope and Radiation Sources; Non-Destructive Testing; Nuclear Imaging; Radioactive Waste Management; Advanced Health Physics; Applied Radiation Measurements; Advanced Laser Application Engineering; Advanced Quantum Engineering; Plasma Diagnostics; Plasma Processing Analysis; Advanced Plasma Engineering; Nuclear Spectroscopy; Thermonuclear Fusion Engineering

  2. India's draft nuclear doctrine

    International Nuclear Information System (INIS)

    Kapur, A.

    2000-01-01

    India's draft nuclear doctrine and its nuclear and missile testing are a response to recent international, regional and domestic developments. Nehru's policy of nuclear disarmament, non-discriminatory international arrangements and unilateral restraint has been overturned in favour of self-reliant security and negotiated nuclear restraints. The draft nuclear doctrine is aimed at transparency and formalization of existing capacities. It is anchored in the United Nations Charter, based on the legitimacy of self-defence and espouses minimum nuclear deterrence. After the launching of Pokhran II, the debate in India has been settled on weaponization and deployment. The doctrine is not country-specific with respect to threat perceptions, but the author posits that the long-term focus is on China and the short-term on Pakistan. The doctrine emphasizes civilian command and control. India's decision to test incurred diplomatic and other economic costs, but afforded new opportunities for the country to assert itself militarily and politically in Asia and in the world. There were no diplomatic costs in issuing the draft nuclear doctrine, but the author estimates the economic costs of a full-blown (triad) Indian nuclear deterrent. (author)

  3. Human-factors engineering-control-room design review: Shoreham Nuclear Power Station. Draft audit report

    International Nuclear Information System (INIS)

    Peterson, L.R.; Preston-Smith, J.; Savage, J.W.; Rousseau, W.F.

    1981-01-01

    A human factors engineering preliminary design review of the Shoreham control room was performed at the site on March 30 through April 3, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The presented sections are numbered to conform to the guidelines of the draft version of NUREG-0700. They summarize the teams's observations of the control room design and layout, and of the control room operators' interface with the control room environment

  4. Staff supplement to the draft report on human engineering guide to control room evaluation: response to comments, sample checklist, draft systems review guidelines, and evaluation procedures

    International Nuclear Information System (INIS)

    1981-03-01

    This staff supplement to Draft Report NUREG/CR-1580, Human Engineering Guide to Control Room Evaluation, provides staff responses to comments on the draft report and supplemental material not provided in the draft report. The supplemental material includes new draft guidelines for the systems review of nuclear power plant control rooms and sample checklists and corresponding human engineering guidelines

  5. Design of hoisting device used in nuclear power plants. KTA safety engineering code. Draft amendment, as of 6/98

    International Nuclear Information System (INIS)

    1998-06-01

    The draft amendment specifies, according to the hazards involved, (a) the general provisions, (b) additional provisions supplementing the general provisions, (c) more stringent provisions relating to aggravated risks, applicable to lifting gear, and (d) additional requirements for elevators in reactor containments and refuelling equipment, to be taken into account in the design of hoisting device used in nuclear power plants. The term hoisting device in this context covers elevators, cranes, winches, trolleys, load carrying equipment, and LWR refuelling machines as are used in nuclear power plants. (orig./CB) [de

  6. Draft audit report, human factors engineering control room design review: Saint Lucie Nuclear Power Plant, Unit No. 2

    International Nuclear Information System (INIS)

    Peterson, L.R.; Lappa, D.A.; Moore, J.W.

    1981-01-01

    A human factors engineering preliminary design review of the Saint Lucie Unit 2 control room was performed at the site on August 3 through August 7, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The review team included human factors consultants from BioTechnology, Inc., Falls Church, Virginia, and from Lawrence Livermore National Laboratory (University of California), Livermore, California

  7. Engineering opportunities in nuclear engineering

    International Nuclear Information System (INIS)

    Walton, D.G.

    1980-01-01

    The pattern of education and training of Nuclear Engineers in the UK is outlined under the headings; degree courses for professional engineers, postgraduate courses, education of technician engineers. Universities which offer specific courses are stated and useful addresses listed. (UK)

  8. 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)

    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

  9. Photographic and drafting techniques simplify method of producing engineering drawings

    Science.gov (United States)

    Provisor, H.

    1968-01-01

    Combination of photographic and drafting techniques has been developed to simplify the preparation of three dimensional and dimetric engineering drawings. Conventional photographs can be converted to line drawings by making copy negatives on high contrast film.

  10. 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)

    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

  11. 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.

  12. 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)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes

  13. 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)

    1994-06-01

    This document analyzes at a pregrammatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For pregrammatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes

  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

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document analyzes at a pregrammatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For pregrammatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes.

  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)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum and maximum treatment, storage, and disposal of US Department of Energy wastes

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum and maximum treatment, storage, and disposal of US Department of Energy wastes.

  17. Nuclear chemical engineering

    International Nuclear Information System (INIS)

    Lee, Geon Jae; Shin, Young Jun

    1989-08-01

    The contents of this book are introduction of chemical engineering and related chemistry on an atomic reactor, foundation of the chemistry nuclear chemical engineering, theory on nuclear engineering, the cycle of uranium and nuclear fuel, a product of nuclear division, nuclear reprocessing, management of spent fuel separation of radioisotope, materials of an atomic reactor, technology and chemistry related water in atomic reactors and utilization of radioisotope and radiation. This book has the exercises and reference books for the each chapter.

  18. 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)

    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

  19. 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)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures

  20. 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)

    1994-06-01

    The US Department of Energy (DOE) is currently deciding the direction of its environmental restoration and waste management programs at the Idaho National Engineering Laboratory (INEL) for the next 10 years. Pertinent to this decision is establishing policies for the environmentally sensitive and safe transport, storage, and management of spent nuclear fuels. To develop these policies, it is necessary to revisit or examine the available options. As a part of the DOE complex, the Hanford Site not only has a large portion of the nationwide DOE-owned inventory of spent nuclear fuel, but also is a participant in the DOE decision for management and ultimate disposition of spent nuclear fuel. Efforts in this process at Hanford include assessment of several options for stabilizing, transporting, and storing all or portions of DOE-owned spent nuclear fuel at the Hanford Site. Such storage and management of spent nuclear fuel will be in a safe and suitable manner until a final decision is made for ultimate disposition of spent nuclear fuel. Five alternatives involving the Hanford Site are being considered for management of the spent nuclear fuel inventory: (1) the No Action Alternative, (2) the Decentralization Alternative, (3) the 1992/1993 Planning Basis Alternative, (4) the Regionalization Alternative, and (5) the Centralization Alternative. AU alternatives will be carefully designed to avoid environmental degradation and to provide protection to human health and safety at the Hanford Site and surrounding region

  1. Dictionary of nuclear engineering

    International Nuclear Information System (INIS)

    Sube, R.

    1985-01-01

    This dictionary covers nuclear engineering defined in its general sense as applied nuclear physics: industrial and other applications of nuclear power, isotopes and ionizing radiation, nuclear materials, nuclear facilities and nuclear weapons together with their scientific and technological fundamentals. During the compilation of terms, great attention was only given to generally valid basic expressions and to special terms where these occurred in all four languages. A great number of textbooks and monographs, as well as specialist journals covering many years, have been evaluated. Detailed attention has been paid to standards. Of importance in nuclear engineering are the international standards of the International Atomic Energy Organization (including the terminology employed by the International Nuclear Information System INIS), the International Organization of Standardization, the Council for Mutual Economic Assistance, the World Energy Conference, the International Electrical Engineering Commission, and also a great many national standards which, unfortunately, frequently deviate from one another as regards definition and, in particular, designation. (orig.)

  2. Development of human factors engineering guide for nuclear power project

    International Nuclear Information System (INIS)

    Wu Dangshi; Sheng Jufang

    1997-01-01

    'THE PRACTICAL GUIDE FOR APPLICATION OF HUMAN FACTORS ENGINEERING TO NUCLEAR POWER PROJECT (First Draft, in Chinese)', which was developed under a research program sponsored by National Nuclear Safety Administration (NNSA) is described briefly. It is hoped that more conscious, more systematical and more comprehensive application of Human Factors Engineering to the nuclear power projects from the preliminary feasibility studies up to the commercial operation will benefit the safe, efficient and economical operations of nuclear power plants in China

  3. 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)

    1994-06-01

    Two types of projects in the spent nuclear fuel and environmental restoration and waste management activities at the Idaho National Engineering Laboratory (INEL) are described. These are: foreseeable proposed projects where some funding for preliminary planning and/or conceptual design may already be authorized, but detailed design or planning will not begin until the Department of Energy (DOE) has determined that the requirements of the National Environmental Policy Act process for the project have been completed; planned or ongoing projects not yet completed but whose National Environmental Policy Act documentation is already completed or is expected to be completed before the Record of Decision for this Envirorunental Impact Statement (EIS) is issued. The section on project summaries describe the projects (both foreseeable proposed and ongoing).They provide specific information necessary to analyze the environmental impacts of these projects. Chapter 3 describes which alternative(s) each project supports. Summaries are included for (a) spent nuclear fuel projects, (b) environmental remediation projects, (c) the decontamination and decommissioning of surplus INEL facilities, (d) the construction, upgrade, or replacement of existing waste management facilities, (e) infrastructure projects supporting waste management activities, and (f) research and development projects supporting waste management activities

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    Two types of projects in the spent nuclear fuel and environmental restoration and waste management activities at the Idaho National Engineering Laboratory (INEL) are described. These are: foreseeable proposed projects where some funding for preliminary planning and/or conceptual design may already be authorized, but detailed design or planning will not begin until the Department of Energy (DOE) has determined that the requirements of the National Environmental Policy Act process for the project have been completed; planned or ongoing projects not yet completed but whose National Environmental Policy Act documentation is already completed or is expected to be completed before the Record of Decision for this Envirorunental Impact Statement (EIS) is issued. The section on project summaries describe the projects (both foreseeable proposed and ongoing).They provide specific information necessary to analyze the environmental impacts of these projects. Chapter 3 describes which alternative(s) each project supports. Summaries are included for (a) spent nuclear fuel projects, (b) environmental remediation projects, (c) the decontamination and decommissioning of surplus INEL facilities, (d) the construction, upgrade, or replacement of existing waste management facilities, (e) infrastructure projects supporting waste management activities, and (f) research and development projects supporting waste management activities.

  5. Nuclear ship engineering simulator

    International Nuclear Information System (INIS)

    Itoh, Yasuyoshi; Kusunoki, Tsuyoshi; Hashidate, Koji

    1991-01-01

    The nuclear ship engineering simulator, which analyzes overall system response of nuclear ship numerically, is now being developed by JAERI as an advanced design tool with the latest computer technology in software and hardware. The development of the nuclear ship engineering simulator aims at grasping characteristics of a reactor plant under the situation generated by the combination of ocean, a ship hull and a reactor. The data from various tests with the nuclear ship 'MUTSU' will be used for this simulator to modulate and verify its functions of reproducing realistic response of nuclear ship, and then the simulator will be utilized for the research and development of advanced marine reactors. (author)

  6. Facts in nuclear engineering

    International Nuclear Information System (INIS)

    Buenemann, D.

    1979-07-01

    This compilation of facts has been published on behalf of Kerntechnische Gesellschaft (Society for Nuclear Engineering), as a basis for the discussion between promoters and opponents of nuclear power. It intends to make the nuclear discussion less emotional by providing relevant data material. (orig./HP) [de

  7. Nuclear engineering vocabulary

    International Nuclear Information System (INIS)

    Dumont, X.; Andrieux, C.

    2001-01-01

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

  8. 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.

  9. Introduction to nuclear engineering

    International Nuclear Information System (INIS)

    Gylys, J.

    1997-01-01

    The textbook, which is the first book in Lithuanian on this subject generalises information on key aspects of nuclear engineering. Specialists in nuclear power for Ignalina NPP and for the infrastructure of nuclear energy sector of Lithuania are prepared at Kaunas University of Technology. The textbooks the students and lecturers have been using to-date were mostly in other languages than Lithuanian and they have not been adapted for teaching in Lithuania's higher educational establishments. This textbook is useful also to anyone who is interested in the issues and future prospects of nuclear power. It contains the chapters on nuclear reactions, theory of nuclear reactors, nuclear reactors kinetics, neutronic analysis, thermalhydraulic calculations of nuclear reactors operation and description of the construction of Ignalina NPP. (author)

  10. Nuclear propulsion systems engineering

    International Nuclear Information System (INIS)

    Madsen, W.W.; Neuman, J.E.: Van Haaften, D.H.

    1992-01-01

    The Nuclear Energy for Rocket Vehicle Application (NERVA) program of the 1960's and early 1970's was dramatically successful, with no major failures during the entire testing program. This success was due in large part to the successful development of a systems engineering process. Systems engineering, properly implemented, involves all aspects of the system design and operation, and leads to optimization of theentire system: cost, schedule, performance, safety, reliability, function, requirements, etc. The process must be incorporated from the very first and continued to project completion. This paper will discuss major aspects of the NERVA systems engineering effort, and consider the implications for current nuclear propulsion efforts

  11. Introduction to nuclear engineering

    International Nuclear Information System (INIS)

    Bouchard, J.; Deffain, J.P.; Gouchet, A.

    2007-01-01

    This book is an introductory course to the technology of nuclear reactors, it is based on lectures given to students engaged in nuclear engineering curricula. A brief historical account of nuclear power is given in which Three Miles Island and Chernobyl accidents appear to be the main milestones because of their big impacts on the way to apprehend the safety in the design of a reactor for the first and on the public controversy of nuclear energy for the second. All the concepts and knowledge required to understand the design of a reactor and how it operates, are described: radioactivity, nuclear safety, irradiation effects on materials, uranium enrichment, reactor kinetics, fission products poisoning,... This book is made up of 4 parts: 1) nuclear power, 2) types of power nuclear reactors (PWR, BWR and fast reactors), 3) the fuel cycle, and 4) neutronics basics. (A.C.)

  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 C, Savannah River Site Spent Nuclear Fuel Mangement Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  13. 76 FR 61402 - Draft Nuclear Regulatory Commission Fiscal Year 2012-2016 Strategic Plan

    Science.gov (United States)

    2011-10-04

    ...-2016 Strategic Plan AGENCY: Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment... comment on draft NUREG-1614, Volume 5. ``U.S. Nuclear Regulatory Commission, FY 2012-2016 Strategic Plan,'' dated September 2011. The NRC's draft FY 2012-2016 strategic plan describes the agency's mission and...

  14. Nuclear engineering vocabulary

    International Nuclear Information System (INIS)

    2006-01-01

    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.)

  15. Traditional Engineering Graphics versus Computer-Aided Drafting: A View from Academe.

    Science.gov (United States)

    Foster, Robert J.

    1987-01-01

    Argues for a legitimate role of manually expressed engineering graphics within engineering education as a needed support for computer-assisted drafting work. Discusses what and how students should learn as well as trends in engineering graphics education. Compares and contrasts manual and computer drafting methods. (CW)

  16. Steps to nuclear power: Draft guidebook

    International Nuclear Information System (INIS)

    1974-01-01

    IAEA has produced this Guidebook as a general summary of the considerations applying to the introduction of nuclear power and in particular the decisions that have to be taken and the requirements for studies, organization and trained manpower on the path to the first nuclear power plant. Nuclear Power is described functionally from the point of view of an alternative energy source in power system expansion

  17. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-06

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

  18. 77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

    Science.gov (United States)

    2012-02-15

    ... Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide... draft regulatory guide (DG) DG-1271 ``Decommissioning of Nuclear Power Reactors.'' This guide describes... Regulatory Guide 1.184, ``Decommissioning of Nuclear Power Reactors,'' dated July 2000. This proposed...

  19. Welding in nuclear engineering

    International Nuclear Information System (INIS)

    1982-01-01

    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) [de

  20. 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.

  1. Nuclear Medicine Engineering

    International Nuclear Information System (INIS)

    Mateescu, Gheorghe; Craciunescu, Teddy

    2000-01-01

    'An image is more valuable than a thousand words' - this is the thought that underlies the authors' vision about the field of nuclear medicine. The monograph starts with a review of some theoretical and engineering notions that grounds the field of nuclear medicine: nuclear radiation, interaction of radiation with matter, radiation detection and measurement, numerical analysis. Products and methods needed for the implementation of diagnostic and research procedures in nuclear medicine are presented: radioisotopes and radiopharmaceuticals, equipment for in-vitro (radioimmunoassay, liquid scintillation counting) and in-vivo investigations (thyroid uptake, renography, dynamic studies, imaging). A special attention is focused on medical imaging theory and practice as a source of clinical information (morphological and functional). The large variety of parameters, components, biological structures and specific properties of live matter determines the practical use of three-dimensional tomographic techniques based on diverse physical principles: single-photon emission, positron emission, X-rays transmission, nuclear magnetic resonance, ultrasounds transmission and reflection, electrical impedance measurement. The fundamental reconstruction algorithms i.e., algorithms based on the projection theorem and Fourier filtering, algebraic reconstruction techniques and the algorithms based on statistical principles: maximum entropy, maximum likelihood, Monte Carlo algorithms, are depicted in details. A method based on the use of the measured point spread function is suggested. Some classical but often used techniques like linear scintigraphy and Anger gamma camera imaging are also presented together with some image enhancement techniques like Wiener filtering and blind deconvolution. The topic of the book is illustrated with some clinical samples obtained with nuclear medicine devices developed in the Nuclear Medicine Laboratory of the National Institute of Nuclear Physics and

  2. Neutrons and Nuclear Engineering

    International Nuclear Information System (INIS)

    Ekkebus, Allen E.

    2007-01-01

    Oak Ridge National Laboratory hosted two workshops in April 2007 relevant to nuclear engineering education. In the Neutron Stress, Texture, and Phase Transformation for Industry workshop (http://neutrons.ornl.gov/workshops/nst2/), several invited speakers gave examples of neutron stress mapping for nuclear engineering applications. These included John Root of National Research Council of Canada, Mike Fitzpatrick of the UK's Open University, and Yan Gao of GE Global Research on their experiences with industrial and academic uses of neutron diffraction. Xun-Li Wang and Camden Hubbard described the new instruments at ORNL that can be used for such studies. This was preceded by the Neutrons for Materials Science and Engineering educational symposium (http://neutrons.ornl.gov/workshops/edsym2007). It was directed to the broad materials science and engineering community based in universities, industry and laboratories who wish to learn what the neutron sources in the US can provide for enhancing the understanding of materials behavior, processing and joining. Of particular interest was the presentation of Donald Brown of Los Alamos about using 'Neutron diffraction measurements of strain and texture to study mechanical behavior of structural materials.' At both workshops, the ORNL neutron scattering instruments relevant to nuclear engineering studies were described. The Neutron Residual Stress Mapping Facility (NRSF2) is currently in operation at the High Flux Isotope Reactor; the VULCAN Engineering Materials Diffractometer will begin commissioning in 2008 at the Spallation Neutron Source. For characteristics of these instruments, as well as details of other workshops, meetings, capabilities, and research proposal submissions, please visit http://neutrons.ornl.gov. To submit user proposals for time on NRSF2 contact Hubbard at hubbardcratornl.gov

  3. 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)

    1994-06-01

    This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering

  4. Metallurgy for nuclear engineering

    International Nuclear Information System (INIS)

    Kozlov, A.F.

    1986-01-01

    Principal ways of development in metallurgy and metallurgical equipment on nuclear engineering plants are discussed. A great attention is paid to changing welded structures for casted and forged ones. These measures give the possibility to increase reliability of NPP components and decrease labour content. The following processing procedures have been introduced: vacuum carbon reduction providing small amount of nonmetallic inclusions in reactor vessel steel; manufacturing steel large-size castings (360 and 420 t) for WWER vessels; rolling at plate mill 5000 etc

  5. Earthquake engineering for nuclear facilities

    CERN Document Server

    Kuno, Michiya

    2017-01-01

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

  6. History of nuclear engineering curricula

    International Nuclear Information System (INIS)

    Murphy, G.

    1975-01-01

    With the realization that nuclear energy had a vast potential for peacetime development, universities throughout the country began to develop courses in nuclear energy. A pioneering educational effort was necessary because there was an inadequate number of trained faculty, no established curricula, no textbooks, and very little suitable equipment. Nevertheless, by the early 1950's, several programs in nuclear science and engineering were beginning to provide instruction to potential nuclear engineers. At that time, the American Society for Engineering Education (ASEE) established a nuclear committee to cooperate with the U. S. Atomic Energy Commission (AEC) in nuclear education matters. With the financial support of the AEC, textbook material was developed, faculty training programs were instituted, and funds were made available for equipment. Because of the large interest shown in the field, many colleges and universities began to develop nuclear engineering curricula. After a few years, the need arose for general guidelines in curricular development. This led to the development of a Committee on Objective Criteria in Nuclear Engineering Education in which ASEE and the American Nuclear Society cooperated with the support of AEC. The committee report emphasized basic science, nuclear energy concepts, and nuclear technology, which have continued to be the significant components of a nuclear engineering curriculum. The last ten years have brought increased emphasis on BS programs, the introduction of extensive computer-based instruction, and an increasing emphasis on the engineering aspects of nuclear reactor power systems

  7. The Process of Legal Drafting Regulation in the Development of the Nuclear Power Plant in Indonesia

    OpenAIRE

    Mardha, Amil

    2009-01-01

    THE PROCESS OF LEGAL DRAFTING REGULATION IN THE DEVELOPMENT OF THE NUCLEAR POWER PLANT IN INDONESIA. In Indonesia, the process of legal drafting to establish the regulation is based on the Act No. 10 Year 2004 on the Establishment of Legislation. The process shall comply with the constitutional and institutional requirements of national political and legal system. In drafting the development of the regulation of nuclear energy, BAPETEN has been involving some other agencies or other related g...

  8. Nuclear engineering in the linelight

    International Nuclear Information System (INIS)

    Blumentritt, G.; Schwaar, L.

    1979-01-01

    An insight is given into the state of art of nuclear engineering considering only essential problems. The subject is covered under the following headings: (1) the way to nuclear fission, (2) detectors for nuclear radiation, (3) measuring systems for nuclear radiation, (4) radioisotopes in industry, (5) aids in medicine, (6) radiation absorption and its utilization, (7) use of radioisotopes in research, (8) the chain reaction in a nuclear reactor, (9) power from nuclear power plants, (10) pressurized water reactors (PWR), (11) high-temperature reactors (HTGR), (12) fast breeder reactors (FBR), (13) nuclear energetics - a new branch of industry, (14) nuclear explosions, (15) nuclear research at Rossendorf, and (16) the energy of the future. An appendix includes definitions of terms used in nuclear engineering. The book is written for a wide circle of readers who are interested in the peaceful uses of nuclear energy

  9. Choosing nuclear engineering: A survey of nuclear engineering undergraduates

    International Nuclear Information System (INIS)

    Shillenn, J.K.; Klevans, E.H.

    1988-01-01

    Maintaining a reliable pool of qualified nuclear engineering graduates depends on the ability of nuclear engineering undergraduate programs to recruit students. With the prospect of declining enrollments in nuclear engineering it is important for nuclear engineering programs to know what factors influence students to choose nuclear engineering as an undergraduate major and why they choose a particular undergraduate program. This type of information can be very important to nuclear engineering programs that develop recruiting strategies. To provide some insight into this area, a questionnaire was designed and given to undergraduate nuclear engineering students at Pennsylvania State University. The purpose of the survey was to provide information on the reasons that students picked nuclear engineering as a career and chose to attend Penn State. The questionnaire was given to 27 students in their junior year during the spring semester of 1987 and again to 35 junior students during the spring semester of 1988. There was little difference except as noted between the two groups on their responses to the questionnaire. A partial listing of the survey results is provided

  10. 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.

  11. Risks in nuclear engineering

    International Nuclear Information System (INIS)

    Lindackers, K.H.

    1982-01-01

    The German nuclear power plant risk assessment study has not contributed to a higher degree of acceptance of light-water reactors among the general public. One reason is the fact that its predictions are much too inaccurate, and the consequences from severe accidents, regardless of their possibly extremely small likelihood, speak for themselves. The work still to be done in Phase B of the risk analysis will only be useful, if the safety factors in risk assessments can be drastically increased. The results of the risk analysis cannot be used in legislation or the administration of justice, because they are too incomplete and inaccurate. Scientific findings in risk analysis show that new designs and new components complicate objective judgement of changes in reactor safety engineering considerably. Every change in the required precautionary safety measures must be carefully considered, and if need be tested under the appropriate conditions. (orig./HSCH) [de

  12. New Tool to Draft National Nuclear Laws. Second Nuclear Law Handbook Available Online

    International Nuclear Information System (INIS)

    Kaiser, Peter

    2011-01-01

    Drafting new national nuclear laws and reviewing existing laws and regulations requires extensive and specialized expertise. For many countries this represents a significant challenge. The IAEA's legislative assistance programme was established to help Member States adopt adequate national nuclear legislation. In 2003, the legistlative assistance programme published the Handbook on Nuclear Law. The reference text provides a fundamental understanding of the key elements and principles of national nuclear legislation. The Handbook is widely utilized by Member States, industry and experts. A second volume of the Handbook was released during the IAEA's 54th General Conference, which convened in Vienna from 20 to 24 September 2010.

  13. 78 FR 55117 - Ultimate Heat Sink for Nuclear Power Plants; Draft Regulatory Guide

    Science.gov (United States)

    2013-09-09

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0203] Ultimate Heat Sink for Nuclear Power Plants; Draft... (DG), DG-1275, ``Ultimate Heat Sink for Nuclear Power Plants.'' This regulatory guide (RG) describes methods and procedures acceptable to the NRC staff that nuclear power plant facility licensees and...

  14. Fluidization in nuclear engineering

    Energy Technology Data Exchange (ETDEWEB)

    Sathiyamoorthy, D; Venugopalan, Ramani; Vijay, P L [Metallurgy Division, Bhabha Atomic Research Centre, Mumbai (India); Varadarajan, T G [Heavy Water Division, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    Fluidization technique has not been fully exploited in nuclear industries mainly due to lack of open literature or unawareness of its applications. Hence in this paper a detailed range of applications of fluidization in uranium extraction, nuclear fuel material preparation, fuel reprocessing and waste disposal is highlighted. A fluidized bed nuclear reactor concept is also presented. The need of fluidization for process improvement and modernization in nuclear programmes is stressed. (author). 40 refs., 3 figs.

  15. Assessment guide for tornado effect on Nuclear Power Plants (draft) with its commentaries

    International Nuclear Information System (INIS)

    Inoue, Hiroto; Fukunishi, Shiro; Suzuki, Tetsuo

    2013-10-01

    In the context of a severe accident at the Fukushima Daiichi Nuclear Power Station (NPS) operated by the Tokyo Electric Power Company (TEPCO) due to the 2011 off the Pacific coast of Tohoku Earthquake and Tsunami, Nuclear Regulation Authority (NRA) was established on September 19, 2012 under the relevant law. After that NRA organized a task force for studying new regulatory standards for nuclear power plants (NPPs) in consideration of lessons learned from the severe accident at Fukushima. In the task force open meeting, through discussing about design basis external natural events which should be considered in the new regulatory standards, tornado was newly introduced into new regulatory standards as an external natural event. Based on the decision that tornado was newly introduced into new regulatory standards, the Secretariat of the Nuclear Regulation Authority (SNRA) commissioned the Japan Nuclear Energy Safety Organization (JNES) to study an assessment guide for tornado effect on NPPs intended to be used for an official safety review for a NPP construction. JNES organized Sectional Committee for Tornado Effect Assessment Guide consisting of experts in meteorology and wind engineering fields, discussing about assessment methods for tornado effect on NPPs, draft version of the assessment guide for tornado effect on NPPs was completed on April 4, 2013, and JNES submitted the draft guide to SNRA on the same date. After that NRA called for public comments for the draft version of the assessment guide, the draft version of the assessment guide was partly amended taking posted public comments account, and tornado effect assessment guide was officially released on June 19, 2013. Contents in this paper are as follows, assessment guide for tornado effect on NPPs (Draft version on April 4, 2013), supplementary documents, calculation examples, and future tasks for further improved reliability of tornado effect assessment on NPPs. This draft guide consists of six chapters

  16. Assessment guide for tornado effect on Nuclear Power Plants (draft) with its commentaries

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, Hiroto; Fukunishi, Shiro; Suzuki, Tetsuo [Japan Nuclear Energy Safety Organization, Seismic Safety Department, Tokyo (Japan)

    2013-10-15

    In the context of a severe accident at the Fukushima Daiichi Nuclear Power Station (NPS) operated by the Tokyo Electric Power Company (TEPCO) due to the 2011 off the Pacific coast of Tohoku Earthquake and Tsunami, Nuclear Regulation Authority (NRA) was established on September 19, 2012 under the relevant law. After that NRA organized a task force for studying new regulatory standards for nuclear power plants (NPPs) in consideration of lessons learned from the severe accident at Fukushima. In the task force open meeting, through discussing about design basis external natural events which should be considered in the new regulatory standards, tornado was newly introduced into new regulatory standards as an external natural event. Based on the decision that tornado was newly introduced into new regulatory standards, the Secretariat of the Nuclear Regulation Authority (SNRA) commissioned the Japan Nuclear Energy Safety Organization (JNES) to study an assessment guide for tornado effect on NPPs intended to be used for an official safety review for a NPP construction. JNES organized Sectional Committee for Tornado Effect Assessment Guide consisting of experts in meteorology and wind engineering fields, discussing about assessment methods for tornado effect on NPPs, draft version of the assessment guide for tornado effect on NPPs was completed on April 4, 2013, and JNES submitted the draft guide to SNRA on the same date. After that NRA called for public comments for the draft version of the assessment guide, the draft version of the assessment guide was partly amended taking posted public comments account, and tornado effect assessment guide was officially released on June 19, 2013. Contents in this paper are as follows, assessment guide for tornado effect on NPPs (Draft version on April 4, 2013), supplementary documents, calculation examples, and future tasks for further improved reliability of tornado effect assessment on NPPs. This draft guide consists of six chapters

  17. Introduction to nuclear facilities engineering

    International Nuclear Information System (INIS)

    Sapy, Georges

    2012-06-01

    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

  18. 76 FR 52355 - NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report...

    Science.gov (United States)

    2011-08-22

    ... Testing at Nuclear Power Plants, Draft Report for Comment'' AGENCY: Nuclear Regulatory Commission. ACTION... Testing at Nuclear Power Plants, Draft Report for Comment,'' and subtitled ``Inservice Testing of Pumps... Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants'' is available electronically...

  19. 76 FR 46330 - NUREG-1934, Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG); Second Draft...

    Science.gov (United States)

    2011-08-02

    ... NUCLEAR REGULATORY COMMISSION [NRC-2009-0568] NUREG-1934, Nuclear Power Plant Fire Modeling... 1023259), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft Report for...), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft for Comment,'' is...

  20. ENEN - European nuclear engineering network

    International Nuclear Information System (INIS)

    Comsa, Olivia; Paraschiva, M.V.; Banutoiu, Maria

    2002-01-01

    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

  1. Nuclear Reactor Engineering Analysis Laboratory

    International Nuclear Information System (INIS)

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

    1998-01-01

    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

  2. Nuclear industry will be short of engineers

    International Nuclear Information System (INIS)

    Yates, M.

    1990-01-01

    This article discusses the potential shortage of nuclear engineers due to reduction of educational and training facilities and difficulty in attracting minorities into nuclear engineering. The article reports on recommendations from the National Research Council Nuclear Education Study Committee on attracting minorities to nuclear engineering, increasing DOE fellowships, funding for research and development, involvement of utilities and vendors, and support of the American Nuclear Society's advocacy of nuclear engineering education

  3. 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 F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering.

  4. Accreditation of nuclear engineering programs

    International Nuclear Information System (INIS)

    Williamson, T.G.

    1989-01-01

    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

  5. Training in nuclear engineering companies

    International Nuclear Information System (INIS)

    Perezagua, R. L.

    2013-01-01

    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)

  6. The future of nuclear engineering

    International Nuclear Information System (INIS)

    Beeden, Jeffrey

    2003-01-01

    Today, nuclear power refers to the splitting of large uranium atoms into smaller atoms with a net release of energy. Tomorrow, nuclear power will refer to the combining of hydrogen into larger atoms with a net release of energy. Nuclear power's future is fusion. The Mechanical Engineers of tomorrow will need to be familiar with the process of creating and harnessing the energy from a fusion reaction. During the oil shortage in the 1970's, America scrambled to initiate alternative methods of producing power. Nuclear fusion was one of them. As time passes, the solution to the world's energy crisis presses the countries of the world to find alternative forms of energy; nuclear fusion may contain the answer. In the near future, the field of fusion will open up and a new wave of engineers will flood into this field. Mechanical engineers will lead the way with advances in materials, computational fluid dynamics, finite element analysis for thermal and structural systems, and heat transfer designs to optimize nuclear fusion reactors and power plants. All this effort is in anticipation of creating a sustained fusion reaction that can generate enough heat to transfer to steam in order to generate electric power to sustain the fusion reaction and introduce power to the grid. (author)

  7. The mathematics of nuclear engineering

    International Nuclear Information System (INIS)

    Lewins, J.D.

    1982-01-01

    The mathematics of nuclear engineering is considered with especial reference to the problems of; the representation of the transformation of matter at the nuclear level by radioactive decay and neutron transmutation, the problem of the distribution of neutrons and other particles as a transport theory problem including some of the approximation methods used in this problem, particularly diffusion theory with particular emphasis on steady-state problems, time-dependent reactor kinetic and control, and the longer term changes involved with the nuclear fuel cycle both within and without the reactor itself. (U.K.)

  8. Development of Simulator Maintenance Engineer Qualification Program Draft

    International Nuclear Information System (INIS)

    Chung, Kyung Hun

    2010-01-01

    As of 2009, KHNP has currently seven full scope simulators that are used for training of Nuclear Power Plant (NPP) Operators. Well-trained Simulator Maintenance Engineers (SME) are required to support these simulators. These SMEs will maintain and address any issues identified or any changes required for keep up the simulator with their respective plant sites. These issues will be identified as Simulator Discrepancy Reports (DR) or Work Order (WO) by the simulator operation personnel in KHNP. The simulator maintenance is a very complex. The simulator consists of many areas of process and requires experts in software modeling for different processes such as Neutronics, thermohydraulics, Logics, control, Electrical systems and computer systems as well as hardware subjects such as I and C, I/O, computers, etc. All these areas need experts the subject expertise need to be divided among SME's. In other word the SME's need to be trained for different expertise as well as having different level of SME's. KHNP has seen the need to outsource the maintenance work for these complex simulators. To have one company concentrating on this work will have many benefits such as: · Provides proper and well trained experts · Maintains consistent support personnel · Maintains the maintenance history for the simulator · Coordinates and Maintains the knowledge in house · The simulator maintenance will be consistent In order to accomplish the goals, KEPCO RI has recognized that there is a need for a program to adequately train and qualify the SME's. KEPCO RI and GSE, which has provided 6 simulators among 7 NPP simulators in Korea, have jointly developed this Simulator Maintenance Engineer Qualification Program (SMEQP). After issue of this plan, KEPCO RI will maintain and modify as needed periodically to meet the goals and purpose of the plan

  9. Introduction to nuclear test engineering

    International Nuclear Information System (INIS)

    O'Neal, W.C.; Paquette, D.L.

    1982-01-01

    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

  10. Nuclear engineering terms and definitions

    International Nuclear Information System (INIS)

    1981-01-01

    The most important nuclear engineering's terms and definitions are given in this standard. The definitions take into account the Austrian Regulations for Radiation Protection, for and pertinent ISO and DIN-Standards as also the OENORM A7006 and OENORM A6601. (M.T.)

  11. Waste management in the nuclear engineering curriculum

    International Nuclear Information System (INIS)

    Tulenko, J.S.

    1989-01-01

    One of the most significant challenges facing the nuclear industry is to successfully close the nuclear fuel cycle and effectively demonstrate to the public that nuclear wastes do not present a health risk. This issue is currently viewed by many as the most important issue affecting public acceptance of nuclear power, and it is imperative that nuclear engineers be able to effectively address the question of nuclear waste from both a generation and disposal standpoint. To address the issue, the area of nuclear waste management has been made one of the fields of specialized study in the Department of Nuclear Engineering Sciences at the University of Florida. The study of radioactive waste management at the University of Florida is designed both for background for the general nuclear engineering student and for those wishing to specialize in it as a multidiscipline study area involving the Departments of Nuclear Engineering Sciences, Environmental Sciences, Material Science and Engineering, Geology, Civil Engineering, and Industrial Engineering

  12. A Survey of Former Drafting & Engineering Design Technology Students. Summary Findings of Respondents District-Wide.

    Science.gov (United States)

    Glyer-Culver, Betty

    In fall 2001 staff of the Los Rios Community College District Office of Institutional Research collaborated with occupational deans, academic deans, and faculty to develop and administer a survey of former Drafting and Engineering Design Technology students. The survey was designed to determine how well courses had met the needs of former drafting…

  13. Government's nuclear draft budget for fiscal 1995 totals 480 billion yen, up 5.2%

    International Nuclear Information System (INIS)

    1995-01-01

    The Japanese government's nuclear draft budget for fiscal 1995 totals 480,756 million yen (excluding the nuclear-related budget for universities under the auspices of the Ministry of Education, Culture and Science), 5.2% increase from the last year. The figure can be broken down into 194,793 million yen general account mainly assigned to research and development projects, and 295,963 million yen special account for power resource development. The total nuclear-related draft budget can be broken down into 344,201 million yen (6.2% increase) for the Science and Technology Agency which governs the various projects on the research and utilization of nuclear energy, and 133,430 million yen (4.6% increase) for the Ministry of International Trade and Industry which controls the development of and the regulation concerning commercial nuclear power plants. As for other ministries, 3,909 million yen for the contribution to IAEA and 283 million yen for OECD/NEA are allocated to the Ministry of Foreign Affairs. The nuclear draft budget of other ministries and agencies than STA and MITI totals 5,443 million yen (3.8% increase over fiscal 1994). The details of the nuclear-related draft budget of STA and MITI are listed. (K.I.)

  14. Fiscal 1990 draft nuclear budget up 2.0 % to 395.5 bil. yen

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The Japanese Government on December 29 approved a yen66.27 trillion general account draft budget for fiscal 1990, up 9.7% on fiscal '89, which will soon be sent to the Diet. The nuclear energy related draft budget in the general account is yen179.8 billion, covering expenditures on the implementation of various measures and actions relating to nuclear energy by ministerial agencies. Of the draft special account for power resources development for fiscal 1990, the nuclear power related budget for the Ministry of International Trade and Industry and the Science and Technology Agency is yen215.7 billion. The total amount of the nuclear energy budget in the two accounts is yen395.5 billion, up 2.0%. By Ministries, the Science and Technology Agency, having jurisdiction over the Japan Atomic Energy Research Institute, the Power Reactor and Nuclear Fuel Development Corp., the National Institute of Radiological Sciencies and other institutions, is alloted yen296.2 billion, up 5.2%. The draft nuclear related budget for the Ministry of International Trade and Industry, governing commercial nuclear power programs, is yen94.8 billion, down 6.7%. The other ministries are allocated yen4.5 billion, down 2.5%. (N.K.)

  15. Career Development in Nuclear Engineering

    International Nuclear Information System (INIS)

    Sibbens, G.

    2015-01-01

    In the eighties it was not common for girls to study engineering. But a few young girls have always been fascinated by science and technical applications and dared to go for a gender untypical education. What are these female engineers doing today? This paper describes the career development of a woman, who completed her Master of Science in Nuclear Engineering, found first a job in an international company as cooperator in the research group of radiation physics and later as head of technical support and quality assurance of medical systems and then succeeded in a competition to be recruited at the European Commission (EC). There she started as an assistant for the primary standardisation of radionuclides and high-resolution alpha-particle spectrometry including the preparation of radioactive sources in the radionuclide metrology sector at the Institute for Reference Materials and Measurements of the European Commission’s Joint Research Centre and consequently published her work in scientific journals. Today, 29 years later, I am the laboratory responsible for the preparation and characterisation of nuclear targets at EC-JRC-IRMM, leading a team that has unique know-how in the preparation of thin film deposits (called targets) tailor-made for nuclear physics measurements at the EC–JRC–IRMM and international accelerator sites. High quality measurements of nuclear data and materials are being asked for in the context of nuclear safety, minimisation of high level nuclear waste and safeguards and security. The different steps of my career development and the repeated process of managing learning, work, family and leisure are presented. The career path across different jobs and responsibilities and the career progress via a certification training programme are also explained to encourage the next generation of female professionals to continue playing a vital role in nuclear science and technology. (author)

  16. 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

  17. 76 FR 80409 - Draft Supplement 2 to Final Environmental Statement Related to the Operation of Watts Bar Nuclear...

    Science.gov (United States)

    2011-12-23

    ... Environmental Statement Related to the Operation of Watts Bar Nuclear Plant, Unit 2; Tennessee Valley Authority..., Related to the Operation of Watts Bar Nuclear Plant [WBN], Unit 2--Draft Report for Comment'' (draft SFES.... Stephen J. Campbell, Chief, Watts Bar Special Projects Branch, Division of Operating Reactor Licensing...

  18. Nuclear Engineering Academic Programs Survey, 2004

    International Nuclear Information System (INIS)

    Oak Ridge Institute for Science and Education

    2005-01-01

    This annual report details the number of nuclear engineering bachelor's, master's, and doctoral degrees awarded at a sampling of academic programs from 1998-2004. It also looks at nuclear engineering degrees by curriculum and the number of students enrolled in nuclear engineering degree programs at 31 U.S. universities in 2004

  19. BS degree in nuclear engineering or a nuclear option

    International Nuclear Information System (INIS)

    Williams on, T.G.

    1988-01-01

    Many nuclear engineering educators are concerned about the health of nuclear engineering academic departments. As part of a review of the BS nuclear engineering degree program at the University of Virginia, the authors surveyed several local utilities with operating nuclear plants about their needs for nuclear engineering graduates. The perception of many of the utility executives about a nuclear engineering degree and about a nuclear option in another engineering curriculum does not agree with the way the authors view these two degrees. The responses to two of the survey questions were of particular interest: (1) does your company have a preference between nuclear engineering graduates and graduates in other fields with a nuclear option? (2) what do you consider to be a minimum level of education in nuclear engineering for a nuclear option in mechanical engineering? All of the four utilities that were surveyed stated a preference for mechanical or electrical engineers with a nuclear option, although two indicated that there are certain jobs for which a nuclear engineering graduate is desired

  20. Nuclear engineering dictionary. Woerterbuch Kerntechnik

    Energy Technology Data Exchange (ETDEWEB)

    Sube, R

    1985-01-01

    This dictionary treats the subject field of nuclear engineering as a field of applied nuclear physics: Industrial and other applications of nuclear energy, isotopes and ionizing radiation, and their, scientific-technical bases. Emphasis is placed on the terminology of the nuclear fuel cycle. Other applications of nuclear energy include military applications, nuclear fusion technology, and plasma physics, as well as methods and equipment of isotope and radiation technology, without the aspects of biological applications. High-energy physics is also excluded. The terminology presented primarily covers general and basic concepts, special terms have been included as far as available and ascertainable in all four languages. For selection of terms, numerous textbooks and monographies have been searched and compared, as well as various subject-related journals which have been regularly scanned for years. Standards have been a main source of information, as e.g. the international standards of the IAEA (including the INIS terminology), of the ISO, of the COMECON, and of the World Energy Conference and the IEC. Numerous national standards have been evaluated in search for definitions and designations. Users will appreciate the introduction of subject-field codes indicating the main field of usage of a term. Explanations and other hints are numerous and extensive in order to clearly define the terms chosen from other, similar terms, and in order to show homonyms.

  1. Computational intelligence in nuclear engineering

    International Nuclear Information System (INIS)

    Uhrig, Robert E.; Hines, J. Wesley

    2005-01-01

    Approaches to several recent issues in the operation of nuclear power plants using computational intelligence are discussed. These issues include 1) noise analysis techniques, 2) on-line monitoring and sensor validation, 3) regularization of ill-posed surveillance and diagnostic measurements, 4) transient identification, 5) artificial intelligence-based core monitoring and diagnostic system, 6) continuous efficiency improvement of nuclear power plants, and 7) autonomous anticipatory control and intelligent-agents. Several Changes to the focus of Computational Intelligence in Nuclear Engineering have occurred in the past few years. With earlier activities focusing on the development of condition monitoring and diagnostic techniques for current nuclear power plants, recent activities have focused on the implementation of those methods and the development of methods for next generation plants and space reactors. These advanced techniques are expected to become increasingly important as current generation nuclear power plants have their licenses extended to 60 years and next generation reactors are being designed to operate for extended fuel cycles (up to 25 years), with less operator oversight, and especially for nuclear plants operating in severe environments such as space or ice-bound locations

  2. Nuclear engineering enrollments and degrees, 1994: Appendixes

    International Nuclear Information System (INIS)

    1995-05-01

    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

  3. Automatic drafting system for lined tanks used for nuclear power plants

    International Nuclear Information System (INIS)

    Sasaki, Ryoichi; Kikuchi, Nobuo

    1981-01-01

    The concrete vessels lined with metallic sheets are used widely in chemical and food industries and nuclear power plants. Especially in nuclear power plants, rectangular lined tanks have been adopted mainly to store radioactive liquid and solid wastes recently, because of the good volume efficiency. Though the basic structure of the lined tanks is the same, the volume and the form change according to the kinds of stored matters and the positions of pipe connections, and the form of individual lining sheets diversifies. As much labor and time are consumed for the drawing, automatic drafting was planned, and the conditions of application were studied. As for the conditions of application, the following metters are conceivable: the standardized method of design of equipments, the handling of figures numerically or by mathematical formulas, troublesome calculation, the works likely to cause mistake, many drawings for production and so on. The lined tanks almost satisfy these conditions, therefore the automatic drafting was promoted, and good results were obtained. the range of application of the automatic drafting system, the standardization of the form of lined tanks, the size of lining sheets, part number and welding number, the composition of the automatic drafting system, the outline of the program, and the effectiveness of automatic drafting are described. (Kako, I.)

  4. The Process of Legal Drafting Regulation in the Development of the Nuclear Power Plant in Indonesia

    International Nuclear Information System (INIS)

    Amil Mardha

    2009-01-01

    In Indonesia, the process of legal drafting to establish the regulation is based on the Act No. 10 Year 2004 on the Establishment of Legislation. The process shall comply with the constitutional and institutional requirements of national political and legal system. In drafting the development of the regulation of nuclear energy, BAPETEN has been involving some other agencies or other related government agencies, and stakeholders such as utility, academic institutions, and publics. In general, in the process of legal drafting, international publications or other country regulations can be a reference and adopted. In the establishment of the regulations of nuclear energy, BAPETEN has issued some Government Regulations and Chairman Regulations of BAPETEN. For nuclear safety of NPP, the regulations have not been completed yet, but some regulations related in the area of siting of NPP have been already available. In this paper, it is discussed the process of the establishment of legislation and of the legal drafting nuclear regulation of NPP, and the current status of NPP regulations. (author)

  5. Nuclear technology terms and definitions. Radiation protection. Draft. Kerntechnik. Begriffe. Strahlenschutz. Entwurf

    Energy Technology Data Exchange (ETDEWEB)

    1979-02-01

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

  6. Engineering and science education for nuclear power

    International Nuclear Information System (INIS)

    1986-01-01

    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

  7. Electrical supply and controls for induced-draft cooling towers at Browns Ferry Nuclear Plant

    International Nuclear Information System (INIS)

    Mock, C.H.; Boehms, J.H.

    1975-01-01

    Design considerations are given for selection of electrical features as required for addition of mechanical-draft-type cooling towers at an existing multiunit nuclear generating station. Environmental and nuclear safety problems were solved economically by use of enclosed 161-kV power connections, oil-filled transformers, supervisory-type control, and unique schemes for redundancy to minimize need for Class 1E construction

  8. Unique nuclear thermal rocket engine

    International Nuclear Information System (INIS)

    Culver, D.W.; Rochow, R.

    1993-06-01

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

  9. Reconstruction of nuclear engineering education in universities

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Tomota, Yo; Tanaka, Shunichi

    2005-01-01

    Nuclear engineering has become the area gradually loosing appeal to the young for these twenty years taking all the circumstances into consideration. However nuclear power is predicted to be primary energy of greatest importance even in the future and this needs highly motivated and excellent personnel in nuclear industry and society so as to develop and maintain nuclear power to a high degree. Under these circumstances discussions on how should be nuclear engineering research and education in the new era were presented from various viewpoints and they led to the direction of reconstruction of nuclear engineering education in universities and relevant organizations to train and ensure personnel. (T. Tanaka)

  10. Implications of draft ICRP recommendations: the View of the OECD Nuclear Energy Agency

    International Nuclear Information System (INIS)

    Magnusson, S.; Lazo, T.

    2006-01-01

    Full text: The OECD Nuclear Energy Agency has taken an active interest in the work being performed by the International Commission on Radiological Protection (ICRP) to develop a new set of general recommendations. As several key junctures, the Nea, through the lead of its Committee on Radiation Protection and Public Health (C.R.P.P.H.) has performed in-depth analyses of the possible implications that draft ICRP materials, in order to inform policy makers of the regulatory and application implications that would result should draft ICRP Recommendations for a system of radiological protection be published. Comments from the Nea have constructively contributed to the ICRP development process, and it is hoped that the final ICRP recommendations in this area will be developed to best serve the needs of national and international radiation protection policy makers, regulators and implementers. Having assessed and commented on previous drafts, the C.R.P.P.H. has co-ordinated the views of all the relevant standing technical committees within the OECD Nuclear Energy Agency to provide constructive suggestions as to how the text could be usefully improved. Comments were requested from the Nea committees dealing with radioactive waste management, nuclear safety, nuclear regulatory activities, nuclear development and nuclear science. The present paper summarises the results of the C.R.P.P.H. review process related to the new ICRP recommendations. (author)

  11. 4+ Dimensional nuclear systems engineering

    International Nuclear Information System (INIS)

    Suh, Kune Y.

    2009-01-01

    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 + D) Technology TM , a critical know how for digital management. ESSE (Engineering Super Simulation Emulation) features a 4 + D Technology TM for nuclear energy systems engineering. The technology proposed in the 3D space and time plus cost coordinates, i.e. 4 + 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 + 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 two machines and losses in

  12. Draft IAEA Action Plan on Nuclear Safety. Report by the Director General

    International Nuclear Information System (INIS)

    Amano, Y.

    2011-01-01

    In accordance with paragraphs 23 and 24 of the Declaration adopted by the Ministerial Conference on Nuclear Safety held on 20-24 June 2011, the Director General was requested to prepare and present to the Board of Governors and the General Conference at their September 2011 meetings a report on the Ministerial Conference and a draft Action Plan, building on the Ministerial Declaration, the conclusions and recommendations of the working sessions of the Ministerial Conference and the expertise and knowledge available therein, and to facilitate consultations among Member States on the draft Action Plan. This draft Action Plan is the result of an extensive process of consultations with Member States and responds to the request contained in the Ministerial Declaration.

  13. 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.

  14. US Nuclear Engineering Education: Status and prospects

    International Nuclear Information System (INIS)

    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, 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

  15. The University of Utah Nuclear Engineering Program

    International Nuclear Information System (INIS)

    Jevremovic, T.; McDonald, L. IV; Schow, R.

    2016-01-01

    As of 2014, the University of Utah Nuclear Engineering Program (UNEP) manages and maintains over 7,000 ft 2 (~650 m 2 ) nuclear engineering facilities that includes 100 kW TRIGA Mark I and numerous laboratories such as radiochemistry, microscopy, nuclear forensics, nuclear medicine, radiation detection and instrumentation laboratories. The UNEP offers prestigious educational and training programs in the field of faculty reserach: reactor physics, reactor design and operation, advanced numerical modeling and visualizations in radiation transport, radiochemistry, nuclear forensics, radiation detection and detector designs, signal processing, nuclear medicine, nuclear space and nuclear robotic’s engineering and radiological sciences. With the state-of-the-art nuclear instrumentation and state-of-the-art numerical modeling tools, reserach reactor and modernized educational and training programs, we positioned ourselves in the last five years as the fastest growing national nuclear engineering program attracting the students from many disciplines such as but not limited to: chemical engineering, civil engineering, environmental engineering, chemistry, physics, astronomy, medical sciences, and others. From 2012, we uniquely developed and implemented the nuclear power plants’ safety culture paradigm that we use for day-to-day operation, management and maintenance of our facilities, as well as train all our students at undergraduate and graduate levels of studies. We developed also a new distance-learning approaches in sharing knowledge about experiential learning based on no-cost internet-tools combined with the use of mobile technologies. (author)

  16. A nuclear power plant system engineering workstation

    International Nuclear Information System (INIS)

    Mason, J.H.; Crosby, J.W.

    1989-01-01

    System engineers offer an approach for effective technical support for operation and maintenance of nuclear power plants. System engineer groups are being set up by most utilities in the United States. Institute of Nuclear Power operations (INPO) and U.S. Nuclear Regulatory Commission (NRC) have endorsed the concept. The INPO Good Practice and a survey of system engineer programs in the southeastern United States provide descriptions of system engineering programs. The purpose of this paper is to describe a process for developing a design for a department-level information network of workstations for system engineering groups. The process includes the following: (1) application of a formal information engineering methodology, (2) analysis of system engineer functions and activities; (3) use of Electric Power Research Institute (EPRI) Plant Information Network (PIN) data; (4) application of the Information Engineering Workbench. The resulting design for this system engineer workstation can provide a reference for design of plant-specific systems

  17. Integrated engineering system for nuclear facilities building

    International Nuclear Information System (INIS)

    Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

    1995-01-01

    In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

  18. European master degree in nuclear engineering

    International Nuclear Information System (INIS)

    Ghitescu, Petre; Prisecaru, Ilie

    2003-01-01

    In order to preserve and to improve the quality of nuclear engineering education and training in Europe, as well to ensure the safe and economic operation of nuclear power plants, the European Nuclear Engineering Network Program (ENEN) started in 2002. It is a program aiming to establish and maintain a set of criteria for specific curricula of nuclear engineering education, in particular, for an European Master Degree in Nuclear Engineering (EMNE). The ENEN program is financed by the FP5 and has the wide support of IAEA, OECD and EU Commission departments dealing with the nuclear engineering knowledge management. The promising results up to now determined the creation of the Asian Nuclear Engineering Network (ANEN) in July 2003 and of the World Nuclear University (WNU) starting in September 2003. The paper presents the future structure of EMNE which will allow the harmonization of the curricula of the universities of Europe until the Bologna Convention will be fully accepted and operational in all European countries. The ENEN program has taken into consideration the curricula of 22 universities and research centres from 15 different European countries and proposed a feasible scheme which allows the undergraduates with a weak to strong nuclear background to continue their graduate education in the nuclear engineering field towards EMNE. As one of the contractors of this program, University 'Politehnica' of Bucharest brings its contribution and actively takes part in all activities establishing the EMNE. (author)

  19. Draft report on the national seminar in nuclear medicine

    International Nuclear Information System (INIS)

    1977-01-01

    The proceedings of the seminar on nuclear medicine have been conducted in four main sessions. In the first session a review of the current status of clinical nuclear medicine in India is reviewed. The use of radioisotopes in thyroid function studies, central nervous systems, liver disorders, lung and bone imaging, renal function studies, dynamic function studies, gastroenterology haematology etc. are described. The existing facilities and the future needs for radioimmunoassay and radiotherapy are discussed. In Session 2, the existing facilities in nuclear medicine in different states in India are reviewed. In Session 3, the available resources in nuclear medicine are reviewed. Radiation protection procedures are outlined. Various nuclear instruments developed at the Bhabha Atomic Research Centre, (BARC), Bombay, for use in nuclear medicine are briefly described. A list of radiopharmaceuticals developed by BARC and in current use, is given. The roles of the physicist, pharmacist and the nuclear medicine technologist in the hospitals having nuclear medicine units, are stressed. The importance of training and education for personnel in nuclear medicine and medical physics is pointed out. (A.K.)

  20. Academic nuclear engineering education - the Dutch way

    International Nuclear Information System (INIS)

    Wallerbos, E.J.M.; Geemert, R. van

    1997-01-01

    The academic nuclear engineering educational program in the Netherlands aims not only to give students a thorough knowledge of reactor physics but also to train them in practical skills and presentation techniques. These three aspects are important to become a successful nuclear engineer. (author)

  1. Engineering and planning for decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Gans, G.M. Jr.

    1982-01-01

    With the publication of NUREG-0586, ''Draft Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities'' in January, 1981 the Nuclear Regulatory Commission staff has put the industry on notice that the termination of operating licenses and the final disposal of physical facilities will require the early consideration of several options and approaches and the preparation of comprehensive engineering and planning documents for the selected option at the end of useful life. This paper opens with a discussion of the options available and the principal aspects of decommissioning. The major emphasis of the composition is the nature of documents, the general approach to be followed, and special considerations to be taken into account when performing the detailed engineering and planning for decommissioning, as the end of life approaches and actual physical disposal is imminent. The author's main point of reference is on-going work by Burns and Roe, with Nuclear Energy Services, under contract to the Department of Energy's Richland Office, to perform the engineering and planning for the decommissioning of the Shippingport Atomic Power Station in Pennsylvania

  2. Lifecycle management for nuclear engineering project documents

    International Nuclear Information System (INIS)

    Zhang Li; Zhang Ming; Zhang Ling

    2010-01-01

    The nuclear engineering project documents with great quantity and various types of data, in which the relationships of each document are complex, the edition of document update frequently, are managed difficultly. While the safety of project even the nuclear safety is threatened seriously by the false documents and mistakes. In order to ensure the integrality, veracity and validity of project documents, the lifecycle theory of document is applied to build documents center, record center, structure and database of document lifecycle management system. And the lifecycle management is used to the documents of nuclear engineering projects from the production to pigeonhole, to satisfy the quality requirement of nuclear engineering projects. (authors)

  3. Thermal hydraulics in undergraduate nuclear engineering education

    International Nuclear Information System (INIS)

    Theofanous, T.G.

    1986-01-01

    The intense safety-related research efforts of the seventies in reactor thermal hydraulics have brought about the recognition of the subject as one of the cornerstones of nuclear engineering. Many nuclear engineering departments responded by building up research programs in this area, and mostly as a consequence, educational programs, too. Whether thermal hydraulics has fully permeated the conscience of nuclear engineering, however, remains yet to be seen. The lean years that lie immediately ahead will provide the test. The purpose of this presentation is to discuss the author's own educational activity in undergraduate nuclear engineering education over the past 10 yr or so. All this activity took place at Purdue's School of Nuclear Engineering. He was well satisfied with the results and expects to implement something similar at the University of California in Santa Barbara in the near future

  4. Nuclear industry - challenges in chemical engineering

    International Nuclear Information System (INIS)

    Sen, S.; Sunder Rajan, N.S.; Balu, K.; Garg, R.K.; Murthy, L.G.K.; Ramani, M.P.S.; Rao, M.K.; Sadhukhan, H.K.; Venkat Raj, V.

    1978-01-01

    As chemical engineering processes and operations are closely involved in many areas of nuclear industry, the chemical engineer has a vital role to play in its growth and development. An account of the major achievements of the Indian chemical engineers in this field is given with view of impressing upon the faculty members of the Indian universities the need for taking appropriate steps to prepare chemical engineers suitable for nuclear industry. Some of the major achievements of the Indian chemical engineers in this field are : (1) separation of useful minerals from beach sand, (2) preparation of thorium nitrate of nuclear purity from monazite, (3) processing of zircon sand to obtain nuclear grade zirconium and its separation from hafnium to obtain zirconium metal sponge, (4) recovery of uranium from copper tailings, (5) economic recovery of nuclear grade uranium from low grade uranium ores found in India, (6) fuel reprocessing, (7) chemical processing of both low and high level radioactive wastes. (M.G.B.)

  5. Views from the japanese nuclear industry and radiation protection professionals on the draft ICRP recommendations

    International Nuclear Information System (INIS)

    Yonekura, Y.; Choi, H.S.; Muto, S.; Oda, K.; Ishiguchi, T.

    2007-01-01

    The views of the Japanese nuclear industry, radiation protection professionals, and medical professionals on the concepts of the draft recommendations were presented. Specific concerns and suggestions were expressed in each of these fields based on practical considerations and experiences in operational radiation protection. It was noted that there is no need to complicate the current system, in particular without effectively expressed and rational reasoning. However, in general, speakers and participants in these discussions showed an understanding of ICRP publications. (authors)

  6. Current status of nuclear engineering education

    International Nuclear Information System (INIS)

    Palladino, N.J.

    1975-01-01

    The 65 colleges and universities offering undergraduate degrees in nuclear engineering and the 15 schools offering strong nuclear engineering options are, in general, doing a good job to meet the current spectrum of job opportunities. But, nuclear engineering programs are not producing enough graduates to meet growing demands. They currently receive little aid and support from their customers --industry and government--in the form of scholarships, grants, faculty research support, student thesis and project support, or student summer jobs. There is not enough interaction between industry and universities. Most nuclear engineering programs are geared too closely to the technology of the present family of reactors and too little to the future breeder reactors and controlled thermonuclear reactors. In addition, nuclear engineering programs attract too few women and members of minority ethnic groups. Further study of the reasons for this fact is needed so that effective corrective action can be taken. Faculty in nuclear engineering programs should assume greater initiative to provide attractive and objective nuclear energy electives for technical and nontechnical students in other disciplines to improve their technical understanding of the safety and environmental issues involved. More aggressive and persistent efforts must be made by nuclear engineering schools to obtain industry support and involvement in their programs

  7. Fiscal 1988 draft budget for nuclear energy up 1.9% to yen 369 billion

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    AT the cabinet meeting held on December 28, the government approved the fiscal 1988 draft budget, with a general account of yen 56.6 trillion. The nuclear energy related budget is yen 181.124 billion from the general account and yen 186.098 billion from the special account for power sources development, totalling yen 367.222 billion, up 1.9% on the previous year. The largest appropriation goes to the Science and Technology Agency (STA) totaling yen 271 billion. The STA is promoting safety studies and R and D for extensive nuclear energy utilization but the budget shows a 0.7% decrease from the previous year, reflecting completion of the construction of JT-60, which is one of the Agency's major projects. MITI, with its budget of yen 91 billion will carry on policies related to the promotion of commercial nuclear power program as well as support for the industrialization program of the nuclear fuel cycle. Nuclear related budget of Ministry of Foreign Affairs is yen 2.8 billion, consisting mainly of IAEA subscriptions and contributions and OECD/NEA subscriptions. Besides these three government agencies, a large sum of yen 1.2 billion is allocated to the Okinawa Development Agency for the prevention and elimination of melon-flies in Kume Island and islands around Okinawa main island. The draft government budget will be submitted to the ordinary session of the Diet when it resumes towards the end of January. After deliberation in the Budget Committees of the House of Representatives and the House of Councilors, the draft budget will be put to the vote in the plenary session. Assuming that all proceeds smoothly, the budget is expected to be approved by the end of March without any major revision. (author)

  8. Software engineers and nuclear engineers: teaming up to do testing

    International Nuclear Information System (INIS)

    Kelly, D.; Cote, N.; Shepard, T.

    2007-01-01

    The software engineering community has traditionally paid little attention to the specific needs of engineers and scientists who develop their own software. Recently there has been increased recognition that specific software engineering techniques need to be found for this group of developers. In this case study, a software engineering group teamed with a nuclear engineering group to develop a software testing strategy. This work examines the types of testing that proved to be useful and examines what each discipline brings to the table to improve the quality of the software product. (author)

  9. Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

    International Nuclear Information System (INIS)

    Glasstone, S.; Sesonske, A.

    1994-01-01

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future

  10. Nuclear engineering in the National Polytechnic Institute

    International Nuclear Information System (INIS)

    Del Valle G, E.

    2008-12-01

    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

  11. Towards the European Nuclear Engineering Education Network

    International Nuclear Information System (INIS)

    Mavko, B.; Giot, M.; Sehgal, B.R.; Goethem, G. Van

    2003-01-01

    Current priorities of the scientific community regarding basic research lie elsewhere than in nuclear sciences. The situation today is significantly different than it was three to four decades ago when much of the present competence base in nuclear sciences 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. To preserve nuclear knowledge and expertise through the higher nuclear engineering education in the 5 th framework program of the European Commission the project ENEN (European Nuclear Engineering Education Network) was launched, since the need to keep the university curricula in nuclear sciences and technology alive has been clearly recognized at European level. As the follow up of this project an international nuclear engineering education consortium of universities with partners from the nuclear sector is presently in process of being established This association called ENEN has as founding members: 14 universities and 8 research institutes from 17 European countries. (author)

  12. Nuclear industry prepares fore shortage of engineers

    International Nuclear Information System (INIS)

    Gauker, Lynn.

    1991-01-01

    It is predicted that the Canadian nuclear industry will experience a shortage of qualified personnel within the next five to ten years. The reasons for this prediction are as follows: enrollment in engineering courses, particularly five courses in nuclear engineering has been declining; immigration can no longer be expected to fill the gap; the workforce is aging. Solutions may include promotional campaigns, student employment programs, and educating workers to a professional level

  13. Education of nuclear engineering in Japan

    International Nuclear Information System (INIS)

    Ozawa, Yasutomo; Yamamuro, Nobuhiro

    1979-01-01

    The research Committee of Nuclear Engineering Education has two working groups. One group has carried out surveyes on the curriculums of nuclear engineering course of universities in Japan and the activities of graduates in the industrial worlds. The other group conducted an investigation on the present status of energy education in senior high schools. This is an interim report on the activity of the research committee. (author)

  14. Nuclear engineering education initiative at Ibaraki University

    International Nuclear Information System (INIS)

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

    2015-01-01

    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.)

  15. Nuclear operations summary Engineering organization for Plowshare nuclear operations

    Energy Technology Data Exchange (ETDEWEB)

    Broadman, Gene A [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

    1970-05-15

    The availability of nuclear explosives for peaceful projects has given the engineer a new dimension in his thinking. He can now seek methods of adapting Plowshare to a variety of industrial applications. The full potential of the Plowshare Program can only be attained when industry begins to use nuclear explosives on a regular basis, for economically sound projects. It is the purpose of this paper to help the engineer familiarize himself with Plowshare technology to hasten the day when 'Plowsharee goes commercial'. An engineering project utilizing nuclear exposives ordinarily involves three main phases: Phase I (a) The theoretical and empirical analysis of effects. (b) Projected economic and/or scientific evaluation. (c) A safety analysis. Phase II (a) Field construction. (b) Safe detonation of the nuclear explosive. (c) Data acquisition. Phase III The evaluation and/or exploitation of the results. This paper will be restricted to Phase II, referred to collectively as the 'nuclear operation'.

  16. 77 FR 74882 - STP Nuclear Operating Company, South Texas Project; Notice of Availability of Draft Supplement 48...

    Science.gov (United States)

    2012-12-18

    ... Operating Company, South Texas Project; Notice of Availability of Draft Supplement 48 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants and Public Meetings for the License Renewal of South Texas Project Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) has...

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

    International Nuclear Information System (INIS)

    2007-01-01

    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

  18. Engineering development in nuclear power plant construction

    International Nuclear Information System (INIS)

    Guenther, P.

    1979-01-01

    Proceeding from the up-to-now experience in the erection of nuclear power stations, especially of the first and second unit of the Greifswald nuclear power plant, the following essential aspects of the development of constructional engineering are discussed: (1) constructional features and criteria, (2) organizational management, (3) current status and problems in prelimary operations, and (4) possibilities of further expenditure reductions in constructing nuclear power stations

  19. Nuclear engineering education in the United States

    International Nuclear Information System (INIS)

    Williamson, T.G.

    1982-01-01

    In discussing nuclear engineering education in the United States it is shown that the most critical issue facing the nuclear engineering education community today is enrolment in a time of increasing demand for graduate engineers. Related to the issue of enrolment is support for graduate students, whether it be fellowships, traineeships, or research assistantships. Other issues are those of maintaining a vital faculty in the face of a competitive job market, of maintaining research facilities and developing new ones, and of determining the directions of educational efforts in the future. (U.K.)

  20. The engineering function in Scottish Nuclear

    International Nuclear Information System (INIS)

    Grant, J.

    1991-01-01

    The work of the Engineering and Development Division of Scottish Nuclear is described in this article. This company, formed since the privatization of electricity generation in the United Kingdom, owns and operates the two Hunterston Magnox reactors and the Torness Advanced Gass Cooled Reactors. Principle responsibilities such as maintaining safety standards, formulating policy for radioactive waste disposal and decommissioning and optimally controlling the nuclear generation cycle are outlined. Objectives for the next five years are identified and explained separately. The experience, knowledge and expertise of engineering staff is stressed as being of key importance to the future success of Scottish Nuclear. (UK)

  1. Draft emergency action level guidelines for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-09-15

    This document is provided for interim use during the initial phases of the NRC effort to promptly improve emergency preparedness at operating nuclear power plants. Changes to the document can be expected as experience is gained in its use and public comments are received. Further, the Commission has initiated a rulemaking procedure, now scheduled for completion in January 1930 in the area of Emergency Planning and Preparedness. Additional requirements are to be expected when rulemaking is completed and some modifications to this document may be necessary. Four classes of Emergency Action Levels are established which replace the classes in Regulatory Guide 1.101, each with associated examples of initiating conditions. The classes are: - Notification of Unusual Event; - Alert; - Site Emergency; - General Emergency. The rationale for the notification and alert classes is to provide early and prompt notification of minor events which could lead to more serious consequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. A gradation is provided to assure fuller response preparations for more serious indicators. The site emergency class reflects conditions where some significant releases are likely or are occurring but where a core melt situation is not indicated based on current information. In this situation full mobilization of emergency personnel in tie :near site environs is indicated as well as dispatch of monitoring teams and associated communications. The general emergency class involves actual or imminent substantial core degradation or malting with the potential for loss of containment. The immediate action for this class is sheltering (staying inside) rather thai evacuation until an assessment can be made that (1) an evacuation is indicated and (2) an evacuation, if indicated, can be completed prior to significant release and transport of radioactive material to the affected

  2. Draft emergency action level guidelines for nuclear power plants

    International Nuclear Information System (INIS)

    1979-09-01

    This document is provided for interim use during the initial phases of the NRC effort to promptly improve emergency preparedness at operating nuclear power plants. Changes to the document can be expected as experience is gained in its use and public comments are received. Further, the Commission has initiated a rulemaking procedure, now scheduled for completion in January 1930 in the area of Emergency Planning and Preparedness. Additional requirements are to be expected when rulemaking is completed and some modifications to this document may be necessary. Four classes of Emergency Action Levels are established which replace the classes in Regulatory Guide 1.101, each with associated examples of initiating conditions. The classes are: - Notification of Unusual Event; - Alert; - Site Emergency; - General Emergency. The rationale for the notification and alert classes is to provide early and prompt notification of minor events which could lead to more serious consequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. A gradation is provided to assure fuller response preparations for more serious indicators. The site emergency class reflects conditions where some significant releases are likely or are occurring but where a core melt situation is not indicated based on current information. In this situation full mobilization of emergency personnel in tie :near site environs is indicated as well as dispatch of monitoring teams and associated communications. The general emergency class involves actual or imminent substantial core degradation or malting with the potential for loss of containment. The immediate action for this class is sheltering (staying inside) rather thai evacuation until an assessment can be made that (1) an evacuation is indicated and (2) an evacuation, if indicated, can be completed prior to significant release and transport of radioactive material to the affected

  3. Draft environmental impact statement on a proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Volume 2, Appendix E, Evaluation of human health effects of overland transportation

    International Nuclear Information System (INIS)

    1995-03-01

    This Appendix provides an overview of the approach used to assess the human health risks that may result from the overland transportation of foreign research reactor spent nuclear fuel. The Appendix includes discussion of the scope of the assessment, analytical methods used for the risk assessment (i.e., computer models), important assessment assumptions, determination of potential transportation routes, and presents the results of the assessment. In addition, to aid in the understanding and interpretation of the results, specific arm of uncertainty are described, with an emphasis an how the uncertainties may affect comparisons of the alternatives. he approach used in this Appendix is modeled after that used in the Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Draft Environmental Impact Statement (SNF ampersand INEL Draft EIS) (DOE, 1994b). The SNF ampersand INEL Draft EIS did not perform as detailed an analysis on the specific actions taken for foreign research reactor spent nuclear fuel because of the breadth necessary to analyze the entire spent fuel management program. However, the fundamental assumptions used in this analysis are consistent with those used in the SNF ampersand INEL Draft EIS (DOE, 1994b), and the same computer codes and generic release and accident data are used. The risk assessment results are presented in this Appendix in terms of ''Per-shipment'' risk factors, as well as for the total risks associated with each alternative. Per-shipment risk factors provide an estimate of the risk from a single spent nuclear fuel shipment between a specific origin and destination. They are calculated for all possible origin and destination pairs for each spent nuclear fuel type. The total risks for a given alternative are found by multiplying the expected number of shipments by the appropriate per-shipment risk factors. This approach provides maximum flexibility for determining the risks for a large number of potential

  4. Mobile filters in nuclear engineering

    International Nuclear Information System (INIS)

    Meuter, R.

    1979-01-01

    The need for filters with high efficiencies which may be used at any place originated in nuclear power plants. Filters of this type, called Filtermobil, have been developed by Sulzer. They have been used successfully in nuclear plants for several years. (orig.) [de

  5. Nuclear engine system simulation (NESS) program update

    International Nuclear Information System (INIS)

    Scheil, C.M.; Pelaccio, D.G.; Petrosky, L.J.

    1993-01-01

    The second phase of development of a Nuclear Thermal Propulsion (NTP) engine system design analysis code has been completed. The standalone, versatile Nuclear Engine System Simulation (NESS) code provides an accurate, detailed assessment of engine system operating performance, weight, and sizes. The critical information is required to support ongoing and future engine system and stage design study efforts. This recent development effort included incorporation of an updated solid-core nuclear thermal reactor model that yields a reduced core weight and higher fuel power density when compared to a NERVA type reactor. NESS can now analyze expander, gas generator, and bleed cycles, along with multi-redundant propellant pump feed systems. Performance and weight of efficient multi-stage axial turbopump can now be determined, in addition to the traditional centrifugal pump

  6. Proceedings of the Scientific Meeting in Nuclear Instrumentation Engineering

    International Nuclear Information System (INIS)

    Achmad Suntoro; Rony Djokorayono; Ferry Sujatno; Utaja

    2010-11-01

    The Proceeding of the Scientific Meeting in Nuclear Instrumentation Engineering held on Nov, 30, 2010 by the Centre for Nuclear Instrumentation Engineering - National Nuclear Energy Agency. The Proceedings of the Scientific Contains 40 papers Consist of Nuclear Instrumentation Engineering for Industry, Environment, and Nuclear Facilities. (PPIKSN)

  7. 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...

  8. Radiation hazards of nuclear engineering

    International Nuclear Information System (INIS)

    Oster, H.

    1981-01-01

    The basic mechanisms and principles of nuclear power plants are discussed, since their knowledge is mandatory for the understanding of the true risk associated with nuclear technology. Differences between predictable and catastrophic accidents are compared, terms which have been frequently confused to the extent that the public has become unjustifiably and irresponsibly alarmed. A description of the jobs and their responsibilities is also given. Known accidents are reported and the role of the physician in the care of accidents and the scheduling of emergency situations is described. Finally, the usefullness, necessity and risk associated with nuclear power are discussed. (orig.) [de

  9. Draft environmental assessment: reference repository location, Hanford Site, Washington. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified a reference repository location at the Hanford Site in Washington as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the reference repository location at the Hanford Site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received on the draft EA. The reference repository location at Hanford is located in the Columbia Plateau, one of five distinct geohydrologic settings that are being considered for the first repository. On the basis of the evaluations reported in this draft EA, the DOE has found that the reference repository location at Hanford is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the reference repository location at Hanford as one of five sites suitable for characterization. Furthermore, having performed a comparative evaluation of the five sites proposed for nomination, the DOE has determined that the reference repository location at Hanford is one of three sites preferred for site characterization

  10. JAERI Nuclear Engineering School and technology transfer

    International Nuclear Information System (INIS)

    Nishimura, Kazuaki; Kawaguchi, Chiyoji

    1978-01-01

    A method is introduced to evaluate the degree of nuclear technology transfer; that is, the output powers of Japanese nuclear reactors constructed in these 20 years are chronologically plotted in a semi-log figure. All reactors plotted are classified into imported and domestic ones according to a value of domestication factor. A space between two historical trajectories of reactor construction may be interpreted as one of the measures indicating the degree of nuclear technology transfer. In connection with this method, historical change of educational and training courses in Nuclear Engineering School of Japan Atomic Energy Research Institute is reviewed in this report. (author)

  11. A nuclear engineer's ethical responsibility to society

    International Nuclear Information System (INIS)

    Kemeny, L.G.

    1989-01-01

    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

  12. Draft CSA standard on environmental risk assessments at class I nuclear facilities and uranium mines and mills

    International Nuclear Information System (INIS)

    Hart, D.; Garisto, N.; Parker, R.; Kovacs, R.; Thompson, B.

    2012-01-01

    The Canadian Standards Association (CSA) is preparing a draft Standard on environmental risk assessments (ERAs) at Class I nuclear facilities and uranium mines and mills (CSA N288.6). It is being prepared by a technical subcommittee of the CSA N288 Technical Committee, including experts from across the nuclear industry, government and regulatory authorities, and environmental service providers, among others. It addresses the design, implementation, and management of environmental risk assessment programs, and is intended to standardize practice across the industry. This paper outlines the scope of the draft Standard and highlights key features. It is under development and subject to change. (author)

  13. Implications of the new Food and Drug Administration draft guidance on human factors engineering for diabetes device manufacturers.

    Science.gov (United States)

    Wilcox, Stephen B; Drucker, Daniel

    2012-03-01

    This article discusses the implications of the new Food and Drug Administration's draft guidance on human factors and usability engineering for the development of diabetes-related devices. Important considerations include the challenge of identifying users, when the user population is so dramatically broad, and the challenge of identifying use environments when the same can be said for use environments. Another important consideration is that diabetes-related devices, unlike many other medical devices, are used constantly as part of the user's lifestyle--adding complexity to the focus on human factors and ease of use emphasized by the draft guidance. © 2012 Diabetes Technology Society.

  14. Civil engineering challenge with nuclear waste

    International Nuclear Information System (INIS)

    Day, D.

    1985-01-01

    The civil engineer can help to solve the problems in disposing of nuclear waste in a deep geologic formation. The site for a nuclear waste repository must be carefully selected so that the geology provides the natural barrier between the waste and the accessible environment specified by the NRC and the EPA. This engineer is familiar with the needed structure and conditions of the host and surrounding rocks, and also the hydraulic mechanisms for limiting the migration of water in the rocks. To dispose of the nuclear waste underground requires stable and long-lasting shafts and tunnels such as civil engineers have designed and constructed for many other uses. The planning, design and construction of the ground surface facilities for a nuclear waste repository involves civil engineering in many ways. The transporation of heavy, metal shielded casks requires special attention to the system of highways and railroads accessing the repository. Structures for handling the shipping casks and transferring the waste onsite and into the deep geologic formation need special considerations. The structures must provide the NRC required containment, including hot cells for remote handling. Therefore, structural design strives for buildings, ventilation structures, shaft headframes, etc., to be earthquake and tornado-proof. These important design bases and considerations for the civil engineer working on a nuclear waste repository are discussed in this paper

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

    International Nuclear Information System (INIS)

    Schoenfelder, Christian

    2014-01-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-15

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

  17. Engineering and science education for nuclear power

    International Nuclear Information System (INIS)

    Mautner-Markhof, F.

    1988-01-01

    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

  18. Draft environmental assessment: Vacherie Dome site, Louisiana. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Vacherie dome in Louisiana as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Vacherie dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Vacherie dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Richton dome site. Although the Vacherie dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. On the basis of these findings, the DOE is proposing to nominate the Richton dome site rather than the Vacherie dome site as one of the five sites suitable for characterization

  19. Draft environmental assessment: Swisher County site, Texas. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified a location in Swisher County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Swisher site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Swisher site is not disqualified under the guidelines. The site is contained in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Deaf Smith site. Although the Swisher site appears to be suitable for site characterization, the DOE has concluded that the Deaf Smith site is the preferred site in the Permian Basin and is proposing to nominate the Deaf Smith site rather than the Swisher site as one of the five sites suitable for characterization

  20. Draft environmental assessment: Cypress Creek Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Cypress Creek dome site in Mississippi as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Cypress Creek dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Cypress Creek dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Richton dome site and the Vacherie dome site. Although the Cypress Creek dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region and is proposing to nominate the Richton dome site rather than the Cypress Creek dome site as one of the three sites suitable for characterization

  1. Draft environmental assessment: Lavender Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Lavender Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Lavender Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Lavender Canyon site is not disqualified under the guidelines. The site is contained in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Davis Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site rather than the Lavender Canyon site as one of the five sites suitable for characterization

  2. The changing face of nuclear engineering education

    International Nuclear Information System (INIS)

    Poston, J.W.

    1991-01-01

    Nuclear engineering education in the US is in a near-crisis situation. Most academic programs are small with limited enrollments and faculty. Some of these programs are being absorbed into larger academic units, while others are being terminated. The number of identifiable academic programs has dropped dramatically over the last several years, and there is genuine concern that this downward trend will continue. The recent report by the National Academy of Sciences highlights the problems, needs, and prospects for nuclear engineering education in this country. At the same time, some programs appear to be relatively healthy and somewhat secure. A closer look at these programs indicates that there has been an evolution in the approach taken by these survivors toward both their academic and research programs. This paper discusses the approaches taken at Texas A and M University over the last 8 to 10 years to strengthen the Department of Nuclear Engineering

  3. European Master of Science in Nuclear Engineering

    International Nuclear Information System (INIS)

    Moons, F.; Safieh, J.; Giot, M.; Mavko, B.; Sehgal, B.R.; Schaefer, A.; Goethem, G. van; D'haeseleer, W.

    2004-01-01

    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)

  4. Exporting nuclear engineering and the industry's viewpoint

    International Nuclear Information System (INIS)

    Barthelt, K.

    1986-01-01

    Nuclear energy offers all possibilities to reduce the energy problems in the world which arise with the world-wide increasing population and the energy demand connected with it. The Federal Republic of Germany lives on the exports of refined technical methods which also include nuclear engineering. The exports of nuclear engineering should lead to a technology transfer with guidance and training on an equal basis between the industrial and developing countries. The preconditions of exporting nuclear-technical systems are a well-functioning domestic market and a certain support by the government, especially with regard to giving guarantees for the special exports risks of these big projects. On the other hand, exports are also needed in order to be able to continue providing high-level technology for the domestic market. (UA) [de

  5. The world nuclear power engineering. 1998 year

    International Nuclear Information System (INIS)

    Preobrazhenskaya, L.B.

    2000-01-01

    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 [ru

  6. Social engineering awareness in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Mohd Dzul Aiman bin Aslan; Mohamad Safuan bin Sulaiman; Abdul Muin bin Abdul Rahman

    2010-01-01

    Social engineering is the best tools to infiltrate an organization weakness. It can go bypass the best fire wall or Intrusion Detection System (IDS) the organization ever had, effectively. Nuclear Malaysia staffs should aware of this technique as information protection it is not only depends on paper and computer. This paper consist a few test cases including e mail, dump ster diving, phishing, malicious web content, and impersonation to acknowledge all Nuclear Malaysia staffs about the method, effect and prevention of social engineering. (author)

  7. Education in nuclear engineering in Slovakia

    International Nuclear Information System (INIS)

    Slugen, V.

    2005-01-01

    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)

  8. Nuclear engineering enrollments and degrees, 1981

    International Nuclear Information System (INIS)

    Little, J.R.; Shirley, D.L.

    1982-05-01

    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

  9. Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 1. Main report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The Draft Environmental Impact Statement (EIS) for the replacement of the Australian Research reactor has been released. An important objective of the EIS process is to ensure that all relevant information has been collected and assessed so that the Commonwealth Government can make an informed decision on the proposal. The environmental assessment of the proposal to construct and operate a replacement reactor described in the Draft EIS has shown that the scale of environmental impacts that would occur would be acceptable, provided that the management measures and commitments made by ANSTO are adopted. Furthermore, construction and operation of the proposed replacement reactor would result in a range of benefits in health care, the national interest, scientific achievement and industrial capability. It would also result in a range of benefits derived from increased employment and economic activity. None of the alternatives to the replacement research reactor considered in the Draft EIS can meet all of the objectives of the proposal. The risk from normal operations or accidents has been shown to be well within national and internationally accepted risk parameters. The dose due to reactor operations would continue to be small and within regulatory limits. For the replacement reactor, the principle of `As Low As Reasonably Achievable` would form an integral part of the design and licensing process to ensure that doses to operators are minimized. Costs associated with the proposal are $286 million (in 1997 dollars) for design and construction. The annual operating and maintenance costs are estimated to be $12 million per year, of which a significant proportion will be covered by commercial activities. The costs include management of the spent fuel from the replacement reactor as well as the environmental management costs of waste management, safety and environmental monitoring. Decommissioning costs for the replacement reactor would arise at the end of its lifetime

  10. An introduction and overview of DRAFT CSA Standard N288.7 Groundwater Protection at Class I Nuclear Facilities and Uranium Mines and Mills

    Energy Technology Data Exchange (ETDEWEB)

    DeWilde, J., E-mail: john_dewilde@golder.com [Golder Associates Ltd., Whitby, ON (Canada); Klukas, M.; Audet, M., E-mail: marc.audet@cnl.ca [Canadian Nuclear Laboratories, Chalk River, ON (Canada)

    2015-07-01

    The DRAFT CSA Standard N288.7 entitled Groundwater Protection at Class I Nuclear Facilities and Uranium Mines and Mills is currently under development and is anticipated to publish in June of 2015. This draft standard identifies a process for the protection and monitoring of groundwater at nuclear facilities but may also be used at any facility (i.e. nuclear facilities that are not Class I or non-nuclear facilities). The paper discusses the background to the draft standard, the formalized methodology described in the draft standard and provides some input on implementation. The paper is intended for people that have responsibilities related to groundwater protection at facilities that may need to comply with the draft standard or any site/facility that has some form of groundwater monitoring program. (author)

  11. Chemical engineering side of nuclear fusion power

    International Nuclear Information System (INIS)

    Johnson, E.F.

    1976-10-01

    It is widely recognized that chemical engineering has important roles to play in the development of national and world wide energy resources through optimal utilization of fossil fuel reserves. It is much less appreciated that there are crucial chemical engineering problems in the development of energy production from other sources. In particular the successful development of nuclear fusion power generating systems will require the solution of many problems that are uniquely suited to chemical engineers. This article presents a brief overview of the fusion development program and an identification of the major technological problems remaining to be solved

  12. Nuclear thermal rocket engine operation and control

    International Nuclear Information System (INIS)

    Gunn, S.V.; Savoie, M.T.; Hundal, R.

    1993-06-01

    The operation of a typical Rover/Nerva-derived nuclear thermal rocket (NTR) engine is characterized and the control requirements of the NTR are defined. A rationale for the selection of a candidate diverse redundant NTR engine control system is presented and the projected component operating requirements are related to the state of the art of candidate components and subsystems. The projected operational capabilities of the candidate system are delineated for the startup, full-thrust, shutdown, and decay heat removal phases of the engine operation. 9 refs

  13. Educating nuclear engineers at German universities

    International Nuclear Information System (INIS)

    Knorr, J.

    1995-01-01

    Nuclear technology is a relatively young university discipline. Yet, as a consequence of the declining public acceptance of the peaceful use of nuclear power, its very existence is already being threatened at many universities. However, if Germany needs nuclear power, which undoubtedly is the case, highly qualified, committed experts are required above all. Nuclear technology develops internationally. Consequently, also university education must meet international standards. Generally, university education has been found to be the most effective way of increasing the number of scientific and engineering personnel. Nuclear techniques have meanwhile found acceptance in many other scientific disciplines, thus advancing those branches of science. Teaching needs research; like research in nucelar technology at the national research centers, also the universities are suffering massive financial disadvantages. Research is possible only if outside funds are solicited, which increase dependency and decreases basic research. (orig.) [de

  14. Exporting nuclear engineering and the government's viewpoint

    International Nuclear Information System (INIS)

    Schill, H.

    1986-01-01

    The reasons for the government's positive attitude to nuclear engineering exports are explained, especially with regard to them being a compensation of the decreasing domestic demand. The federal government considers such exports to be necessary and correct for economical and energy-political reasons. Their contribution reaches from accompanying measures to the provision of state guarantees of export financing activities. (UA) [de

  15. Current situation of nuclear engineering education

    International Nuclear Information System (INIS)

    Queral, C.; Minguez, E.

    2001-01-01

    The last few years have seen a growing concern with the decreasing number of suitably qualified engineers and university graduates in the field of Nuclear Technology. The gap between supply and demand is now a fact in several countries, and for the reason the international community has prepared several reports on the issue that are summarized here. (Author) 4 refs

  16. Abbreviations of nuclear power plant engineering

    International Nuclear Information System (INIS)

    Freyberger, G.H.

    1979-01-01

    The edition of this English and German list of abbreviations comprises about 5200 entries in English and about 1400 entries in German as well as the most important American, English, German and other foreign Utilities and component manufacturers frequently quoted in nuclear engineering literature and documentation. (orig./HP) [de

  17. Midwest Nuclear Science and Engineering Consortium

    International Nuclear Information System (INIS)

    Volkert, Wynn; Kumar, Arvind; Becker, Bryan; Schwinke, Victor; Gonzalez, Angel; McGregor, Douglas

    2010-01-01

    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.

  18. 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.

  19. Nuclear Targeting Terms for Engineers and Scientists

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-02-01

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

  20. Draft environmental statement related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    1984-07-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with the operation of Millstone Nuclear Power Station, Unit 3, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs

  1. General Drafting. Technical Manual.

    Science.gov (United States)

    Department of the Army, Washington, DC.

    The manual provides instructional guidance and reference material in the principles and procedures of general drafting and constitutes the primary study text for personnel in drafting as a military occupational specialty. Included is information on drafting equipment and its use; line weights, conventions and formats; lettering; engineering charts…

  2. Nuclear engineering. Stable industry for bright minds

    International Nuclear Information System (INIS)

    Geisler, Maja

    2009-01-01

    The Deutsches Atomforum (DAtF) invited 35 students and graduate students for 'colloquies for professional orientation' to Luenen on March 8-11, 2009. Another 39 students were guests in Speyer between March 15 and 18 this year. Participants included graduates in physics, chemistry, radiation protection, and mechanical engineering as well as students of process engineering, electrical engineering and environmental technology. The colloquies for professional orientation are a service provided by the Informationskreis Kernenergie (IK) to member firms of DAtF. At the same time, the IK in this way fulfils its duty to promote young scientists and engineers within the framework of the DAtF's basic public relations activities. After all, nuclear technology in Germany is not about to end its life. Firms with international activities are in urgent need of highly qualified young staff members. Personnel is needed for a variety of activities ranging from nuclear power plant construction to fuel fabrication to waste management and the demolition and disposal of nuclear power plants. All these areas are in need of new qualified staff. Some 750 students so far have attended the DAtF colloquies for professional orientation since 2002. Many participants were hired by industries straight away or were given opportunities as trainees or students preparing their diploma theses in the nuclear industry. These contacts with the nuclear industry should not remain a one-off experience for the students. For this reason, the IK invites the participants in colloquies again this year to attend the Annual Meeting on Nuclear Technology in Dresden on May 12-14, 2009. (orig.)

  3. Human modeling in nuclear engineering

    International Nuclear Information System (INIS)

    Yoshikawa, Hidekazu; Furuta, Kazuo.

    1994-01-01

    Review on progress of research and development on human modeling methods is made from the viewpoint of its importance on total man-machine system reliability surrounding nuclear power plant operation. Basic notions on three different approaches of human modeling (behavioristics, cognitives and sociologistics) are firstly introduced, followed by the explanation of fundamental scheme to understand human cognitives at man-machine interface and the mechanisms of human error and its classification. Then, general methodologies on human cognitive model by AI are explained with the brief summary of various R and D activities now prevailing in the human modeling communities around the world. A new method of dealing with group human reliability is also introduced which is based on sociologistic mathematical model. Lastly, problems on human model validation are discussed, followed by the introduction of new experimental method to estimate human cognitive state by psycho-physiological measurement, which is a new methodology plausible for human model validation. (author)

  4. Draft environmental assessment: Richton Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy identified the Richton dome site as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Richton dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Richton dome site is not disqualified under the guidelines. The site is in the Gulf Interior Region of the Gulf Coastal Plain. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Vacherie dome site. Although these other two sites appear to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Richton dome site as one of five sites suitable for characterization. Having compared the Richton dome site with the other four sites proposed for nomination, the DOE has determined that the Richton dome site is not one of the three preferred sites for recommendation to the President as candidates for characterization

  5. Draft environmental assessment: Davis Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. The site is in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Lavender Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site as one of five sites suitable for characterization. Having compared the Davis Canyon site with the other four sites proposed for nomination, the DOE has determined that the Davis Canyon site is not one of the three preferred sites for recommendation to the President as candidates for characterization

  6. Draft environmental assessment: Deaf Smith County site, Texas. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy identified a location in Deaf Smith County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Deaf Smith site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment, which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Deaf Smith site is not disqualified under the guidelines. The site is in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Swisher site. Although the Swisher site appears to be suitable for site characterization, DOE has concluded that the Deaf Smith site is the preferred site. The DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Deaf Smith site as one of five sites suitable for characterization. Having compared the Deaf Smith site with the other four sites proposed for nomination, the DOE has determined that the Deaf Smith site is one of the three preferred sites for recommendation to the President as candidates for characterization

  7. 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.

  8. Quality assurance system in nuclear engineering

    International Nuclear Information System (INIS)

    Adams, H.W.; Hoensch, V.

    1985-01-01

    Due to the close connection between the German Atomic Energy Law and the nuclear control regulations, quality systems in nuclear engineering have taken on a special form. Quality assurance systems as a stipulated organisation of structure and procedure to assure quality have implications for the organisation of the electric supply company at the planning, erection and commissioning stage and for the organisation of the nuclear power station facility. To supervise the application and effectiveness of the stipulated organisation of structure and procedure internally and externally among contractors, special organisation units have been set up at the plant suppliers, manufactures, electric supply companies and nuclear power station facilities, which in the electric supply field go by the name of Quality Assurance Supervision. (orig.) [de

  9. NUKEM. Innovative solutions for nuclear engineering

    International Nuclear Information System (INIS)

    Scheffler, Beate

    2011-01-01

    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.)

  10. Nuclear industry - challenges in chemical engineering

    International Nuclear Information System (INIS)

    Sen, S.; Sunder Rajan, N.S.; Balu, K.; Garg, R.K.; Murthy, L.G.K.; Ramani, M.P.S.; Rao, M.K.; Sadhukhan, H.K.; Venkat Raj, V.

    1978-01-01

    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.)

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

    International Nuclear Information System (INIS)

    Kerrick, Sharon S.; Vincent, Charles D.

    2007-01-01

    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

  12. Application of nuclear photon engines for deep-space exploration

    International Nuclear Information System (INIS)

    Gulevich, Andrey V.; Ivanov, Eugeny A.; Kukharchuk, Oleg F.; Poupko, Victor Ya.; Zrodnikov, Anatoly V.

    2001-01-01

    Conception of using the nuclear photon rocket engines for deep space exploration is proposed. Some analytical estimations have been made to illustrate the possibility to travel to 100-10000 AU using a small thrust photon engine. Concepts of high temperature nuclear reactors for the nuclear photon engines are also discussed

  13. Nuclear Engineering Enrollments and Degrees Survey, 2005 Data

    International Nuclear Information System (INIS)

    Oak Ridge Institute for Science and Education

    2006-01-01

    This annual report details the number of nuclear engineering bachelor's, master's, and doctoral degrees awarded at a sampling of academic programs from 1998-2005. it also looks at nuclear engineering degrees by curriculum and the number of students enrolled in nuclear engineering degree programs at 30 U.S. universities in 2005

  14. European Master of Science in Nuclear Engineering

    International Nuclear Information System (INIS)

    Moons, Frans; Safieh, Joseph; Giot, Michel; Mavko, Borut; Sehgal, Bal Raj; Schaefer, Anselm; Goethem, Georges van; D'Haeseleer, William

    2005-01-01

    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

  15. Nuclear engineering education in the United States

    International Nuclear Information System (INIS)

    Williamson, T.G.

    1982-01-01

    The critical issue facing the nuclear engineering education community today is first and foremost enrollment in a time of increasing demand for graduate engineers. Related to the issue of enrollment is support for graduate students, whether it be fellowships, traineeships, or research assistantships. Other issues are those of maintaining a vital faculty in the face of competitive job market, of maintaining research facilities and developing new ones, and last and certainly not least that of determining the directions of our educational efforts in the future. These issues are examined in the paper. (author)

  16. Civil engineering firms and the nuclear programme

    International Nuclear Information System (INIS)

    Giral, J.L.

    1988-01-01

    Pointing out that the realization of the electronuclear programme accounted for just under 5 % of the annual turnover of civil engineering firms from 1975 to 1987, the author lists the main types of work entrusted to these firms for the bulding of the power stations: electrical work, structural work (civil engineering, metal structures. He then describes the two main problems which the profession has to face in the nuclear field: the management of final contract stages and adaptation to the slowing down in the rate of commitment of power plants [fr

  17. Piping engineering for nuclear power plant

    International Nuclear Information System (INIS)

    Curto, N.; Schmidt, H.; Muller, R.

    1988-01-01

    In order to develop piping engineering, an adequate dimensioning and correct selection of materials must be secured. A correct selection of materials together with calculations and stress analysis must be carried out with a view to minimizing or avoiding possible failures or damages in piping assembling, which could be caused by internal pressure, weight, temperature, oscillation, etc. The piping project for a nuclear power plant is divided into the following three phases. Phase I: Basic piping design. Phase II: Final piping design. Phase III: Detail engineering. (Author)

  18. Terminology standardisation in the nuclear engineering field

    International Nuclear Information System (INIS)

    Kraut, A.

    1987-01-01

    Terminological standardisation is made for the purpose of unambiguous understanding, at least among experts in a given field of knowledge. The author explains a number of criteria and aspects to be taken into account in the process of standardisation by referring to the work of the Terminology Committee on Nuclear Engineering. He discusses the word formation in a technical language and the features of standardised terminology. Accepted terminology is a main factor in all procedures concerning design, testing, and approval and licensing of nuclear facilities, and also is of importance in terms of economics. (HP) [de

  19. Reactor physics for non-nuclear engineers

    International Nuclear Information System (INIS)

    Lewis, E.E.

    2011-01-01

    A one-term undergraduate course in reactor physics is described. The instructional format is strongly influenced by its intended audience of non-nuclear engineering students. In contrast to legacy treatments of the subject, the course focuses on the physics of nuclear power reactors with no attempt to include instruction in numerical methods. The multi-physics of power reactors is emphasized highlighting the close interactions between neutronic and thermal phenomena in design and analysis. Consequently, the material's sequencing also differs from traditional treatments, for example treating kinetics before the neutron diffusion is introduced. (author)

  20. Some radiation chemical aspects of nuclear engineering

    International Nuclear Information System (INIS)

    Pikaev, A.K.; Kabakchi, S.A.; Egorov, G.F.

    1988-01-01

    Some radiation chemical aspects of nuclear engineering are discussed (predominantly on the base of the works performed in the Soviet Union). The data on the influence of temperature within the range of 0-300 0 C on the yields of water radiolysis products are considered. The results obtained from the study of reactivity of actinide ions towards inorganic free radicals in acid aqueous solutions are summarized. The information on composition and properties of the products of radiolytic transformations of different extragents and diluents and on their influence on the behaviour of extraction systems during processing of irradiated nuclear fuel is presented. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Musilek, Ladislav; Matejka, Karel [Czech Technical University in Prague, Faculty of Nuclear Sciences and Physical Engineering, Brehova 7, 115 19 Prague 1 (Czech Republic)

    1993-07-01

    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 {sup e}cologisation{sup .} Among other activities priority is given to cooperation with mass media as the press, TV etc. Direct contacts with high and

  2. 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)

    Musilek, Ladislav; Matejka, Karel

    1993-01-01

    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 e cologisation . Among other activities priority is given to cooperation with mass media as the press, TV etc. Direct contacts with high and grammar

  3. Development of nuclear rocket engine technology

    International Nuclear Information System (INIS)

    Gunn, S.V.

    1989-01-01

    Research sponsored by the Atomic Energy Commission, the USAF, and NASA (later on) in the area of nuclear rocket propulsion is discussed. It was found that a graphite reactor, loaded with highly concentrated Uranium 235, can be used to heat high pressure liquid hydrogen to temperatures of about 4500 R, and to expand the hydrogen through a high expansion ratio rocket nozzle assembly. The results of 20 reactor tests conducted at the Nevada Test Site between July 1959 and June 1969 are analyzed. On the basis of these results, the feasibility of solid graphite reactor/nuclear rocket engines is revealed. It is maintained that this technology will support future space propulsion requirements, using liquid hydrogen as the propellant, for thrust requirements ranging from 25,000 lbs to 250,000 lbs, with vacuum specific impulses of at least 850 sec and with full engine throttle capability. 12 refs

  4. Nuclear engineering education in italian universities

    International Nuclear Information System (INIS)

    Dulla, S.; Panella, B.; Ravetto, P.

    2011-01-01

    The paper illustrates the evolution and the present situation of the university-level nuclear engineering education in Italy. The problems connected with the need of qualified faculty in view of a dramatic increase of students is pointed out. A short description of the programs at present available at Italian universities is also presented, together with some statistics referred to Politecnico di Torino. The mathematical and computation content of each programs is also analyzed. (author)

  5. Nuclear Engineering Academic Programs Survey, 2003

    International Nuclear Information System (INIS)

    Science and Engineering Education, Oak Ridge Institute for Science and Education

    2004-01-01

    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

  6. Welding problems in nuclear power engineering

    International Nuclear Information System (INIS)

    Zubchenko, A.S.

    1986-01-01

    The problems of welding industry in nuclear power plant engineering, mainly related to the improvement of molten bath protection, are considered. Development of new materials for welding electrodes, for cladding and welding fluxes, is pointed out. Production of the following equipment is brought to a commercial level: welding heads and welding machines for branch pipe welding, anticorrosion cladding, zonal thermal treatment, electron beam welding facilities for the welding and maintenance of turbineblades, equipment for nondestructive testing of welded joints

  7. New trends in nuclear power engineering development

    International Nuclear Information System (INIS)

    Krasin, A.K.

    1974-01-01

    The specific features are considered of three designs of nuclear power plants with fast reactors: three-circuit nuclear power plant with liquid sodium as primary and secondary coolant, in the third circuit water vapor being used as turbine working medium, dual cycle nuclear power plant with pressurized helium as primary coolant and water vapor as turbine working medium, direct cycle nuclear power plant with a dissociating gas (nitrogen tetroxide N 2 O 4 ) as reactor coolant and turbine working medium. The version of the direct cycle nuclear power plant with dissociating N 2 O 4 was proposed and being developed by the Institute of Nuclear Engineering of the Academy of Sciencies of the BSSR. The thermal and physical properties of the dissociating gas allow a high-power-density reactor core to be used with a hard neutron spectra resulting in a high breeding ratio and a short doubling time. The pressure range from 150 to 170 bar was proven for this coolant under laboratory conditions and structural materials were chosen that ensure all the components of the direct cycle nuclear power plant to be workable. At present it is difficult to say which of the three versions is the most advantageous. The further development of a full-scale prototypes of a commercial nuclear power plant with a fast reactor and investigation of their technical and economic parameters remain the problems of utmost importance. A possible use of nuclear reactors is shortly considered for process heat production, in ferrous metallurgy, for hydrogen and new isotope production, and for radiation chemistry as well

  8. Nuclear thermal propulsion engine cost trade studies

    International Nuclear Information System (INIS)

    Paschall, R.K.

    1993-01-01

    The NASA transportation strategy for the Mars Exploration architecture includes the use of nuclear thermal propulsion as the primary propulsion system for Mars transits. It is anticipated that the outgrowth of the NERVA/ROVER programs will be a nuclear thermal propulsion (NTP) system capable of providing the propulsion for missions to Mars. The specific impulse (Isp) for such a system is expected to be in the 870 s range. Trade studies were conducted to investigate whether or not it may be cost effective to invest in a higher performance (Isp>870 s) engine for nuclear thermal propulsion for missions to Mars. The basic cost trades revolved around the amount of mass that must be transported to low-earth orbit prior to each Mars flight and the cost to launch that mass. The mass required depended on the assumptions made for Mars missions scenarios including piloted/cargo flights, number of Mars missions, and transit time to Mars. Cost parameters included launch cost, program schedule for development and operations, and net discount rate. The results were very dependent on the assumptions that were made. Under some assumptions, higher performance engines showed cost savings in the billions of dollars; under other assumptions, the additional cost to develop higher performance engines was not justified

  9. Infiltration of quality concepts in nuclear engineering education

    International Nuclear Information System (INIS)

    Woodall, D.M.

    1993-01-01

    The principles of total quality management (TQM) have been applied increasingly in the nuclear power industry over the last decade. The involvement of industrial professionals on the advisory boards of engineering colleges and departments has increasingly led in recent years to the recommendation that TQM be applied as appropriate to engineering education. This paper describes the concepts of TQM in their application to engineering education, specifically in the nuclear engineering area. A summary of the concerns expressed by nuclear engineering academics, as well as the record of successful implementation of TQM in the nuclear engineering education environment is provided in this paper

  10. Development and application of nuclear safety goals in Japan. Lessons learnt from the case of 2003 draft safety goals

    International Nuclear Information System (INIS)

    Sugawara, Shin-etsu; Inamura, Tomoaki

    2016-01-01

    The Nuclear Safety Commission in Japan offered a detailed draft of nuclear safety goals to the public in 2003, though its position was ambiguous in nuclear safety regulation. This report shows the circumstances behind the development and application of 2003 draft safety goals based on our interviews with the experts who had been involved in making the draft. According to our interviews, they had intention to utilize safety goals for improving risk management of regulatory authority and nuclear energy industry, such as ameliorating deterministic regulations, accumulating experience of risk assessment and management, promoting related research, and communicating risks with general public. In practice, however, safety goals had functioned as a tool for emphasizing an assertion that 'nuclear power plants had already been safe enough'. We identified the following four major impediments to utilizing safety goals; 1) lack of sharing overall recognition of the importance of establishing safety goals among nuclear community, 2) excessive emphasis of internal event risks which leads to an inferior priority to tackle with the issue of external events risks, 3) adverse effect of 'tunnel-visioned incrementalism', that is, nuclear energy industrial entities are attracted their foci too much on what they have been told to do by regulators or local governments, and, 4) negative attitude to disclose the outcomes of risk assessment for fear of societal reactions. To encourage upcoming safety goals and risk management, this report provides the following points for overcoming these problems; 1) sharing insights on the reasons why nuclear community set up safety goals, 2) introducing the concept of adaptive risk management for maintaining questioning attitude, 3) conducting a periodic review of goal attainment level and also safety goals themselves from the eyes of a detached observer, and, 4) rebuilding relationship with society beginning with arguments with local stakeholders over

  11. Targeted initiatives. Support for nuclear engineering education in the USA

    International Nuclear Information System (INIS)

    Gutteridge, John

    2001-01-01

    Recruitment and education of a new generation of nuclear engineers stands to benefit in the USA from a range of programmes involving governmental bodies, universities, and industry groups. They are part of efforts to attract more students to consider and prepare for careers in the nuclear industry, and to provide financial support for nuclear research and education. Career prospects in the nuclear field are brightening. The demand for nuclear engineers and nuclear trained personnel is on the rise as the new century opens. During the past year several studies were completed in an attempt to ascertain the problems in nuclear engineering education and define initiatives to address these problems

  12. Industry perceptions of the impact of the U.S. Nuclear Regulatory Commission on nuclear power plant activities. Draft report

    Energy Technology Data Exchange (ETDEWEB)

    Davis, A Bert; Pederson, Cynthia D

    1990-03-01

    Teams of senior managers from the U.S. Nuclear Regulatory Commission (NRC) surveyed licensee staff members representing 13 nuclear power utilities from across the country to obtain their candid views of the effectiveness and impact of NRC regulatory activities. Licensee comments addressed the full scope of NRC activities and the impact of agency actions on licensee resources, staff performance, planning and scheduling, and organizational effectiveness. The principal themes of the survey respondents' comments are that (1) licensees acquiesce to NRC requests to avoid poor ratings on NRC Systematic Assessment of Licensee Performance (SALP) reports and the consequent financial and public perception problems that result, even if the requests require the expenditure of significant resources on matters of marginal safety significance, and (2) NRC so dominates licensee resources through its existing and changing formal and informal requirements that licensees believe that their plants, though not unsafe, would have better reliability, and may even achieve a higher degree of safety, if licensees were freer to manage their own resources. This draft report does not attempt to defend any NRC position; endorse or refute licensee perceptions; or explain any action taken by NRC in fulfilling its responsibilities to protect the health and safety of the public. Senior RC managers have made a preliminary evaluation of the information in this report and have made recommendations to address licensee concerns in some areas. The final evaluation and recommendations will be published at a later date as the final NUREG. (author)

  13. Draft fracture mechanics code case for American Society of Mechanical Engineers NUPACK rules

    International Nuclear Information System (INIS)

    McConnell, P.; Sorenson, K.; Nickell, R.; Saegusa, T.

    2004-01-01

    The containment boundaries of most spent-fuel casks certified for use in the United States by the Nuclear Regulatory Commission are constructed with stainless steel, a material that is ductile in an engineering sense at all temperatures and for which, therefore, fracture mechanics principles are not relevant for the containment application. Ferritic materials may fail in a nonductile manner at sufficiently low temperatures, so fracture mechanics principles may be applied to preclude nonductile fracture. Because of the need to transport and store spent nuclear fuel safely in all types of climatic conditions, these vessels have regulatory lowest service temperatures that range down to -40 C (-40 F) for transport application. Such low service temperatures represent a severe challenge in terms of fracture toughness to many ferritic materials. Linear-elastic and elastic-plastic fracture mechanics principles provide a methodology for evaluating ferritic materials under such conditions

  14. Draft Federal Act of the Russian Federation 'The Civil Liability for Nuclear Damage and its Financial Security'

    International Nuclear Information System (INIS)

    Lebedeva, Yulia

    2014-01-01

    The use of nuclear power by states in the modern world requires supplements to international law through the development of national legislation on civil liability for nuclear damage and compensation. The situation in the Russian Federation is no exception. Russian law on civil liability for nuclear damage has not fully evolved, and currently, there is no specific law covering liability for nuclear damage, nor is there a law regarding the financial and insurance mechanisms for compensation. Instead, the current laws establish a state system of benefits and compensation for damage to health and property of citizens. Since 1996, Russia has been actively working to develop a draft federal act to cover liability for nuclear damage. A bill was first introduced in the State Duma of the Federal Assembly of the Russian Federation on 16 July 1996, and was originally called 'The Compensation for Nuclear Damage and Nuclear Insurance'. In 1997, the official representative of the Government of the Russian Federation, Head of Russian Federal Inspectorate for Nuclear and Radiation Safety, Yuri Vishnevsky, was appointed to present this bill for discussion in the chambers of the Federal Assembly of the Russian Federation. In September 1998, the State Duma rejected the draft federal act and instead adopted in the first reading a different draft federal act: No. 96700118-2, 'The Civil Liability for Nuclear Damage and its Financial Security' ('the bill'). In this case, the State Duma Committee on Ecology was charged with incorporating the incoming amendments into a final bill and submitting it to the State Duma for a second reading. In 2005, Russia ratified the Vienna Convention on Civil Liability for Nuclear Damage. This ratification required significant amendments to 'The Civil Liability for Nuclear Damage and its Financial Security' bill. But, even though the Russian Federation had not yet ratified the Vienna Convention, the drafters were still careful to take into account the

  15. Summary of aerospace and nuclear engineering activities

    Science.gov (United States)

    1988-01-01

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

  16. Developing safety culture in nuclear power engineering

    International Nuclear Information System (INIS)

    Tevlin, S.A.

    2000-01-01

    The new issue (no. 11) of the IAEA publications series Safety Reports, devoted to the safety culture in nuclear engineering Safety culture development in the nuclear activities. Practical recommendations to achieve success, is analyzed. A number of recommendations of international experts is presented and basic general indicators of satisfactory and insufficient safety culture in the nuclear engineering are indicated. It is shown that the safety culture has two foundations: human behavior and high quality of the control system. The necessity of creating the confidence by the management at all levels of the enterprise, development of individual initiative and responsibility of the workers, which make it possible to realize the structural hierarchic system, including technical, human and organizational constituents, is noted. Three stages are traced in the process of introducing the safety culture. At the first stage the require,emts of scientific-technical documentation and provisions of the governmental, regional and control organs are fulfilled. At the second stage the management of the organization accepts the safety as an important direction in its activities. At the third stage the organization accomplishes its work, proceeding from the position of constant safety improvement. The general model of the safety culture development is considered [ru

  17. Impact of quality concepts on nuclear engineering accreditation

    International Nuclear Information System (INIS)

    Woodall, D.M.

    1993-01-01

    This paper is an update of the accreditation process for nuclear engineering education at the undergraduate and graduate level in U.S. universities and colleges. The Engineering Accreditation Commission (EAC) of the Accreditation Board for Engineering and Technology (ABET) has made a number of major changes in the process for engineering accreditation in recent years. This paper identifies those changes that have taken place, discusses the rationale for those changes, and encourages U.S. universities with nuclear engineering programs to respond

  18. Draft Law on the creation, attribution, organization and functioning of a ''Regulatory Authority and Nuclear Safety'' (ARSN)

    International Nuclear Information System (INIS)

    Issoufou, Mahamadou

    2016-08-01

    This Draft Law deals with the establishment, responsibilities, organization and functioning of an Autority Control and Nuclear Safety. Through this law, the Regulatory and Nuclear Safety Autority is responsible for regulation of nuclear and radiological activities to ensure the safety, security and protection of persons and the environment against the effects of radiation throughout the national territory. [fr

  19. Engineering thermal engine rocket adventurer for space nuclear application

    International Nuclear Information System (INIS)

    Nam, Seung H.; Suh, Kune Y.; Kang, Seong G.

    2008-01-01

    The conceptual design for the first-of-a-kind engineering of Thermal Engine Rocket Adventure (TERA) is described. TERA comprising the Battery Omnibus Reactor Integral System (BORIS) as the heat resource and the Space Propulsion Reactor Integral System (SPRIS) as the propulsion system, is one of the advanced Nuclear Thermal Rocket (NTR) engine utilizing hydrogen (H 2 ) propellant being developed at present time. BORIS in this application is an open cycle high temperature gas cooled reactor that has eighteen fuel elements for propulsion and one fuel element for electricity generation and propellant pumping. Each fuel element for propulsion has its own small nozzle. The nineteen fuel elements are arranged into hexagonal prism shape in the core and surrounded by outer Be reflector. The TERA maximum power is 1,000 MW th , specific impulse 1,000 s, thrust 250,000 N, and the total mass is 550 kg including the reactor, turbo pump and auxiliaries. Each fuel element comprises the fuel assembly, moderators, pressure tube and small nozzle. The TERA fuel assembly is fabricated of 93% enriched 1.5 mm (U, Zr, Nb)C wafers in 25.3% voided Square Lattice Honeycomb (SLHC). The H 2 propellant passes through these flow channels. This study is concerned with thermohydrodynamic analysis of the fuel element for propulsion with hypothetical axial power distribution because nuclear analysis of TERA has not been performed yet. As a result, when the power distribution of INSPI's M-SLHC is applied to the fuel assembly, the local heat concentration of fuel is more serious and the pressure of the initial inlet H 2 is higher than those of constant average power distribution applied. This means the fuel assembly geometry of 1.5 mm fuel wafers and 25.3% voided SLHC needs to be changed in order to reduce thermal and mechanical shocks. (author)

  20. Nuclear science and engineering education at a university research reactor

    International Nuclear Information System (INIS)

    Loveland, W.

    1993-01-01

    The role of an on-site irradiation facility in nuclear science and engineering education is examined. Using the example of a university research reactor, the use of such devices in laboratory instruction, public outreach programs, special instructional programs, research, etc. is discussed. Examples from the Oregon State University curriculum in nuclear chemistry, nuclear engineering and radiation health are given. (author) 1 tab

  1. Civil engineering in the nuclear industry

    International Nuclear Information System (INIS)

    Dexter-Smith, R.

    1991-01-01

    Civil Engineering has an important contribution to make at every stage of the nuclear fuel cycle, from the choice of site and conception of the design of a major power station or fuel plan, through modifications during modifications, during operation, to the final stages of designing and building waste management stores and repositories and the decommissioning of stations and plants. The conference papers published here -twenty four in total - cover many of these stages. All the papers are indexed separately. Two international papers are presented, one on French PWRs, the other on repository design. Four papers look at site investigations, four are concerned with earthquake engineering, four with structural analysis, three with quality assurance, three with design and four with in-service performance and decommissioning. (UK)

  2. Engineering design guidelines for nuclear criticality safety

    International Nuclear Information System (INIS)

    Waltz, W.R.

    1988-08-01

    This document provides general engineering design guidelines specific to nuclear criticality safety for a facility where the potential for a criticality accident exists. The guide is applicable to the design of new SRP/SRL facilities and to major modifications Of existing facilities. The document is intended an: A guide for persons actively engaged in the design process. A resource document for persons charged with design review for adequacy relative to criticality safety. A resource document for facility operating personnel. The guide defines six basic criticality safety design objectives and provides information to assist in accomplishing each objective. The guide in intended to supplement the design requirements relating to criticality safety contained in applicable Department of Energy (DOE) documents. The scope of the guide is limited to engineering design guidelines associated with criticality safety and does not include other areas of the design process, such as: criticality safety analytical methods and modeling, nor requirements for control of the design process

  3. Malignant pleural mesothelioma in a nuclear engineer

    International Nuclear Information System (INIS)

    Huncharek, M.

    1988-01-01

    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)

  4. Nuclear reactor safety: physics and engineering aspects

    International Nuclear Information System (INIS)

    Kinchin, G.H.

    1982-01-01

    In order to carry out the sort of probabilistic analysis referred to by Farmer (Contemp. Phys.; 22:349(1981)), it is necessary to have a good understanding of the processes involved in both normal and accident conditions in a nuclear reactor. Some of these processes, for a variety of different reactor systems, are considered in sections dealing with the neutron chain reaction, the removal of heat from the reactor, material problems, reliability of protective systems and a number of specific topics of particular interest from the point of view of physics or engineering. (author)

  5. Replacement Nuclear Research Reactor. Supplement to Draft Environmental Impact Statement. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-01-01

    The Draft Environmental Impact Statement for a replacement research reactor at Lucas Heights, was available for public examination and comment for some three months during 1998. A Supplement to the Draft Environmental Impact Statement (Draft EIS) has been completed and was lodged with Environment Australia on 18 January 1999. The Supplement is an important step in the overall environmental assessment process. It reviews submissions received and provides the proponent`s response to issues raised in the public review period. General issues extracted from submissions and addressed in the Supplement include concern over liability issues, Chernobyl type accidents, the ozone layer and health issues. Further studies, relating to issues raised in the public submission process, were undertaken for the Supplementary EIS. These studies confirm, in ANSTO`s view, the findings of the Draft EIS and hence the findings of the Final EIS are unchanged from the Draft EIS

  6. Replacement Nuclear Research Reactor. Supplement to Draft Environmental Impact Statement. Volume 3

    International Nuclear Information System (INIS)

    1999-01-01

    The Draft Environmental Impact Statement for a replacement research reactor at Lucas Heights, was available for public examination and comment for some three months during 1998. A Supplement to the Draft Environmental Impact Statement (Draft EIS) has been completed and was lodged with Environment Australia on 18 January 1999. The Supplement is an important step in the overall environmental assessment process. It reviews submissions received and provides the proponent's response to issues raised in the public review period. General issues extracted from submissions and addressed in the Supplement include concern over liability issues, Chernobyl type accidents, the ozone layer and health issues. Further studies, relating to issues raised in the public submission process, were undertaken for the Supplementary EIS. These studies confirm, in ANSTO's view, the findings of the Draft EIS and hence the findings of the Final EIS are unchanged from the Draft EIS

  7. Do nuclear engineering educators have a special responsibility

    International Nuclear Information System (INIS)

    Weinberg, A.M.

    1977-01-01

    Each 1000 MW(e) reactor in equilibrium contains 15 x 10 9 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)

  8. Environmental and waste disposal options in nuclear engineering curricula

    International Nuclear Information System (INIS)

    Elleman, T.S.; Gilligan, J.G.

    1991-01-01

    The strong national emphasis on waste and environmental issues has prompted increasing interest among nuclear engineering students in study options that will prepare them for careers in these areas. Student interest appears to focus principally on health physics, radioactive waste disposal, and environmental interactions with radionuclides. One motivation for this interest appears to be the growing national programs in environmental restoration and waste remediation that have produced fellowship support for nuclear engineering students as well as employment opportunities. Also, the recent National Academy of sciences study on nuclear engineering education specifically emphasized the importance of expanding nuclear engineering curricula and research programs to include a greater emphasis on radioactive waste and environmental issues. The North Carolina State University (NCSU) Department of Nuclear Engineering is attempting to respond to these needs through the development of course options that will allow students to acquire background in environmental subjects as a complement to the traditional nuclear engineering education

  9. Nuclear engineering questions: power, reprocessing, waste, decontamination, fusion

    International Nuclear Information System (INIS)

    Walton, R.D. Jr.

    1979-01-01

    This volume contains papers presented at the chemical engineering symposium on nuclear questions. Specific questions addressed by the speakers included: nuclear power - why and how; commercial reprocessing - permanent death or resurrection; long-term management of commercial high-level wastes; long-term management of defense high-level waste; decontamination and decommissioning of nuclear facilities, engineering aspects of laser fusion I; and engineering aspects of laser fusion II. Individual papers have been input to the Energy Data Base previously

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

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    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. Centre for nuclear engineering University of Toronto annual report 1984

    International Nuclear Information System (INIS)

    1984-12-01

    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

  12. Study on the evolution of nuclear engineering professions

    International Nuclear Information System (INIS)

    2008-01-01

    Based on interviews of experts belonging to different companies and institutions (EDF, AREVA, CEA, ASN, IRSN, INSTN), subcontractors, engineers and technicians of the nuclear sector, persons in charge of education, pupils and students, this study gives a synthetic vision of the general context of the needs for nuclear engineering professionals, at the world scale, in the French context, the perceived difficulties faced by this sector, the use of subcontracting, the recruitment needs, the educational profile of engineers and technicians, their revenues, their opinion about their work, the adequacy between education and employment in this sector. It gives estimated figures for engineer and technician recruitment needs for different abilities in the French nuclear engineering

  13. A comprehensive program of nuclear engineering and science education

    International Nuclear Information System (INIS)

    Bereznai, G.; Lewis, B.

    2014-01-01

    The University of Ontario Institute of Technology offers undergraduate degrees in nuclear engineering, nuclear power, health physics and radiation science, graduate degrees (masters as well as doctorate) in nuclear engineering, and graduate diplomas that encompass a wide range of nuclear engineering and technology topics. Professional development programs tailored to specific utility needs are also offered, and the sharing of course material between the professional development and university education courses has strengthened both approaches to ensuring the high qualification levels required of professionals in the nuclear industry. (author)

  14. Nuclear science and engineering education at a university research reactor

    International Nuclear Information System (INIS)

    Loveland, W.

    1990-01-01

    The research and teaching operations of the Nuclear Chemistry Division of the Dept. of Chemistry and the Dept. of Nuclear Engineering are housed at the Oregon State University Radiation Center. This facility which includes a 1.1 MW TRIGA reactor was used for 53 classes from a number of different academic departments last year. About one-half of these classes used the reactor and ∼25% of the reactor's 45 hour week was devoted to teaching. Descriptions will be given of reactor-oriented instructional programs in nuclear engineering, radiation health and nuclear chemistry. In nuclear chemistry, classes in (a) nuclear chemistry for nuclear engineers, (b) radiotracer methods, (c) elementary and advanced activation analysis, and (d) advanced nuclear instrumentation will be described in detail. The use of the facility to promote general nuclear literacy among college students, high school and grade school students and the general population will also be covered

  15. Undergraduate education in nuclear engineering in the USA

    International Nuclear Information System (INIS)

    Martin, W.R.

    1993-01-01

    The discipline of nuclear engineering is described, giving some historical background to explain the structure of the curricula commonly found in nuclear engineering programs in the U.S. Typical curricula are described, along with a specific example given by the University of Michigan undergraduate program in nuclear engineering. The National Academy of Sciences report on U.S. nuclear engineering education is summarized, and the major findings are presented, including data on the number of programs, number of degrees, and enrollment trends. Some discussion is made of manpower trends and the degree to which nuclear programs can supply nuclear engineers to meet the anticipated demands of the current decade and into the next century. (author) 12 refs.; 2 figs.; 4 tabs

  16. Experience with performance based training of nuclear criticality safety engineers

    International Nuclear Information System (INIS)

    Taylor, R.G.

    1993-01-01

    For non-reactor nuclear facilities, the U.S. Department of Energy (DOE) does not require that nuclear criticality safety engineers demonstrate qualification for their job. It is likely, however, that more formalism will be required in the future. Current DOE requirements for those positions which do have to demonstrate qualification indicate that qualification should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis is incompletely developed in some areas

  17. Virginia power nuclear power station engineer training program

    International Nuclear Information System (INIS)

    Williams, T.M.; Haberstroh-Timpano, S.

    1987-01-01

    In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

  18. Guidelines for inservice testing at nuclear power plants. Draft report for comment

    International Nuclear Information System (INIS)

    Campbell, P.

    1993-11-01

    In this report, the staff gives licensees guidelines for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The report includes U.S. Nuclear Regulatory Commission (NRC) guidance and recommendations on inservice testing issues. The staff discusses the regulations, the components to be included in an inservice testing program, and the preparation and content of cold shutdown and refueling outage justifications and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information for application at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code

  19. HIGH SERVE '90 - nuclear engineering services

    International Nuclear Information System (INIS)

    Bauer, K.G.

    1991-01-01

    Nuclear engineering services do not start only with maintenance or repair, but already with the early detection of imminent problems long before they become problems. Services concerning the decommissioning of plants also belong to it. A selection of the extraordinary services rendered nowadays is presented in more than 20 papers in this booklet. These papers may roughly be divided into three groups of subjects: monitoring and operational management; maintenance, repair and improvements; radioactive waste treatment and management. The first group of subjects, in particular, covers papers dealing with early detection, monitoring and diagnosing systems, using highly advanced hard- and software technologies. Modernization of instrumentation and control systems and exchange of process computer systems is another task this service has to accomplish. Process computers of the past have developed into high performance process information systems. (orig./DG) [de

  20. Reactor physics computations for nuclear engineering undergraduates

    International Nuclear Information System (INIS)

    Huria, H.C.

    1989-01-01

    The undergraduate program in nuclear engineering at the University of Cincinnati provides three-quarters of nuclear reactor theory that concentrate on physical principles, with calculations limited to those that can be conveniently completed on programmable calculators. An additional one-quarter course is designed to introduce the student to realistic core physics calculational methods, which necessarily requires a computer. Such calculations can be conveniently demonstrated and completed with the modern microcomputer. The one-quarter reactor computations course includes a one-group, one-dimensional diffusion code to introduce the concepts of inner and outer iterations, a cell spectrum code based on integral transport theory to generate cell-homogenized few-group cross sections, and a multigroup diffusion code to determine multiplication factors and power distributions in one-dimensional systems. Problem assignments include the determination of multiplication factors and flux distributions for typical pressurized water reactor (PWR) cores under various operating conditions, such as cold clean, hot clean, hot clean at full power, hot full power with xenon and samarium, and a boron concentration search. Moderator and Doppler coefficients can also be evaluated and examined

  1. A new undergraduate course: Problems in nuclear engineering

    International Nuclear Information System (INIS)

    Larsen, Edward W.

    2011-01-01

    During the past five years, a new third-year undergraduate nuclear engineering course has been developed and taught at the University of Michigan. The course was created to correct certain deficiencies in the undergraduate nuclear engineering curriculum. Here we discuss the origins of the new course and our experience with it. (author)

  2. Congressional perspective on the prospects for tomorrow's nuclear engineers

    International Nuclear Information System (INIS)

    Lloyd, M.

    1986-01-01

    This paper reviews in some detail the nature of the directions in the federally supported nuclear energy research program and discusses the potential opportunities in nuclear engineering education to make contributions to the nation's nuclear power research efforts. The potential impacts of deficit reduction measures on the budgets for nuclear fission programs are also described and the subcommittee priorities for the DOE nuclear fission program within the budget framework are discussed

  3. Several aspects of the effect of nuclear power engineering and thermal power engineering on the environment

    Energy Technology Data Exchange (ETDEWEB)

    Malenchenko, A F

    1979-01-01

    A survey is made of the comparative effect of nuclear power engineering and thermal power engineering on environment and man. The most significant approaches to solution of radio-ecological problems of APS are found.

  4. Essentials of the successful drafting of invention applications on nuclear technology in the view of patent examination

    International Nuclear Information System (INIS)

    Zhai Chenyang

    2010-01-01

    Up to now, there has been a comparatively low ratio of domestic authorization in terms of invention applications in the field of nuclear technology. In this paper, the main reasons according to my experience in the patent examination are revealed in the following three aspects: (1) there is a lack of novelty or inventive step; (2) the scope of some claims is not clearly defined; (3) the description is improperly drafting. Common problems are shown and analyzed. Suggestion for avoiding the problems and corresponding solutions are given. (author)

  5. Inherently safe nuclear-driven internal combustion engines

    International Nuclear Information System (INIS)

    Alesso, P.; Chow, Tze-Show; Condit, R.; Heidrich, J.; Pettibone, J.; Streit, R.

    1991-01-01

    A family of nuclear driven engines is described in which nuclear energy released by fissioning of uranium or plutonium in a prompt critical assembly is used to heat a working gas. Engine performance is modeled using a code that calculates hydrodynamics, fission energy production, and neutron transport self-consistently. Results are given demonstrating a large negative temperature coefficient that produces self-shutoff of energy production. Reduced fission product inventory and the self-shutoff provide inherent nuclear safety. It is expected that nuclear engine reactor units could be scaled from 100 MW on up. 7 refs., 3 figs

  6. Establishment of professional nuclear power architectural engineering company

    International Nuclear Information System (INIS)

    Guo Dongli; Chen Hua

    2006-01-01

    The rapid development of nuclear power industry in China requires specialized management for the nuclear power engineering projects. It is necessary to establish the nuclear power architectural engineering company to meet the increasing market needs by providing the owner with specialized nuclear engineering project management and overall contracting services. It is imperative that the purpose of establishing the corporation and enterprise core competitiveness should be clearly identified when it is established. Its organizational structure should be geared to the enterprise operation management and development to facilitate the intensified project management and control, and improve its risk-proof ability. (authors)

  7. Nuclear engineering education in the United States: a status report

    International Nuclear Information System (INIS)

    Miller, D.W.; Spinrad, B.I.

    1986-01-01

    The executive summary of the White Paper entitled The Revitalization of Nuclear Energy Education in the United States is the major component of this paper. The White Paper was completed under the auspices of the Nuclear Engineering Department Heads Organization (NEDHO). The presentation highlights events and program changes that have occurred in 1985-1986 following publication of the NEDHO White Paper. Many of these events provide optimism for the revitalization of nuclear engineering education

  8. Design of compact nuclear power marine engineering simulator

    International Nuclear Information System (INIS)

    Gao Jinghui; Xing Hongchuan; Zhang Ronghua; Yang Yanhua; Xu Jijun

    2004-01-01

    The essentiality of compact nuclear power marine engineering simulator (NPMES) is discussed. The technology of nuclear power plant engineering simulator (NPPES) for NPMES development is introduced, and the function design, general design and model design are given in details. A compact NPMES based on the nuclear power marine of 'Mutsu' is developed. The design can help the development of NPMES, which will improve operation safety and management efficiency of marine. (authors)

  9. Nuclear engineering education: A competence based approach to curricula development

    International Nuclear Information System (INIS)

    2014-01-01

    Maintaining nuclear competencies in the nuclear industry is a one of the most critical challenges in the near future. With the development of a number of nuclear engineering educational programmes in several States, this publication provides guidance to decision makers in Member States on a competence based approach to curricula development, presenting the established practices and associated requirements for educational programmes in this field. It is a consolidation of best practices that will ensure sustainable, effective nuclear engineering programmes, contributing to the safe, efficient and economic operation of nuclear power plants. The information presented is drawn from a variety of recognized nuclear engineering programmes around the world and contributes to the main areas that are needed to ensure a viable and robust nuclear industry

  10. Nuclear reactor engineering: Reactor design basics. Fourth edition, Volume One

    International Nuclear Information System (INIS)

    Glasstone, S.; Sesonske, A.

    1994-01-01

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in design and operation of nuclear power plants. Extensively updated, the fourth edition includes new material on reactor safety and risk analysis, regulation, fuel management, waste management, and operational aspects of nuclear power. This volume contains the following: energy from nuclear fission; nuclear reactions and radiations; neutron transport; nuclear design basics; nuclear reactor kinetics and control; radiation protection and shielding; and reactor materials

  11. Draft environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received on the draft EA. The Yucca Mountain site is located in the Great Basin, one of five distinct geohydrologic settings that are being considered for the first repository. On the basis of the evaluations reported in this draft EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Yucca Mountain site as one of five sites suitable for characterization. Furthermore, having performed a comparative evaluation of the five sites proposed for nomination, the DOE has determined that the Yucca Mountain site is one of three sites preferred for site characterization

  12. Introducing Knowledge Management in Study Program of Nuclear Engineering

    International Nuclear Information System (INIS)

    Pleslic, S.

    2012-01-01

    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

  13. Expertise preservation in nuclear technology - the new master course ''nuclear safety engineering'' at the RWTH Aachen

    International Nuclear Information System (INIS)

    Backus, Sabine; Heuters, Michael

    2011-01-01

    The energy concept of the German federal Government in 2010 emphasizes the importance of nuclear energy within the energy policy. The lifetime extension of German nuclear power plants and the long-term safety of radioactive waste storage is the new challenge with respect to the expertise preservation in Germany. The owners of nuclear utilities have started to assist new research programs in the field of nuclear engineering at the German universities. RWE Power and ThyssenKrupp have signed a cooperation contract in 2007 with the RWTH Aachen. The companies bear the expenses for professorships ''nuclear fuel cycle'', ''simulation in nuclear engineering'' and ''reactor safety and engineering''. An elongation of the contract is planned. A master course ''nuclear safety engineering'' over 4 semesters covers the complete fuel cycle. The authors discuss issues concerning the information of students, experiences with the expectations of students concerning their future employment, acceptance of nuclear energy and related topics.

  14. Labor market trends for nuclear engineers through 2005

    International Nuclear Information System (INIS)

    Seltzer, N.; Blair, L.M.

    1996-10-01

    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

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

    International Nuclear Information System (INIS)

    Bonin, H.W.

    2002-01-01

    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)

  16. Estimates of the radiation environment for a nuclear rocket engine

    International Nuclear Information System (INIS)

    Courtney, J.C.; Manohara, H.M.; Williams, M.L.

    1992-01-01

    Ambitious missions in deep space, such as manned expeditions to Mars, require nuclear propulsion if they are to be accomplished in a reasonable length of time. Current technology is adequate to support the use of nuclear fission as a source of energy for propulsion; however, problems associated with neutrons and gammas leaking from the rocket engine must be addressed. Before manned or unmanned space flights are attempted, an extensive ground test program on the rocket engine must be completed. This paper compares estimated radiation levels and nuclear heating rates in and around the rocket engine for both a ground test and space environments

  17. 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.

  18. Integrating design and purchasing [in nuclear engineering] with Ingecad

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    Ingecad was developed by the Ingevision division of Framatome to overcome deficiencies in traditional computer-aided design. It was developed for nuclear power project engineering around the principle of the shared management of a common database, thus making it possible to integrate several engineering disciplines. The multiuser database is managed and accessed by the different application softwares, corresponding to particular aspects of the engineering task: electrical and process control schematics; plant piping design; pressurized equipment design etc. The use of a common database ensures coherence between the different engineering disciplines, particularly between the process engineering, the plant layout design, the piping, and the instrumentation and control engineering. (author)

  19. Nuclear energy and professional engineers. Possibility of utilization of professional engineer system

    International Nuclear Information System (INIS)

    Tanaka, Shunichi; Nariai, Hideki; Madarame, Haruki; Hattori, Takuya; Kitamura, Masaharu; Fujie, Takao

    2008-01-01

    Nuclear and radiation professional engineer system started in 2004 and more than 250 persons have passed the second-step professional engineer examination, while more than 1,000 persons for the first-step examination. This special issue on possibility of utilization of professional engineer system consists of six relevant articles from experts of nuclear organizations and academia. They expect the role of professional engineer in the area of nuclear energy to enhance technology advancement and awareness of professional ethics from their respective standpoints. (T. Tanaka)

  20. Development of System Engineering Technology for Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Kim, Hodong; Choi, Iljae

    2013-04-01

    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 demonstration of pyroprocess technology which is proliferation resistance nuclear fuel cycle technology can reduce spent fuel and recycle effectively. Through this, people's trust and support on nuclear power would be obtained. Deriving the optimum nuclear fuel cycle alternative would contribute to establish a policy on back-end nuclear fuel cycle in the future, and developing the nuclear transparency-related technology would contribute to establish amendments of the ROK-U. S. Atomic Energy Agreement scheduled in 2014

  1. Engine cycle design considerations for nuclear thermal propulsion systems

    International Nuclear Information System (INIS)

    Pelaccio, D.G.; Scheil, C.M.; Collins, J.T.

    1993-01-01

    A top-level study was performed which addresses nuclear thermal propulsion system engine cycle options and their applicability to support future Space Exploration Initiative manned lunar and Mars missions. Technical and development issues associated with expander, gas generator, and bleed cycle near-term, solid core nuclear thermal propulsion engines are identified and examined. In addition to performance and weight the influence of the engine cycle type on key design selection parameters such as design complexity, reliability, development time, and cost are discussed. Representative engine designs are presented and compared. Their applicability and performance impact on typical near-term lunar and Mars missions are shown

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

    International Nuclear Information System (INIS)

    Blair, Larry M.

    2010-01-01

    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.

  3. Nuclear Engineering Enrollments and Degrees Survey, 2007 Data

    International Nuclear Information System (INIS)

    Analysis and Evaluation, Science Education Programs

    2008-01-01

    The survey includes degrees granted between September 1, 2006, and August 1, 2007, and fall 2007 enrollments. Thirty-one academic programs reported having nuclear engineering programs during 2007, and data was obtained for all thirty-one

  4. Nuclear Engineering Enrollments and Degrees Survey, 2008 Data

    International Nuclear Information System (INIS)

    2009-01-01

    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

  5. Fuzzy systems and soft computing in nuclear engineering

    International Nuclear Information System (INIS)

    Ruan, D.

    2000-01-01

    This book is an organized edited collection of twenty-one contributed chapters covering nuclear engineering applications of fuzzy systems, neural networks, genetic algorithms and other soft computing techniques. All chapters are either updated review or original contributions by leading researchers written exclusively for this volume. The volume highlights the advantages of applying fuzzy systems and soft computing in nuclear engineering, which can be viewed as complementary to traditional methods. As a result, fuzzy sets and soft computing provide a powerful tool for solving intricate problems pertaining in nuclear engineering. Each chapter of the book is self-contained and also indicates the future research direction on this topic of applications of fuzzy systems and soft computing in nuclear engineering. (orig.)

  6. Human factor engineering applied to nuclear power plant design

    International Nuclear Information System (INIS)

    Manrique, A.; Valdivia, J.C.; Jimenez, A.

    2001-01-01

    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)

  7. Russian center of nuclear science and education is the way of nuclear engineering skilled personnel training

    International Nuclear Information System (INIS)

    Murogov, V.M.; Sal'nikov, N.L.

    2006-01-01

    Nuclear power engineering as the key of nuclear technologies is not only the element of the power market but also the basis of the country's social-economic progress. Obninsk as the first science town in Russia is the ideal place for the creation of integrated Science-Research Center of Nuclear Science and Technologies - The Russian Center of Nuclear Science and Education (Center for conservation and development of nuclear knowledge) [ru

  8. Development of Draft Regulatory Guide on Accident Analysis for Nuclear Power Plants with New Safety Design Features

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Young Seok; Woo, Sweng Woong; Hwang, Tae Suk [KINS, Daejeon (Korea, Republic of); Sim, Suk K; Hwang, Min Jeong [Environment and Energy Technology, Daejeon (Korea, Republic of)

    2016-05-15

    The present paper discusses the development process of the draft version of regulatory guide (DRG) on accident analysis of the NPP having the NSFD and its result. Based on the consideration on the lesson learned from the previous licensing review, a draft regulatory guide (DRG) on accident analysis for NPP with new safety design features (NSDF) was developed. New safety design features (NSDF) have been introduced to the new constructing nuclear power plants (NPP) since the early 2000 and the issuance of construction permit of SKN Units 3 and 4. Typical examples of the new safety features includes Fluidic Device (FD) within Safety Injection Tanks (SIT), Passive Auxiliary Feedwater System (PAFS), ECCS Core Barrel Duct (ECBD) which were adopted in APR1400 design and/or APR+ design to improve the safety margin of the plants for the postulated accidents of interest. Also several studies of new concept of the safety system such as Hybrid ECCS design have been reported. General and/or specific guideline of accident analysis considering the NSDF has been requested. Realistic evaluation of the impact of NSDF on accident with uncertainty and separated accident analysis accounting the NSDF impact were specified in the DRG. Per the developmental process, identification of key issues, demonstration of the DRG with specific accident with specific NSDF, and improvement of DGR for the key issues and their resolution will be conducted.

  9. Consultation draft: Site characterization plan overview, Deaf Smith County Site, Texas: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    The Department of Energy (DOE) is preparing a site characterization plan for the candidate site in Deaf Smith County, Texas. The DOE has provided, for information and review, a consultation draft of the plan to the State of Texas and the US Nuclear Regulatory Commission. The site characterization plan is a lengthy document that describes in considerable detail the program that will be conducted to characterize the geologic, hydrologic, and other conditions relevant to the suitability of the site for a repository. The overview presented here consists of brief summaries of important topics covered in the consultation draft of the site characterization plan; it is not a substitute for the site characterization plan. The arrangement of the overview is similar to that of the plan itself, with brief descriptions of the repository system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Deaf Smith County site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization. 15 figs., 1 tab

  10. Status of nuclear engineering education in the United States

    International Nuclear Information System (INIS)

    Brown, G.J.

    2000-01-01

    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

  11. Institute of Nuclear Engineering: report 1974-1976

    International Nuclear Information System (INIS)

    Amyot, L.

    1976-01-01

    The Institute of Nuclear Engineering is described in terms of its objectives, resources, instructional duties, and research. Basically the Institute is involved in the study of technical, economic and ecological aspects of nuclear installations, basic radioisotopic methods, and general energy problems. (E.C.B.)

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

    International Nuclear Information System (INIS)

    Silva, A.G. da; Cabral, S.C.; Bastos, M.A.V.

    1987-01-01

    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.) [pt

  13. Education and training in nuclear science/engineering in Taiwan

    International Nuclear Information System (INIS)

    Chung, C.

    1994-01-01

    The present status of nuclear education and training in Taiwan is reviewed. The nuclear science/engineering program has been established in Taiwan under the College of Nuclear Science at the National Tsing Hua University since 1956; it remains the only program among 123 universities and colleges in Taiwan where education and training in nuclear fields are offered. The program, with 52 faculty members, offers advanced studies leading to BSc, MSc, and PhD degrees. Lectures and lab classes are given to 600 students currently registered in the program. Career placement program geared for the 200 graduate and 400 undergraduate students is to orientate them into the local nuclear power utilities as well as agricultural, medical, industrial, academic and governmental sectors where nuclear scientists and engineers at all levels are needed. 8 refs., 1 fig

  14. Fundamentals of nuclear science and engineering

    CERN Document Server

    Shultis, J Kenneth

    2007-01-01

    FUNDAMENTAL CONCEPTS Modern Units The Atom Chart of Nuclides MODERN PHYSICS CONCEPTS The Special Theory of Relativity Radiation as Waves and Particles Quantum Mechanics Derivation of Some Special Relativity Results Solutions to Schrodinger's Wave Equation ATOMIC/NUCLEAR MODELS Development of the Modern Atom Model Models of the Nucleus NUCLEAR ENERGETICS Binding Energy Nucleon Separation Energy Nuclear Reactions Examples of Binary Nuclear Reactions Q-Value for a Reaction Conservation of Charge and the Calculation of Q-values Q-Value for reactions Producing Excited Nuclei RADIOACTIVITY Overview Types of Radioactive Decay Radioactive Decay Diagrams Energetics of Radioactive Decay Characteristics of Radioactive Decay Decay Dynamics Naturally Occurring Radionuclides Radiodating Radioactive Decay Data BINARY NUCLEAR REACTIONS Types of Binary Reactions Kinematics of Binary Two-Product Nuclear Reactions Reaction Threshold Energy Applications of Binary Kinematics Reactions...

  15. Development of Czechoslovak nuclear power engineering

    International Nuclear Information System (INIS)

    Keher, J.

    1985-01-01

    The output of Czechoslovak nuclear power plants is envisaged at 2200 MW by 1985, 4400 MW by 1990 and 10,280 MW by the year 2000. The operation so far is assessed of Bohunice V-1 and Bohunice V-2 power plants as is the construction of the Dukovany nuclear power plant. International cooperation in the fulfilment of the nuclear power programme is based on the General Agreement on Cooperation in the Prospective Development and Interlinkage of CMEA Power Systems to the year 1990, the Agreement on Multilateral International Specialization and Cooperation of Production and on Mutual Deliveries of Nuclear Power Plant Equipment. The most important factor in international cooperation is the Programme of Cooperation between the CSSR and the USSR. The primary target in the coming period is the Temelin nuclear power plant project and the establishment of unified control of the nuclear power complex. (M.D.)

  16. Draft statement by the Watt Committee on Safety and related topics as respects nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    1982-03-01

    The following topics are examined, with particular reference to nuclear power: the nature of risk; waste disposal to the environment (ecological damage and radiation damage due to nuclear plants and fossil-fuel plants); the benefits of nuclear power (including discussion of the following matters: need to conserve fossil fuels; safety; and possibility of diversion to nuclear weapons).

  17. Establishing Requirements for Nuclear Engineering Educational Programs

    International Nuclear Information System (INIS)

    Geraskin, N.I.; Kosilov, A.N.; Sbaffoni, M.M.

    2014-01-01

    Conclusions: » There is no single approach in curricula development. » New programmes must fit into national requirements. » Because of the strong international interdependency of all nations using nuclear energy, it is critically important that a competent staff is engaged at all nuclear power plants in every country. » International approach for benchmarking university programs is to be in place with a direct benefit to the countries with new nuclear power projects

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

    International Nuclear Information System (INIS)

    1993-01-01

    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

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

    International Nuclear Information System (INIS)

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

    2013-01-01

    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)

  20. The Belgian Nuclear Higher Education Network: Your way to the European Master in Nuclear Engineering

    International Nuclear Information System (INIS)

    Moons, F.; D'haeseleer, W.; Giot, M.

    2004-01-01

    BNEN, the Belgian Nuclear Higher Education Network has been created in 2001 by five Belgian universities and the Belgian Nuclear Research Centre (SCK CEN) as a joint effort to maintain and further develop a high quality programme in nuclear engineering in Belgium. More information: http://www.sckcen.be/BNEN. (author)

  1. Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1995

    International Nuclear Information System (INIS)

    1996-08-01

    This is an annual report prepared on research education action, operation state of research instruments and others in FY 1995 at Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The laboratory has four large instruments such as high speed neutron source reactor, 'Yayoi', electron linac, fundamentally experimental equipment for blanket design of nuclear fusion reactor, and heavy radiation research equipment (HIT), of which former two are used for cooperative research with universities in Japan, and the next blanket and the last HIT are also presented for cooperative researches in Faculty of Engineering and in University of Tokyo, respectively. FY 1995 was the beginning year of earnest discussion on future planning of this facility with concentrated effort. These four large research instruments are all in their active use. And, their further improvement is under preparation. In this report, the progress in FY 1995 on operation and management of the four large instruments are described at first, and on next, research actions, contents of theses for degree and graduation of students as well as research results of laboratory stuffs are summarized. These researches are constituted mainly using these large instruments in the facility, aiming at development of advanced and new field of atomic energy engineering and relates to nuclear reactor first wall engineering, nuclear reactor fuel cycle engineering, electromagnetic structure engineering, thermal-liquid engineering, mathematical information engineering, quantum beam engineering, new type reactor design and so on. (G.K.)

  2. Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    This is an annual report prepared on research education action, operation state of research instruments and others in FY 1995 at Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The laboratory has four large instruments such as high speed neutron source reactor, `Yayoi`, electron linac, fundamentally experimental equipment for blanket design of nuclear fusion reactor, and heavy radiation research equipment (HIT), of which former two are used for cooperative research with universities in Japan, and the next blanket and the last HIT are also presented for cooperative researches in Faculty of Engineering and in University of Tokyo, respectively. FY 1995 was the beginning year of earnest discussion on future planning of this facility with concentrated effort. These four large research instruments are all in their active use. And, their further improvement is under preparation. In this report, the progress in FY 1995 on operation and management of the four large instruments are described at first, and on next, research actions, contents of theses for degree and graduation of students as well as research results of laboratory stuffs are summarized. These researches are constituted mainly using these large instruments in the facility, aiming at development of advanced and new field of atomic energy engineering and relates to nuclear reactor first wall engineering, nuclear reactor fuel cycle engineering, electromagnetic structure engineering, thermal-liquid engineering, mathematical information engineering, quantum beam engineering, new type reactor design and so on. (G.K.)

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

    International Nuclear Information System (INIS)

    2003-03-01

    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.)

  4. Advances in chemical engineering in nuclear and process industries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

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

  5. Advances in chemical engineering in nuclear and process industries

    International Nuclear Information System (INIS)

    1994-06-01

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

  6. Matching grant program for university nuclear engineering education

    International Nuclear Information System (INIS)

    Bajorek, Stephen M.

    2002-01-01

    The grant augmented funds from Westinghouse Electric Co. to enhance the Nuclear Engineering program at KSU. The program was designed to provide educational opportunities and to train engineers for careers in the nuclear industry. It provided funding and access to Westinghouse proprietary design codes for graduate and undergraduate studies on topics of current industrial importance. Students had the opportunity to use some of the most advanced nuclear design tools in the industry and to work on actual design problems. The WCOBRA/TRAC code was used to simulate loss of coolant accidents (LOCAs)

  7. Educational experiments of radiochemistry in the nuclear engineering school

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1995-06-01

    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 60 Co, liquid scintillation spectrometry and half-life determination of 87 Rb, and determination of 137 Cs 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)

  8. Experience with performance based training of nuclear criticality safety engineers

    International Nuclear Information System (INIS)

    Taylor, R.G.

    1993-01-01

    Historically, new entrants to the practice of nuclear criticality safety have learned their job primarily by on-the-job training (OJT) often by association with an experienced nuclear criticality safety engineer who probably also learned their job by OJT. Typically, the new entrant learned what he/she needed to know to solve a particular problem and accumulated experience as more problems were solved. It is likely that more formalism will be required in the future. Current US Department of Energy requirements for those positions which have to demonstrate qualification indicate that it should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis i's incompletely developed in some areas. Details of this analysis are provided in this report

  9. Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1998-01-01

    This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a)

  10. Chaos and fractals. Applications to nuclear engineering

    International Nuclear Information System (INIS)

    Clausse, A.; Delmastro, D.F.

    1990-01-01

    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) [es

  11. Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 1. Main report

    International Nuclear Information System (INIS)

    1998-07-01

    The Draft Environmental Impact Statement (EIS) for the replacement of the Australian Research reactor has been released. An important objective of the EIS process is to ensure that all relevant information has been collected and assessed so that the Commonwealth Government can make an informed decision on the proposal. The environmental assessment of the proposal to construct and operate a replacement reactor described in the Draft EIS has shown that the scale of environmental impacts that would occur would be acceptable, provided that the management measures and commitments made by ANSTO are adopted. Furthermore, construction and operation of the proposed replacement reactor would result in a range of benefits in health care, the national interest, scientific achievement and industrial capability. It would also result in a range of benefits derived from increased employment and economic activity. None of the alternatives to the replacement research reactor considered in the Draft EIS can meet all of the objectives of the proposal. The risk from normal operations or accidents has been shown to be well within national and internationally accepted risk parameters. The dose due to reactor operations would continue to be small and within regulatory limits. For the replacement reactor, the principle of 'As Low As Reasonably Achievable' would form an integral part of the design and licensing process to ensure that doses to operators are minimized. Costs associated with the proposal are $286 million (in 1997 dollars) for design and construction. The annual operating and maintenance costs are estimated to be $12 million per year, of which a significant proportion will be covered by commercial activities. The costs include management of the spent fuel from the replacement reactor as well as the environmental management costs of waste management, safety and environmental monitoring. Decommissioning costs for the replacement reactor would arise at the end of its lifetime

  12. Fuel Receiving and Storage Station. Nuclear Regulatory Commission's draft environmental statement

    International Nuclear Information System (INIS)

    1975-05-01

    A draft of the environmental impact statement for the Barnwell Fuel Receiving and Storage Station is presented. This facility is being constructed on a 1700 acre site about six miles west of the city of Barnwell in Barnwell County, South Carolina. The following topics are discussed: the site, the station, environmental effects of site preparation and station construction, environmental effects of station operation, effluent and environmental monitoring programs, environmental effects of accidents , need for the station, benefit-cost analysis of alternatives, and conclusions. (U.S.)

  13. A nuclear engineering curriculum for Asia-Pacific

    International Nuclear Information System (INIS)

    Bereznai, G.; Sumitra, T.; Chankow, N.; Chanyotha, S.

    1996-01-01

    This paper describes the nuclear engineering education and professional development curricula that are being developed at Chulalongkorn University in Bangkok, Thailand. The program was initiated in response to the Thai Government's policy to keep the option of nuclear electric generation available as the country responds to the rapid growth of industrialization and increased standard of living, and the accompanying increase in electricity consumption. The program has three main thrusts: university education, professional development, and public education. Although this paper concentrates on the university curriculum, it is shown how the university program is integrated with the development of industry professionals. The Nuclear Engineering Curricula being developed and implemented at Chulalongkorn University will offer programs at the Bachelor, Master and Doctorate levels. The curricula are designed to provide comprehensive education and training for engineers and scientists planning careers in the peaceful use of nuclear energy, with emphasis on the applications to industry and for nuclear electric generation. The Project of Human Resource Development in the Nuclear Engineering field is the result of a cooperative effort between agencies of the Thai and Canadian Governments, including the Electricity Generating Authority of Thailand, the Office of Atomic Energy for Peace, Chulalongkorn University and several other Thai Universities; Atomic Energy of Canada Limited, the Canadian International Development Agency, several Canadian Universities as well as members of the Canadian Nuclear Industry. (author)

  14. Nuclear Engineering Education in Support of Thailand’s Nuclear Power Programme

    International Nuclear Information System (INIS)

    Chanyotha, S.; Pengvanich, P.; Nilsuwankosit, S.

    2015-01-01

    This paper aims to introduce the nuclear engineering education at the Department of Nuclear Engineering, Chulalongkon University, Bangkok Thailand. The department has been offering curriculum in nuclear engineering to support the national nuclear power programme since 1970s. It is the oldest established nuclear engineering educational programme in the South East Asia region. Nevertheless, since the nuclear power programme has been postponed several times due to various reasons, the educational programme at the department has been continuously adapted to meet the nation’s needs. Several areas of study have been introduced, including nuclear power engineering, industrial applications of radioisotope, nuclear instrumentation, radioisotope production, radiation processing, environment and safety, nuclear materials, as well as the newly created nuclear security and non-proliferation. With the renewed interest in using nuclear power in Thailand in 2007, the department has been actively assisting both the government and the electric utility in preparing human resources to support the nuclear power programme through various educational and training modules. Realizing the importance of establishing and balancing all 3 aspects of the nuclear 3S (safety, security and safeguard) in Thailand and in the Southeast Asian region. The new curriculum of nuclear security and safeguard programme has been offered since 2013. Since the establishment, the department has produced hundreds of graduates (Diploma, Master’s, and Ph.D. levels) to feed the continuously expanding Thai nuclear industry. The full paper will provide detailed information of the curriculum, the challenges and obstacles that the department has encountered, as well as the national and international linkages which have been established over the years. (author)

  15. Nuclear power engineering: Public understanding and public opinion

    International Nuclear Information System (INIS)

    Kryshev, A.I.; Sazykina, T.G.

    1998-01-01

    Subjective and objective reasons for the formation of public opinion about nuclear power engineering of Russia were analyzed. Some methodological errors in work with the Russian public on the problems of nuclear energy and possible methods of their correction were discussed. The social groups of the general public, which are of greatest importance in forming the attitude towards nuclear power engineering were indicated. The conclusion was reached that opinion of the ordinary population is often indicative of real drawbacks in the work of specialists in the nuclear fuel cycle. Consequently, careful surveys of public opinion about the problems of the nuclear industry should be very useful in organizing research work properly and improving the radiation safety. (author)

  16. The midwest workshop on preparing nuclear engineering professionals

    International Nuclear Information System (INIS)

    Danofsky, R.A.; Rohach, A.F.; Spinrad, B.I.; Nodean, W.C.

    1988-01-01

    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

  17. How the engineers are sinking nuclear power

    International Nuclear Information System (INIS)

    Mintz, J.

    1983-01-01

    Poor concrete work, improper welds, and construction and installation errors at nuclear power plants are blamed on budget and schedule pressures and the nuclear industry's lack of quality assurance. Nuclear Regulatory Commission Chairman Nunzio Palladino, who trained under the exacting Admiral Rickover, has ordered the industry to upgrade its quality assurance and to take safety regulations and training more seriously. The industry's response is a program that will send a team of Institute of Nuclear Power Operators (INPO) investigators to each plant under construction every 18 months to make spot checks of worker training and performance. The Electric Power Research Institute is also developing equipment to test construction quality. Both industry officials and critics remain skeptical that quality assurance will improve with more regulation

  18. Ergonomics in nuclear and human factors engineering

    International Nuclear Information System (INIS)

    Muench, E.; Schultheiss, G.F.

    1988-01-01

    The work situation including man-machine-relationships in nuclear power plants is described. The overview gives only a compact summary of some important ergonomic parameters, i.e. human body dimension, human load, human characteristics and human knowledge. (DG)

  19. Evolutionary computing in Nuclear Engineering Institute/CNEN-Brazil

    International Nuclear Information System (INIS)

    Pereira, Claudio M.N.A.; Lapa, Celso M.F.; Lapa, Nelbia da Silva; Mol, Antonio C.

    2000-01-01

    This paper aims to discuss the importance of evolutionary computation (CE) for nuclear engineering and the development of this area in the Instituto de Engenharia Nuclear (IEN) at the last years. Are describe, briefly, the applications realized in this institute by the technical group of CE. For example: nuclear reactor core design optimization, preventive maintenance scheduling optimizing and nuclear reactor transient identifications. It is also shown a novel computational tool to implementation of genetic algorithm that was development in this institute and applied in those works. Some results were presents and the gains obtained with the evolutionary computation were discussing. (author)

  20. Speciation Profiles and Toxic Emission Factors for Nonroad Engines: DRAFT REPORT

    Science.gov (United States)

    This document details the research and development behind how MOVES2014a estimates air toxic emissions for nonroad engines and equipment run on conventional gasoline without ethanol (E0) and gasoline blended with 10% ethanol (E10) as well as diesel fuel, compressed natural gas (C...

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

    International Nuclear Information System (INIS)

    Dragusin, O.; Goicea, A.

    2005-01-01

    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)

  2. Labor market trends for nuclear engineers through 2000

    International Nuclear Information System (INIS)

    Seltzer, N.; Blair, L.M.; Baker, J.G.

    1995-01-01

    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

  3. Corrosion engineering in nuclear power industry

    International Nuclear Information System (INIS)

    Prazak, M.; Tlamsa, J.; Jirousova, D.; Silber, K.

    1990-01-01

    Corrosion problems in nuclear power industry are discussed from the point of view of anticorrosion measures, whose aim is not only increasing the lifetime of the equipment but, first of all, securing ecological safety. A brief description is given of causes of corrosion damage that occurred at Czechoslovak nuclear power plants and which could have been prevented. These involve the corrosion of large-volume radioactive waste tanks made of the CSN 17247 steel and of waste piping of an ion exchange station made of the same material, a crack in a steam generator collector, contamination of primary circuit water with iron, and corrosion of CrNi corrosion-resistant steel in a spent fuel store. It is concluded that if a sufficient insight into the corrosion relationships exists and a reasonable volume of data is available concerning the corrosion state during the nuclear facility performance, the required safety can be achieved without adopting extremely costly anticorrosion measures. (Z.M.)

  4. Nuclear science and engineering in China

    Energy Technology Data Exchange (ETDEWEB)

    von Becker, K

    1979-01-01

    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 research reactors in China, a 3.5-MW LWR and 10 MW HWR, two cyclotrons and a 90-cm tokamak. These institutes also conduct investigations on solid-state physics, low-temperature physics, high-pressure physics, lasers, radiation biology, radiation chemistry, etc.

  5. Draft WNP-1 [Washington Nuclear Plant] and -3 study: 1987 resource strategy

    International Nuclear Information System (INIS)

    1986-01-01

    With this study Bonneville seeks to conclude whether WNP-1 and -3 should be preserved, terminated, or completed on a fixed construction schedule. Bonneville has completed an intensive review and analysis of issues related to this question. Bonneville's draft study conclusion is that preserving both WNP-1 and -3 is the most prudent course of action in the short run, pending the resolution of several critical factors. This conclusion is based on the following key study findings. Bonneville found that, economically, continued preservation is the lower-risk alternative. Termination creates the risk that the region would have to eventually build new coal plants, costing over $2 billion more in present value than completing WNP-1 and -3. Alternatively, preservation creates the smaller risk that preservation costs, amounting to $150 million in present value, will be spent over the next 14 years on projects that turn out not to be needed

  6. Master's degree in nuclear engineering by videotaped courses

    International Nuclear Information System (INIS)

    Corradini, M.L.; Vogelsang, W.F.

    1991-01-01

    In 1986, a group of northern midwest utilities met with faculty from the nuclear engineering department at the University of Wisconsin (UW) to discuss the possibility of offering graduate courses by videotape for academic credit and earning a master's degree. Four years later, two utility employees from Northern States Power (NSP) and Wisconsin Electric Power Companies (WEPCO) graduated from the University of Wisconsin with master's degrees earned entirely by taking videotape graduate courses at their individual nuclear power plant sites. Within these 4 years, more than a dozen videotaped graduate courses were developed by the faculty of the department in a formalized master's degree program in nuclear engineering and engineering physics. This paper outlines the program's development and its current features

  7. Site characterization plan overview: reference repository location, Hanford Site, Washington: Consultation draft: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    As part of the process for siting the nation's first geologic repository for radioactive waste, the Department of Energy (DOE) is preparing a site characterization plan for the Hanford site in Benton County, Washington. As a step in the preparation of that plan, the DOE has provided, for information and review, a consultation draft of the plan to the State of Washington, the affected Indian Tribes - the Confederated Tribes of the Umatilla Indian Reservation, the Nez Perce Indian Tribe, and the Yakima Indian Nation - and the US Nuclear Regulatory Commission. The Hanford site is one of three sites that the DOE currently plans to characterize;the other sites are the Deaf Smith County site in Texas and the Yucca Mountain site in Nevada. After site characterization has been completed and its results evaluated, the DOE will identify from among the three characterized sites the site that is preferred for the repository. The overview presented here consists of brief summaries of important topics covered in the consulation draft of the site characterization plan;it is not a substitute for the site characterization plan. The arrangement of the overview is similar to that of the plan itself, with breif descriptions of the dispoal system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Hanford site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization

  8. Reactor use in nuclear engineering programs

    International Nuclear Information System (INIS)

    Murray, R.L.

    1975-01-01

    Nuclear reactors for dual use in training and research were established at about 50 universities in the period since 1950, with assistance by the U. S. Atomic Energy Commission and the National Science Foundation. Most of the reactors are in active use for a variety of educational functions--laboratory teaching of undergraduates and graduate students, graduate research, orientation of visitors, and nuclear power plant reactor operator training, along with service to the technical community. As expected, the higher power reactors enjoy a larger average weekly use. Among special programs are reactor sharing and high-school teachers' workshops

  9. Graduate nuclear engineering programmes motivate educational and research activities

    International Nuclear Information System (INIS)

    Mavko, B.

    2000-01-01

    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)

  10. 76 FR 24018 - Notice of Availability of the Draft Supplemental Environmental Impact Statement for the Nuclear...

    Science.gov (United States)

    2011-04-29

    ... includes two construction options, the Deep Excavation Option and the Shallow Excavation Option. The two... technological capabilities that support nuclear materials handling, processing and fabrication; stockpile...

  11. Engineered barrier development for a nuclear waste repository in basalt

    International Nuclear Information System (INIS)

    Smith, M.J.

    1980-05-01

    The BWIP Engineered Barrier Program has been developed to provide an integrated approach to the development of site-specific Engineered Barrier assemblages for a repository located in basalt. The goal of this program is to specify engineered and natural barriers which will ensure that nuclear and non-radioactive hazardous materials emplaced in a repository in basalt do not exceed acceptable rates of release to the biosphere. A wide range of analytical and experimental activities related to the basalt repository environment, waste package environment, waste/barrier/rock interactions, and barrier performance assessment provide the basis for selection of systems capable of meeting licensing requirements. Work has concentrated on specifying and testing natural and man-made materials which can be used to plug boreholes in basalt and which can be used as multiple barriers to surround nuclear waste forms and containers. The Engineered Barriers Program is divided into two major activities: multiple barrier studies and borehole plugging. 8 figures, 4 tables

  12. Nuclear plant engineering work and integrated management system

    International Nuclear Information System (INIS)

    Ohkubo, Y.; Obata, T.; Tanaka, K.

    1992-01-01

    The Application of computers to the design, engineering, manufacturing and construction works of nuclear power plants has greatly contributed to improvement of productivity and reliability in the nuclear power plants constructed by Mitsubishi Nuclear Group for more than ten years. However, in most cases, those systems have been developed separately and utilized independently in different computer software and hardware environments and have not been fully utilized to achieve high efficiency and reliability. In order to drastically increase the productivity and efficiency, development of NUclear power plant engineering Work and INtegrated manaGement System (NUWINGS) started in 1987 to unify and integrate various conventional and developing systems using the state-of-the-art computer technology. The NUWINGS is almost completed and is now applied to actual plant construction. (author)

  13. Nuclear engineering in Belgium and abroad

    International Nuclear Information System (INIS)

    Gaube, M.

    1992-01-01

    The new facilities for the treatment and storage of radioactive waste in Mol/Dessel are described. In 1985 - 1990 the Doel-1 and Doel-2 nuclear power stations were fitted with new safety systems. These are presented briefly as is Belgian work for Poland (assessment of the Zarnowiec Project) and Taiwan (data bank system for radioactive waste). 2 figs

  14. Human factor engineering applied to nuclear power plant design

    International Nuclear Information System (INIS)

    Manrique, A.; Valdivia, J.C.

    2007-01-01

    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. 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. Such a plan should state: -) Activities to be performed, and -) Creation of a Human Factor Engineering team adequately qualified. The Human Factor Engineering team is an integral part of the design team and is strongly linked to the engineering organizations but simultaneously has independence to act and is free to evaluate designs and propose changes in order to enhance human behavior. TECNATOM S.A. (a Spanish company) has been a part of the Design and Human Factor Engineering Team and has collaborated in the design of an advanced Nuclear Power Plant, developing methodologies and further implementing those methodologies in the design of the plant systems through the development of the plant systems operational analysis and of the man-machine interface design. The methodologies developed are made up of the following plans: -) Human Factor Engineering implementation in the Man-Machine Interface design; -) Plant System Functional Requirement Analysis; -) Allocation of Functions to man/machine; -) Task Analysis; -) Human-System Interface design; -) Control Room Verification and -) Validation

  15. Certain aspects of the environmental impact of nuclear power engineering and thermal power engineering

    Energy Technology Data Exchange (ETDEWEB)

    Malenchenko, A F [AN Belorusskoj SSR, Minsk. Inst. Yadernoj Ehnergetiki

    1979-01-01

    A review is made of the both environmental impact and hazard to man resulting from nuclear power engineering as compared with those of thermal power engineering. At present, in addition to such criteria, as physical-chemical characteristic of energy sources, their efficiency and accessibility for exploitation, new requirements were substantiated in relation to safety of their utilization for environment. So, one of essential problems of nuclear power engineering development consists in assessment and prediction of radioecological consequence. The analysis and operating experience of more than 1000 reactor/years with no accidents and harm for pupulation show, that in respect to impact on environment and man nuclear power engineering is much more safe in comparison with energy sources using tradidional fossile fuel.

  16. IEEE [Institute of Electrical and Electronics Engineers] standards and nuclear software quality engineering

    International Nuclear Information System (INIS)

    Daughtrey, T.

    1988-01-01

    Significant new nuclear-specific software standards have recently been adopted under the sponsorship of the American Nuclear Society and the American Society of Mechanical Engineers. The interest of the US Nuclear Regulatory Commission has also been expressed through their issuance of NUREG/CR-4640. These efforts all indicate a growing awareness of the need for thorough, referenceable expressions of the way to build in and evaluate quality in nuclear software. A broader professional perspective can be seen in the growing number of software engineering standards sponsored by the Institute of Electrical and Electronics Engineers (IEEE) Computer Society. This family of standards represents a systematic effort to capture professional consensus on quality practices throughout the software development life cycle. The only omission-the implementation phase-is treated by accepted American National Standards Institute or de facto standards for programming languages

  17. 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.

  18. 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.)

  19. Advanced software development workstation. Engineering scripting language graphical editor: DRAFT design document

    Science.gov (United States)

    1991-01-01

    The Engineering Scripting Language (ESL) is a language designed to allow nonprogramming users to write Higher Order Language (HOL) programs by drawing directed graphs to represent the program and having the system generate the corresponding program in HOL. The ESL system supports user generation of HOL programs through the manipulation of directed graphs. The components of this graphs (nodes, ports, and connectors) are objects each of which has its own properties and property values. The purpose of the ESL graphical editor is to allow the user to create or edit graph objects which represent programs.

  20. Current earthquake engineering practice for Japanese nuclear power plants

    International Nuclear Information System (INIS)

    Hofmayer, C.H.; Park, Y.J.; Costello, J.F.

    1992-01-01

    This paper provides a brief overview of seismic research being conducted in Japan and describes USNRC efforts to understand Japanese seismic practice. Current earthquake engineering practice for Japanese nuclear power plants is descried in JEAG 4601-1987, ''Technical Guidelines for Aseismic Design of Nuclear Power Plants.'' The USNRC has sponsored BNL to translate this document into English. Efforts are underway to study and understand JEAG 4601-1987 and make the translation more readily available in the United States

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

    Science.gov (United States)

    1973-01-01

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

  2. The School for Nuclear Engineering is 25 years old: Where teachers go to school

    International Nuclear Information System (INIS)

    Knapp, W.

    1986-01-01

    For a quarter of a century the School for Nuclear Engineering at the Karlsruhe Nuclear Research Centre has provided further education in all areas of nuclear engineering. The courses are attended by all kinds of people: school teachers, shift managers in nuclear power stations and engineers from the Third World, for example. (orig.) [de

  3. Nuclear piston engine and pulsed gaseous core reactor power systems

    International Nuclear Information System (INIS)

    Dugan, E.T.

    1976-01-01

    The investigated nuclear piston engines consist of a pulsed, gaseous core reactor enclosed by a moderating-reflecting cylinder and piston assembly and operate on a thermodynamic cycle similar to the internal combustion engine. The primary working fluid is a mixture of uranium hexafluoride, UF 6 , and helium, He, gases. Highly enriched UF 6 gas is the reactor fuel. The helium is added to enhance the thermodynamic and heat transfer characteristics of the primary working fluid and also to provide a neutron flux flattening effect in the cylindrical core. Two and four-stroke engines have been studied in which a neutron source is the counterpart of the sparkplug in the internal combustion engine. The piston motions which have been investigated include pure simple harmonic, simple harmonic with dwell periods, and simple harmonic in combination with non-simple harmonic motion. The results of the conducted investigations indicate good performance potential for the nuclear piston engine with overall efficiencies of as high as 50 percent for nuclear piston engine power generating units of from 10 to 50 Mw(e) capacity. Larger plants can be conceptually designed by increasing the number of pistons, with the mechanical complexity and physical size as the probable limiting factors. The primary uses for such power systems would be for small mobile and fixed ground-based power generation (especially for peaking units for electrical utilities) and also for nautical propulsion and ship power

  4. Development of System Engineering Technology for Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Kim, Ho Dong; Kim, Sung Ki; Song, Kee Chan

    2010-04-01

    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

  5. Comparing the market for nuclear power in Alberta and Saskatchewan - draft paper

    Energy Technology Data Exchange (ETDEWEB)

    Bratt, D. [Dept. of Policy Studies, Mount Royal College, Calgary, Alberta (Canada)], E-mail: dbratt@mtroyal.ca

    2009-07-01

    This paper compares the markets for nuclear power in Alberta and Saskatchewan. This is done by comparing the two provincial panels that were released in Spring 2009 (Saskatchewan's Uranium Development Partnership and Alberta's Nuclear Power Expert Panel). Each panels terms of reference, membership, process, analysis, recommendations, and public consultation process are examined. Other variables for comparison include the history of its involvement in the nuclear sector, the political support, and public support. It concludes by arguing that Saskatchewan is a better market for nuclear power and that it is likely that a nuclear reactor will be built in Saskatchewan, but that surplus electricity will also be exported to Alberta. The possibility of building new nuclear power plants in both Alberta and Saskatchewan is increasing. This would not only increase the size of the Canadian nuclear industry it would also geographically expand it. Many non-Westerners see the prairies as a homogenous whole, but there are critical differences between Alberta and Saskatchewan. Analyzing these political and market differences would provide a good predicative power over the ultimate success of the nuclear power initiatives. This paper conducts a detailed comparison of the Alberta Government's Nuclear Power Expert Panel (NPEP) report and the Saskatchewan Government's Uranium Development Partnership (UDP) report. Topics for comparison include the terms of reference, membership, process, analysis, recommendations, and public consultation process. It also examines the history of each province's involvement in the nuclear industry; the level of political support including the positions of the provincial political parties; and the level of public support and knowledge. (author)

  6. Comparing the market for nuclear power in Alberta and Saskatchewan - draft paper

    International Nuclear Information System (INIS)

    Bratt, D.

    2009-01-01

    This paper compares the markets for nuclear power in Alberta and Saskatchewan. This is done by comparing the two provincial panels that were released in Spring 2009 (Saskatchewan's Uranium Development Partnership and Alberta's Nuclear Power Expert Panel). Each panels terms of reference, membership, process, analysis, recommendations, and public consultation process are examined. Other variables for comparison include the history of its involvement in the nuclear sector, the political support, and public support. It concludes by arguing that Saskatchewan is a better market for nuclear power and that it is likely that a nuclear reactor will be built in Saskatchewan, but that surplus electricity will also be exported to Alberta. The possibility of building new nuclear power plants in both Alberta and Saskatchewan is increasing. This would not only increase the size of the Canadian nuclear industry it would also geographically expand it. Many non-Westerners see the prairies as a homogenous whole, but there are critical differences between Alberta and Saskatchewan. Analyzing these political and market differences would provide a good predicative power over the ultimate success of the nuclear power initiatives. This paper conducts a detailed comparison of the Alberta Government's Nuclear Power Expert Panel (NPEP) report and the Saskatchewan Government's Uranium Development Partnership (UDP) report. Topics for comparison include the terms of reference, membership, process, analysis, recommendations, and public consultation process. It also examines the history of each province's involvement in the nuclear industry; the level of political support including the positions of the provincial political parties; and the level of public support and knowledge. (author)

  7. Problem solving in nuclear engineering using supercomputers

    International Nuclear Information System (INIS)

    Schmidt, F.; Scheuermann, W.; Schatz, A.

    1987-01-01

    The availability of supercomputers enables the engineer to formulate new strategies for problem solving. One such strategy is the Integrated Planning and Simulation System (IPSS). With the integrated systems, simulation models with greater consistency and good agreement with actual plant data can be effectively realized. In the present work some of the basic ideas of IPSS are described as well as some of the conditions necessary to build such systems. Hardware and software characteristics as realized are outlined. (orig.) [de

  8. Engineering effects of underground nuclear explosions

    Energy Technology Data Exchange (ETDEWEB)

    Boardman, Charles R [CER Geonuclear Corporation, Las Vegas, NV (United States)

    1970-05-01

    Useful effects of contained underground nuclear explosions are discussed in light of today's most promising potential applications. Relevant data obtained through exploration of explosion environments of nine U.S. tests in competent rock are summarized and presented as a practical basis for estimating magnitudes of effects. Effects discussed include chimney configuration, permeability, and volume as well as rubble particle size distributions and extents of permeability change in the chimney wall rock. Explosion mediums include shale, granite, dolomite, and salt. (author)

  9. Engineering effects of underground nuclear explosions

    International Nuclear Information System (INIS)

    Boardman, Charles R.

    1970-01-01

    Useful effects of contained underground nuclear explosions are discussed in light of today's most promising potential applications. Relevant data obtained through exploration of explosion environments of nine U.S. tests in competent rock are summarized and presented as a practical basis for estimating magnitudes of effects. Effects discussed include chimney configuration, permeability, and volume as well as rubble particle size distributions and extents of permeability change in the chimney wall rock. Explosion mediums include shale, granite, dolomite, and salt. (author)

  10. Should Nuclear Safety Care About Resilience Engineering?

    International Nuclear Information System (INIS)

    Paries, J.

    2016-01-01

    The current nuclear industry safety paradigm is based on the deterministic and/or probabilistic anticipation of all potential situations, and the predetermination of all the (safe) responses. Even the defense in depth concept, which is the core of the nuclear safety strategy and is intended to handle situations in which part of the control is lost, heavily relies on detailed anticipations. In other words, nuclear safety is mainly expected from the real world’s conformity to a designed-to-be-safe world, i.e., a well controlled world, where organizations, processes, hardware, teams, and individuals comply with their rationally predetermined behaviors. In this “command and control” perspective, risk is seen as mainly generated by deviations and variations from rules, procedures, norms, and expectations. However, real operations are complex, even in normal situations, which means that they include some unpredictable events and adaptation behaviors. The traditional “command and control” perspective fail to properly acknowledge the limits to predictability inherent to a complex adaptive system. It actually strives to reduce complexity through tighter compliance to specifications and to improve predictions capabilities through a tighter monitoring of “weak signals” and “precursors”. But in a complex world, precursors are usually obvious after the event, while not identifiable before. And the efforts made to reduce complexity may also simultaneously tighten couplings between system’s components— hence increase complexity — and reduce the diversity and flexibility needed to respond to it.

  11. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 9

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-03-01

    140 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  12. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 7

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-03-01

    139 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  13. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 13

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-12-01

    136 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  14. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 14

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-12-01

    136 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  15. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 11

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-07-01

    158 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  16. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 6

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-03-01

    135 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  17. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 5

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-03-01

    133 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  18. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 12

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-12-01

    136 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  19. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 8

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-03-01

    141 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  20. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 4

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-03-01

    135 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  1. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 15

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-12-01

    137 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  2. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 10

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1979-07-01

    142 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are available on a loan basis from ZfK Rossendorf, Information Department, Dresden

  3. Title list of selected Soviet reports in the fields of nuclear research and nuclear engineering. 0

    International Nuclear Information System (INIS)

    Schumann, G.; Sube, R.

    1977-09-01

    161 titles of reports issued by Soviet institutes (KFTI, EFI, IAE, IFVE, ITEF, NIIAR, NIIEFA, FEI, RI, SFTI) in the fields of nuclear research and nuclear engineering have been arranged according to the INIS subject scope. The reports are availabl on a loan basis from ZfK Rossendorf, Information Department, Dresden

  4. 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.

  5. Ground motion prediction needs for nuclear engineering design

    International Nuclear Information System (INIS)

    Hadjian, A.H.

    1985-01-01

    The basic design philosophy of nuclear power plants stipulates that the risk to the public be as low as reasonably achievable. As a result of this philosophy, the seismic design of nuclear power plants has tended, over time, to diverge from that of other engineered structures. The emphasis at the present time is to specify ground motion at a nuclear facility site as realistically as possible and to design all safety-related structures to respond to the specified ground motion in the elastic range. The characteristics of this realistic design ground motion are discussed and present prediction needs identified

  6. 4+DTM Soft Power for Nuclear Systems Engineering

    International Nuclear Information System (INIS)

    Suh, Kune Y.

    2006-01-01

    Nuclear Power Plants (NPPs) of a bulky and complex structure consisting of hundreds of thousands of parts require huge volume of data during the design, construction, operation, maintenance and decommissioning stages. The systems engineering thus calls for a fully automated way of managing the information spanning their life cycle, i. e. from cradle to grave. In line with practice in disciplines of naval architecture, aerospace engineering, and automotive manufacturing, the paper proposes total digital systems engineering based on three-dimensional (3D) computer-aided design (CAD) models. The signature in the proposal lies with the four-plus-dimensional (4 + D) TM Soft Power engineering, a critical technology for digital management. The technology proposed in the 3D space and time plus cost coordinates, i. e. 4 + D TM coordinates, constitutes, the backbone of digital engineering in the nuclear systems design. This solution will help the preliminary simulation capability for NPP to supply the vital information not only for the design and management of the engineered structures but also for the online maintenance. NPP can be built utilizing the optimized construction schedule and the structural design. The efficiency of project management will also be improved by dynamically storing voluminous information in the advanced database. The 4 + D TM digital engineering will eventually lead to paperless design and construction planing in the global marker place

  7. Reliability engineering for nuclear and other high technology systems

    International Nuclear Information System (INIS)

    Lakner, A.A.; Anderson, R.T.

    1985-01-01

    This book is written for the reliability instructor, program manager, system engineer, design engineer, reliability engineer, nuclear regulator, probability risk assessment (PRA) analyst, general manager and others who are involved in system hardware acquisition, design and operation and are concerned with plant safety and operational cost-effectiveness. It provides criteria, guidelines and comprehensive engineering data affecting reliability; it covers the key aspects of system reliability as it relates to conceptual planning, cost tradeoff decisions, specification, contractor selection, design, test and plant acceptance and operation. It treats reliability as an integrated methodology, explicitly describing life cycle management techniques as well as the basic elements of a total hardware development program, including: reliability parameters and design improvement attributes, reliability testing, reliability engineering and control. It describes how these elements can be defined during procurement, and implemented during design and development to yield reliable equipment. (author)

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

    International Nuclear Information System (INIS)

    Malaviya, B.K.

    1990-01-01

    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

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

    International Nuclear Information System (INIS)

    Nam, Seung Hyun; Chang, Soon Heung

    2013-01-01

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

  10. 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.

  11. Qualitative knowledge engineering for nuclear applications

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  12. Nuclear instrument engineering - the measuring and informative basis of nuclear science and technology

    International Nuclear Information System (INIS)

    Matveev, V.V.; Krasheninnikov, I.S.; Murin, I.D.; Stas', K.N.

    1977-01-01

    The cornerstones of developing nuclear instrument engineering in the USSR are shortly discussed. The industry is based on a well developed theory. A system approach is a characteristic feature of the present-day measuring and control systems engineering. Major functions of reactor instruments measuring different types of ionizing radiation are discussed at greater length. Nuclear measuring and control instruments and methods are widely used in different fields of science and technoloay and in different industries in the USSR. The efficient and safe operation of a nuclear facility is underlined to depend strongly upon a correlation between a technological process and the information and control system of the facility

  13. Risk analysis with regard to nuclear engineering

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1980-01-01

    The author discusses the following questions: why are risk analyses elaborated. How are they carried out and which problems may arise. Completeness problem, data, human factors, common-mode-failures, accident simulation. To give an idea of the applicability of the results of risk analyses the author deals with systems comparison and system optimization, maintenance and testing strategies, incidents and the course of accidents that have to be considered in designing technical safety measures for nuclear power plants. Finally, the author tries to enter into questions that might arise due to the effects risk analyses may create in the general public. (HSCH) [de

  14. Draft nuclear energy policy statement for DOE report to the International Energy Agency: long version

    International Nuclear Information System (INIS)

    1994-01-01

    US national energy policy recognizes that the continued development of commercial nuclear power in the United States is vital to US national security and energy stability since it is a significant domestic energy resource that is relatively free from international pressures. As of this writing (August 1989) the United States had 108 nuclear power reactors in commercial status. In January 1989 nuclear energy produced 46 billion KwH or 20% of total US electricity generated in contrast to 45 billion KwH (18.8%) produced in January 1988. The US Federal Government has been engaged in a variety of activities to ensure that nuclear energy remains a safe, economically competitive and environmentally acceptable option. Much of the federal effort in recent months has been devoted to developing initiatives designed to remove institutional and regulatory obstacles to the continued use of nuclear power as part of the US energy system. Within this context, the following paragraphs summarize the major features of the current status of the US nuclear energy program and policies

  15. 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.

  16. GTNDSE: The GA Tech nuclear data search engine

    International Nuclear Information System (INIS)

    Kulp, W.D.; Wood, J.L.

    2004-01-01

    The function of the search engine is to retrieve data from ENSDF-formatted files and to write data in user-selected format. The purposes are horizontal systematics of nuclear mass surface, comparison with experimental data and to assist in data analysis and evaluation

  17. Engineering - a key aspect of the UK nuclear policy review

    International Nuclear Information System (INIS)

    Bindon, J.L.; Butcher, Sally

    1993-01-01

    In anticipation of the forthcoming nuclear review, a forum on issues relevant to the industry was held at the Institution of Electrical Engineers HQ in London, in association with the Institute of Energy and the Watt Committee on Energy. The forum was divided into five sections, dealing with energy policy, the environment, industry, economics and safety. (author)

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

    International Nuclear Information System (INIS)

    Kameda, Hiroyuki; Takada, Tsuyoshi; Ebisawa, Katsumi; Nakamura, Susumu

    2012-01-01

    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)

  19. Safety Research Experiment Facilities, Idaho National Engineering Laboratory, Idaho. Draft environmental statement

    International Nuclear Information System (INIS)

    1977-01-01

    This environmental statement was prepared in accordance with the National Environmental Policy Act of 1969 (NEPA) in support of the Energy Research and Development Administration's (ERDA) proposal for legislative authorization and appropriations for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evalution of some design options and in the assessment of the long-term potential risk associated with wide-scale deployment of the FBR

  20. Qualitative knowledge engineering for nuclear applications

    International Nuclear Information System (INIS)

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

    1998-01-01

    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

  1. Engineering properties of nuclear waste slurries - 16378

    International Nuclear Information System (INIS)

    Biggs, Simon; Fairweather, Michael; Hunter, Timothy; Omokanye, Qanitalillahi; Peakall, Jeffrey

    2009-01-01

    The type of particulate systems encountered in legacy nuclear waste slurries is highly complicated, with the aggregation and flow behaviour being at times very variable. However, deconstructing the complex overall slurry activity to singular particle-particle interactions can lead to a greater understanding of the mechanisms involved with particle aggregation, and so to predictions of their settling and flow in nuclear systems. Of particular importance to legacy waste is the role of salts in controlling the attraction of particles (and so in dictating the rheological properties of the system) as sludge may contain a variety of specific ions and generally have high ionic conductivity [1]. In this paper, particle-particle interactions are characterised using a number of complimentary methods, and their influence on resulting flow and bed compression is measured. The methods used to characterise the particle-particle interactions under various salt and pH conditions were electro-acoustic analysis (zeta potential) and atomic force microscopy (AFM). Following on from the analysis of particle-particle properties, bulk sediment behaviour was investigated using shear and compressive yield stress measurements, vital parameters in dictating flow and dewatering performance, respectively. Together, these techniques enable the characterisation of a range of particulate systems that may be encountered in legacy wastes, and results point to a number of important factors that can help explain the observed variability in industrial slurry behaviour. (authors)

  2. Reaching the next generation of nuclear engineers

    International Nuclear Information System (INIS)

    Djokic, Denia; Fratoni, Massimiliano

    2008-01-01

    The University of California, Berkeley (UCB) American Nuclear Society (ANS) Student Section hosted two outreach events for young students between the ages of seven and twelve. The students were part of a private after-school club called Adventures Through Open Minds Science TM club for kids (A.T.O.M.S. club for kids) heated by Leslie Buchalter. Buchalter is an expert in early education and teaches children fundamental scientific concepts by using 'kid language' and associating usually difficult ideas with something even the very young children can understand. The greatest challenge for us UCB student organizers was to follow this manner of teaching and to construct activities that would always keep the attention of the children. We put together an array of fundamental concept demonstrations based on this philosophy. For example, the concept of half-life was taught by repeatedly tossing M and M's onto a surface and removing the upside down M and M's, and the concept of a nuclear chain reaction was introduced using a mousetrap-and-ping-pong-ball contraption. The main lessons learned were that the children most successfully absorbed ideas by engaging the students activity in the concept demonstrations, by using concepts and vocabulary already familiar to them which encouraged them to answer questions about familiar topics, and by creating a playful game out of every learning opportunity. (author)

  3. Design of nuclear power generation plants adopting model engineering method

    International Nuclear Information System (INIS)

    Waki, Masato

    1983-01-01

    The utilization of model engineering as the method of design has begun about ten years ago in nuclear power generation plants. By this method, the result of design can be confirmed three-dimensionally before actual production, and it is the quick and sure method to meet the various needs in design promptly. The adoption of models aims mainly at the improvement of the quality of design since the high safety is required for nuclear power plants in spite of the complex structure. The layout of nuclear power plants and piping design require the model engineering to arrange rationally enormous quantity of things in a limited period. As the method of model engineering, there are the use of check models and of design models, and recently, the latter method has been mainly taken. The procedure of manufacturing models and engineering is explained. After model engineering has been completed, the model information must be expressed in drawings, and the automation of this process has been attempted by various methods. The computer processing of design is in progress, and its role is explained (CAD system). (Kako, I.)

  4. Gaseous core nuclear-driven engines featuring a self-shutoff mechanism to provide nuclear safety

    International Nuclear Information System (INIS)

    Heidrich, J.; Pettibone, J.; Chow, Tze-Show; Condit, R.; Zimmerman, G.

    1991-11-01

    Nuclear driven engines are described that could be run in either pulsed or steady state modes. In the pulsed mode nuclear energy is released by fissioning of uranium or plutonium in a supercritical assembly of fuel and working gas. In a steady state mode a fuel-gas mixture is injected into a magnetic nozzle where it is compressed into a critical state and produces energy. Engine performance is modeled using a code that calculates hydrodynamics, fission energy production, and neutron transport self-consistently. Results are given demonstrating a large negative temperature coefficient that produces self-shutoff or control of energy production. Reduced fission product inventory and the self-shutoff provide inherent nuclear safety. It is expected that nuclear engine reactor units could be scaled up from about 100 MW e

  5. State of Nevada comments on the US Department of Energy draft environmental assessment for the proposed high-level nuclear waste site at Yucca Mountain

    International Nuclear Information System (INIS)

    1985-03-01

    In order to assure development of a comprehensive and coordinated State response to the Nevada draft EA, the State Nuclear Waste Project Office (NWPO) performed an extensive review of the draft document and its supporting references. Comments were also solicited from other State agencies and from local governments in southern Nevada. The results of this overall State effort are contained in subsequent sections of this document. Because the draft EA and the decision process of which it is a part are of major importance to the state as a whole as well as to individual local communities (especially those in southern Nevada), we have attempted to organize the State response in such a way as to clearly reflect areas of commonality without abridging the need for a clear delineation of issues of specific concern to local governments and individual State agencies. Part I of our response document focuses on those issues and topics that are considered to be of major concern. These comments are relatively general in nature and are organized according to subject area--not according to chapter or location in the draft EA. As such, this section represents something of an overview of our response to the document

  6. 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.

  7. Engineering and economic aspects of centalized heating from nuclear boilers

    International Nuclear Information System (INIS)

    Emel'yanov, I.Ya.; Baturov, B.B.; Korytnikov, V.P.; Koryakin, Yu.I.; Chernyaev, V.A.; Kovylyanskij, Ya.A.; Galaktionov, I.V.

    1979-01-01

    Some engineering and economic aspects for deployment of centralized nuclear boilers (NB) in the USSR are considered. Engineering, maintenance and economic features of NB as compared to organic-fuelled boilers and nuclear thermal power plants are discussed. Among major factors governing economic efficiency of NB underlined are oraganic fuel costs, reactor unit power, location relative to heat-consuming centres and capacity factor. It is concluded that NB can be economical for heating large consumers (more than 1500 G kal/hr). At the periphery NB can be competitive already at reactor unit power of several MWth. The development of HTGR type reactor-based nuclear-chemical boilers and lines for heat transport in a chemically bound state (e.g., CH 4 → H 2 +CO 2 +CO → CH 4 ) opens the way for a substantial breakthrow in the centralized NB efficiency

  8. Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Laats, E.T.

    1986-10-01

    The Nuclear Plant Analyzer (NPA) is a state-of-the-art safety analysis and engineering tool being used to address key nuclear power plant safety issues. Under the sponsorship of the US Nuclear Regulatory Commission (NRC), the NPA has been developed to integrate the NRC's computerized reactor behavior simulation codes such as RELAP5, TRAC-BWR and TRAC-PWR, with well-developed computer color graphics programs and large repositories of reactor design and experimental data. An important feature of the NPA is the capability to allow an analyst to redirect a RELAP5 or TRAC calculation as it progresses through its simulated scenario. The analyst can have the same power plant control capabilities as the operator of an actual plant. The NPA resides on the dual Control Data Corporation Cyber 176 mainframe computers at the Idaho National Engineering Laboratory and Cray-1S computers at the Los Alamos National Laboratory (LANL) and Kirtland Air Force Weapons Laboratory (KAFWL)

  9. International cooperation for promotion of nuclear science and engineering research

    International Nuclear Information System (INIS)

    Shibata, Toshikazu; Sugiyama, Kazusuke; Nakazawa, Masaharu; Katoh, Toshio; Kimura, Itsuro.

    1993-01-01

    For promotion of nuclear science and engineering research, examinations were made on the possibilities and necessary measures to extend joint research at international level. The present article is a summary of the reports of investigations performed during FY 1986 through 1991 by the Special Committee of the AESJ for Feasibility Study on International Cooperation for Promotion of Nuclear Science and Engineering Research, under contract with Science and Technology Agency of Japan. Background information was collected on the present status of scientific research facilities in US, European and Asian countries on one hand, and on the expectations and prospects of Japanese scientists on the other hand. Based on the analysis of these data, some measures necessary to expand the international cooperation were proposed. It was emphasized that international joint research on a reciprocal basis would be effective in order to strengthen the technological basis of peaceful uses of nuclear energy. Problems to be solved for the new development were also discussed. (author)

  10. Important statistics on engineering and construction of nuclear power plants

    International Nuclear Information System (INIS)

    Budwani, R.N.

    1976-01-01

    During the past seven years, a study was made of the engineering and craft manpower/manhour requirements, craft breakdowns by totals and peaks, material requirements, unit man-hours, rate of manhour/capital expenditures, and schedule requirements of representative nuclear power plants across the United States. The study is based on information received from electric utilities, engineer-constructors, site visits, the Nuclear Regulatory Commission (NRC), personal contacts, and the exchange of information with knowledgeable people. Preliminary data in the form of tables and figures are presented. Factors which have and will influence manpower, manhours, material requirements, building volumes, and schedules are outlined, and a list of recommendations is presented. The objective of this study has been to show in a concise fashion what the trend has been and what may be anticipated for future nuclear power plants

  11. Preliminary draft: environmental impact statement for Hot Engineering Test Project at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Boyle, J.W.; Baxter, B.J.; Carpenter, J.A.

    1978-08-01

    The project considered is the Hot Engineering Test Project (HETP), which is to be located in largely existing facilities at Oak Ridge National Laboratory (ORNL). The project is a part of the National High Temperature Gas-Cooled Reactor Fuel Recycle Program, which seeks to demonstrate the technological feasibility of the recycle processes. The HETP will attempt to confirm the operability of the processes (proven feasible in cold or nonradioactive, benchtop experimentation) under the more realistic radioactive condition. As such, the operation will involve the reprocessing and refabrication of spent HTGR fuel rods obtained from the Fort St. Vrain reactor. The reference fuel is highly enriched uranium. No significant radiological impacts are expected from routine operation of the facility to any biota or ecosystem. Concentrations of one or more radionuclides in Whiteoak Lake will increase as a result of the combination of HETP wastes with other ORNL wastes. Nonradiological effects from construction activities and routine operation should be insignificant on land and water use and on terrestrial and aquatic ecosystems. No significant socioeconomic impacts should occur from either construction or operation of the facility. Some conservative accident scenarios depict significant releases of radioactivity. Effects should be localized and would not be severe for all but the most unlikely of such incidents. No significant long-term commitment of resources is expected to be required for the project. Nor are any large quantities of scarce or critical resources likely to be irreversibly or irretrievably committed to the project. Principal alternatives considered were: relocation of the project site, postponement of the project schedule, project cancellation, and chemical process variations

  12. Human factors engineering in nuclear plant rehabilitations

    International Nuclear Information System (INIS)

    Bernston, K.; Remisz, M.; Malcolm, S.

    2001-01-01

    There are several unique considerations when creating and maintaining a human factors program for a plant refurbishment. These consideration arise from a variety of sources, including budget and time constraints on life extension projects, working to existing plant protocols and current acceptable HFE practices, and issues relating to function and task analysis. This results in a need to streamline and carefully time HFE practices from project start up to completion. In order to perform this task adequately, a comprehensive Human Factors Engineering Program Plan should be designed and tailored to the project. Systems of planning and prioritization are essential, and the required HFE designer training needs to be established. HFE specialists need to be aware of the existing plant constraints, and he prepared to work within them when providing support. The current paper discusses these aspects in the context of major refurbishment work at CANDU stations. (author)

  13. Draft Environmental Impact Statement on a proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel. Volume 1

    International Nuclear Information System (INIS)

    1995-03-01

    The United States Department of Energy and United States Department of State are jointly proposing to adopt a policy to manage spent nuclear fuel from foreign research reactors. Only spent nuclear fuel containing uranium enriched in the United States would be covered by the proposed policy. The purpose of the proposed policy is to promote U.S. nuclear weapons nonproliferation policy objectives, specifically by seeking to reduce highly-enriched uranium from civilian commerce. Environmental effects and policy considerations of three Management Alternative approaches for implementation of the proposed policy are assessed. The three Management Alternatives analyzed are: (1) acceptance and management of the spent nuclear fuel by the Department of Energy in the United States, (2) management of the spent nuclear fuel at one or more foreign facilities (under conditions that satisfy United States nuclear weapons nonproliferation policy objectives), and (3) a combination of components of Management Alternatives 1 and 2 (Hybrid Alternative). A No Action Alternative is also analyzed. For each Management Alternative, there are a number of alternatives for its implementation. For Management Alternative 1, this document addresses the environmental effects of various implementation alternatives such as varied policy durations, management of various quantities of spent nuclear fuel, and differing financing arrangements. Environmental impacts at various potential ports of entry, along truck and rail transportation routes, at candidate management sites, and for alternate storage technologies are also examined. For Management Alternative 2, this document addresses two subalternatives: (1) assisting foreign nations with storage; and (2) assisting foreign nations with reprocessing of the spent nuclear fuel. Management Alternative 3 analyzes a hybrid alternative. This document is Vol. 1 of 2 plus summary volume

  14. Background information document to support NESHAPS rulemaking on nuclear power reactors. Draft report

    International Nuclear Information System (INIS)

    Colli, A.; Conklin, C.; Hoffmeyer, D.

    1991-08-01

    The purpose of this Background Information Document (BID) is to present information relevant to the Administrator of the Environmental Protection Agency's (EPA) reconsideration of the need for a NESHAP to control radionuclides emitted to the air from commercial nuclear power reactors. The BID presents information on the relevant portions of the regulatory framework that NRC has implemented for nuclear power plant licensees, under the authority of the Atomic Energy Act, as amended, to protect the public's health and safety. To provide context, it summarizes the rulemaking history for Subpart I. It then describes NRC's regulatory program for routine atmospheric emissions of radionuclides and evaluates the doses caused by actual airborne emissions from nuclear power plants, including releases resulting from anticipated operational occurrences

  15. Nuclear scientists and engineers in Canada - A coming shortage?

    International Nuclear Information System (INIS)

    Stoll, P.

    1995-01-01

    A survey of large Canadian employers was used to identify the current level of employment of engineers and scientists in applications of nuclear technology. The survey assessed the labour market implications of three alternative future scenarios for the industry over the period 1994-2009 to determine the capability of the industry to maintain a competitive Canadian presence in domestic and international markets for nuclear generating facilities. The study found that under the nuclear phase-out and no-growth scenarios the requirements for nuclear experts decline from present levels of employment, but the Canadian industry retains to ability to meet an eventual renewed demand for CANDU generating systems. Under the growth scenario, requirements for nuclear scientists and engineers increase, although at a rate which can be met from domestic sources. The Canadian situation was compared with that in other OECD countries, as assessed by a study conducted by the OECD/NEA. According to this source, labour market conditions for nuclear qualified human resources in most participating OECD member countries resemble those of Canada. (author). 3 refs, 2 figs, 4 tabs

  16. Early site reviews for nuclear power facilities: procedures and possible technical review options. Draft

    International Nuclear Information System (INIS)

    1978-02-01

    The document provides guidance for utility companies, State and other governmental agencies, and others who may request or may wish to participate in an early review of site suitability issues related to a site proposed for a nuclear power or test reactor. Although the emphasis of this document is on a nuclear electric generating station, the guidance provided can be used for a test reactor or other kinds of reactors. The procedures to be followed by applicants for construction permits and by others are described and the possible significant areas of technical review are delineated

  17. Draft report on compilation of generic safety issues for light water reactor nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    A generally accepted approach to characterizing the safety concerns in nuclear power plants is to express them as safety issues which need to be resolved. When such safety issues are applicable to a generation of plants of a particular design or to a family of plants of similar design, they are termed generic safety issues. Examples of generic safety issues are those related to reactor vessel embrittlement, control rod insertion reliability or strainer clogging. The safety issues compiled in this document are based on broad international experience. This compilation is one element in the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. Refs.

  18. Draft report on compilation of generic safety issues for light water reactor nuclear power plants

    International Nuclear Information System (INIS)

    1997-07-01

    A generally accepted approach to characterizing the safety concerns in nuclear power plants is to express them as safety issues which need to be resolved. When such safety issues are applicable to a generation of plants of a particular design or to a family of plants of similar design, they are termed generic safety issues. Examples of generic safety issues are those related to reactor vessel embrittlement, control rod insertion reliability or strainer clogging. The safety issues compiled in this document are based on broad international experience. This compilation is one element in the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. Refs

  19. Annular tidal regenerator engine for nuclear circulatory support systems

    International Nuclear Information System (INIS)

    Hagen, K.G.; Ruggles, A.E.; Fam, S.S.; Torti, V.A.

    1975-01-01

    In order to simplify the configuration of the tidal regenerator engine nuclear-powered circulatory support system, thereby drastically reducing its size and improving the intrinsic reliability, the engine has been redesigned. This redesign focuses on allowing power to be extracted at the low temperature end of the engine utilizing a piston-cylinder arrangement wherein all of the necessary heat transfer processes occur in the annular gap between the piston and cylinder. In all other respects the engine retains its basic characteristics as a hybrid between a Stirling engine and a Rankine engine. A significant advantage of the new arrangement is the ability to raise the superheat temperature limit from 650 0 F to over 900 0 F. This has yielded an increase in engine efficiency from 10 percent to 14 percent, and further increases are anticipated by utilizing an expansion and/or a binary version of the engine. The implantable system volume has been reduced by a factor of three and orientation insensitivity with respect to gravity has been demonstrated. Many system components have already demonstrated endurances of several thousand hours

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

    International Nuclear Information System (INIS)

    Rodriguez, A.G.

    1986-04-01

    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

  1. Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1996

    International Nuclear Information System (INIS)

    1997-08-01

    This report summarizes research and educational activities, operation status of the research facilities of the Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo on fiscal year 1996. This facility has four major research facilities such as fast neutron source reactor 'Yayoi', electron Linac, fundamental experiment facility for nuclear fusion reactor blanket design and high fluence irradiation facility(HIT). Education and research activities are conducted in a wide fields of nuclear engineering using these facilities. The former two facilities are available for various studies by universities all over Japan, facility for nuclear fusion reactor blanket design is utilized for research within the Faculty of Engineering and HIT is used for the research within the University of Tokyo. The facility established a plan to reorganized into a nation wide research collaboration center in fiscal year 1995 and after further discussion of a future program it is decided to hold 'Nuclear energy symposium' periodically after fiscal year 1997 as a part of the activity for appealing the research results to the public. (G.K.)

  2. Computer simulation in nuclear science and engineering

    International Nuclear Information System (INIS)

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

    1992-01-01

    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.)

  3. Convergent engineering techniques for management of nuclear processes

    International Nuclear Information System (INIS)

    Carabulea, A.; Popa, I.

    1995-01-01

    The paper briefly presents the concept of convergent arhemo-systematical engineering, its advantages in comparison with classical methods of research, design, manufacture. The convergent engineering application supposes the usage of the advanced methods, techniques and equipment corresponding to the domain and specific for the corresponding branch of computer science. Starting from the convergent engineering principles and concept, the paper proposes two models applicable for new products and also for improving and optimizing the existing ones. The models are based on two levels of feedback corresponding to two levels of control and they assume the utilization of expert and robot-expert systems. The economical efficiency of the application of the convergent engineering method is evaluated for the case of a nuclear power plant by calculation the main technical and economical indicators. (Author) 2 Figs., 5 Refs

  4. Teaching WWERs at Hacettepe University Nuclear Engineering Department in Turkey

    International Nuclear Information System (INIS)

    Ergun, S.

    2011-01-01

    In this study, the challenges faced in the teaching WWER design for the reactor engineering course, which is taught in the Hcettepe University Nuclear Engineering Department are discussed. Since the course is designated taking a western reactor design into account, the computer programs and class projects prepared for the course include models and correlations suitable for these designs. The attempts for modifying the course and developing codes or programs for the course become a challenge especially in finding proper information sources on design in English. From finding proper material properties to exploring the design ideas, teaching WWER designs and using analysis tools for better teaching are very important to modify the reactor engineering course. With the study presented here, the reactor engineering course taught is described, the teaching tools are listed and attempts of modifying the course to teach and analyze WWER designs are explained

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

    International Nuclear Information System (INIS)

    Ghitescu, Petre; Prisecaru, Ilie

    2007-01-01

    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

  6. Nuclear engineering technology's role in providing a multitalented workforce

    International Nuclear Information System (INIS)

    Sherrard, J.R.; Pascal, D.D. Jr.

    1996-01-01

    In today's very competitive economic climate, all businesses are reassessing every aspect of their operations to remain economically viable. One of the most costly factors remaining is personnel costs. Substantial downsizing and restructuring have been a universal result. Nuclear utilities have had to undertake these same actions, primarily to remain competitive in the near term with inexpensive fossil-fuel-fired plants. In assessing personnel needs, nuclear utilities have determined that their nuclear operations employee of the future will be a multitalented individual with a diverse, quality education. Industry can no longer afford to have numerous specialists but instead needs fewer generalists. The success of a nuclear engineering associates degree program at Three Rivers Community College is discussed

  7. Role of nuclear engineering in the national power complex

    International Nuclear Information System (INIS)

    Petros'yants, A.M.; Baturov, B.B.

    1981-01-01

    Role of nuclear power in power engineering and fuel-power system of the country in the whole is discussed. Economic advantages of NPP's as compared with thermal power plants for district heating (TPP) are grounded. Advisability of combined production of thermal and electric power at TPP as compared with separate heat generation at NPP for district heating and electric power generation at NPP is reported. Data on perspectives of development of nuclear engineering in the light of ''Main directions of economic and social development of the USSR in 1981-1985 and up to 1990'' are presented. It is concluded that nuclear power introduction into national economy would bring important technical, economic and social consequences. Large-scale NPP construction would result in radical revision of the industry structure in the whole fuel-power system including output and transport on the base of modern technology and recent scientific-technical achievements providing essential economic and national economic effect essentially higher labour productivity in fuel power branches of industry. Besides, nuclear engineering creates conditions for better preservation of environment, reduction of expenditures for power and fuel transport, bringing industry centres nearer to centres of energy consumption as well as pre-conditions for removing threat of the so-called ''power hunger'' [ru

  8. Source term estimation during incident response to severe nuclear power plant accidents. Draft

    Energy Technology Data Exchange (ETDEWEB)

    McKenna, T J; Giitter, J

    1987-07-01

    The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. The goal is to present a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. (author)

  9. Source term estimation during incident response to severe nuclear power plant accidents. Draft

    International Nuclear Information System (INIS)

    McKenna, T.J.; Giitter, J.

    1987-01-01

    The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. The goal is to present a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. (author)

  10. Training of engineers for Czechoslovak nuclear programme at Czech Technical University in Prague

    International Nuclear Information System (INIS)

    Klik, F.; Stoll, I.

    1983-01-01

    Between the year 1959 and the 1970's specialists for the Czechoslovak nuclear programme were only educated at the Faculty of Nuclar and Physics Engineering. In the early 1970's instruction and research related to nuclear power generation was introduced at the mechanical engineering and electrical engineering faculties. The specialization ''Nuclear power facilities'' was introduced within the study field ''Thermal and nuclear machines and equipment'' at the mechanical engineering faculty, and the electrical engineering faculty opened the study course ''Nuclear power plants'' in the study year 1975/1976. Most specialists for the nuclear programme are educated at the Faculty of Nuclear and Physics Engineering in the field ''Nuclear chemical engineering'' and in specializations ''Theory and technology of nuclear reactors'', ''Dosimetry and application of ionizing radiation'' in the study field ''Nuclear engineering''. The Faculty of Nuclear and Physics Engineering also trains specialists in the field ''Structure and materials properties'', the study courses ''Measuring technology'' and ''Control technology'' are run at the electrical engineering faculty and at the mechanical engineering faculty were introduced study courses of ''Applied mechanics'' and ''Mechanical engineering technology''. Graduates of all said study courses may be employed in the nuclear programme. (E.S.)

  11. Optimized application of systems engineering to nuclear waste repository projects

    International Nuclear Information System (INIS)

    Miskimin, P.A.; Shepard, M.

    1986-01-01

    The purpose of this presentation is to describe a fully optimized application of systems engineering methods and philosophy to the management of a large nuclear waste repository project. Knowledge gained from actual experience with the use of the systems approach on two repository projects is incorporated in the material presented. The projects are currently evaluating the isolation performance of different geologic settings and are in different phases of maturity. Systems engineering methods were applied by the principal author at the Waste Isolation Pilot Plant (WIPP) in the form of a functional analysis. At the Basalt Waste Isolation Project (BWIP), the authors assisted the intergrating contractor with the development and application of systems engineering methods. Based on this experience and that acquired from other waste management projects, an optimized plan for applying systems engineering techniques was developed. The plan encompasses the following aspects: project organization, developing and defining requirements, assigning work responsibilities, evaluating system performance, quality assurance, controlling changes, enhancing licensability, optimizing project performance, and addressing regulatory issues. This information is presented in the form of a roadmap for the practical application of system engineering principles to a nuclear waste repository project

  12. The Wm. H. Zimmer Nuclear Power Station: Draft environmental statement (Docket No. 50-358)

    International Nuclear Information System (INIS)

    1976-10-01

    The proposed action is the issuance of an operating license to the Cincinnati Gas and Electric Company, the Columbus and Southern Ohio Electric Company, and the Dayton Power and Light Company for the startup and operation of the Wm. H. Zimmer Nuclear Power Station (Docket No. 50-358) (the station), located on the Ohio River in Clermont County, about 24 miles southeast of Cincinnati, Ohio. The information in this statement represents the second assessment of the environmental impact associated with the Zimmer Nuclear Power Station pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receipt of an application in 1970 to construct this plant, the staff carried out a review of impact that would occur during the plant's construction and operation. This evaluation was issued as a final environmental statement in September 1972. As the result of this environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and a public hearing in Cincinnati, Ohio, the AEC (now NRC) issued a permit in October 1972 for the construction of Unit 1 of the Zimmer Nuclear Power Station. As of June 1976, the construction of the plant was 54% complete. With a proposed fuel-loading data of April 1978, the applicant has petitioned for license to operate Unit 1 and has submitted (September 1975) the required safety and environmental reports to substantiate this petition. 96 refs., 17 figs., 34 tabs

  13. Savannah River Site, spent nuclear fuel management, draft environmental impact statement

    International Nuclear Information System (INIS)

    1998-12-01

    The management of spent nuclear fuel (SNF) has been an integral part of the mission of the Savannah River Site (SRS) for more than 40 years. Until the early 1990s, SNF management consisted primarily of short-term onsite storage and reprocessing in the SRS chemical separation facilities to produce strategic nuclear materials. With the end of the Cold War, the US Department of Energy (DOE) decided to phase out reprocessing of SNF for the production of nuclear weapons materials. Therefore, the management strategy for this fuel has shifted from short-term storage and reprocessing for the recovery of highly-enriched uranium and transuranic isotopes to stabilization, when necessary, and interim storage pending final disposition that includes preparing aluminum-based SNF for placement in a geologic repository. In addition to the fuel already onsite, the SRS will receive SNF from foreign research reactors until 2009 and from domestic research reactors until, potentially, 2035. As a result, the safe and efficient management of SNF will continue to be an important SRS mission. This EIS evaluates the potential environmental impacts of DOE's proposed plans for management SNF assigned to SRS

  14. Universities and national laboratory roles in nuclear engineering

    International Nuclear Information System (INIS)

    Sackett, J.I.

    1991-01-01

    Nuclear Engineering Education is being significantly challenged in the United States. 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 is needed to deal with 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. The Universities must increasingly identify challenges facing nuclear power that demand innovative solutions and pursue them. To be drawn into the technology the best students must see a future, a need and identify challenges that they can 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

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

    International Nuclear Information System (INIS)

    Mann, Kulwinder Singh

    2017-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-06-15

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

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

    Directory of Open Access Journals (Sweden)

    Kulwinder Singh Mann

    2017-06-01

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

  18. 75 FR 17970 - Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Science.gov (United States)

    2010-04-08

    ... waste streams include filter sludge, spent ion exchange resin, and dry active waste (DAW). DAW includes... filter sludge. The licensee's analysis indicates that the estimated increase in solid radioactive waste... of Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power Reactor...

  19. 75 FR 13600 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Science.gov (United States)

    2010-03-22

    ... waste streams include filter sludge, spent ion exchange resin, and dry active waste (DAW). DAW includes... filter sludge. The licensee's analysis indicates that the estimated increase in solid radioactive waste... Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power Reactor. Therefore, there would...

  20. 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.

  1. Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on an issues hierarchy and data needs for site characterization

    International Nuclear Information System (INIS)

    Harrison, W.; Fenster, D.F.; Ditmars, J.D.; Paddock, R.A.; Rote, D.M.; Hambley, D.F.; Seitz, M.G.; Hull, A.B.

    1986-12-01

    At the request of the Salt Repository Project (SRPO), Argonne National Laboratory conducted an independent peer review of a report by the Battelle Office of Nuclear Waste Isolation entitled ''Salt Repository Project Issues Hierarchy and Data Needs for Site Characterization (Draft).'' This report provided a logical structure for evaluating the outstanding questions (issues) related to selection and licensing of a site as a high-level waste repository. It also provided a first estimate of the information and data necessary to answer or resolve those questions. As such, this report is the first step in developing a strategy for site characterization. Microfiche copies of ''Draft Issues Hierarchy, Resolution Strategy, and Information Needs for Site Characterization and Environmental/Socioeconomic Evaluation - July, 1986'' and ''Issues Hierarchy and Data Needs for Site Characterization - February, 1985'' are included in the back pocket of this report

  2. Combustion Engineering adjusts to slump in nuclear orders

    International Nuclear Information System (INIS)

    Masters, R.

    1980-01-01

    It is three years since Combustion Engineering (C-E) received an order for a nuclear steam system supplier and it could be three or four years before a new order is placed. Although C-E will not work through its current backlog until the late 1990s, the lack of new business and the needs for backfitting are having a major impact on the way the company operates. C-E's determination to stay in the nuclear business is as strong as ever. (author)

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

    Science.gov (United States)

    1973-01-01

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

  4. Postgraduate education in nuclear engineering: towards an european degree

    International Nuclear Information System (INIS)

    Giot, M.

    2000-01-01

    This paper presents the postgraduate degree in nuclear engineering jointly organised by four universities of the French Community of Belgium, and its possible evolution towards an European degree. The project includes the location of the programme outside the partner universities at the premises of the SCK.CEN, a modular structure of the curriculum, and an increased co-operation of the teaching staff within small groups of experts including academics, researchers and practitioners from the nuclear industry. This programme would favour the exchange of students and professors through a network of top quality European institutions pursuing the same teaching objectives. (author)

  5. A consideration on public acceptance on nuclear engineering. Anti-nuclear leader is radical

    International Nuclear Information System (INIS)

    Seki, Yosinobu

    1996-01-01

    Many-times an introduction of nuclear engineering to the public, makes some confusion on their usage and safety aspects. Even what in easy to be understood to pro-nuclear people, could not be so easily accepted by the anti-nuclear people. It might be a big problem for them. To fill the difference between them, it might not go well because they do not know well on the nuclear, and anti-nuclear leader might be more skillful and attractive to talk to the people. He has a better technique to talk to the public. His talk makes the people to feel better to join to his party. But non emotional people would not go in that way, because he knows the way to think and his pile up knowledge points would not be broken down so easily. We should know the difference and use it to talk with the anti-nuclear leader. (author)

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

    International Nuclear Information System (INIS)

    1993-07-01

    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.)

  7. 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)

  8. Replacement Nuclear Research Reactor: Draft Environmental Impact Statement. Vol. 2. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The appendices contains additional relevant information on: Environment Australia EIS Guidelines, composition of the Study Team, Consultation Activities and Resuits, Relevant Legislation and Regulatory Requirements, Exampies of Multi-Purpose Research Reactors, Impacts of Radioactive Emissions and Wastes Generated at Lucas Heights Science and Technology Centre, Technical Analysis of the Reference Accident, Flora and Fauna Species Lists, Summary of Environmental Commitments and an Outline of the Construction Environmental Management Plan Construction Environmental Management Plan figs., ills., refs. Prepared for Australian Nuclear Science and Technology Organisation (ANSTO)

  9. Conducting need-for-power review for nuclear power plants: guidelines to states. Draft report

    International Nuclear Information System (INIS)

    Nash, D.A.

    1982-12-01

    The report is intended to describe the state regulatory commissions and other state agencies the standards and criteria used by NRC in conducting need-for-power evaluations for the licensing of nuclear power plants. These are intended as guidelines to states which may wish to perform a need-for-power review that will suffice for adoption by the NRC in its licensing process. Three methodologies which have been used for need-for-power evaluations and which meet NRC standards are included

  10. High level nuclear waste repository in salt: Sealing systems status and planning report: Draft report

    International Nuclear Information System (INIS)

    1985-09-01

    This report documents the initial conceptual design studies for a repository sealing system for a high-level nuclear waste repository in salt. The first step in the initial design studies was to review the current design level, termed schematic designs. This review identified practicality of construction and development of a design methodology as two key issues for the conceptual design. These two issues were then investigated during the initial design studies for seal system materials, seal placement, backfill emplacement, and a testing and monitoring plan. The results of these studies have been used to develop a program plan for completion of the sealing system conceptual design. 60 refs., 26 figs., 18 tabs

  11. Application of plasma technology to nuclear engineering fields

    International Nuclear Information System (INIS)

    Suzuki, Masaaki; Akatsuka, Hiroshi

    1996-01-01

    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)

  12. Picket engineer concept in Swiss nuclear power plants

    International Nuclear Information System (INIS)

    Steffen, W.

    1982-01-01

    Switzerland has four plants already in operation, three of the 300 MW Class and one of 1000 MW, with a further 1000 MW plant under construction. Nuclear energy is of vital importance to the country, in 1980 it accounted for almost 30% of the year's total electricity production. Great economic and political importance is attached to the safety and availability of the nuclear power plants. For safety reasons neither the plant owners nor the Authority were willing to dispense with having a qualified engineer in permanent attendance at the plant, particularly during incidents, accidents or emergencies. For this reason the concept of picket engineer was introduced in 1972, through the initiative of the plant owners and with the approval of the Authority

  13. Teaching problem-solving skills to nuclear engineering students

    Science.gov (United States)

    Waller, E.; Kaye, M. H.

    2012-08-01

    Problem solving is an essential skill for nuclear engineering graduates entering the workforce. Training in qualitative and quantitative aspects of problem solving allows students to conceptualise and execute solutions to complex problems. Solutions to problems in high consequence fields of study such as nuclear engineering require rapid and accurate analysis of the problems, design of solutions (focusing on public safety, environmental stewardship and ethics), solution execution and monitoring results. A three-month course in problem solving, modelling and simulation was designed and a collaborative approach was undertaken with instructors from both industry and academia. Training was optimised for the laptop-based pedagogy, which provided unique advantages for a course that includes modelling and simulation components. The concepts and tools learned as part of the training were observed to be utilised throughout the duration of student university studies and interviews with students who have entered the workforce indicate that the approaches learned and practised are retained long term.

  14. Application of smart transmitter technology in nuclear engineering measurements

    International Nuclear Information System (INIS)

    Kang, Hyun Gook; Seong, Poong Hyun

    1993-01-01

    By making use of the microprocessor technology, instrumentation system becomes intelligent. In this study a programmable smart transmitter is designed and applied to the nuclear engineering measurements. In order to apply the smart transmitter technology to nuclear engineering measurements, the digital time delay compensation function and water level change detection function are developed and applied in this work. The time compensation function compensates effectively the time delay of the measured signal, but it is found that the characteristics of the compensation function should be considered through its application. It is also found that the water level change detection function reduces the detection time to about 7 seconds by the signal processing which has the time constant of over 250 seconds and which has the heavy noise. (Author)

  15. 10 CFR 51.74 - Distribution of draft environmental impact statement and supplement to draft environmental impact...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Distribution of draft environmental impact statement and supplement to draft environmental impact statement; news releases. 51.74 Section 51.74 Energy NUCLEAR... Impact Statements § 51.74 Distribution of draft environmental impact statement and supplement to draft...

  16. Civil engineering in nuclear power stations: design of the turbine building and nuclear auxiliary building

    International Nuclear Information System (INIS)

    Lacroix, R.

    1985-01-01

    After enumerating the specific features of civil engineering in nuclear power stations. One goes on to examine the principal deliberations undertaken with the aim of optimising projects for transition from the P4 to P'4 and then N4 generations of nuclear power stations. The courses of action decided with respect to the design of the machine room and auxiliary equipment building are described [fr

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

    International Nuclear Information System (INIS)

    Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

    2004-01-01

    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

  18. Some current engineering topics in nuclear power plant components

    International Nuclear Information System (INIS)

    Amana, M.

    1977-01-01

    An analysis based on the principle of fracture mechanics, is presented for several engineering problems occuring in nuclear power plant components. The specific problems covered are: underclad cracking; stress corrosion cracking; cracks in HAZ of nozzle weld; feedwater nozzle corner crack; shift of transition temperature due to neutron irradiation; LWR local-ECC thermal shock experiment; and design and material selection of RPV in terms of fracture mechanics. (B.R.H.)

  19. International and national standardisation for quality assurance in nuclear engineering

    International Nuclear Information System (INIS)

    Becker, K.

    1992-01-01

    After a summarising description of international developments (ISO 6216, ISO 9000 series, IAEA 50 SG-QA) an overview of the total of around 200 national quality standards and regulations from almost 20 countries is given. Finally the relationships between rules of engineering and the rules of laws, mechanisms and trends in the development of nuclear energy standards with particular consideration of the possibilities for European harmonisation are presented in brief. 1 fig., 5 tabs

  20. Attempt of application of prefabrication techniques to nuclear engineering

    International Nuclear Information System (INIS)

    Frangi, Roger

    1981-01-01

    Prefabrication can apply to nuclear civil engineering for the execution of complicated or tall shuttering or casing work, requiring shoring that one would wish to simplify or suppress. This technique saves on work hours and improves quality and safety. A few examples carried out on the Saint-Laurent-des-Eaux and Chinon power stations are given as well as that which will be undertaken on the Belleville power station [fr

  1. Engineering for new-built nuclear power plant projects

    International Nuclear Information System (INIS)

    Gonzalez Lopez, A.

    2012-01-01

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

  2. Developing engineering analysis capabilities at a nuclear utility

    International Nuclear Information System (INIS)

    Miller, J.S.

    1992-01-01

    When a nuclear plant is originally designed and constructed, a large staff of analytical and design personnel is used by the architectural and engineering (A/E) firm(s) and the nuclear steam supply system (NSSS) engineering firm(s) to provide the technical specifications needed for the plant to function and satisfy US Nuclear Regulatory Commission (NRC) requirements. During this design process, thousands of calculations are performed, some using large sophisticated computer programs. Once the plant is operational, the utility assumes the large responsibility for plant design. Utility personnel must understand the fundamentals of operating the plant, the technical information in the updated safety analysis report, all calculations used to design the plant, and the input for all design specification documents. Without this knowledge, utility personnel cannot successfully perform modifications or new analyses required by the NRC, such as probabilistic risk assessment (PRA) and motor-operated valve programs, and maintain the safe and reliable operation of the plant. Therefore, it is very important to have on-site personnel who understand how the calculations are performed and used in the design basis. This paper discusses the organization of the engineering analysis group, which provides technical support for River Bend Station (RBS) of Gulf States Utilities

  3. Education and training in nuclear engineering and safety

    International Nuclear Information System (INIS)

    Moons, F.; Safieh, J.; Giot, M.; Mavko, B.; Sehgal, Raj B.; Schaefer, A.; Van Goethem, G.; D'haeseleer, W.

    2007-01-01

    The need to preserve, enhance or strengthen nuclear knowledge is worldwide recognized since a couple of years. Within the 5th framework program the European Commission supports the European nuclear higher education network. The ENEN contract started on Jan 1, 2002 and lasts for 24 months. The Commission support for this 'accompanying measure' amounts to EUR 197 716. Based upon a year-long extensive exchange of views between the partners of ENEN, consisting of a representative cross section of nuclear academic institutions and research laboratories of the EU-25, a coherent and practicable concept for a European Master of Science in Nuclear Engineering has emerged. The concept is compatible with the Bologna philosophy of higher education for academic education in Europe. Pursuing the sustainability of the concept, the ENEN partners organized themselves in a non-profit-making association. Within the 6th framework program, the Commission services favourably evaluated the proposal: 'Nuclear European Platform of Training and University Organisations'. The objectives of the NEPTUNO co-ordination action are to establish a fair dialogue and a strong interaction between the academic and the industrial world and to bring all nuclear education and training activities under a common strategy of the ENEN type. The present proposal schedules for 18 months and the Commission earmarked a financial contribution of EUR 830 619. (author)

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

    Science.gov (United States)

    Guarnieri, Franck; Travadel, Sébastien

    2014-11-01

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

  5. In situ calibration of nuclear plant resistance thermometers using Johnson noise. Draft

    International Nuclear Information System (INIS)

    Blalock, T.V.; Roberts, M.J.; Shepard, R.L.

    1984-01-01

    Methods have been demonstrated in operating nuclear plants for the in situ calibration of resistance thermometers with agreement between measured noise temperatures and dc calibration temperatures well within these required by the plant. A comparison of the results of Johnson noise power testing results and uncertainties, the requirements for accuracy, and PRT calibration tolerances is shown. The methods use Johnson noise measurements and provide an absolute calibration independent of the prior dc calibration. The methods include techniques for characterization of the installed extension cables and the quantitative determination of induced EMI and its effect on the calibration. The techniques are applicable to ordinary 4-wire platinum resistance thermometers operating over their entire design temperature range and to extension cables of about 100 ft length. Careful attention needs to be paid to the choice or cables, location of terminal boxes, and grounding and shielding practices in the plant installation to achieve comparable results

  6. Approaches to nontraditional delivery of nuclear engineering education

    International Nuclear Information System (INIS)

    Malaviya, B.K.

    1991-01-01

    At Rensselaer Polytechnic Institute, the faculty of the nuclear engineering and engineering physics department have, over the years, been involved in a variety of such approaches in response to the changing needs of nuclear industry personnel. A number of different types of short course and workshop programs have been developed and implemented both on and off campus in such areas as basic nuclear technology, reactor design computer codes and applications, nuclear power plant design and maintenance, reactor operations, health physics, modern developments in boiling heat transfer and two-phase flow, and probabilistic risk assessment. Customized coursed tailored to meet the particular needs of personnel in specialized areas can also be offered on specific industrial site locations, generally resulting in substantial savings of time as well as costs associated with tuition, travel, lodging. The Rensselaer Satellite Video Program (RSVP) brings the latest technological aids to the nontraditional delivery of courses and provides the facilities and opportunities for off-campus students and professional personnel to participate in regular academic programs and courses without leaving their industrial sites

  7. Feasibility study of a contained pulsed nuclear propulsion engine

    International Nuclear Information System (INIS)

    Parlos, A.G.; Metzger, J.D.

    1994-01-01

    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

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

    International Nuclear Information System (INIS)

    Kusunoki, Tsuyoshi; Kyouya, Masahiko; Takahashi, Teruo; Kobayashi, Hideo; Ochiai, Masa-aki; 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)

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

    International Nuclear Information System (INIS)

    O'Hara, John; Higgins, James

    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

  10. 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.

  11. Report of Task Force for review of nuclear waste management. Draft

    International Nuclear Information System (INIS)

    1978-02-01

    Some of the findings of the Task Force are: a majority of independent technical experts have concluded that high-level waste can be safely disposed in geological media, but validation of the specific technical choices will be an important element of the licensing process. Reprocessing is not required for the safe disposal of commercial spent fuel. Consideration should be given to an early demonstration of the geologic disposal of a limited number of spent fuel assemblies in the waste Isolation Pilot Plant. The Spent Fuel Policy announced by President Carter in October 1977 must be integrated with the Waste Management Policy. The Task Force report highlights the importance of away from reactor storage that occurs between on-site storage of spent fuel at utilities and ultimate disposal. The target for initial operation in 1985 os a National Waste Repository for the permanent disposal of commercial high-level waste as spent fuel may not be met; this does not affect the early 1980s schedule for the Waste Isolation Pilot Plant. The responsibility for the ultimate disposal for all forms of nuclear waste should be with the Federal Government and long-term waste disposal facilities should be subject to NRC licensing. The NEPA process is an essential part of the nuclear waste management program and Department of Energy efforts in this regard must be strengthened. Policy and program management responsibility for Waste Management should be raised to a higher level in the Department of Energy. There are substantial budgetary impacts of the Task Force recommendations and legislation would be required to carry out many of the suggested changes

  12. 75 FR 63519 - Notice of Availability of Draft Environmental Assessment and Draft Finding of No Significant...

    Science.gov (United States)

    2010-10-15

    ... reduced for certain environmental resource areas (i.e., for transportation, public and occupational health... NUCLEAR REGULATORY COMMISSION [NRC-2009-0435] Notice of Availability of Draft Environmental... of Availability of Draft Environmental Assessment and Draft Finding of No Significant Impact; Notice...

  13. Principles of education and training of plant engineers for nuclear power stations

    International Nuclear Information System (INIS)

    Ackermann, G.; Meyer, K.; Brune, W.

    1978-01-01

    Experience in education and advanced training of nuclear engineers in the GDR is reviewed. The basic education of engineers is carried out at universities and colleges. Graduate engineers who have been working in non-nuclear industries for a longer time receive their basic education in nuclear engineering through postgraduate studies. Graduate engineers with a basic knowledge of nuclear engineering are trained at the Nuclear Power Plant School of the Rheinsberg nuclear power plant and at the nuclear power plants of the GDR under operational conditions relating to their future job. In addition to basic theoretical knowledge, training at a nuclear power plant simulator plays an important role. This permits training of the staff under normal operating conditions including transient processes and under unusual conditions. Further particular modes of advanced professional training such as courses in radiation protection and further postgraduate studies are described. This system of education has proved successful. It will be developed further to meet the growing demands. (author)

  14. ABB.-Combustion Engineering's Experience in Nuclear Power Plant Engineering and Construction in Korea

    International Nuclear Information System (INIS)

    Veris, James W.

    1992-01-01

    The Yonggwang Nuclear Project is a milestone project for the Korean Nuclear Industry. The Project has the two objectives of obtaining self-reliance in all aspects of nuclear technology and of constructing two modern nuclear power plants under the leadership of Korean companies acting as prime contractors. ABB.-Combustion Engineering 1000 MW System 80+ TM was chosen in 1987 as the NSLS design to meet these two objectives. This paper summarizers the significant experiences and lessons learned through the first four years of the Project as well as identifying implications for such future projects. The unique challenges of the project are identified and an evaluation of the experiences in the technology, self-reliance program and in the design and manufacturing processes will be made

  15. 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)

    Trethewey, K.R.; Beeley, P.A.; Lockwood, R.S.; Harrop, I.

    2004-01-01

    The Nuclear Department at HMS SULTAN provides education, training and research support to the Royal Navy Nuclear Propulsion Programme, as well as a growing number of civilian programmes within the wider British nuclear industry. As an aspiring centre of excellence in nuclear engineering, the Department will play an important role as a repository of nuclear knowledge for the foreseeable future. (author)

  16. NUKEM. Innovative solutions for nuclear engineering; Innovative Loesungen rund um nukleares Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Scheffler, Beate [NUKEM Technologies GmbH, Alzenau (Germany)

    2011-03-15

    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.)

  17. 4+D digital engineering for advanced nuclear energy systems

    International Nuclear Information System (INIS)

    Jeong, S. G.; Suh, K. Y.; Nam, S. K.

    2007-01-01

    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 automated way of managing the information flow spanning their life cycle. In line with practice in disciplines of naval architecture, aerospace engineering, and automotive manufacturing, the paper proposes total digital systems engineering based on three-dimensional (3D) computer-aided design (CAD) models. The signature in the proposal lies with the four-plus-dimensional (4 + D) Technology T M, a critical know-how for digital management. The so-called OPIUM (Optimized Plant Integrated Ubiquitous Management) features a 4 + D Technology T M for nuclear energy systems engineering. The technology proposed in the 3D space and time plus cost coordinates, i.e. 4 + D, is the backbone of digital engineering in the nuclear systems design and management. Based on an integrated 3D configuration management system, OPIUM consists of solutions NOTUS (Nuclear Optimization Technique Ubiquitous System), VENUS (Virtual Engineering Nuclear Ubiquitous System), INUUS (Informatics Nuclear Utilities Ubiquitous System), JANUS (Junctional Analysis Numerical Ubiquitous System) and EURUS (Electronic Unit Research Ubiquitous System). These solutions will help initial simulation capability for NPPs to supply the crucial information. 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

  18. Artificial intelligence in nuclear engineering: developments, lesson learned and future directions

    Energy Technology Data Exchange (ETDEWEB)

    Ruan, Da [The Belgian Nuclear Research Centre (SCK.CEN), Mol (Belgium)]. E-mail: druan@sckcen.be

    2005-07-01

    Full text of publication follows: In this lecture, an overview on artificial intelligence (AI) from control to decision making in nuclear engineering will be given mainly based on the 10 years progress of the FLINS forum (Fuzzy Logic and Intelligent Technology in Nuclear Science). Some FLINS concrete examples on nuclear reactor operation, nuclear safeguards information management, and cost estimation under uncertainty for a large nuclear project will be illustrated for the potential use of AI in nuclear engineering. Recommendations and future research directions on AI in nuclear engineering will be suggested from a practical point of view. (author)

  19. Artificial intelligence in nuclear engineering: developments, lesson learned and future directions

    International Nuclear Information System (INIS)

    Ruan, Da

    2005-01-01

    Full text of publication follows: In this lecture, an overview on artificial intelligence (AI) from control to decision making in nuclear engineering will be given mainly based on the 10 years progress of the FLINS forum (Fuzzy Logic and Intelligent Technology in Nuclear Science). Some FLINS concrete examples on nuclear reactor operation, nuclear safeguards information management, and cost estimation under uncertainty for a large nuclear project will be illustrated for the potential use of AI in nuclear engineering. Recommendations and future research directions on AI in nuclear engineering will be suggested from a practical point of view. (author)

  20. Draft environmental statement related to the Western Nuclear, Inc. Split Rock Mill (Fremont County, Wyoming)

    International Nuclear Information System (INIS)

    1978-11-01

    The proposed action is the renewal of Source Material License SUA-56 (with amendments) issued to Western Nuclear, Inc. (WNI), for the operation of the Split Rock uranium mill near Jeffrey City and the Green Mountain ion-exchange facility, both in Fremont County, Wyoming. The license also permits possession of material from past operations at four ancillary facilities in the Gas Hills mining area--the Bullrush, Day-Loma, Frazier-Lamac, and Rox sites (Docket No. 40-1162). The Split Rock mill is an acid-leach, ion-exchange and solvent-extraction uranium-ore processing mill with a design capacity of 1540 MT (1700 tons) of ore per day. WNI has proposed by license amendment request to increase the storage capacity of the tailings ponds in order to permit the continuation of present production rates of U 3 O 8 through 1996 using lower-grade ores. Conditions for the protection of the environment include reclamation, tailings, stabilization, archeological survey, monitoring, etc

  1. PACCOM: A nuclear waste packaging facility cost model: Draft technical report

    International Nuclear Information System (INIS)

    Dippold, D.G.; Tzemos, S.; Smith, D.J.

    1985-05-01

    PACCOM is a computerized, parametric model used to estimate the capital, operating, and decommissioning costs of a variety of nuclear waste packaging facility configurations. The model is based upon a modular waste packaging facility concept from which functional components of the overall facility have been identified and their design and costs related to various parameters such as waste type, waste throughput, and the number of operational shifts employed. The model may be used to either estimate the cost of a particular waste packaging facility configuration or to explore the cost tradeoff between plant capital and labor. That is, one may use the model to search for the particular facility sizes and associated cost which when coupled with a particular number of shifts, and thus staffing level, leads to the lowest overall total cost. The functional components which the model considers include hot cells and their supporting facilities, transportation, cask handling facilities, transuranic waste handling facilities, and administrative facilities such as warehouses, security buildings, maintenance buildings, etc. The cost of each of these functional components is related either directly or indirectly to the various independent design parameters. Staffing by shift is reported into direct and indirect support labor. These staffing levels are in turn related to the waste type, waste throughput, etc. 2 refs., 11 figs., 3 tabs

  2. LXII International conference NUCLEUS 2012. Fundamental problems of nuclear physics, atomic power engineering and nuclear technologies (LXII Meeting on nuclear spectroscopy and nuclear structure). Book of abstracts

    International Nuclear Information System (INIS)

    Vlasnikov, A.K.

    2012-01-01

    The scientific program of the conference covers almost all problems in nuclear physics and its applications. The recent results of experimental investigations of atomic nuclei properties and nuclear reaction mechanisms are presented. The theoretical problems of atomic nuclei and fundamental interactions as well as nuclear reactions are discussed. The new techniques and methods of nuclear physical experiments are considered. The particular attention is given to fundamental problems of nuclear power and qualitative training of russian and foreign specialist in field of nuclear physics and atomic power engineering [ru

  3. Engineering and maintenance applied to safety-related valves in nuclear power plants

    International Nuclear Information System (INIS)

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

    2014-01-01

    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)

  4. 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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

    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 CO 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 describes

  6. 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

  7. Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo

    2016-01-01

    Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

  8. Draft environmental impact statement. River Bend Nuclear Power Station, Unit 1

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    Federal financing of an undivided ownership interest of River Bend Nuclear Power Station Unit 1 on a 3293-acre site near St. Francisville, Louisiana is proposed in a supplement to the final environmental impact statement of September 1974. The facility would consist of a boiling-water reactor that would produce a maximum of 2894 megawatts (MW) of electrical power. A design level of 3015 MW of electric power could be realized at some time in the future. Exhaust steam would be cooled by mechanical cooling towers using makeup water obtained from and discharged to the Mississippi River. Power generated by the unit would be transmitted via three lines totaling 140 circuit miles traversing portions of the parishes of West Feliciana, East Feliciana, East Baton Rouge, West Baton Rouge, Pointe Coupee, and Iberville. The unit would help the applicant meet the power needs of rural electric consumers in the region, and the applicant would contribute significanlty to area tax base and employment rolls during the life of the unit. Construction related activities would disturb 700 forested acres on the site and 1156 acres along the transmission routes. Of the 60 cubic feet per second (cfs) taken from the river, 48 cfs would evaporate during the cooling process and 12 cfs would return to the river with dissolved solids concentrations increased by 500%. The terrace aquifer would be dewatered for 16 months in order to lower the water table at the building site, and Grants Bayou would be transformed from a lentic to a lotic habitat during this period. Fogging and icing due to evaporation and drift from the cooling towers would increase slightly. During the construction period, farming, hunting, and fishing on the site would be suspended, and the social infractructure would be stressed due to the influx of a maximum of 2200 workers

  9. Calculated concentrations of any radionuclide deposited on the ground by release from underground nuclear detonations, tests of nuclear rockets, and tests of nuclear ramjet engines

    International Nuclear Information System (INIS)

    Hicks, H.G.

    1981-11-01

    This report presents calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from three types of event that deposited detectable radioactivity outside the Nevada Test Site complex, namely, underground nuclear detonations, tests of nuclear rocket engines and tests of nuclear ramjet engines

  10. History of the Development of NERVA Nuclear Rocket Engine Technology

    International Nuclear Information System (INIS)

    David L., Black

    2000-01-01

    During the 17 yr between 1955 and 1972, the Atomic Energy Commission (AEC), the U.S. Air Force (USAF), and the National Aeronautics and Space Administration (NASA) collaborated on an effort to develop a nuclear rocket engine. Based on studies conducted in 1946, the concept selected was a fully enriched uranium-filled, graphite-moderated, beryllium-reflected reactor, cooled by a monopropellant, hydrogen. The program, known as Rover, was centered at Los Alamos Scientific Laboratory (LASL), funded jointly by the AEC and the USAF, with the intent of designing a rocket engine for long-range ballistic missiles. Other nuclear rocket concepts were studied during these years, such as cermet and gas cores, but are not reviewed herein. Even thought the program went through the termination phase in a very short time, the technology may still be fully recoverable/retrievable to the state of its prior technological readiness in a reasonably short time. Documents; drawings; and technical, purchasing, manufacturing, and materials specifications were all stored for ease of retrieval. If the U.S. space program were to discover a need/mission for this engine, its 1972 'pencils down' status could be updated for the technology developments of the past 28 yr for flight demonstration in 8 or fewer years. Depending on today's performance requirements, temperatures and pressures could be increased and weight decreased considerably

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

    Energy Technology Data Exchange (ETDEWEB)

    Ansley, Shannon Leigh

    2002-02-01

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

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

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

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

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

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

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

  14. Nuclear Power Engineering Education Program, University of Illinois

    International Nuclear Information System (INIS)

    Jones, B.G.

    1993-01-01

    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

  15. Educating nuclear engineers by nuclear science and technology master at UPM

    Energy Technology Data Exchange (ETDEWEB)

    Ahnert, C.; Minguez, E.; Perlado, M. [Universidad Politecnica de Madrid (Spain). Dept. de Ingenieria Nuclear; and others

    2014-05-15

    One of the main objectives of the Master on Nuclear Science and Technology implemented in the Universidad Politecnica de Madrid, is the training for the development of methodologies of simulation and advanced analysis necessary in research and in professional work in the nuclear field, for Fission Reactors and Nuclear Fusion, including fuel cycle and safety aspects. The students are able to use the current computational methodologies/codes for nuclear engineering that covers a difficult gap between nuclear reactor theory and simulations. Also they are able to use some facilities, as the Interactive Graphical Simulator of PWR power plant that is 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 equipment on a nuclear power plant. The new Internet reactor laboratory to be implemented will help to understand the Reactor Physics concepts. The experimental set-ups for neutron research and for coating fabrication offer new opportunities for training and research activities. All of them are relevant tools for motivation of the students, and to complete the theoretical lessons. They also follow the tendency recommended for the European Space for higher Education (Bologna) adapted studies. (orig.)

  16. Educating nuclear engineers by nuclear science and technology master at UPM

    International Nuclear Information System (INIS)

    Ahnert, C.; Minguez, E.; Perlado, M.

    2014-01-01

    One of the main objectives of the Master on Nuclear Science and Technology implemented in the Universidad Politecnica de Madrid, is the training for the development of methodologies of simulation and advanced analysis necessary in research and in professional work in the nuclear field, for Fission Reactors and Nuclear Fusion, including fuel cycle and safety aspects. The students are able to use the current computational methodologies/codes for nuclear engineering that covers a difficult gap between nuclear reactor theory and simulations. Also they are able to use some facilities, as the Interactive Graphical Simulator of PWR power plant that is 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 equipment on a nuclear power plant. The new Internet reactor laboratory to be implemented will help to understand the Reactor Physics concepts. The experimental set-ups for neutron research and for coating fabrication offer new opportunities for training and research activities. All of them are relevant tools for motivation of the students, and to complete the theoretical lessons. They also follow the tendency recommended for the European Space for higher Education (Bologna) adapted studies. (orig.)

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

    International Nuclear Information System (INIS)

    Hochreiter, L. E.; Zimmerman, D. L.; Brenizer Jr, J. S.; Stark, M. A.

    2006-01-01

    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)

  18. Role of testing in requalifying Transamerica Delaval, Inc., engines for nuclear service

    International Nuclear Information System (INIS)

    Nesbitt, J.F.; Dingee, D.A.; Laity, W.W.

    1985-03-01

    This paper discusses the role of testing in requalifying Transamerica Delaval, Inc. (TDI) diesel generators for use as emergency standby power sources at nuclear power plants. ''Lead'' engine tests (to confirm the design adequacy of key engine components under conditions that could induce high-cycle fatigue) and ''following'' engine tests (for engines of the same model and equipped with the same components as the ''lead'' engine) have been conducted at several nuclear power plants. The tests conducted by Duke Power Company (Catawba Nuclear Station Unit 1) and Long Island Lighting Company (Shoreham Nuclear Power Station Unit 1) are discussed. 2 refs

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

    International Nuclear Information System (INIS)

    Slember, R.J.

    1990-01-01

    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

  20. Research works at the Physics Institute nuclear reactor for the nuclear power engineering

    International Nuclear Information System (INIS)

    Gavars, V.V.; Kalnin'sh, D.O.; Lapenas, A.A.; Tomsons, E.Ya.; Ulmanis, U.A.

    1985-01-01

    Methods for neutron spectra determination in the nuclear reactor core and vessel have been developed. On their base the neutron spectra at the Novo-Voronezh and kola NPPs have been measured. Such measurements are necessary for the determination of the nuclear fuel reprocessing coefficients, for the evaluation of the construction radiation-damage stability and the NPP economical efficiency on the whole. A new type of the reactor regulator - a liquid metal one - has been created. Such regulators are promising in respect of their use at the NPPs. The base for studying new radiation-damage-stable insulators has been founded. The materials obtained are now applied to designing the reactors of the second (fast) and the third (thermonuclear H) generations. There have developed and by a long-time exploitation checked a hot loop, used for materials irradiation. the nuclear reactor in Salaspils provides training of students being the new brain-power for the nuclear power engineering

  1. 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…

  2. 10 CFR Appendix S to Part 50 - Earthquake Engineering Criteria for Nuclear Power Plants

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Earthquake Engineering Criteria for Nuclear Power Plants S... FACILITIES Pt. 50, App. S Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power Plants... nuclear power plant structures, systems, and components important to safety to withstand the effects of...

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

    International Nuclear Information System (INIS)

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

    1992-01-01

    Interagency panels evaluating nuclear thermal propulsion development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and design issues of a proposed ground test complex for evaluating nuclear thermal propulsion engines and fuel elements being developed for the Space Nuclear Thermal Propulsion (SNTP) program. 2 refs

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

    International Nuclear Information System (INIS)

    Block, Carsten; Henkel, Fritz-Otto; Bauer, Thomas

    2014-01-01

    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.)

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

    International Nuclear Information System (INIS)

    1970-05-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-05-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-05-15

    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.

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

    International Nuclear Information System (INIS)

    1970-05-01

    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

  9. Nuclear engineering aspects of glioma BNCT research in Italy

    International Nuclear Information System (INIS)

    Curzio, G.; Mazzini, M.

    1998-01-01

    A research project on Boron Neutron Capture Therapy (BNCZ) of gliomas has been set up in Italy, with the participation of Departments of Oncology and Mechanical and Nuclear Construction (DCMN) of the University of Pisa, as well as the Neuroscience and Physics Departments of the Universities of Roma. The specific objective of DCMN Research Unit is the study of the physical-engineering aspects related to BNCT. The paper outlines the research lines in progress at DCMN: Monte Carlo calculations of neutron dose distribution for BNCT treatment planning; measurements of neutron fluxes, spectra and doses by neutron detectors specifically set up; design of modifications to the nuclear reactors of ENEA Casaccia Center. In particular, the paper emphasizes the most original contributions on dosimetric aspects, both from informatic and experimental points of view.(author)

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

    International Nuclear Information System (INIS)

    O'Hara, J.; Higgins, J.; Goodman, C.; Galletti, G.: Eckenrode, R.

    1993-01-01

    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

  11. Nuclear engineering R ampersand D at the Savannah River Site

    International Nuclear Information System (INIS)

    Strosnider, D.R.; Ferrara, W.R.

    1991-01-01

    The Westinghouse Savannah River Company (WSRC) is the prime operating contractor for the US Department of Energy at the Savannah River Site (SRS), located near Aiken, South Carolina. One division of WSRC, the Savannah River Laboratory (SRL), has the primary responsibility for research and development, which includes supporting the safe and efficient operation of the SRS production reactors. Several Sections of SRL, as well as other organization in WSRC, pursue R ampersand D and oversight activities related to nuclear engineering. The Sections listed below are described in more detail in this document: (SRL) nuclear reactor technology and scientific computations department; (SRL) safety analysis and risk management department; (WSRC) new production reactor program; and (WSRC) environment, safety, health, and quality assurance division

  12. Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Laats, E.T.; Beelman, R.J.; Charlton, T.R.; Hampton, N.L.; Burtt, J.D.

    1985-01-01

    The Nuclear Plant Analyzer (NPA) is a state-of-the-art safety analysis and engineering tool being used to address key nuclear power plant safety issues. The NPA has been developed to integrate the NRC's computerized reactor behavior simulation codes such as RELAP5, TRAC-BWR, and TRAC-PWR, with well-developed computer graphics programs and large repositories of reactor design and experimental data. An important feature of the NAP is the capability to allow an analyst to redirect a RELAP5 or TRAC calculation as it progresses through its simulated scenario. The analyst can have the same power plant control capabilities as the operator of an actual plant. The NPA resides on the dual CDS Cyber-176 mainframe computers at the INEL and is being converted to operate on a Cray-1S computer at the LANL. The subject of this paper is the program conducted at the INEL

  13. Practical application of computer graphics in nuclear power plant engineering

    International Nuclear Information System (INIS)

    Machiba, Hiroshi; Kawamura, Hirobumi; Sasaki, Norio

    1992-01-01

    A nuclear power plant is composed of a vast amount of equipment, piping, and so on, and six or seven years are required to complete the design and engineering from the initial planning stage to the time of commercial operation. Furthermore, operating plants must be continually maintained and improved for a long period. Computer graphics were first applied to the composite arrangement design of nuclear power plants in the form of 3-dimensional CAD. Subsequently, as the introduction of CAE has progressed, a huge assortment of information has been accumulated in database, and measures have been sought that would permit the convenient utilization of this information. Using computer graphics technologies, improvement of the interface between the user and such databases has recently been accomplished. In response to the growth in environmental consciousness, photo-realistic simulations for artistic design of the interior and overviews showing harmony with the surroundings have been achieved through the application of computer graphics. (author)

  14. Study on the morals of nuclear power engineers

    International Nuclear Information System (INIS)

    Kosaka, Takashi; Kotani, Fumio; Morikawa, Shin'ichi; Hiramoto, Mitsuru; Koya, Masahiko

    2000-01-01

    Regarding the incident that occurred in October 1998 in which records of containers for transporting spent fuel were altered, the morals of engineers was pointed out as one reason for the problem. Since then, much effort has been exerted to prevent the re-occurrence of such an incident and to reform the corporate climate at electric power companies. From an objective point of view the Institute of Nuclear Safety Systems, inc., the Institute of Social Research conducted an analysis regarding of the conditions faced by that engineers are faced with and discussing how the engineers should deal with the issue of morals as professionals under such circumstances. In this research, teaching materials were compiled, such as a checklist and examples of case studies, to be used for morals education/training and others. This will be useful for engineers who are working for an organization and are in a number of complicated relationships, in dealing with a wide variety of moral issues in their day-to-day activities. (author)

  15. Physical, technical and engineer concept of ultradeep nuclear geoprobes

    International Nuclear Information System (INIS)

    Vaschenko, V.; Vachev, B.; Pisarenko, T.

    2009-01-01

    This report presents information on the results of works dedicated to theoretical, physical and technical justification of contact thermal melting method of low thermal conductivity substances and to prospects of its practical realization as autonomous geoprobe for penetrating into deep Earth interior. The following problems and tasks were investigated and solved by the authors: 1) Investigation of processes of heat and mass transfer by contact melting in near-bore region due to movement of heat source of arbitrary form. 2) Development of methods and estimate of principal engineer parameters of contact thermal penetrating in low heat conducting environment. 3) Analysis of modern high-temperature materials and element base for construction of autonomous ultra deep thermoprobe. 4) Investigation of ecological consequences of possible emergency in case nuclear thermal heat source loss of sealing. 5) Mathematical problem formulation of ultra deep contact thermal penetrating by melting the environment for heat source of arbitrary form moving under gravity force and propose approach to its solution. 6) Formulation and solution of contact thermal penetration process optimization problem. 7) Development of methods of main engineering parameters of contact thermal melting of low heat conducting substances estimate. 8) Development of base of physical, engineering and technical concept of autonomous geoprobe for ultra deep penetrating into Earth interior. It is important that the results obtained may be used in engineering and constructing development of ultra deep geoprobe and also for calculation of technological apparatus and processes that use contact thermal melting of low thermal conducting materials

  16. 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.

  17. Applications of super - high intensity lasers in nuclear engineering

    International Nuclear Information System (INIS)

    Salomaa, R.; Hakola, A.; Santala, M.

    2007-01-01

    Laser-plasma interactions arising when a super intense ultrashort laser pulse impinges a solid target creates intense partly collimated and energy resolved photons, high energy electron and protons and neutrons. In addition the plasma plume can generate huge magnetic and electric fields. Also ultra short X-ray pulses are created. We have participated in some of such experiments at Rutherford and Max-Planck Institute and assessed the applications of such kind as laser-driven accelerators. This paper discusses applications in nuclear engineering (neutron sources, isotope separation, fast ignition and transmutation, etc). In particular the potential for extreme time resolution and to partial energy resolution are assessed

  18. Grain boundary engineering for structure materials of nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Tan, L., E-mail: tanl@ornl.gov [Materials Science and Technology Division, Oak Ridge National Laboratory (United States); Allen, T.R. [Department of Engineering Physics, University of Wisconsin–Madison (United States); Busby, J.T. [Materials Science and Technology Division, Oak Ridge National Laboratory (United States)

    2013-10-15

    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. EDF's Engineering Experience and Contribution to the Nuclear Development

    International Nuclear Information System (INIS)

    Salha, Bernard; Fourest, Bernard; Arpino, Jean-Marc

    2002-01-01

    Electricite de France (EDF) is now operating 58 nuclear power units which produce 76% of the electricity generated in France. This EDF's industrial success is the result of its capacity to master and optimize its production tool, from design through operation. EDF's integrated engineering is in the heart of this process of technical expertise and economic optimization. It allows to be in interface between the needs of operators and industrials suppliers, while accumulating a significant feedback of operating experience. The will of achieving the process of frenchifying PWR technology and to implement new industrial innovations have ended up in the new NPP of 100 % french design, the N4 series and its significant innovations. EDF energy policy is to keep the nuclear option open for the future. This strategy results from the need to improve the availability and the life extension of the units in operation and to prepare the replacement of the operating reactors around 2015. This is the objective of the European Pressurized Reactor (EPR), a French-German joint project. EDF is also applying this industrial process in its international projects. For example China, which desires to implement a standardized nuclear program and to move forward the complete autonomy of its nuclear industry, has decided to adopt a similar approach to EDF's one. (authors)

  20. Research on application of knowledge engineering to nuclear power stations

    International Nuclear Information System (INIS)

    Umeda, Takeo; Kiyohashi, Satoshi

    1990-01-01

    Recently, the research on the software and hardware regarding knowledge engineering has been advanced eagerly. Especially the applicability of expert systems is high. When expert systems are introduced into nuclear power stations, it is necessary to make the plan for introduction based on the detailed knowledge on the works in nuclear power stations, and to improve the system repeatedly by adopting the opinion and request of those in charge upon the trial use. Tohoku Electric Power Co. was able to develop the expert system of practically usable scale 'Supporting system for deciding fuel movement procedure'. The survey and analysis of the works in nuclear power stations, the selection of the system to be developed and so on are reported. In No. 1 plant of Onagawa Nuclear Power Station of BWR type, up to 1/3 of the fuel is replaced at the time of the regular inspection. Some fuel must be taken to outside for ensuring the working space. The works of deciding fuel movement procedure, the development of the system and its evaluation are described. (K.I.)

  1. To all of you who continue supporting Japanese Nuclear Power. A letter from nuclear engineer

    International Nuclear Information System (INIS)

    Sato, Satoshi

    2012-01-01

    Fukushima accident could not justify nuclear power and obliged nuclear engineers to accept public opinion such as 'nuclear power phase out' in 2030s. During the 'phase out' period, selected nuclear power plants would be restarted taking account of safety and accident effects with reinforced safety countermeasures against Fukushima accident, while shutdown reactor decommissioning with best technologies and intermediate storage of spent fuels before final disposal would be implemented. At the completion of 'phase out', Japanese nuclear power would end. However, renewable energy could not make such progress as expected and consumption of fossil energy would not decrease, which worsened environment and climate in Japan terribly and the public might think wrong decision of 'phase out' in 2012 and again request nuclear power. This nuclear power should be based on 'most advanced safety in the world', whose principle should be discussed and related R and D should be conducted beforehand. Such reactor would be developed to prevent core meltdown or assure containment integrity with 100% passive phenomena without any external power or human works against any cause's accidents, while spent fuels with not containing significant amount of long-life radioactive materials should be stored within artificial structures so as to reduce radioactivity level equivalent to outer environment. (T. Tanaka)

  2. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  3. The draft on the act in the reorganisation of responsibility in nuclear waste management; Der Gesetzentwurf zur Neuordnung der Verantwortung in der kerntechnischen Entsorgung

    Energy Technology Data Exchange (ETDEWEB)

    Raetzke, Christian [CONLAR Consulting on Nuclear Law and Regulation, Leipzig (Germany)

    2016-12-15

    The German Federal Cabinet passed the draft ''Act for the Reorganisation of Responsibility in Nuclear Waste Management''. The individual elements of the act shape an overall concept. The public sector, also assumes the interim storage of the waste in addition to the previous responsibility for final disposal of radioactive waste. Both tasks will be financed by a new public fund into which the operators pay their provisions. By paying an additional risk premium the operators can also exclude future margin requirements. This new concept is to be welcomed because it would lead to a structurally viable and sustainable solution for the final disposal of nuclear wastes, not withstanding many difficulties and partly uncertainties in detail.

  4. Peer-review study of the draft handbook for human-reliability analysis with emphasis on nuclear-power-plant applications, NUREG/CR-1278

    Energy Technology Data Exchange (ETDEWEB)

    Brune, R. L.; Weinstein, M.; Fitzwater, M. E.

    1983-01-01

    This report describes a peer review of the draft Handbook for Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications, NUREG/CR-1278. The purpose of the study was to determine to what extent peers agree with the human behavior models and estimates of human error probabilities (HEPs) contained in the Handbook. Twenty-nine human factors experts participated in the study. Twenty of the participants were Americans; nine were from other countries. The peers performed human reliability analyses of a variety of human performance scenarios describing operator activities in nuclear power plant settings. They also answered questionnaires pertaining to the contents and application of the Handbook. An analysis of peer solutions to the human reliability analysis problems and peer responses to the questionnaire was performed. Recommendations regarding the format and contents of the Handbook were developed from the study findings.

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

    International Nuclear Information System (INIS)

    Berkvens, T.; Coeck, M.

    2014-01-01

    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)

  6. 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.

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

    International Nuclear Information System (INIS)

    Landis, J.W.; Jacobs, S.B.

    1984-01-01

    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)

  8. Seismic qualification of equipment in operating nuclear power plants. Unresolved safety issue A-46, draft report for comment

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1985-08-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants should be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46 by the Nuclear Regulatory Commission staff and its contractors, Idaho National Engineering Laboratory, Southwest Research Institute, Brookhaven National Laboratory, and Lawrence Livermore National Laboratory. In addition, the collection and review of seismic experience data by the Seismic Qualification Utility Group and the review and recommendations of a group of seismic consultants, the Senior Seismic Review Advisory Panel, are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experience data base

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

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A.

    2012-11-01

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

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

    International Nuclear Information System (INIS)

    1984-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    1984-03-12

    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.

  12. 30-th anniversary of nuclear power engineering in the USSR. Safety problems of nuclear engineering

    International Nuclear Information System (INIS)

    Kulov, E.V.; Sidorenko, V.A.; Kovalevich, O.M.

    1984-01-01

    The problems of safety and protection of personnel, population and environments from the NPP radiation effect in the Soviet Union in cases of possible accidents and in the course of normal operation are discussed. The problem of safety assurance includes scientific technological and organizational aspects. The necessity of accounting the ''national factor'' in the form of a possible NPP location, existing legislation experience gained, etc. is noted. The main trends in ensuring safety are a high quality of equipment manufacturing and assembly, quality control of equipment at all stages of operation, development and realization of efficient protective measures and devices, assurance of safety precautions at all stages of designing equipment production, NPP operation and maintenance, functioning of the system of state control of NPP safety assurance. The skill and training of personnel are necessary prerequisite for ensuring safety of nuclear power plants

  13. The future of nuclear energy. Safety and nuclear power plants. Contribution of engineering companies

    International Nuclear Information System (INIS)

    Garcia Rodriguez, A.

    1995-01-01

    Risk, its consideration and its acceptance or rejection, are parameters which to a large extent are independent and sometimes difficult to interrelate. Nuclear energy, unlike motoring or civil aviation, has not gained sufficient public acceptance, this despite the fact that the risk to population is by far the least of the three. It is therefore necessary to continue with its improvement is an attempt to create the same confidence in the nuclear industry, as society has placed in civil aviation. Improvement in future nuclear power plants must be a combination of improved safety and a reduction in capital investment. This objective can only be reached through standardization and international cooperation. Engineering has a very important part to play in the standardization process. An increase in engineering input during the design, construction, operation and maintenance phases of future nuclear power plants, and the application of increasingly sophisticated analysis and management tools are anticipated. Nevertheless, the financial impact on the cost of each plant will fall as a result of increased input spread throughout the range of standard plants. Our current Advanced Reactor Power Plant Programme enables the Spanish industry to participate actively in the creation of future standards nuclear power plants. Having a presence in selected engineering activities, which guarantees access to the state of the art in this area, is one of our priorities, since it will facilitate the presence of the rest of the industry in future projects. If the objectives described above are to be reached, the present involvement of the spanish industry in this programme must be maintained in the medium and long term. (Author)

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

    International Nuclear Information System (INIS)

    Ferronsky, V.I.

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1989-01-01

    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.) [pt

  16. Lecture notes for introduction to nuclear engineering 101

    International Nuclear Information System (INIS)

    Fullwood, R.; Cadwell, J.

    1992-03-01

    The lecture notes for introductory nuclear engineering are provided for Department of Energy personnel that are recent graduates, transfers from non-nuclear industries, and people with minimum engineering training. The material assumes a knowledge of algebra and elementary calculus. These notes support and supplement a three-hour lecture. The reader is led into the subject from the familiar macroscopic world to the microscopic world of atoms and the parts of atoms called elementary particles. Only a passing reference is made to the very extensive world of quarks and tansitory particles to concentrate on those associated with radioactivity and fission. The Einsteinian truth of mass-energy equivalence provides an understanding of the forces binding a nucleus with a resulting mass defect that results in fusion at one end of the mass spectrum and fission at the other. Exercises are provided in calculating the energy released in isotopic transformation, reading and understanding the chart of the nuclides. The periodic table is reviewed to appreciate that the noble elements are produced by quantum mechanical shell closings. Radioactive decay is calculated as well as nuclear penetration and shielding. The geometric attenuation of radiation is studied for personal protection; the use of shielding materials for radiation protection is presented along with the buildup factor that renders the shielding less effective than might be supposed. The process of fission is presented along with the fission products and energies produced by fission. The requirements for producing a sustained chain reactor are discussed. The lecture ends with discussions of how radiation and dose is measured and how dose is converted to measures of the damage of radiation to our bodies

  17. Educational laboratory experiments on chemistry in a nuclear engineering school

    International Nuclear Information System (INIS)

    Akatsu, E.

    1982-01-01

    An educational laboratory experiment on radiochemistry was investigated by students in the general course of the Nuclear Engineering School of Japan Atomic Energy Research Institute. Most of them are not chemical engineers, but electrical and mechanical engineers. Therefore, the educational experiment was designed for them by introducing a ''word experiment'' in the initial stage and by reducing the chemical procedure as far as possible. It began with calculations on a simple solvent extraction process-the ''word experiment''--followed by the chemical separation of 144 Pr from 144 Ce with tri-n-butyl phosphate in a nitric acid system and then measurement of the radioactive decay and growth of the separated 144 Pr and 144 Ce, respectively. The chemical procedure was explained by the phenomenon but not by the mechanism of chelation. Most students thought the experiment was an exercise in solvent extraction or radiochemical separation rather than a radioactive equilibrium experiment. However, a pure chemist considered it as a sort of physical experiment, where the chemical procedure was used only for preparation of measuring samples. Another experiment, where 137 Cs was measured after isolation with ammonium phosphomolybdate, was also investigated. The experiment eliminated the need for students who were not chemists to know how to use radioactive tracers. These students appreciated the realization that they could understand the radioactivity in the environmental samples in a chemical frame of reference even though they were not chemists

  18. Labor supply of engineers and scientists for nuclear electric utilities, 1987-1992

    International Nuclear Information System (INIS)

    Blair, L.M.

    1988-01-01

    An assessment of the adequacy of the supply of health physicists, nuclear engineers, and other engineers for the nuclear electric utility industry is based on job openings for scientists and engineers in broader nuclear-power-related fields, which include engineering and design, manufacturing, fabrication, supporting services, and government. In assessing the likely adequacy of labor supplies for commercial nuclear power job openings over the next 5 yr, consideration has been given to competing sources of labor demands, including nuclear energy research and development activities, nuclear defense, and the total US economy, and to the likely supply of new graduates. In particular, over the last 3 yr, the number of degrees awarded and enrollments in nuclear engineering programs have declined 12 and 14%, respectively, and in health physics programs, 5 and 14%, respectively. For health physics and nuclear engineers, tight labor market conditions (i.e. labor supplies and demand balanced at relatively high salaries) are expected over the next 5 yr because of declining enrollments and slowly growing employment levels plus job replacement needs. The commercial nuclear power field is expected to face tight labor markets for electrical and materials engineers because of strong competing demands in the economy. Other engineering occupations are likely to have adequate supplies for the nuclear power field but at salaries that continue to be relatively higher than salaries for other professional occupations

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

    International Nuclear Information System (INIS)

    Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

    2004-01-01

    In a joint effort with the Argonne National Laboratory - West (ANL-W), the Idaho National Engineering and Environmental Laboratory (INEEL) has assumed the lead role for nuclear energy reactor research for the United States Government. In 2005, these two laboratories will be combined into one entity, the Idaho National Laboratory (INL). There are two objectives for the INL: (1) to act as the lead systems integrator for the Department of Energy's Office of Nuclear Energy Science and Technology and, (2) to establish a Center for Advanced Energy Studies. Focusing on the Center for Advanced Energy Studies, this paper presents a Human Resources Pipeline Model outlining a nuclear educational pathway that leads to university and industry research partnerships. The pathway progresses from education to employment and into retirement. Key to the model is research and mentoring and their impact upon each stage. The Center's success will be the result of effective and advanced communications, faculty/student involvement, industry support, inclusive broadbased involvement, effective long-term partnering, and increased federal and state support. (author)

  20. Emergency Cooling of Nuclear Power Plant Reactors With Heat Removal By a Forced-Draft Cooling Tower

    Energy Technology Data Exchange (ETDEWEB)

    Murav’ev, V. P., E-mail: murval1@mail.ru

    2016-07-15

    The feasibility of heat removal during emergency cooling of a reactor by a forced-draft cooling tower with accumulation of the peak heat release in a volume of precooled water is evaluated. The advantages of a cooling tower over a spray cooling pond are demonstrated: it requires less space, consumes less material, employs shorter lines in the heat removal system, and provides considerably better protection of the environment from wetting by entrained moisture.

  1. Continuing Professional Development (CPD) of the nuclear and radiation professional engineers

    International Nuclear Information System (INIS)

    Sasaki, Satoru

    2016-01-01

    Professional Engineer is the national qualification stipulated by the Professional Engineer Act. A Professional Engineer in this Act means a person who conducts business on matters of planning, research, design, analysis, testing, evaluation or guidance thereof, which requires application of extensive scientific and technical expertise, and has three obligation and two responsibility related to engineer ethic. A technical discipline for nuclear and radiation technology in 2004, was established for the purpose of upgrading the skills of engineers in nuclear technology fields, utilizing their ability in nuclear safety regulation fields, and further strengthening safety management system in each entity. The activity of the nuclear and radiation professional engineers for the past 10 years was evaluated. For the next ten years, awareness of the role of the professional engineer to talk with general public is needed, and it is important to continue professional development. (author)

  2. 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.

  3. Interactive virtual laboratory for distance education in nuclear engineering

    International Nuclear Information System (INIS)

    Jain, P.; Stubbins, J.; Uddin, R.

    2006-01-01

    A real time, distance lab module is being developed and implemented in the Dept. of Nuclear, Plasma and Radiological Engineering at the Univ. of Illinois at Urbana-Champaign. This internet based system allows remote personnel to watch the experiments, acquire data, and interact with on-site personnel. The e-lab broadcasts not only the live scenes of laboratory and experiments, but also the real time data and plots being measured and displayed in graphical and other formats. Moreover, use of LabVIEW's remote front panel feature allows communications between the local lab and remote client so that, if permitted, remote client can control part or all of the experiment in real-time. (authors)

  4. Application of carbon fiber reinforced carbon composite to nuclear engineering

    International Nuclear Information System (INIS)

    Ishihara, Masahiro

    2003-01-01

    Carbon fiber reinforced carbon matrix composite (C/C composite) is thought to be one of promising structural materials with high temperature resistivity in the nuclear engineering field. In the high temperature gas-cooled reactors with gas outlet temperature maximum around 1000degC, high performance core internal structures, such as control rod sheath, core restraint mechanism, will be expected to achieve by the C/C composite application. Moreover, in the fusion reactors, plasma facing structures having high temperature with high neutron irradiation and particle collision will be expected to achieve by the C/C composite application. In this paper, current research and development studies of the C/C composite application on both reactors are reviewed and vista of the future on the C/C composite application is mentioned. (author)

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

    International Nuclear Information System (INIS)

    Baptista Filho, Benedito Dias

    2002-01-01

    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)

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

    International Nuclear Information System (INIS)

    Johnson, L.H.; Tait, J.C.; Shoesmith, D.W.; Crosthwaite, J.L.; Gray, M.N.

    1994-01-01

    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

  7. Pipe drafting and design

    CERN Document Server

    Parisher, Roy A; Parisher

    2000-01-01

    Pipe designers and drafters provide thousands of piping drawings used in the layout of industrial and other facilities. The layouts must comply with safety codes, government standards, client specifications, budget, and start-up date. Pipe Drafting and Design, Second Edition provides step-by-step instructions to walk pipe designers and drafters and students in Engineering Design Graphics and Engineering Technology through the creation of piping arrangement and isometric drawings using symbols for fittings, flanges, valves, and mechanical equipment. The book is appropriate primarily for pipe

  8. Dictionary of nuclear engineering. In four languages: English, German, French, Russian

    Energy Technology Data Exchange (ETDEWEB)

    Sube, R [comp.

    1985-01-01

    This dictionary covers nuclear engineering defined in its general sense as applied nuclear physics: industrial and other applications of nuclear power, isotopes and ionizing radiation, nuclear materials, nuclear facilities and nuclear weapons together with their scientific and technological fundamentals. During the compilation of terms, great attention was only given to generally valid basic expressions and to special terms where these occurred in all four languages. A great number of textbooks and monographs, as well as specialist journals covering many years, have been evaluated. Detailed attention has been paid to standards. Of importance in nuclear engineering are the international standards of the International Atomic Energy Organization (including the terminology employed by the International Nuclear Information System INIS), the International Organization of Standardization, the Council for Mutual Economic Assistance, the World Energy Conference, the International Electrical Engineering Commission, and also a great many national standards which, unfortunately, frequently deviate from one another as regards definition and, in particular, designation.

  9. Parallel multiphysics algorithms and software for computational nuclear engineering

    International Nuclear Information System (INIS)

    Gaston, D; Hansen, G; Kadioglu, S; Knoll, D A; Newman, C; Park, H; Permann, C; Taitano, W

    2009-01-01

    There is a growing trend in nuclear reactor simulation to consider multiphysics problems. This can be seen in reactor analysis where analysts are interested in coupled flow, heat transfer and neutronics, and in fuel performance simulation where analysts are interested in thermomechanics with contact coupled to species transport and chemistry. These more ambitious simulations usually motivate some level of parallel computing. Many of the coupling efforts to date utilize simple code coupling or first-order operator splitting, often referred to as loose coupling. While these approaches can produce answers, they usually leave questions of accuracy and stability unanswered. Additionally, the different physics often reside on separate grids which are coupled via simple interpolation, again leaving open questions of stability and accuracy. Utilizing state of the art mathematics and software development techniques we are deploying next generation tools for nuclear engineering applications. The Jacobian-free Newton-Krylov (JFNK) method combined with physics-based preconditioning provide the underlying mathematical structure for our tools. JFNK is understood to be a modern multiphysics algorithm, but we are also utilizing its unique properties as a scale bridging algorithm. To facilitate rapid development of multiphysics applications we have developed the Multiphysics Object-Oriented Simulation Environment (MOOSE). Examples from two MOOSE-based applications: PRONGHORN, our multiphysics gas cooled reactor simulation tool and BISON, our multiphysics, multiscale fuel performance simulation tool will be presented.

  10. Nuclear engineering as a historical individual and a paradigma

    International Nuclear Information System (INIS)

    Radkau, J.

    1992-01-01

    The author starts his study with considerations on the technology genesis research to decipher the individual 'genes' and their combinations in order to see together with the origin mechanism also the activity mechanisms and thus establish a connection between technology genesis and technology consequences. He then outlines several prospects of nuclear engineering: economical scenarios: push and pull; 'science-based industries', and omnipotence of experience; 'development' - the pseudorevolutionism of technology history; consensus and community of nuclear economy; the power of things, state technology and national technology - styles. The last paragraph deals with the uniqueness of technology history and describes its systematic and practical aspects. Several outlined trends come to an image of technological development under which the entire process is something unique, and innovative models ar to be assigned to certain phases of a singular process. From predetermination of a technology by its genetic stage it follows that 'technology consequence estimation' increasingly moves towards technology genesis, and that for a good reason. Experience, however, does not give cause to particularly great optimism with regard to the shapeability of future technology development by means of a reasonable social discourse. (orig.) [de

  11. Comprehensive nuclear science and engineering for the future

    Energy Technology Data Exchange (ETDEWEB)

    Fujiie, Y [Japan Atomic Energy Commission (Japan)

    2001-07-01

    Japan's nuclear policy and long-term nuclear program are illuminated. It is noted, that Japan's basic stance towards the peaceful use of nuclear science and engineering must be established. Japan, one of the advanced nations in the field of science and engineering, must take the initiative in cooperating with Kazakhstan, Russia, the US, Europe, Asia, and other regions/countries concerned for common national interests. In particular. the cooperative activities with Kazakhstan are as follows: As part of a safety study regarding severe accidents in light-water reactors, the 'COTELS project' using a molten material behavior test device, LAVA, at the National Nuclear Center (NNC) in Kazakhstan is now under way. This test is being conducted to clarify the interaction between debris and water or concrete on the assumption that a pressure vessel is destroyed after the meltdown of a reactor core and molten materials (debris) falls to the bottom of a containment vessel. This COTELS project, one of the earliest joint research projects being conducted by Japan and Kazakhstan, began in 1995 and was completed in 1999. A project for testing debris cooling capability in a pressure vessel has also started. Also, in the field of fast reactor development, the 'EAGLE project' began progress in 1998 to utilize experimental facilities including an impulse graphite reactor (IGR) at the NNC. A new experimental facility recently went into operation for this project. The objective of this joint project is to provide a dear perspective on the safety characteristics of a fast reactor core under severe accident conditions. The inherent safety features of core materials expelled from the core without recriticality in the course of core melting will be investigated in a series of experiments. Safety issues are major concerns as well as economic efficiency, effective use of natural resources, nuclear non-proliferation, and the reduction of environmental burdens for the development of fast

  12. Comprehensive nuclear science and engineering for the future

    International Nuclear Information System (INIS)

    Fujiie, Y.

    2001-01-01

    Japan's nuclear policy and long-term nuclear program are illuminated. It is noted, that Japan's basic stance towards the peaceful use of nuclear science and engineering must be established. Japan, one of the advanced nations in the field of science and engineering, must take the initiative in cooperating with Kazakhstan, Russia, the US, Europe, Asia, and other regions/countries concerned for common national interests. In particular. the cooperative activities with Kazakhstan are as follows: As part of a safety study regarding severe accidents in light-water reactors, the 'COTELS project' using a molten material behavior test device, LAVA, at the National Nuclear Center (NNC) in Kazakhstan is now under way. This test is being conducted to clarify the interaction between debris and water or concrete on the assumption that a pressure vessel is destroyed after the meltdown of a reactor core and molten materials (debris) falls to the bottom of a containment vessel. This COTELS project, one of the earliest joint research projects being conducted by Japan and Kazakhstan, began in 1995 and was completed in 1999. A project for testing debris cooling capability in a pressure vessel has also started. Also, in the field of fast reactor development, the 'EAGLE project' began progress in 1998 to utilize experimental facilities including an impulse graphite reactor (IGR) at the NNC. A new experimental facility recently went into operation for this project. The objective of this joint project is to provide a dear perspective on the safety characteristics of a fast reactor core under severe accident conditions. The inherent safety features of core materials expelled from the core without recriticality in the course of core melting will be investigated in a series of experiments. Safety issues are major concerns as well as economic efficiency, effective use of natural resources, nuclear non-proliferation, and the reduction of environmental burdens for the development of fast

  13. Draft revision of human factors guideline HF-010

    International Nuclear Information System (INIS)

    Lee, Hyun Chul; Lee, Yong Hee; Oh, In Seok; Lee, Jung Woon; Cha, Woo Chang; Lee, Dhong Ha

    2003-05-01

    The Application of Human Factors to the design of Man-Machine Interfaces System(MMIS) in the nuclear power plant is essential to the safety and productivity of the nuclear power plants, human factors standards and guidelines as well as human factors analysis methods and experiments are weightily used to the design application. A Korean engineering company has developed a human factors engineering guideline, so-call HF-010, and has used it for human factors design, however the revision of HF-010 is necessary owing to lack of the contents related to the advanced MMI(Man-Machine Interfaces). As the results of the reviews of HF-010, it is found out that the revision of Section 9. Computer Displays of HF-010 is urgent, thus the revision was drafted on the basis of integrated human factors design guidelines for VDT, human factors design guidelines for PMAS SPADES display, human factors design guidelines for PMAS alarm display, and human factors design guidelines for electronic displays developed by the surveillance and operation support project of KOICS. The draft revision of HF-010 Section 9 proposed in this report can be utilized for the human factors design of the advanced MMI, and the high practical usability of the draft can be kept up through the continuous revision according to the advancement of digital technology

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

    International Nuclear Information System (INIS)

    Phanse, N.R.

    2001-01-01

    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

  15. Maintenance of civil engineering structures important to safety of Nuclear Power Plants

    International Nuclear Information System (INIS)

    2002-03-01

    Civil engineering structures in nuclear installations form an important feature having implications to safety performance of these installations. This safety standard is written to specify the objectives and minimum requirements for the design of civil engineering buildings/structures that are to be fulfilled to provide adequate assurance for safety of nuclear installations in India

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

    International Nuclear Information System (INIS)

    Dragusin, O.; Burghelea, A.

    2001-01-01

    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)

  17. Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320): Draft

    International Nuclear Information System (INIS)

    1986-12-01

    In accordance with the National Environmental Policy Act and the Commission's implementing regulations and its April 27, 1981 Statement of Policy, the Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2 NUREG-0683 (PEIS) is being supplemented. This draft supplement updates the environmental evaluation of accident-generated water disposal alternatives published in the PEIS, utilizing more complete and current information. Also, the draft supplement includes a specific environmental evaluation of the licensee's recently submitted proposal for water disposition

  18. KINGS Model: Achieving Sustainable Change in Nuclear Engineering Education for the Post-COP21 Era

    International Nuclear Information System (INIS)

    Oh, S.-K.

    2016-01-01

    Full text: In spite of the world nuclear community’s systematic and multilateral efforts during the COP21, most of the conference participants were reluctant to acknowledge the value of nuclear as a low-carbon energy source. In fact, the on-going aftermath of the Fukushima nuclear disaster has been overwhelming despite the evidence that there was neither any critical technical flaw nor fatal radiation casualties. This shows that advanced nuclear knowledge failed to resonate with public perception on nuclear energy. In this respect, it is now time to focus on achieving sustainable change in nuclear engineering education for the future. The KEPCO International Nuclear Graduate School (KINGS) was established to nurture leadership-level nuclear power professionals in the global standard. It affiliates with Korean nuclear industry to achieve three major goals that are also a universal prerequisite for higher education of engineering in the 21st century as follows: “a balance between education and training,” “harmony between engineering and managerial skills,” and “the application of systems engineering to nuclear power projects.” KINGS curriculum requires transdisciplinary coordination among engineering disciplines, engineering specialties, and socioeconomic methods. (author

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

    International Nuclear Information System (INIS)

    Bode, P.

    2009-01-01

    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)

  20. Engineering management at feasibility study stage of nuclear power plant under EPC mode

    International Nuclear Information System (INIS)

    Wang Zhiqiang

    2015-01-01

    After the investment reform by the State Council in 2004, NDRC carries out approval system for enterprises to invest in nuclear power plants. Feasibility study stage is a critical stage on the mainline of nuclear power project approval, which intersects with the license application, and engineering design. The owners of nuclear power plants are required stringently in engineering management. From the owners' management point of view under EPC mode, this paper sorts the preliminary project process for nuclear power plants, focusing on the management in the feasibility study stage. License application and engineering design management in the feasibility study stage are also discussed. (author)