WorldWideScience

Sample records for select nuclear concepts

  1. A systems evaluation model for selecting spent nuclear fuel storage concepts

    International Nuclear Information System (INIS)

    Postula, F.D.; Finch, W.C.; Morissette, R.P.

    1982-01-01

    This paper describes a system evaluation approach used to identify and evaluate monitored, retrievable fuel storage concepts that fulfill ten key criteria for meeting the functional requirements and system objectives of the National Nuclear Waste Management Program. The selection criteria include health and safety, schedules, costs, socio-economic factors and environmental factors. The methodology used to establish the selection criteria, develop a weight of importance for each criterion and assess the relative merit of each storage system is discussed. The impact of cost relative to technical criteria is examined along with experience in obtaining relative merit data and its application in the model. Topics considered include spent fuel storage requirements, functional requirements, preliminary screening, and Monitored Retrievable Storage (MRS) system evaluation. It is concluded that the proposed system evaluation model is universally applicable when many concepts in various stages of design and cost development need to be evaluated

  2. NATO's new strategic concept and the future of nuclear disarmament in Europe

    International Nuclear Information System (INIS)

    Dembinski, Matthias; Mueller, Harald

    2010-01-01

    The study on NATO's new strategic concept and the future of nuclear disarmament in Europe covers the following topics: From the Prague speech to the strategic concept - the significance and role of the substrategic nuclear weapons in Europe: the substrategic nuclear weapons (SSNW) in the USA: relict of the Cold war or clamps of the transatlantic security? The future of the SSNW from the Prague speech to the strategic concept. The positions of selected NATO members and Russia. Conclusions and recommendations: From the significance of the US nuclear weapons in Europe. Arms control policy options.

  3. Nuclear site selection studies

    International Nuclear Information System (INIS)

    Gharib, A.; Zohoorian Izadpanah, A.A.; Iranmanesh, H.

    2000-01-01

    It is of special importance, especially from the nuclear safety viewpoint, to select suitable sites for different nuclear structures with the considered future activities. Site selection sometimes involves high costs not necessarily for merely selecting of site but for some preliminary measures to be taken so as the site may have the necessary characteristics. The more suitable the natural characteristics of the site for the considered project, the more successful and efficient the project, the lower the project costs and the longer the project operation period. If so, the project will cause the growth of public culture and sustainable socioeconomic development. This paper is the result of the conclusion of numerous massive reports of this activity in the preliminary phase based on theories, practices and the related safety principles on this ground as well as the application of data and information of the past and a glance to the future. The conception of need for a site for medium structures and nuclear research projects and how to perform this process are presented step by step here with a scientific approach to its selection during the investigations. In this study, it is practically described how the site is selected, by determining and defining the characteristics of research and nuclear projects with medium structures and also its fitting to the optimum site. The discovered sites typically involve the best advantages in technical and economic aspects and no particular contrast with the concerned structures

  4. Considerations in managing the assessment of the Canadian nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Gillespie, P.A.; Whitaker, S.H.

    1992-01-01

    This paper reports that in developing a concept for disposal of Canada's nuclear fuel waste, AECL has faced challenges because the acceptability of the concept must be established before a site is selected, no agency has been made responsible for implementing the concept if it is selected, and many stakeholders in the review must be satisfied if the concept is to be accepted. The challenges have thus far been met by a program that is well-integrated technically and administratively. However, interactions with stakeholders reviewing the concept present a problem in communication. The authors believe the nature of the nuclear fuel waste disposal issue calls for a cooperative rather than an adversarial approach to problem solving to efficiently deal with the requirements of all the stakeholders

  5. Concept of risk: risk assessment and nuclear safety

    International Nuclear Information System (INIS)

    Thompson, P.B.

    1980-01-01

    The dissertation is a critical examination of risk assessment and its role in public policy. Nuclear power safety safety issues are selected as the primary source of illustrations and examples. The dissertation examines how risk assessment studies develop a concept of risk which becomes decisive for policy choices. Risk-assessment techniques are interpreted as instruments which secure an evaluation of risk which, in turn, figures prominently in technical reports on nuclear power. The philosophical critique is mounted on two levels. First, an epistemological critique surveys distinctions between the technical concept of risk and more familiar senses of risk. The critique shows that utilization of risk assessment re-structures the concept of risk. The technical concept is contrasted to the function of risk within a decision-maker's conceptual agenda and hierarchy of values. Second, an ethical critique exposes the value commitments of risk assessment recommendations. Although some of these values might be defended for policy decisions, the technical character of risk assessment obfuscates normative issues. Risk assessment is shown to be a form of factual enquiry which, nonetheless, represents a commitment to a specific selection of ethical and social values. Risk assessment should not be interpreted as a primary guide to decision unless the specific values incorporated into its concept of risk are stated explicitly and justified philosophically. Such a statement would allow value questions which have been sublimated by the factual tone of the analytic techniques to be debated on clear, social and ethical grounds

  6. Law on the peaceful uses of nuclear energy: key concepts

    International Nuclear Information System (INIS)

    Pompignan, D. de

    2005-01-01

    The key concepts which ought to be included in legislation governing the peaceful uses of nuclear energy can be divided into two categories depending on whether they derive from the fundamental principles of nuclear law or reflect categories of general law. Their inclusion results in compliance with a shared obligation when they derive from a binding international instrument. It also permits the transposition into law of broader nuclear concepts and principles, and the more specific characteristics of a general nuclear law, which is to lay down priorities. When the resulting classification is tested in reality, we can see that it is difficult to measure the effectiveness of the two concept categories inasmuch as this depends not only on quantifiable and controllable legal elements but also on non-legal behavioural factors, an obvious example of which is safety culture. Once the difficulties of defining a legal framework for nuclear activities and selecting the key concepts to guide them are known, the inclusion of a concept in a general nuclear law is determined by national legal and ethical considerations. Thus, a general nuclear law should indicate the way in which the legal principles which reflect various prevailing ethical imperatives with regard to the environment, participation, and public interest, are applicable to the development of the peaceful uses of nuclear energy, having regard to the national specificities of each country and the particular nature of these activities. This means that there is a need to find original legal solutions reconciling the constraints of a specific law with the requirements of the ordinary law, i.e. the key concepts deriving from the principles of nuclear law. Given the possible reluctance of lawmakers to commit themselves for the future by formulating detailed provisions valid over the long term, it has been suggested that a code of good practice for the nuclear industry should be introduced which would go beyond the

  7. Nuclear energy. An introduction to the concepts, systems, and applications of nuclear processes. 3. ed.

    International Nuclear Information System (INIS)

    Murray, R.L.

    1988-01-01

    An overview of nuclear energy and its uses is given, aimed at nuclear engineers, plant designers and radiation physicists. The three parts deal with the basic concepts, nuclear systems (including particle accelerators, radiation detectors, breeder reactors and fusion reactors) and nuclear energy and man. This latter section includes chapters on the history of nuclear energy, effects of radiation, isotopes, reactor safety, nuclear propulsion, radiation protection, radioactive waste disposal, laws and regulations economics and nuclear explosions. The final chapter looks to the future of nuclear energy. Each of the 27 chapters has a brief summary and exercises at the end. The appendices give selected references, conversion factors and atomic and nuclear data. (U.K.)

  8. Benchmarking of nuclear reactors selected in the frame of GIF project

    International Nuclear Information System (INIS)

    Azpitarte, O; Villanueva, A; Ramos, R; Ramilo, L; Alvarez, M; Yorio, D; Herrero, V

    2012-01-01

    In this article a comparative assessment of the six reactor concepts selected in the frame of the Generation IV International Forum (GIF) project is presented. The assessment was carried out in the areas of Viability of the concept, Design and nuclear safety, Economics, Sustainability, Proliferation resistance, Nuclear fuel, Reprocessing, Materials and Balance of Plant, by means of qualification of chosen performance indicators (author)

  9. New reactor concepts for new generation of nuclear power in the USA: An overview

    International Nuclear Information System (INIS)

    Vujic, J.; Greenspan, E.; Milosevic, M. . E-mail addresses of corresponding authors: vujic@nuc.berkeley.edu , mmilos@vin.bg.ac.yu; Vujic, J.; Milosevic, M.)

    2005-01-01

    With the growing demands for more reliable energy sources, there is an international interest in the development of new nuclear energy systems to be deployed between 2010 and 2030, that will improve safety and reliability, decrease proliferation risks, improve radioactive waste management and lower cost of nuclear energy production. Six nuclear energy systems were selected as candidates for this Generation IV initiative. In this paper we will explore each of these concepts, as well as several of more advanced concepts. (author)

  10. Reconsidering relations between nuclear energy and security concepts

    International Nuclear Information System (INIS)

    Irie, Kazutomo

    2004-01-01

    Relations between nuclear energy and security concepts can be clarified through investigation into the multivocal nature of security concepts. While military uses of nuclear energy significantly influence national security, peaceful uses of nuclear energy contribute energy security, which is an expanded concept of national security. Military and peaceful uses of nuclear energy have reciprocal actions, thus influencing national security and energy security, respectively. Nuclear security, which means security of nuclear systems themselves, recently attracts the attention of the international society. Nuclear security directly influences national security issues. On the other hand, along with nuclear safety, nuclear security becomes a prerequisite for energy security through peaceful uses of nuclear energy. In investigating into relations between nuclear energy and security concepts, the difficulty of translating the English word of 'nuclear security' into Japanese as well as other languages is found. (author)

  11. The nuclear thermal electric rocket: a proposed innovative propulsion concept for manned interplanetary missions

    Science.gov (United States)

    Dujarric, C.; Santovincenzo, A.; Summerer, L.

    2013-03-01

    Conventional propulsion technology (chemical and electric) currently limits the possibilities for human space exploration to the neighborhood of the Earth. If farther destinations (such as Mars) are to be reached with humans on board, a more capable interplanetary transfer engine featuring high thrust, high specific impulse is required. The source of energy which could in principle best meet these engine requirements is nuclear thermal. However, the nuclear thermal rocket technology is not yet ready for flight application. The development of new materials which is necessary for the nuclear core will require further testing on ground of full-scale nuclear rocket engines. Such testing is a powerful inhibitor to the nuclear rocket development, as the risks of nuclear contamination of the environment cannot be entirely avoided with current concepts. Alongside already further matured activities in the field of space nuclear power sources for generating on-board power, a low level investigation on nuclear propulsion has been running since long within ESA, and innovative concepts have already been proposed at an IAF conference in 1999 [1, 2]. Following a slow maturation process, a new concept was defined which was submitted to a concurrent design exercise in ESTEC in 2007. Great care was taken in the selection of the design parameters to ensure that this quite innovative concept would in all respects likely be feasible with margins. However, a thorough feasibility demonstration will require a more detailed design including the selection of appropriate materials and the verification that these can withstand the expected mechanical, thermal, and chemical environment. So far, the predefinition work made clear that, based on conservative technology assumptions, a specific impulse of 920 s could be obtained with a thrust of 110 kN. Despite the heavy engine dry mass, a preliminary mission analysis using conservative assumptions showed that the concept was reducing the required

  12. Categorization and selection of regulatory approaches for nuclear power plants

    International Nuclear Information System (INIS)

    Sugaya, Junko; Harayama, Yuko

    2009-01-01

    Several new regulatory approaches have been introduced to Japanese nuclear safety regulations, in which a prescriptive and deterministic approach had traditionally predominated. However, the options of regulatory approaches that can possibly be applied to nuclear safety regulations as well as the methodology for selecting the options are not systematically defined. In this study, various regulatory approaches for nuclear power plants are categorized as prescriptive or nonprescriptive, outcome-based or process-based, and deterministic or risk-informed. 18 options of regulatory approaches are conceptually developed and the conditions for selecting the appropriate regulatory approaches are identified. Current issues on nuclear regulations regarding responsibilities, transparency, consensus standards and regulatory inspections are examined from the viewpoints of regulatory approaches to verify usefulness of the categorization and selection concept of regulatory approaches. Finally, some of the challenges at the transitional phase of regulatory approaches are discussed. (author)

  13. Extending the Candu Nuclear Reactor Concept: The Multi-Spectrum Nuclear Reactor

    International Nuclear Information System (INIS)

    Allen, Francis; Bonin, Hugues

    2008-01-01

    The aim of this work is to examine the multi-spectrum nuclear reactor concept as an alternative to fast reactors and accelerator-driven systems for breeding fissile material and reducing the radiotoxicity of spent nuclear fuel. The design characteristics of the CANDU TM nuclear power reactor are shown to provide a basis for a novel approach to this concept. (authors)

  14. Extending the Candu Nuclear Reactor Concept: The Multi-Spectrum Nuclear Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Allen, Francis [Director General Nuclear Safety, 280 Slater St, Ottawa, K1A OK2 (Canada); Bonin, Hugues [Royal Military College of Canada, 11 General Crerar Cres, Kingston, K7K 7B4 (Canada)

    2008-07-01

    The aim of this work is to examine the multi-spectrum nuclear reactor concept as an alternative to fast reactors and accelerator-driven systems for breeding fissile material and reducing the radiotoxicity of spent nuclear fuel. The design characteristics of the CANDU{sup TM} nuclear power reactor are shown to provide a basis for a novel approach to this concept. (authors)

  15. Selection and development of advanced nuclear fuel products

    International Nuclear Information System (INIS)

    Stucker, David L.; Miller, Richard S.; Arnsberger, Peter L.

    2004-01-01

    The highly competitive international marketplace requires a continuing product development commitment, short development cycle times and timely, on-target product development to assure customer satisfaction and continuing business. Westinghouse has maintained its leadership position within the nuclear fuel industry with continuous developments and improvements to fuel assembly materials and design. This paper presents a discussion of the processes used by Westinghouse in the selection and refinement of advanced concepts for deployment in the highly competitive US and international nuclear fuel fabrication marketplace. (author)

  16. Spent nuclear fuel storage - Basic concept

    International Nuclear Information System (INIS)

    Krempel, Ascanio; Santos, Cicero D. Pacifici dos; Sato, Heitor Hitoshi; Magalhaes, Leonardo de

    2009-01-01

    According to the procedures adopted in others countries in the world, the spent nuclear fuel elements burned to produce electrical energy in the Brazilian Nuclear Power Plant of Angra do Reis, Central Nuclear Almirante Alvaro Alberto - CNAAA will be stored for a long time. Such procedure will allow the next generation to decide how they will handle those materials. In the future, the reprocessing of the nuclear fuel assemblies could be a good solution in order to have additional energy resource and also to decrease the volume of discarded materials. This decision will be done in the future according to the new studies and investigations that are being studied around the world. The present proposal to handle the nuclear spent fuel is to storage it for a long period of time, under institutional control. Therefore, the aim of this paper is to introduce a proposal of a basic concept of spent fuel storage, which involves the construction of a new storage building at site, in order to increase the present storage capacity of spent fuel assemblies in CNAAA installation; the concept of the spent fuel transportation casks that will transfer the spent fuel assemblies from the power plants to the Spent Fuel Complementary Storage Building and later on from this building to the Long Term Intermediate Storage of Spent Fuel; the concept of the spent fuel canister and finally the basic concept of the spent fuel long term storage. (author)

  17. Nuclear energy an introduction to the concepts, systems, and applications of nuclear processes

    CERN Document Server

    Murray, Raymond L; Murphy, Arthur T; Rosenthal, Daniel I

    1987-01-01

    Nuclear Energy: An Introduction to the Concepts, Systems, and Applications of Nuclear Processes introduces the reader to the concepts, systems, and applications of nuclear processes. It provides a factual description of basic nuclear phenomena, as well as devices and processes that involve nuclear reactions. The problems and opportunities that are inherent in a nuclear age are also highlighted.Comprised of 27 chapters, this book begins with an overview of fundamental facts and principles, with emphasis on energy and states of matter, atoms and nuclei, and nuclear reactions. Radioactivi

  18. Selection of concepts for monitored retrievable storage of spent nuclear fuel and high-level radioactive wastes

    International Nuclear Information System (INIS)

    1984-04-01

    The monitored retrievable storage (MRS) concepts considered are: metal cask (stationary and transportable); concrete cask (sealed storage cask); concrete cask-in-trench; field drywell; tunnel drywell; open cycle vault; closed cycle vault; and tunnel rack vault. These concepts were compared primarily upon the relative performance of the storage units on seven criteria which together encompass the key considerations for selecting an MRS concept, namely their ability to satisfy the MRS mission requirements. These criteria were: safety and licensing; environmental impacts; socioeconomic impacts; siting requirements; cost; concept maturity; and flexibility. Evaluations of the candidate concepts indicate that all of the concepts could satisfactorily serve in an MRS facility. However, using the above criteria, the two concepts selected for further design studies are the concrete cask (primary concept), better entitled the sealed storage cask, and the field drywell (alternate concept). It was recognized that the transportable metal storage cask may be used to supplement at-reactor storage until such time as the repository or MRS becomes available. Consequently, a hybrid storage facility may be required (e.g., one using concrete casks or field drywells, with the capability of receiving and storing the transportable cask). Both the concrete cask and the field drywell concepts can easily accommodate the transportable cask. Further design efforts will ensure the compatibility of the MRS designs with the transportable cask

  19. Flaws in the Concept of Nuclear Deterrance

    Directory of Open Access Journals (Sweden)

    John Scales Avery

    2012-04-01

    Full Text Available The concept of nuclear deterrence is seriously flawed, and it violates the fundamental ethical principles of all major religions. Besides being morally unacceptable, nuclear weapons are also illegal according to a historic 1996 decision of the International Court of Justice, a ruling that reflects the opinion of the vast majority of the worldʼs peoples. Even a small nuclear war would be an ecological catastrophe, not only killing civilian populations indiscriminately in both belligerent and neutral countries, but also severely damaging global agriculture and making large areas of the earth permanently uninhabitable through radioactive contamination. The danger of accidental nuclear war continues to be very great today, and the danger of nuclear terrorism is increasing. In this perilous situation, it is necessary for the nuclear nations to acknowledge that the concept of deterrence has been a mistake, which is threatening the lives of all human beings as well as threatening devastation of the biosphere. Acknowledging that the policy of nuclear deterrence has been a grave error can reduce risk of nuclear weapons proliferation.

  20. Concepts of IAEA nuclear materials accounting

    International Nuclear Information System (INIS)

    Oakberg, John A.

    2001-01-01

    The paper describes nuclear material accounting from the standpoint of IAEA Safeguards and how this accounting is applied by the Agency. The basic concepts of nuclear material accounting are defined and the way these apply to States with INFCIRC/153-type safeguards agreements is presented. (author)

  1. Purification of radionuclides for nuclear medicine: The multicolumn selectivity inversion generator concept

    International Nuclear Information System (INIS)

    Horwitz, E.P.; Bond, A.H.

    2003-01-01

    A new radionuclide generator system has been developed and demonstrated for the production of 212 Bi from 224 Ra/ 212 Pb and for 90 Y from 90 Sr. The new concept, called a Multicolumn Selectivity Inversion Generator, involves the selective retention of the desired daughter radionuclide from a solution of the parent or parents by a primary separation column followed by stripping the daughter radionuclide from the primary column, and immediately without feed adjustment, passing the daughter through a secondary separation (guard) column that retains the parents while the daughter elutes unrestrained. The new generator system minimises the effects of radiation damage to the support material permitting the reliable production of nuclides of high chemical and radionuclidic purity. (author)

  2. The Los Alamos accelerator-driven transmutation of nuclear waste (ATW) concept development of the ATW target/blanket system

    International Nuclear Information System (INIS)

    Venneri, F.; Williamson, M.A.; Ning, L.

    1997-01-01

    In the past several years, the Los Alamos ADTT program has conducted studies of an innovative technology for solving the nuclear waste problem and building a new generation of safer and non-proliferant nuclear power plants. The ATW concept destroys higher actinides, plutonium and selected fission products in a liquid-fuel subcritical assembly. In this paper special attention is given to the basic design of the ATW Molten Salt concept and the safety perspective. 40 refs., 11 figs

  3. Siting of nuclear facilities. Selections from Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.

    1976-07-01

    The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

  4. Siting of nuclear facilities. Selections from Nuclear Safety

    International Nuclear Information System (INIS)

    Buchanan, J.R.

    1976-07-01

    The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria

  5. Computers in nuclear medicine: introductory concepts

    International Nuclear Information System (INIS)

    Weber, D.A.

    1978-01-01

    Computers play an important role in image and data processing in nuclear medicine. Applications extend from relatively simple mathematical processing of in vitro specimen assays to more sophisticated image reconstruction procedures for emission tomography. The basic concepts and terminology associated with computer applications in image and data processing in nuclear medicine are presented here

  6. Disposing of nuclear waste: an economic analysis of two alternative concepts

    International Nuclear Information System (INIS)

    Dippold, D.G.; Tzemos, S.

    1987-01-01

    WADCOM II is a nuclear waste disposal cost model intended to provide its users with relatively quick, although macro, insight into the economics of hypothetical nuclear waste disposal scenarios. The nuclear waste management system represented by the model, the philosophy underlying the model's design, and the logic of the model itself are described. The model is used to analyze the economics of two nuclear waste disposal concepts, the borehold package concept and the generic package concept. Results indicate the generic package concept leads to the higher costs under all the assumed conditions

  7. A Method to Select Human–System Interfaces for Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Jacques V. Hugo

    2016-02-01

    Full Text Available The new generation of nuclear power plants (NPPs will likely make use of state-of-the-art technologies in many areas of the plant. The analysis, design, and selection of advanced human–system interfaces (HSIs constitute an important part of power plant engineering. Designers need to consider the new capabilities afforded by these technologies in the context of current regulations and new operational concepts, which is why they need a more rigorous method by which to plan the introduction of advanced HSIs in NPP work areas. Much of current human factors research stops at the user interface and fails to provide a definitive process for integration of end user devices with instrumentation and control and operational concepts. The current lack of a clear definition of HSI technology, including the process for integration, makes characterization and implementation of new and advanced HSIs difficult. This paper describes how new design concepts in the nuclear industry can be analyzed and how HSI technologies associated with new industrial processes might be considered. It also describes a basis for an understanding of human as well as technology characteristics that could be incorporated into a prioritization scheme for technology selection and deployment plans.

  8. Nuclear energy. Selective bibliography

    International Nuclear Information System (INIS)

    2011-07-01

    This bibliography gathers articles and books from the French National Library about civil nuclear energy, its related risks, and its perspectives of evolution: general overview (figures, legal framework, actors and markets, policies); what price for nuclear energy (environmental and health risks, financing, non-proliferation policy); future of nuclear energy in energy policies (nuclear energy versus other energies, nuclear phase-out); web sites selection

  9. Materials technologies for advanced nuclear energy concepts

    International Nuclear Information System (INIS)

    DiStefano, J.; Harms, B.

    1983-01-01

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

  10. Concepts for reducing nuclear utility inventory carrying costs

    International Nuclear Information System (INIS)

    Graybill, R.E.; DiCola, F.E.; Solanas, C.H.

    1985-01-01

    Nuclear utilities are under pressure to reduce their operating and maintenance expenses such that the total cost of generating electricity through nuclear power remains an economically attractive option. One area in which expenses may be reduced is total inventory carrying cost. The total inventory carrying cost consists of financing an inventory, managing the inventory, assuring quality, engineering of acceptable parts specifications, and procuring initial and replenishment stock. Concepts and methodology must be developed to reduce the remaining expenses of a utility's total inventory carrying cost. Currently, two concepts exist: pooled inventory management system (PIMS), originally established by General Electric Company and a group of boiling water reactor owners, and Nuclear Parts Associates' (NUPA) shared inventory management program (SIMP). Both concepts share or pool parts and components among utilities. The SIMP program objectives and technical activities are summarized

  11. Concepts for institutional arrangements for the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1979-02-01

    These concepts deal with establishing a framework for the analysis of institutional arrangements, with institutional arrangements under consideration in the working groups on fuel and heavy water availability, enrichment availability, assurances of long-term supply, reprocessing-plutonium handling-recycling, fast breeder reactors, spent fuel management, waste management and disposal, and advanced reactor concepts. The standardization of nuclear practices, joint commercial and development undertakings, nuclear supply assurances, developing a consensus in international nuclear co-operation, and settlements of disputes are treated

  12. Nuclear data uncertainties: I, Basic concepts of probability

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.L.

    1988-12-01

    Some basic concepts of probability theory are presented from a nuclear-data perspective, in order to provide a foundation for thorough understanding of the role of uncertainties in nuclear data research. Topics included in this report are: events, event spaces, calculus of events, randomness, random variables, random-variable distributions, intuitive and axiomatic probability, calculus of probability, conditional probability and independence, probability distributions, binomial and multinomial probability, Poisson and interval probability, normal probability, the relationships existing between these probability laws, and Bayes' theorem. This treatment emphasizes the practical application of basic mathematical concepts to nuclear data research, and it includes numerous simple examples. 34 refs.

  13. Nuclear data uncertainties: I, Basic concepts of probability

    International Nuclear Information System (INIS)

    Smith, D.L.

    1988-12-01

    Some basic concepts of probability theory are presented from a nuclear-data perspective, in order to provide a foundation for thorough understanding of the role of uncertainties in nuclear data research. Topics included in this report are: events, event spaces, calculus of events, randomness, random variables, random-variable distributions, intuitive and axiomatic probability, calculus of probability, conditional probability and independence, probability distributions, binomial and multinomial probability, Poisson and interval probability, normal probability, the relationships existing between these probability laws, and Bayes' theorem. This treatment emphasizes the practical application of basic mathematical concepts to nuclear data research, and it includes numerous simple examples. 34 refs

  14. Considerations on a concept of nuclear security culture and its development

    International Nuclear Information System (INIS)

    Miyamoto, Naoki

    2013-01-01

    In March 2012, domestic regulations regarding physical protection measures of nuclear facilities were amended to strengthen those measures. By these amendments, nuclear operators were requested to stipulate their corporate system to develop nuclear security culture on their physical protection plans, and therefore, attention has been drawn on a concept of nuclear security culture and its development. In the light of these situations, this presentation will consider the concept of nuclear security culture and its development. Firstly, focusing attention on 'culture', a concept of 'corporate culture' which is emphasized in corporate management will be analyzed. Then, with reference to 'safety culture', elements that seems to correspond to the concept of nuclear security culture will be extracted. Secondly, particularizing a 'corporate system to develop nuclear security culture', by reviewing a notion of 'Corporate Social Responsibility (CSR)' which attracts lots of attention recent years in terms of corporate sustainable development, results of examination regarding commitment structure of corporate chief executive and corporate risk management framework, which are considered to be efficient for the development of nuclear security culture, will be reported. (author)

  15. New concept for nuclear force: implications for nuclear structure and hadronic processes

    International Nuclear Information System (INIS)

    Kukulin, V.I.

    2005-01-01

    Full text: A new concept for nuclear force is discussed. The concept is based on idea about production of the intermediate six-quark bag (dibaryon) dressed with meson fields main of which are π-, σ-, p-, and ω-fields. The whole approach has been strongly motivated by our previous detailed analysis of various inner contradictions and inconsistencies in the conventional meson-exchange (i.e. Yukawa like) mechanism of nuclear force. The new force model predicts inevitable strong attractive 3N-force of scalar nature originated from σ-exchange between the dressed dibaryon and third nucleon. This new 3N-force has been demonstrated earlier to result in, at least, a half the total binding energy in lightest nuclei and contribute strongly to all nuclear properties like r. m. s. charge radius, nucleon momentum distribution, new electromagnetic currents and leads, very likely, to new understanding of saturation properties in nuclear matter. In the talk many other implications of the suggested new force model in hadronic and nuclear physics will be discussed

  16. Concept for Underground Disposal of Nuclear Waste

    Science.gov (United States)

    Bowyer, J. M.

    1987-01-01

    Packaged waste placed in empty oil-shale mines. Concept for disposal of nuclear waste economically synergistic with earlier proposal concerning backfilling of oil-shale mines. New disposal concept superior to earlier schemes for disposal in hard-rock and salt mines because less uncertainty about ability of oil-shale mine to contain waste safely for millenium.

  17. A nuclear power reactor concept for Brazil

    International Nuclear Information System (INIS)

    Sefidvash, F.

    1980-01-01

    For the purpose of developing an independent national nuclear technology and effective manner of transferring such a technology, as well as developing a modern reactor, a new nuclear power reactor concept is proposed which is considered as a suitable and viable project for Brazil to support its development and finally construct its prototype as an indigeneous venture. (Author) [pt

  18. Assessment of nuclear reactor concepts for low power space applications

    Science.gov (United States)

    Klein, Andrew C.; Gedeon, Stephen R.; Morey, Dennis C.

    1988-01-01

    The results of a preliminary small reactor concepts feasibility and safety evaluation designed to provide a first order validation of the nuclear feasibility and safety of six small reactor concepts are given. These small reactor concepts have potential space applications for missions in the 1 to 20 kWe power output range. It was concluded that low power concepts are available from the U.S. nuclear industry that have the potential for meeting both the operational and launch safety space mission requirements. However, each design has its uncertainties, and further work is required. The reactor concepts must be mated to a power conversion technology that can offer safe and reliable operation.

  19. A CONCEPT FOR NATIONAL NUCLEAR FORENSIC LIBRARIES

    International Nuclear Information System (INIS)

    Wacker, John F.; Curry, Michael

    2010-01-01

    The interpretation of data from the nuclear forensic analysis of illicit nuclear material of unknown origin requires comparative data from samples of known origin. One way to provide such comparative data is to create a system of national nuclear forensics libraries, in which each participating country stores information about nuclear or other radioactive material that either resides in or was manufactured by that country. Such national libraries could provide an authoritative record of the material located in or produced by a particular country, and thus forms an essential prerequisite for a government to investigate illicit uses of nuclear or other radioactive material within its borders. We describe the concept of the national nuclear forensic library, recommendations for content and structure, and suggested querying methods for utilizing the information for addressing nuclear smuggling.

  20. Selecting concepts for a concept-based curriculum: application of a benchmark approach.

    Science.gov (United States)

    Giddens, Jean Foret; Wright, Mary; Gray, Irene

    2012-09-01

    In response to a transformational movement in nursing education, faculty across the country are considering changes to curricula and approaches to teaching. As a result, an emerging trend in many nursing programs is the adoption of a concept-based curriculum. As part of the curriculum development process, the selection of concepts, competencies, and exemplars on which to build courses and base content is needed. This article presents a benchmark approach used to validate and finalize concept selection among educators developing a concept-based curriculum for a statewide nursing consortium. These findings are intended to inform other nurse educators who are currently involved with or are considering this curriculum approach. Copyright 2012, SLACK Incorporated.

  1. New types of nuclear energy concepts

    International Nuclear Information System (INIS)

    Ledinegg, E.; Heindler, M.

    1978-10-01

    The article summarises the results of a conference on new concepts of nuclear energy, held from 29 - 31 March 1978. Principles of known systems are briefly outlined, mainly from the standpoint of neutron formation by fission, blanket breeding etc, and power production by plasma focussing and thermonuclear fusion. The new concepts include the Migma system and micro-explosions. A section is included on 'hybrid' reactors using a electronuclear source (ENQ) as neutron supply, and 'symbiotic' reactors using ENQ for fuel supply. (G.C.)

  2. Changing concepts of geologic structure and the problem of siting nuclear reactors: examples from Washington State

    International Nuclear Information System (INIS)

    Tabor, R.W.

    1986-01-01

    The conflict between regulation and healthy evolution of geological science has contributed to the difficulties of siting nuclear reactors. On the Columbia Plateau in Washington, but for conservative design of the Hanford reactor facility, the recognition of the little-understood Olympic-Wallowa lineament as a major, possibly still active structural alignment might have jeopardized the acceptability of the site for nuclear reactors. On the Olympic Peninsula, evolving concepts of compressive structures and their possible recent activity and the current recognition of a subducting Juan de Fuca plate and its potential for generating great earthquakes - both concepts little-considered during initial site selection - may delay final acceptance of the Satsop site. Conflicts of this sort are inevitable but can be accommodated if they are anticipated in the reactor-licensing process. More important, society should be increasing its store of geologic knowledge now, during the current recess in nuclear reactor siting

  3. Concept for the Emergency Protection in the Vicinity of Nuclear Power Plants

    International Nuclear Information System (INIS)

    1998-03-01

    In 1991, the Swiss Federal Nuclear Safety Inspectorate (HSK) issued a concept of the regulations for the cloud phase 1 of an nuclear power plant accident in Switzerland valid at that time in co-operation with the Federal Commission for AC Protection (KOMAC) and the Swiss Federal Nuclear Safety Commission (KSA). This concept replaced the version of 1977, which then formed the basis for emergency preparedness in Switzerland. Legal changes, such as the civil protection legislation and the ordinance on the distribution of iodine tablets to the population, as well as experience gained from the emergency exercises necessitated a revision of the existing concept. The present concept is issued by the Federal Commission for AC Protection (KOMAC) and deals with all phases of an accident sequence in a Swiss nuclear power plant focussing on the pre- and cloud phase. It also gives an overview of responsibilities and alert procedures for accidents at foreign nuclear power plants and other nuclear installations, as well as of accidents in connection with transportation of radioactive materials. The concept is designed to help the federal and cantonal authorities in the vicinity of nuclear power plants in charge of emergency protection in preparing their emergency procedure specifications, and in the realisation of the readiness for emergencies. Furthermore, it shall serve the cantons as a guideline for the preparation of emergency specifications for the communities. The concept is based on the assumption that the executive bodies and emergency forces provided for the general civil protection are employed in case of an accident at a nuclear power plant. (authors)

  4. Large amplitude collective nuclear motion and soliton concept

    International Nuclear Information System (INIS)

    Kartavenko, V.G.; Joint Inst. for Nuclear Research, Dubna

    1993-01-01

    An application of a soliton theory methods to some nonlinear problems in low and intermediate energies (E ∼ 10--100MeV/nucleon) nucleus - nucleus collisions are presented. Linear and nonlinear excitations of the nuclear density are investigated in the framework of nuclear hydrodynamics. The problem of dynamical instability and clusterization phenomena in a breakup of excited nuclear systems are considered from the points of view of a soliton concept

  5. A concept of safety indicator system for nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, E.

    1995-12-01

    The fundamental principle in the safety technology of nuclear power is embodied in the strategy of defence in depth. The defence lines of the strategy, completed with a PSA logic model and structure, are considered to provide an appropriate framework for identification and structuring of the operational safety performance areas for nuclear power plants. Once these areas are identified the safety indicators can be defined. Based on this approach a concept of safety indicator system was outlined. About one hundred indicator specifications have been collected, refined and related to the performance areas. The specifications enable the utilities and authorities to check the coverage of their indicators set from the operational safety point of view and select or refine indicators for testing and routine use. Finally various statistical approaches and methods for using indicators in performance evaluation are presented. (orig.) (16 refs., 2 figs., 2 tabs.)

  6. Feasibility of the recent Russian nuclear electric propulsion concept: 2010

    International Nuclear Information System (INIS)

    Zakirov, Vadim; Pavshook, Vladimir

    2011-01-01

    Highlights: → The paper focuses on feasibility of the Russian nuclear electric propulsion (NEP) concept. → The Russian NEP concept is based on the past experience and is, therefore, technically feasible. → The big concern is that the program will be cancelled due to non-technical issues. - Abstract: The paper introduces recent Russian nuclear electric propulsion (NEP) concept for space exploration. The concept advantages are listed along with future missions. The current development status for the two main enabling technologies is presented and the feasibility analysis of the up-to-date experience is performed. The main features of NEP concept are discussed. Revision of these features and available technologies demonstrates that the NEP concept is a logical continuation of the previous efforts by the former Soviet Union. Because no breakthrough technologies are needed for NEP development while the existing technologies only need to be adapted to the megawatt (MW) class NEP the development is considered technically feasible, low risk program likely to succeed unless cancelled by the listed non-technical reasons. Successful NEP space vehicle development is going to bring practical space exploration of solar system to the new level as well as require supplementary payload program, supporting monitoring and communication radar networks. Nuclear safety during future NEP missions can be ensured by adherence to the United Nations guidelines in the same way it was done during the Soviet Topaz Nuclear Power System (NPS) missions.

  7. Feasibility of the recent Russian nuclear electric propulsion concept: 2010

    Energy Technology Data Exchange (ETDEWEB)

    Zakirov, Vadim, E-mail: v.zakirov@mail.tsinghua.edu.c [Room 3121, Yifu Building, School of Aerospace, Tsinghua University, Haidian District, Beijing 100084 (China); Pavshook, Vladimir, E-mail: vap_ki@mail.r [Russian Research Center ' Kurchatov Institute' , Kurchatov Sq. 1, Moscow 123182 (Russian Federation)

    2011-05-15

    Highlights: The paper focuses on feasibility of the Russian nuclear electric propulsion (NEP) concept. The Russian NEP concept is based on the past experience and is, therefore, technically feasible. The big concern is that the program will be cancelled due to non-technical issues. - Abstract: The paper introduces recent Russian nuclear electric propulsion (NEP) concept for space exploration. The concept advantages are listed along with future missions. The current development status for the two main enabling technologies is presented and the feasibility analysis of the up-to-date experience is performed. The main features of NEP concept are discussed. Revision of these features and available technologies demonstrates that the NEP concept is a logical continuation of the previous efforts by the former Soviet Union. Because no breakthrough technologies are needed for NEP development while the existing technologies only need to be adapted to the megawatt (MW) class NEP the development is considered technically feasible, low risk program likely to succeed unless cancelled by the listed non-technical reasons. Successful NEP space vehicle development is going to bring practical space exploration of solar system to the new level as well as require supplementary payload program, supporting monitoring and communication radar networks. Nuclear safety during future NEP missions can be ensured by adherence to the United Nations guidelines in the same way it was done during the Soviet Topaz Nuclear Power System (NPS) missions.

  8. Missing concepts in natural selection theory reconstructions.

    Science.gov (United States)

    Ginnobili, Santiago

    2016-09-01

    The concept of fitness has generated a lot of discussion in philosophy of biology. There is, however, relative agreement about the need to distinguish at least two uses of the term: ecological fitness on the one hand, and population genetics fitness on the other. The goal of this paper is to give an explication of the concept of ecological fitness by providing a reconstruction of the theory of natural selection in which this concept was framed, that is, based on the way the theory was put to use in Darwin's main texts. I will contend that this reconstruction enables us to account for the current use of the theory of natural selection. The framework presupposed in the analysis will be that of metatheoretical structuralism. This framework will provide both a better understanding of the nature of ecological fitness and a more complete reconstruction of the theory. In particular, it will provide what I think is a better way of understanding how the concept of fitness is applied through heterogeneous cases. One of the major advantages of my way of thinking about natural selection theory is that it would not have the peculiar metatheoretical status that it has in other available views. I will argue that in order to achieve these goals it is necessary to make several concepts explicit, concepts that are frequently omitted in usual reconstructions.

  9. Nuclear energy an introduction to the concepts, systems, and applications of nuclear processes

    CERN Document Server

    Murray, Raymond L

    1993-01-01

    This expanded, revised, and updated fourth edition of Nuclear Energy maintains the tradition of providing clear and comprehensive coverage of all aspects of the subject, with emphasis on the explanation of trends and developments. As in earlier editions, the book is divided into three parts that achieve a natural flow of ideas: Basic Concepts, including the fundamentals of energy, particle interactions, fission, and fusion; Nuclear Systems, including accelerators, isotope separators, detectors, and nuclear reactors; and Nuclear Energy and Man, covering the many applications of radionuclides, r

  10. The systematics of emerging nuclear energy concepts

    International Nuclear Information System (INIS)

    Harms, A.A.; Ligou, J.

    1980-01-01

    The basic systematics pertaining to emerging nuclear energy concepts are examined from a historical and categorical perspective. For this purpose a complementary formulation of the interdependence of the vital fission-fusion-acceleration processes is established and then developed to accommodate explicitly recent developments for advanced synergetic nuclear energy proposals. The papers presented at the conference which form these proceeding are shown to integrate well and thus ecluidate the generalized systematics of this formulation. (orig.) [de

  11. The decommissioning concept for nuclear facilities in Ukraine

    International Nuclear Information System (INIS)

    Yaroslavtsev, G.F.; Korchagin, P.A.

    2000-01-01

    The basic task of the conception is a formulation of the basic directions and priorities, terms of schedules and plans, calculation of costs of works on endurance, preservations, dismantlement of nuclear facilities and returning of territories in the unlimited usage. Independent of the development rate of nuclear energy in Ukraine, this problem must now be solved. (author)

  12. NATO's new strategic concept and the future of nuclear disarmament in Europe; Das Neue Strategische Konzept der NATO und die Zukunft der nuklearen Abruestung in Europa

    Energy Technology Data Exchange (ETDEWEB)

    Dembinski, Matthias; Mueller, Harald

    2010-07-01

    The study on NATO's new strategic concept and the future of nuclear disarmament in Europe covers the following topics: From the Prague speech to the strategic concept - the significance and role of the substrategic nuclear weapons in Europe: the substrategic nuclear weapons (SSNW) in the USA: relict of the Cold war or clamps of the transatlantic security? The future of the SSNW from the Prague speech to the strategic concept. The positions of selected NATO members and Russia. Conclusions and recommendations: From the significance of the US nuclear weapons in Europe. Arms control policy options.

  13. Selected topics in nuclear structure

    International Nuclear Information System (INIS)

    1994-01-01

    The collection of abstracts on selected topics in nuclear structure are given. Special attention pays to collective excitations and high-spin states of nuclei, giant resonance structure, nuclear reaction mechanisms and so on

  14. 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

  15. Design concepts of nuclear desalination plants

    International Nuclear Information System (INIS)

    2002-11-01

    Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This has been motivated by a variety of factors, including economic competitiveness of nuclear energy, the growing need for worldwide energy supply diversification, the need to conserve limited supplies of fossil fuels, protecting the environment from greenhouse gas emissions, and potentially advantageous spin-off effects of nuclear technology for industrial development. Various studies, and at least one demonstration project, have been considered by Member States with the aim of assessing the feasibility of using nuclear energy for desalination applications under specific conditions. In order to facilitate information exchange on the subject area, the IAEA has been active for a number of years in compiling related technical publications. In 1999, an inter regional technical co-operation project on Integrated Nuclear Power and desalination System Design was launched to facilitate international collaboration for the joint development by technology holders and potential end users of an integrated nuclear desalination system. This publication presents material on the current status of nuclear desalination activities and preliminary design concepts of nuclear desalination plants, as made available to the IAEA by various Member States. It is aimed at planners, designers and potential end-users in those Member States interested in further assessment of nuclear desalination. Interested readers are also referred to two related and recent IAEA publications, which contain useful information in this area: Introduction of Nuclear Desalination: A Guidebook, Technical Report Series No. 400 (2000) and Safety Aspects of Nuclear Plants Coupled with Seawater Desalination Units, IAEA-TECDOC-1235 (2001)

  16. The concept of nuclear threshold and its political and strategic implications

    International Nuclear Information System (INIS)

    Sitt, Bernard

    2013-07-01

    The notion of the nuclear threshold first appeared in reference to those States beyond the five Nuclear-Weapon States recognised by the Nuclear Non-Proliferation Treaty (NPT) that had acquired or were in the process of acquiring nuclear weapons. Historically, the first States to be dubbed threshold States were Israel, India, and Pakistan, but the term has since been extended, at least in expert analytical circles and in certain official declarations, to include other countries, both States Parties and non-States Parties to the NPT, such as South Africa, Iraq, North Korea, and, more recently, Iran. Aside from the fact that they constitute or have constituted a scenario of extremely advanced nuclear proliferation, these different countries have very little in common. Situated in singular geopolitical contexts, these countries' specific political/ strategic developments have for the most part provoked nuclear crises, to which the international community has sought to respond via an appropriate diplomatic approach (with the use of force remaining the exception to the rule), with contrasting results. Moreover, with the exception of Iraq and South Africa, the exact extent of the technical and operational development of these States' military nuclear capabilities remains unknown, a point that clearly illustrates the vague nature of the nuclear threshold concept. Indeed, this concept is very much multidimensional, given its simultaneous political, military, diplomatic, strategic, industrial, scientific, and technical characteristics. It also refers to discourses or deterrence postures that vary from one proliferating State to another, which thus require specific interpretation, analysis, and responses to the ensuing crises, which are always likely to weaken the global non-proliferation regime. In this context, an overarching review of the concept and its implications would be extremely useful, all the more so given that no study of this kind has appeared in academic

  17. Issues of integrating high-tech concepts into nuclear power plant operation

    International Nuclear Information System (INIS)

    Kisner, R.A.; Carter, R.J.; Lindsay, R.W.

    1990-01-01

    The stockpile of new ideas continues to grow for monitoring nuclear power plant parameters, characteristics, and vital signs and for controlling systems, subsystems, and components. This wide selection of monitoring and control software increases the difficulty of designing an integrated control room. As plant control room operators increase their reliance on computerized systems, including real-time plant data and data base systems, the integration of monitoring, diagnostics, and control software into uniform and seamless environment becomes imperative. A systematic approach to evaluating the usefulness of such high-tech control concepts is needed. This paper concentrates on methods to evaluate control concepts by assessing factors that determine a system's potential effectiveness within the context of the overall environment, including both human and machine components. Although not an in-depth study, this paper serves to outline several measures of utility. 21 refs., 3 figs., 2 tabs

  18. A framework for selecting suitable control technologies for nuclear power plant systems

    International Nuclear Information System (INIS)

    Kisner, R.A.

    1992-01-01

    New concepts continue to emerge for controlling systems, subsystems, and components and for monitoring parameters, characteristics, and vital signs in nuclear power plants. The steady stream of new control theories and the evolving state of control software exacerbates the difficulty of selecting the most appropriate control technology for nuclear power plant systems. As plant control room operators increase their reliance on computerized systems, the integration of monitoring, diagnostic, and control functions into a uniform and understandable environment becomes imperative. A systematic framework for comparing and evaluating the overall usefulness of control techniques is needed. This paper describes nine factors that may be used to evaluate alternative control concepts. These factors relate to a control system's potential effectiveness within the context of the overall environment, including both human and machine components. Although not an in-depth study, this paper serves to outline an evaluation framework based on several measures of utility. 32 refs

  19. Selected topics in nuclear structure

    Energy Technology Data Exchange (ETDEWEB)

    Solov` ev, V G; Gromov, K Ya; Malov, L A; Shilov, V M

    1994-12-31

    The Fourth International Conference on selected topics in nuclear structure was held at Dubna in July 1994 on recent experimental and theoretical investigations in nuclear structure. Topics discussed were the following: nuclear structure at low-energy excitations (collective quasiparticle phenomena, proton-neutron interactions, microscopic and phenomenological theories of nuclear structure; nuclear structure studies with charged particles). heavy ions, neutrons and photons; nuclei at high angular momenta and superdeformation, structure and decay properties of giant resonances, charge-exchange resonances and {beta}-decay; semiclassical approach of large amplitude collective motion and structure of hot nuclei.

  20. Selected topics in nuclear structure

    International Nuclear Information System (INIS)

    Solov'ev, V.G.; Gromov, K.Ya.; Malov, L.A.; Shilov, V.M.

    1994-01-01

    The Fourth International Conference on selected topics in nuclear structure was held at Dubna in July 1994 on recent experimental and theoretical investigations in nuclear structure. Topics discussed were the following: nuclear structure at low-energy excitations (collective quasiparticle phenomena, proton-neutron interactions, microscopic and phenomenological theories of nuclear structure; nuclear structure studies with charged particles. heavy ions, neutrons and photons; nuclei at high angular momenta and superdeformation, structure and decay properties of giant resonances, charge-exchange resonances and β-decay; semiclassical approach of large amplitude collective motion and structure of hot nuclei

  1. Concepts of nuclear quality assurance

    International Nuclear Information System (INIS)

    Randers, G.; Morris, P.A.; Pomeroy, D.

    1976-01-01

    While the safety record of the nuclear industry continues to be excellent, the forced outage rates for recent years continue to be 15% or more. Quality assurance, therefore, needs to be applied not only to nuclear safety matters, but to the goals of increased productivity and reduced construction and operating costs. Broadening the application of the general concept of quality assurance in this way leads to the introduction of reliability technology. The total activity might better be called reliability assurance. That effective quality assurance systems do pay off is described by examples from the utility industry, from a manufacturer of instruments and systems and from the experience of Westinghouse Electric Company's manufacturing divisions. The special situation of applying quality assurance to nuclear fuel is discussed. Problems include the lack of a fully developed regulatory policy in this area, incomplete understanding of the mechanism for pellet-clad interaction failures, incomplete access to manufacturers design and process information, inability to make desirable changes on a timely basis and inadequate feedback of irradiation experience. (author)

  2. Off-site protective action selection for nuclear reactor accidents

    International Nuclear Information System (INIS)

    Weerakkody, S.D.

    1986-01-01

    A computer program based upon a model using a rational theoretical basis was developed to select appropriate off-site protective actions during nuclear reactor accidents. The special features of this program include (a) introduction of a precursor concept that uses the history of the accident progression to determine the spectrum of potential accident scenarios and estimates of the likelihoods of each accident scenario; (b) use of statistical decision theory and the concept of entropy of a spectrum to select the appropriate protective actions using either the minimax principle or the Bayes action method; and (c) introduction of methods to quantify evacuation travel risks. In order to illustrate the usefulness of the computer program, it was applied at three stages of the Three Mile Island accident scenario. Quantified non-radiological risks of evaluation have been used to establish dose thresholds below which evacuations are not justified. Using the Poisson analysis for evacuation risks and the absolute L-L BEIR model for radiation risk suggests 330 mrems as a reasonable value for this threshold. The usefulness of the program in developing a technical basis to select the size of the plume exposure pathway emergency planning zone (EPZ) is discussed. Quantified evacuation risks, cost, and the current rationale upon which the EPZ is based, justify an EPZ between 5-10 miles for WASH-1400 source-terms

  3. Nuclear-reactor remote-monitoring systems - concepts and implementations

    International Nuclear Information System (INIS)

    Rudolf, A.

    1987-01-01

    The paper presents general concepts and some examples of implemented nuclear-reactor remote-monitoring (RM) systems. Some functions and tasks of RM systems are demonstrated and three concepts are described in detail and assessed globally. Three examples of implemented RM systems are discussed using the Baden-Wurttemberg RM system for a description in greater detail. A brief prognosis of the future development of RM systems is made. (orig./DG) [de

  4. A new design concept for offshore nuclear power plants with enhanced safety features

    International Nuclear Information System (INIS)

    Lee, Kihwan; Lee, Kang-Heon; Lee, Jeong Ik; Jeong, Yong Hoon; Lee, Phill-Seung

    2013-01-01

    Highlights: ► A new design concept for offshore nuclear power plants is proposed. ► The total general arrangement for the concept is suggested. ► A new emergency passive containment cooling system (EPCCS) is proposed. ► A new emergency passive reactor-vessel cooling system (EPRVCS) is proposed. ► Safety features against earthquakes, tsunamis, and storms are discussed. - Abstract: In this paper, we present a new concept for offshore nuclear power plants (ONPP) with enhanced safety features. The design concept of a nuclear power plant (NPP) mounted on gravity-based structures (GBSs), which are widely used offshore structures, is proposed first. To demonstrate the feasibility of the concept, a large-scale land-based nuclear power plant model APR1400, which is the most recent NPP model in the Republic of Korea, is mounted on a GBS while minimizing modification to the original features of APR1400. A new total general arrangement (GA) and basic design principles are proposed and can be directly applied to any existing land based large scale NPPs. The proposed concept will enhance the safety of a NPP due to several aspects. A new emergency passive containment cooling system (EPCCS) and emergency passive reactor-vessel cooling system (EPRVCS) are proposed; their features of using seawater as coolant and safety features against earthquakes, Tsunamis, storms, and marine collisions are also described. We believe that the proposed offshore nuclear power plant is more robust than conventional land-based nuclear power plants and it has strong potential to provide great opportunities in nuclear power industries by decoupling the site of construction and that of installation.

  5. Physics of nuclear radiations concepts, techniques and applications

    CERN Document Server

    Rangacharyulu, Chary

    2013-01-01

    Physics of Nuclear Radiations: Concepts, Techniques and Applications makes the physics of nuclear radiations accessible to students with a basic background in physics and mathematics. Rather than convince students one way or the other about the hazards of nuclear radiations, the text empowers them with tools to calculate and assess nuclear radiations and their impact. It discusses the meaning behind mathematical formulae as well as the areas in which the equations can be applied. After reviewing the physics preliminaries, the author addresses the growth and decay of nuclear radiations, the stability of nuclei or particles against radioactive transformations, and the behavior of heavy charged particles, electrons, photons, and neutrons. He then presents the nomenclature and physics reasoning of dosimetry, covers typical nuclear facilities (such as medical x-ray machines and particle accelerators), and describes the physics principles of diverse detectors. The book also discusses methods for measuring energy a...

  6. Financial operation and management concepts in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Bennington, J.L.; Handmaker, H.; Freedman, G.S. (eds.)

    1977-01-01

    Separate abstracts were prepared on two of the 19 chapters in this book that discuss current concepts of management, accounting, and systems techniques of nuclear medicine facilities to insure that the services are used intelligently and frugally.

  7. Spin temperature concept verified by optical magnetometry of nuclear spins

    Science.gov (United States)

    Vladimirova, M.; Cronenberger, S.; Scalbert, D.; Ryzhov, I. I.; Zapasskii, V. S.; Kozlov, G. G.; Lemaître, A.; Kavokin, K. V.

    2018-01-01

    We develop a method of nonperturbative optical control over adiabatic remagnetization of the nuclear spin system and apply it to verify the spin temperature concept in GaAs microcavities. The nuclear spin system is shown to exactly follow the predictions of the spin temperature theory, despite the quadrupole interaction that was earlier reported to disrupt nuclear spin thermalization. These findings open a way for the deep cooling of nuclear spins in semiconductor structures, with the prospect of realizing nuclear spin-ordered states for high-fidelity spin-photon interfaces.

  8. Fuel element concept for long life high power nuclear reactors

    Science.gov (United States)

    Mcdonald, G. E.; Rom, F. E.

    1969-01-01

    Nuclear reactor fuel elements have burnups that are an order of magnitude higher than can currently be achieved by conventional design practice. Elements have greater time integrated power producing capacity per unit volume. Element design concept capitalizes on known design principles and observed behavior of nuclear fuel.

  9. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

    1985-07-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

  10. Nuclear fuel waste management and disposal concept: Report. Federal environmental assessment review process

    International Nuclear Information System (INIS)

    1998-01-01

    The Canadian concept for disposing CANDU reactor waste or high-level nuclear wastes from reprocessing involves underground disposal in sealed containers emplaced in buffer-filled and sealed vaults 500--1,000 meters below ground, in plutonic rock of the Canadian Shield. This document presents the report of a panel whose mandate was to review this concept (rather than a specific disposal project at a specific site) along with a broad range of related policy issues, and to conduct that review in five provinces (including reviews with First Nations groups). It first outlines the review process and then describes the nature of the problem of nuclear waste management. It then presents an overview of the concept being reviewed, its implementation stages, performance assessment analyses performed on the concept, and implications of a facility based on that concept (health, environmental, social, transportation, economic). The fourth section examines the criteria by which the safety and acceptability of the concept should be evaluated. This is followed by a safety and acceptability evaluation from both technical and social perspectives. Section six proposes future steps for building and determining acceptability of the concept, including an Aboriginal participation process, creation of a Nuclear Fuel Waste Management Agency, and a public participation process. The final section discusses some issues outside the panel's mandate, such as energy policy and renewable energy sources. Appendices include a chronology of panel activities, a review of radiation hazards, comparison between nuclear waste management and the management of other wastes, a review of other countries' approaches to long-term management of nuclear fuel wastes, and details of a siting process proposed by the panel

  11. State of the art of the fluidized bed nuclear reactor concept

    International Nuclear Information System (INIS)

    Sefidvash, F.; Vilhena, M.T.M.B. de; Streck, E.; Borges, V.; Johansson, M.

    1987-01-01

    A small and simple nuclear reactors with inherent safety using the fluidized bed concept is under research and study. In this paper a brief study neutronics and thermal hydraulics of this reactor concept is presented. (Author) [pt

  12. The marketing concept of nuclear power plant constructors

    International Nuclear Information System (INIS)

    Czakainski, M.

    1980-01-01

    The paper examines the largely non-investigated area of marketing theory and energy sciences. The author considers the structure of the nuclear power industry and of marketing, analyses the nuclear power station market and its factors of influence, and gives a market forecast. The marketing concept requires especially a typologization of the investment good nuclear power plant. Project-dependent and project-independent marketing activities are coordinated in a marketing programme, and are integrated into mixed marketing efforts. Problems result from insecurity related to the further development of political, social and economic factors of influence. Constructors of nuclear power plants in the Federal Republic of Germany have to adapt to this insecurity and to face risks presented by entrepreneurial activities and the environment by means of flexible planning. (HSCH) [de

  13. The Nuclear Organization and Management Analysis Concept methodology: Four years later

    International Nuclear Information System (INIS)

    Haber, S.B.; Shurberg, D.A.; Barriere, M.T.; Hall, R.E.

    1992-01-01

    The Nuclear Organization and Management Analysis Concept was first presented at the IEEE Human Factors meeting in Monterey in 1988. In the four years since that paper, the concept and its associated methodology has been demonstrated at two commercial nuclear power plants (NPP) and one fossil power plant. In addition, applications of some of the methods have been utilized in other types of organizations, and products are being developed from the insights obtained using the concept for various organization and management activities. This paper will focus on the insights and results obtained from the two demonstration studies at the commercial NPPs. The results emphasize the utility of the methodology and the comparability of the results from the two organizations

  14. Nuclear station safety standardization from a risk concept

    International Nuclear Information System (INIS)

    Veksler, L.M.

    1986-01-01

    This paper presents a method of standardizing safety-system reliability on an entirely new basis: all hypothetical accidents are approximated as groups, for each of which one proposes permissible frequencies on the basis of the risk concept. In this risk concept, the ''average person'' is a person living near a nuclear station or working in it, who is of average age, average state of health, and so on. Therefore, the risk can be found by summing the estimated individual risks for a particular group in the population followed by division by the number of people in that group. Basic assumptions in deriving permissible safety-system reliability are presented. Estimated permissible failure probabilities are given to illustrate the proposed method and to refine the initial data. The probabilities may also be used to lay down the reliability requirements for safety systems in particular nuclear stations on the risk basis

  15. An integral reactor design concept for a nuclear co-generation plant

    International Nuclear Information System (INIS)

    Lee, D.J.; Kim, J.I.; Kim, K.K.; Chang, M.H.; Moon, K.S.

    1997-01-01

    An integral reactor concept for nuclear cogeneration plant is being developed at KAERI as an attempt to expand the peaceful utilization of well established commercial nuclear technology, and related industrial infrastructure such as desalination technology in Korea. Advanced technologies such as intrinsic and passive safety features are implemented in establishing the design concepts to enhance the safety and performance. Research and development including laboratory-scale tests are concurrently underway to evaluate the characteristics of various passive safety concepts and provide the proper technical data for the conceptual design. This paper describes the preliminary safety and design concepts of the advanced integral reactor. Salient features of the design are hexagonal core geometry, once-through helical steam generator, self-pressurizer, and seismic resistant fine control CEDMS, passive residual heat removal system, steam injector driven passive containment cooling system. (author)

  16. A feasibility study for a contained pulsed nuclear propulsion concept

    International Nuclear Information System (INIS)

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

    1993-01-01

    A preliminary analysis of a pulsed propulsion concept is performed utilizing the enormously dense energy generated by small nuclear detonations. The concept feasibility is based on the premise that current materials technology has undergone significant breakthroughs, allowing design of pressure vessels capable of containing the blast associated with such detonations. Furthermore, the rapid energy transfer to the propellant, allows generation of high thrust levels for up to 10 ms following the detonation. Preliminary reevaluation of the concept using off-the-shelf materials technology appears to indicate that the contained pulsed nuclear propulsion concept has no major flaws, and it can provide thrust levels resulting in average thrust-to-weight ratios on the order of 2--2.5 over an engine operating cycle. Furthermore, even though the specific impulse is not a good performance indicator for impulsive engines, operating-cycle-averaged specific impulse of approximately 1800 s has been calculated. The engine mass associated with this performance is on the order of 50 Mg. The concept appears attractive for a number of missions planned for the Space Exploration Initiative, however, there are still a number of issues that must be addressed

  17. The Quality Assurance Concept as Applied in Nuclear industry

    International Nuclear Information System (INIS)

    Aly, A.E.

    1999-01-01

    A statistical evaluation performed on a 1300 MW Nuclear power plants built in Germany has revealed an amazing quantity and complexity features: About 700 participating manufactures, suppliers and sub suppliers; 14000 to 18000 component and parts; 60000 interfaces among the individual organizations participating in planning, design procurement, etc; 10 millions quality characteristics to defined in specifications and to be verified on the hardware by means of Non destructive and / or destructive testing; Over one million pages of records from tests and examinations.To cope the above mentioned work and activities planned and systematic actions are necessary to provide adequate confidence on the performance. These planned and systematic actions are the Quality Assurance (QA). QA is an essential aspect of good management which contributes to the achievement of quality through analysis of the task to be performed, the identification of the skills required, the selections and training of appropriate personnel, the use of appropriate equipment, the creation of a satisfactory environment in which activity can be performed and recognition of the responsibility of the individual who is to perform the task. Briefly stated, provides that each task affecting quality has been satisfactory performed, and production of documentary evidence to demonstrate that the required quality has been achieved. The presented paper shall highlight the concept of QA as specified in the International Atomic Energy Agency (IAEA) Nuclear Safety Standards (NUSS) and also some other National/ International Standards. The paper shall also address the QA requirements as stated in the IAEA Safety Code of the Nuclear Research Reactors

  18. SCW Pressure-Channel Nuclear Reactors: Some Design Features and Concepts

    International Nuclear Information System (INIS)

    Duffey, R.B.; Pioro, I.L.; Gabaraev, B.A.; Kuznetsov, Yu. N.

    2006-01-01

    Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950's and 1960's in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with supercritical water (SCW) became attractive again as the ultimate development path for water-cooling. The main objectives of using SCW in nuclear reactors are 1) to increase the thermal efficiency of modern nuclear power plants (NPPs) from 33 -- 35% to about 40 -- 45%, and 2) to decrease capital and operational costs and hence decrease electrical energy costs (∼$ 1000 US/kW). SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625 deg. C), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost, due to increased reaction rates. Pressure-channel SCW nuclear reactor concepts are being developed in Canada and Russia. Design features related to both channels and fuel bundles are discussed in this paper. Also, Russian experience with operating supercritical steam heaters at NPP is presented. The main conclusion is that development of SCW pressure-channel nuclear reactors is feasible and significant benefits can be expected over other thermal energy systems. (authors)

  19. Russian conceptions of plant life management and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Bugaenko, S.E.; Butorin, S.L.

    2000-01-01

    Plant life management (PLIM) of nuclear power plant is the concept and practice to provide profitability of safe operation of nuclear electricity-generating installations. Therefore, application of the PLIM technology is a unique possibility for the nuclear power not only to preserve its presence at the generated electricity market but also to enlarge it there at the first quarter of the third millennium. PLIM is considered as the concept and procedure covering the whole life cycle of NPP, consisting of three main phases: pre-operation, operation, post-operation. When considering the list of the main standard works for PLIM, one can notice that the structure of a full volume of works can be presented as the sum of two constituents: specific for a particular power unit and universal one. A specific constituent implies realising the PLIM process at a particular power unit, and universal one implies development scientific-methodological, technological and normative basis supporting PLIM process. The concept of decommissioning NPP power units was developed and adopted in 1991, and nowadays is renewed. Its main principles and provisions correspond to a general approach to decommissioning nuclear power plants which was adopted in international practice and recommended in the IAEA documents. Elimination of NPP power unit is adopted in it as the basic option

  20. Concepts and strategies for management of nuclear wastes

    International Nuclear Information System (INIS)

    1979-11-01

    Three modes of reactor strategies are chosen and discussed; (1) Once-through type light water reactor, (2) U-Pu cycle light water reactor, and (3) U-Pu cycle fast breeder reactor. The arising of wastes in each mode of nuclear fuel cycle is first estimated for unit nuclear power generation of 1 GWe.year and the amount of wastes to be managed in each year is then calculated. Assuming the 2nd and the 3rd reprocessing plants are not operative, the decrease of waste arising is also estimated, which, nevertheless, claims the need for spent fuel storage pools. In addition, the arisings of decommissioning wastes are evaluated to identify their effect on waste management. Based on above fact, a generic logic of waste management is brought about, placing major emphasis on volume reduction, barrier- and decay-effects. According to the characteristics, the wastes arisen at each stage of nuclear fuel cycle can be categorized into (1) extremely low-level waste, (2) low- and intermediate-level waste, (3) alpha-waste and (4) high-level waste, and the suitable isolation periods for the specified categories can be set by the aid of hazard index, suggesting that the disposal options may possibly be selected. The waste disposal gives environmental impacts through dispersion and migration of contained nuclides into biosphere; the dispersion and migration paths are investigated and a mathematical expression to evaluate the impacts as dose commitment is presented. A multi-barrier concept is proposed since combined artificial and natural barriers have possibility of lengthening the migration path to enable safe disposal. Finally, items of research/development in waste management are represented from the viewpoints of (1) establishment of management system, (2) safety assessment covering verification of technology and system, and (3) regulation, giving recommendations for national policy making as well as for international co-operation. (JPN)

  1. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 2

    International Nuclear Information System (INIS)

    Gillespie, P.A.; Wuschke, D.M.; Guvanasen, V.M.; Mehta, K.K.; McConnell, D.B.; Tamm, J.A.; Lyon, R.B.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the burial of corrosion-resistant containers of waste in a vault located deep in plutonic rock in the Canadian Shield. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluatin of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have if the concept were implemented. The second assessment was performed in 1984 and is documented in Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1 to 4. This volume, entitled Background, discusses Canadian nuclear fuel wastes and the desirable features of a waste disposal method. It outlines several disposal options being considered by a number of countries, including the option chosen for development and assessment in Canada. The reference disposal systems assumed for the second assessment are described, and the approach used for concept assessment is discussed briefly. 79 refs

  2. Selection of nuclear power information database management system

    International Nuclear Information System (INIS)

    Zhang Shuxin; Wu Jianlei

    1996-01-01

    In the condition of the present database technology, in order to build the Chinese nuclear power information database (NPIDB) in the nuclear industry system efficiently at a high starting point, an important task is to select a proper database management system (DBMS), which is the hinge of the matter to build the database successfully. Therefore, this article explains how to build a practical information database about nuclear power, the functions of different database management systems, the reason of selecting relation database management system (RDBMS), the principles of selecting RDBMS, the recommendation of ORACLE management system as the software to build database and so on

  3. An energy amplifier fluidized bed nuclear reactor concept

    International Nuclear Information System (INIS)

    Sefidvash, F.; Seifritz, W.

    2001-01-01

    The concept of a fluidized bed nuclear reactor driven by an energy amplifier system is described. The reactor has promising characteristics of inherent safety and passive cooling. The reactor can easily operate with any desired spectrum in order to be a plutonium burner or have it operate with thorium fuel cycle. (orig.) [de

  4. Nuclear Burning Wave Modular Fast Reactor Concept

    International Nuclear Information System (INIS)

    Kodochigov, N.G.; Sukharev, Yu.P.

    2014-01-01

    The necessity to provide nuclear power industry, comparable in a scope with power industry based on a traditional fuel, inspired studies of an open-cycle fast reactor aimed at: - solution of the problem of fuel provision by implementing the highest breeding characteristics of new fissile materials of raw isotopes in a fast reactor and applying accumulated fissile isotopes in the same reactor, independently on a spent fuel reprocessing rate in the external fuel cycle; - application of natural or depleted uranium for makeup fuel, which, with no spent fuel reprocessing, forms the most favorable non-proliferation conditions; - application of inherent properties of the core and reactor for safety provision. The present report, based on previously published papers, gives the theoretical backgrounds of the concept of the reactor with a nuclear burning wave, in which an enriched-fuel core (driver) is replaced by a blanket, and basic conditions for nuclear burning wave initiating and keeping are shown. (author)

  5. Cation-selective extraction column study for the conception of nuclear medical radionuclide generators

    International Nuclear Information System (INIS)

    Streng, Roman

    2012-01-01

    The topic of the present work is the conception of a Yttrium-90 radionuclide generator for nuclear medicine applications. Due to its physical properties Yttrium-90 is considered as one of the most useful nuclides for radiotherapeutic cancer treatment. The parent nuclide Strontium-90 is gained during reprocessing of fission products. Thus, the sustained availability of large quantities of Yttrium-90 is limited to a number of research facilities. A radionuclide generator provides an independent Yttrium-90 source and enhances the capacities for radiopharmaceutical research and biomedical applications. The present work focussed on the identification of appropriate column materials for the separation of Strontium and Yttrium. The results for two materials are reported: AnaLig registered Sr-01 and crystalline antimonic acid. Based on the mode of operation of the Technetium-99m generator the aim was to enable the construction of a compact, enclosed apparatus. The projected device comprises a reservoir for the eluant, the ion-exchange column, pipings and radiation shielding. Elution of Yttrium-90 could then be easily performed by connecting evacuated vials to the outlet tube. The prospected concept involves physical and chemical confinements that exclude most of the known processes for Strontium-Yttrium separation. For example no ligands, no oxidizing reactants (e.g. nitric acid) and no organic solvents are to be used, but small volumes of isotonic or buffer solutions and dilute acids respectively. AnaLig registered Sr-01 is a commercially available resin used in extraction chromatography. Its high selectivity for Strontium cations results from the strictly defined cavity of the imbedded cryptand. Determination of weight distribution coefficients, elution studies and pre-generator experiments were carried out. Quantitative separation of Yttrium from Strontium and Zirconium is possible using small volumes of 0,05 M hydrochloric acid as eluant. Furthermore, high flow rates

  6. Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

    Energy Technology Data Exchange (ETDEWEB)

    Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

    2007-03-21

    In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for

  7. Nuclear rights - nuclear wrongs

    Energy Technology Data Exchange (ETDEWEB)

    Paul, E.F.; Miller, F.D.; Paul, J.; Ahrens, J.

    1986-01-01

    This book contains 11 selections. The titles are: Three Ways to Kill Innocent Bystanders: Some Conundrums Concerning the Morality of War; The International Defense of Liberty; Two Concepts of Deterrence; Nuclear Deterrence and Arms Control; Ethical Issues for the 1980s; The Moral Status of Nuclear Deterrent Threats; Optimal Deterrence; Morality and Paradoxical Deterrence; Immoral Risks: A Deontological Critique of Nuclear Deterrence; No War Without Dictatorship, No Peace Without Democracy: Foreign Policy as Domestic Politics; Marxism-Leninism and its Strategic Implications for the United States; Tocqueveille War.

  8. Project Icarus: Nuclear Fusion Propulsion Concept Comparison

    Science.gov (United States)

    Stanic, M.

    Project Icarus will use nuclear fusion as the primary propulsion, since achieving breakeven is imminent within the next decade. Therefore, fusion technology provides confidence in further development and fairly high technological maturity by the time the Icarus mission would be plausible. Currently there are numerous (over 2 dozen) different fusion approaches that are simultaneously being developed around the World and it is difficult to predict which of the concepts is going to be the most successful one. This study tried to estimate current technological maturity and possible technological extrapolation of fusion approaches for which appropriate data could be found. Figures of merit that were assessed include: current technological state, mass and volume estimates, possible gain values, main advantages and disadvantages of the concept and an attempt to extrapolate current technological state for the next decade or two. Analysis suggests that Magnetic Confinement Fusion (MCF) concepts are not likely to deliver sufficient performance due to size, mass, gain and large technological barriers of the concept. However, ICF and PJMIF did show potential for delivering necessary performance, assuming appropriate techno- logical advances. This paper is a submission of the Project Icarus Study Group.

  9. Integrated Global Nuclear Materials Management Preliminary Concepts

    International Nuclear Information System (INIS)

    Jones, E; Dreicer, M.

    2006-01-01

    The world is at a turning point, moving away from the Cold War nuclear legacy towards a future global nuclear enterprise; and this presents a transformational challenge for nuclear materials management. Achieving safety and security during this transition is complicated by the diversified spectrum of threat 'players' that has greatly impacted nonproliferation, counterterrorism, and homeland security requirements. Rogue states and non-state actors no longer need self-contained national nuclear expertise, materials, and equipment due to availability from various sources in the nuclear market, thereby reducing the time, effort and cost for acquiring a nuclear weapon (i.e., manifestations of latency). The terrorist threat has changed the nature of military and national security requirements to protect these materials. An Integrated Global Nuclear Materials Management (IGNMM) approach would address the existing legacy nuclear materials and the evolution towards a nuclear energy future, while strengthening a regime to prevent nuclear weapon proliferation. In this paper, some preliminary concepts and studies of IGNMM will be presented. A systematic analysis of nuclear materials, activities, and controls can lead to a tractable, integrated global nuclear materials management architecture that can help remediate the past and manage the future. A systems approach is best suited to achieve multi-dimensional and interdependent solutions, including comprehensive, end-to-end capabilities; coordinated diverse elements for enhanced functionality with economy; and translation of goals/objectives or standards into locally optimized solutions. A risk-informed basis is excellent for evaluating system alternatives and performances, and it is especially appropriate for the security arena. Risk management strategies--such as defense-in-depth, diversity, and control quality--help to weave together various technologies and practices into a strong and robust security fabric. Effective

  10. EU DEMO blanket concepts safety assessment. Final report of Working Group 6a of the Blanket Concept Selection Exercise

    International Nuclear Information System (INIS)

    Kleefeldt, K.; Porfiri, T.

    1996-06-01

    The European Union has been engaged since 1989 in a programme to develop tritium breeding blankets for application in a fusion power reactor. There are four blanket concepts under development. Two of them use lithium ceramics, the other two concepts employ an eutectic lead-lithium alloy (Pb-17Li) as breeder material. The two most promising concepts were to select in 1995 for further development. In order to prepare the selection, a Blanket Concept Selection Exercise (BCSE) has been inititated by the participating associations under the auspices of the European Commission. This BCSE has been performed in 14 working groups which, in a comparative evaluation of the four blanket concepts, addressed specific fields. The working group safety addressed the safety implications. This report describes the methodology adopted, the safety issues identified, their comparative evaluation for the four concepts, and the results and conclusions of the working group to be entered into the overall evaluation. There, the results from all 14 working groups have been combined to yield a final ranking as a basis for the selection. In summary, the safety assessment showed that the four European blanket concepts can be considered as equivalent in terms of the safety rating adopted, each concept, however, rendering safety concerns of different quality in different areas which are substantiated in this report. (orig.) [de

  11. Micro-structured nuclear fuel and novel nuclear reactor concepts for advanced power production

    International Nuclear Information System (INIS)

    Popa-Simil, Liviu

    2008-01-01

    Many applications (e.g. terrestrial and space electric power production, naval, underwater and railroad propulsion and auxiliary power for isolated regions) require a compact-high-power electricity source. The development of such a reactor structure necessitates a deeper understanding of fission energy transport and materials behavior in radiation dominated structures. One solution to reduce the greenhouse-gas emissions and delay the catastrophic events' occurrences may be the development of massive nuclear power. The actual basic conceptions in nuclear reactors are at the base of the bottleneck in enhancements. The current nuclear reactors look like high security prisons applied to fission products. The micro-bead heterogeneous fuel mesh gives the fission products the possibility to acquire stable conditions outside the hot zones without spilling, in exchange for advantages - possibility of enhancing the nuclear technology for power production. There is a possibility to accommodate the materials and structures with the phenomenon of interest, the high temperature fission products free fuel with near perfect burning. This feature is important to the future of nuclear power development in order to avoid the nuclear fuel peak, and high price increase due to the immobilization of the fuel in the waste fuel nuclear reactor pools. (author)

  12. Preliminary concepts: materials management in an internationally safeguarded nuclear-waste geologic repository

    International Nuclear Information System (INIS)

    Ostenak, C.A.; Whitty, W.J.; Dietz, R.J.

    1979-11-01

    Preliminary concepts of materials accountability are presented for an internationally safeguarded nuclear-waste geologic repository. A hypothetical reference repository that receives nuclear waste for emplacement in a geologic medium serves to illustrate specific safeguards concepts. Nuclear wastes received at the reference repository derive from prior fuel-cycle operations. Alternative safeguards techniques ranging from item accounting to nondestructive assay and waste characteristics that affect the necessary level of safeguards are examined. Downgrading of safeguards prior to shipment to the repository is recommended whenever possible. The point in the waste cycle where international safeguards may be terminate depends on the fissile content, feasibility of separation, and practicable recoverability of the waste: termination may not be possible if spent fuels are declared as waste

  13. AECL's concept for the disposal of nuclear fuel waste and the importance of its implementation

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-07-01

    Since 1978, Canada has been investigating a concept for permanently dealing with the nuclear fuel waste from Canadian CANDU (Canada Deuterium Uranium) nuclear generating stations. The concept is based on disposing of the waste in a vault excavated 500 to 1000 m deep in intrusive igneous rock of the Canadian Shield. AECL Research will soon be submitting an environmental impact statement (EIS) on the concept for review by a Panel through the federal environmental assessment and review process (EARP). In accordance with AECL Research's mandate and in keeping with the detailed requirements of the review Panel, AECL Research has conducted extensive studies on a wide variety of technical and socio-economic issues associated with the concept. If the concept is accepted, we can and should continue our responsible approach and take the next steps towards constructing a disposal facility for Canada's used nuclear fuel waste

  14. Selective retrieval of memory and concept sequences through neuro-windows

    OpenAIRE

    Kakeya, Hideki; Okabe, Yoichi

    1999-01-01

    This letter presents a crosscorrelational associative memory model which realizes selective retrieval of pattern sequences. When hierarchically correlated sequences are memorized, sequences of the correlational centers can be defined as the concept sequences. The authors propose a modified neuro-window method which enables selective retrieval of memory sequences and concept sequences. It is also shown that the proposed model realizes capacity expansion of the memory which stores random sequen...

  15. Concept licensing procedure for an HTR-module nuclear power plant

    International Nuclear Information System (INIS)

    Brinkmann, G.; Will, M.

    1990-01-01

    In April 1987 the companies Siemens and Interatom applied in the West German state of Lower Saxony for a concept licensing procedure to be initiated for an HTR-Module nuclear power plant. In addition to a safety analysis report, numerous additional papers were submitted to the authorized experts. In April 1989 proceedings were suspended for political and legal reasons. By this time both the fire protection report and the plant security concept report had been completed. The safety concept review was continued by order of the Federal Minister for Research and Technology. The draft safety concept report was completed in July 1989. The final version was completed at the end of 1989. (orig.)

  16. Application of Resource Portfolio Concept in Nuclear Regulatory Infrastructure Support

    International Nuclear Information System (INIS)

    Lee, Y. E.; Ha, J. T.; Chang, H. S.; Kam, S. C.; Ryu, Y. H.

    2010-01-01

    As the new entrants in the global nuclear construction market are increasing and the establishment of an effective and sustainable regulatory infrastructure becomes more important, they have requested international assistance from the international nuclear communities with mature nuclear regulatory programmes. It needs to optimize the use of limited resources from regulatory organization providing support to regulatory infrastructure of new comers. This paper suggests the resource portfolio concept like a GE/Mckinsey Matrix used in business management and tries to apply it to the current needs considered in the regulatory support program in Korea as the case study

  17. Design of Korean nuclear reliability data-base network using a two-stage Bayesian concept

    International Nuclear Information System (INIS)

    Kim, T.W.; Jeong, K.S.; Chae, S.K.

    1987-01-01

    In an analysis of probabilistic risk, safety, and reliability of a nuclear power plant, the reliability data base (DB) must be established first. As the importance of the reliability data base increases, event reporting systems such as the US Nuclear Regulatory Commission's Licensee Event Report and the International Atomic Energy Agency's Incident Reporting System have been developed. In Korea, however, the systematic reliability data base is not yet available. Therefore, foreign data bases have been directly quoted in reliability analyses of Korean plants. In order to develop a reliability data base for Korean plants, the problem is which methodology is to be used, and the application limits of the selected method must be solved and clarified. After starting the commercial operation of Korea Nuclear Unit-1 (KNU-1) in 1978, six nuclear power plants have begun operation. Of these, only KNU-3 is a Canada Deuterium Uranium pressurized heavy-water reactor, and the others are all pressurized water reactors. This paper describes the proposed reliability data-base network (KNRDS) for Korean nuclear power plants in the context of two-stage Bayesian (TSB) procedure of Kaplan. It describes the concept of TSB to obtain the Korean-specific plant reliability data base, which is updated with the incorporation of both the reported generic reliability data and the operation experiences of similar plants

  18. Design of nuclear desalination concentrate plant by using zero discharge desalination concept for Bangka Island

    International Nuclear Information System (INIS)

    Erlan Dewita, Siti Alimah

    2015-01-01

    Nuclear desalination is a process to separate salt of seawater by using nuclear energy. Desalination concentrate is a problem in nuclear desalination. Desalination concentrate is sometimes discharged directly into the seawater, therefore it can affects the water quality of beach and rise negative effects on the biota in the vicinity of the output. ZDD (Zero Discharge Desalination) concept can be applied to minimized environment impact. This study is conducted by using PWR type NPP as nuclear heat source and using ZDD concept to process desalination waste. ZDD is a concept for processing of desalination concentrate into salt and chemical products which have economic values. Objectives of this study is to design nuclear desalination concentrate processing plant in Bangka Island. The methodology is literature assessment and calculation with excel programme. The results of this study shows that the main the products are NaCl (pharmaceutical salt) and cakes BaSO4, Mg(OH)2BaCO3 as by products. (author)

  19. IAEA safety fundamentals: the safety of nuclear installations and the defence in depth concept

    International Nuclear Information System (INIS)

    Aro, I.

    2005-01-01

    This presentation is a replica of the similar presentation provided by the IAEA Basic Professional Training Course on Nuclear Safety. The presentation utilizes the IAEA Safety Series document No. 110, Safety Fundamentals: the Safety of Nuclear Installations. The objective of the presentation is to provide the basic rationale for actions in provision of nuclear safety. The presentation also provides basis to understand national nuclear safety requirements. There are three Safety Fundamentals documents in the IAEA Safety Series: one for nuclear safety, one for radiation safety and one for waste safety. The IAEA is currently revising its Safety Fundamentals by combining them into one general Safety Fundamentals document. The IAEA Safety Fundamentals are not binding requirements to the Member States. But, a very similar text has been provided in the Convention on Nuclear Safety which is legally binding for the Member State after ratification by the Parliament. This presentation concentrates on nuclear safety. The Safety Fundamentals documents are the 'policy documents' of the IAEA Safety Standards Series. They state the basic objectives, concepts and principles involved in ensuring protection and safety in the development and application of atomic energy for peaceful purposes. They will state - without providing technical details and without going into the application of principles - the rationale for actions necessary in meeting Safety Requirements. Chapter 7 of this presentation describes the basic features of defence in depth concept which is referred to in the Safety Fundamentals document. The defence in depth concept is a key issue in reaching high level of safety specifically at the design stage but as the reader can see the extended concept also refers to the operational stage. The appendix has been taken directly from the IAEA Basic Professional Training Course on Nuclear Safety and applied to the Finnish conditions. The text originates from the references

  20. Application of the concept of traceability to the management of nuclear data

    International Nuclear Information System (INIS)

    Furnari, J.C.; Cohen, I.M.

    1998-01-01

    The connotations of the quality of nuclear data in the quality of experimental results are discussed. The authors show the analogies existent between metrological standards and literature data and propose the adoption of the concept of traceability of nuclear data. The conditions to be fulfilled for the publication of nuclear data, concerning the establishment of traceability, are discussed. Criteria for renormalization are presented. The requirements of nuclear data in neutron activation analysis and the role of the analyst are discussed

  1. Selection of JAERI'S HTGR-GT concept

    International Nuclear Information System (INIS)

    Muto, Y.; Ishiyama, S.; Shiozawa, S.

    2001-01-01

    In JAERI, a feasibility study of HTGR-GT has been conducted as an assigned work from STA in Japan since January 1996. So far, the conceptual or preliminary designs of 600, 400 and 300 MW(t) power plants have been completed. The block type core and pebble-bed core have been selected in 600 MW(t) and 400/300 MW(t), respectively. The gas-turbine system adopts a horizontal single shaft rotor and then the power conversion vessel is separated into a turbine vessel and a heat exchanger vessel. In this paper, the issues related to the selection of these concepts are technically discussed. (author)

  2. Summary of the Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1994-01-01

    This is the Summary of the Environmental Impact Statement (EIS) prepared by Atomic Energy of Canada Limited (AECL) on the concept for disposal of Canada's nuclear fuel waste. The proposed concept is a method for geological disposal, based on a system of natural and engineered barriers. The EIS provides information requested by the Environmental Assessment Panel reviewing the disposal concept and presents AECL's case for the acceptability of the concept. The introductory chapter of this Summary provides background information on several topics related to nuclear fuel waste, including current storage practices for used fuel, the need for eventual disposal of nuclear fuel waste, the options for disposal, and the reasons for Canada's focus on geological disposal. Chapter 2 describes the concept for disposal of nuclear fuel waste. Because the purpose of implementing the concept would he to protect human health and the natural environment far into the future, we discuss the long-term performance of a disposal system and present a case study of potential effects on human health and the natural environment after the closure of a disposal facility. The effects and social acceptability of disposal would depend greatly on how the concept was implemented. Chapter 3 describes AECL's proposed approach to concept implementation. We discuss how the public would be involved in implementation; activities that would be undertaken to protect human health, the natural environment, and the socio-economic environment; and a case study of the potential effects of disposal before the closure of a disposal facility. The last chapter presents AECL's Conclusion, based on more than 15 years of research and development, that implementation of the disposal concept represents a means by which Canada can safely dispose of its nuclear fuel waste. This chapter also presents AECL's recommendation that Canada progress toward disposal of its nuclear fuel waste by undertaking the first stage of concept

  3. Risk concepts in UK nuclear safety decision-making

    International Nuclear Information System (INIS)

    Brighton, P.W.M.

    2001-01-01

    This paper discusses the concept of risk as understood in the UK, with particular reference to the use of probabilistic safety assessment (PSA) in nuclear safety decision making. The way 'risk' appears in UK fundamental legislation means that the concept cannot be limited to evaluation of numerical probabilities of physical harm. Rather the focus is on doing all that is reasonably practicable to reduce risks: this entails applying relevant good practice and then seeking further safety measures until the money, time and trouble required are grossly disproportionate to the residual risk. PSA is used to inform rather than dictate such decisions. This approach is reinforced by considering how far any practical PSA can be said to measure risk. The behaviour of complex socio-technical systems such as nuclear power stations does not meet the conditions under which probability theory can be applied in an absolutely objective statistical sense. Risk is not an intrinsic real property of such systems. Rather PSA is a synthesis of data and subjective expert judgements, dependent on the extent of detailed knowledge of the plant. There are many other aspects of engineering judgement involved in safety decisions which cannot be so captured. (author)

  4. Nuclear power safety reporting system feasibility analysis and concept description

    International Nuclear Information System (INIS)

    Finlayson, F.C.; Ims, J.R.; Hussman, T.A.

    1984-01-01

    The Aerospace Corporation is assisting the US Nuclear Regulatory Commission (NRC) in the evaluation of the potential attributes of a voluntary, nonpunitive data gathering system for identifying and quantifying the factors that contribute to the occurrence of significant safety problems involving humans in nuclear power plants. The objectives of the Aerospace Administration (FAA)/National Aeronautics and Space Administration (NASA) Aviation Safety Reporting System (ASRS) in order to determine whether it would be feasible to apply part (or all) of the ASRS concepts for collecting data on human factor related incidents to the nuclear industry; and (2) to identify and define the basic elements and requirements of a Nuclear Power Safety Reporting System (NPSRS), assuming the feasibility of implementing such a system was established

  5. MAPLE: a Canadian multipurpose reactor concept for national nuclear development

    International Nuclear Information System (INIS)

    Lidstone, R.F.

    1984-06-01

    Atomic Energy of Canada Limited, following an investigation of Canadian and international needs and world-market prospects for research reactors, has developed a new multipurpose concept, called MAPLE (Multipurpose Applied Physics Lattice Experimental). The MAPLE concept combines H 2 O- and D 2 O-moderated lattices within a D 2 O calandria tank in order to achieve the flux advantages of a basic H 2 O-cooled and moderated core along with the flexibility and space of a D 2 O-moderated core. The SUGAR (Slowpoke Uprated for General Applied Research) MAPLE version of the conept provides a range of utilization that is well suited to the needs of countries with nuclear programs at an early stage. The higher power MAPLE version furnishes high neutron flux levels and the variety of irradiation facilities that are appropriate for more advanced nuclear programs

  6. Low Pressure Nuclear Thermal Rocket (LPNTR) concept

    International Nuclear Information System (INIS)

    Ramsthaler, J.H.

    1991-01-01

    A background and a description of the low pressure nuclear thermal system are presented. Performance, mission analysis, development, critical issues, and some conclusions are discussed. The following subject areas are covered: LPNTR's inherent advantages in critical NTR requirement; reactor trade studies; reference LPNTR; internal configuration and flow of preliminary LPNTR; particle bed fuel assembly; preliminary LPNTR neutronic study results; multiple LPNTR engine concept; tank and engine configuration for mission analysis; LPNTR reliability potential; LPNTR development program; and LPNTR program costs

  7. The Cigar Lake uranium deposit: Analog information for Canada's nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Cramer, J.J.

    1995-05-01

    The Cigar Lake uranium deposit, located in northern Saskatchewan, has many features that parallel those being considered within the Canadian concept for disposal of nuclear fuel waste. The study of these natural structures and processes provides valuable insight toward the eventual design and site selection of a nuclear fuel waste repository. The main feature of this analog is the absence of any indication on the surface of the rich uranium ore 450 m below. This shows that the combination of natural barriers has been effective in isolating the uranium ore from the surface environment. More specifically, the deposit provides analog information relevant to the stability of UO 2 fuel waste, the performance of clay-based and general aspects of water-rock interaction. The main geotechnical studies on this deposit focus on the evolution of groundwater compositions in the deposit and on their redox chemistry with respect to the uranium, iron and sulphide systems. This report reviews and summarizes the analog information and data from the Cigar Lake analog studies for the processes and scenarios expected to occur in the disposal system for used nuclear fuel proposed in Canada. (author). 45 refs., 10 figs

  8. A partitioning-free transmutation concept of nuclear waste reduction

    International Nuclear Information System (INIS)

    Taczanowski, S.

    1996-01-01

    The idea of a symbiotic nuclear energy system, consisted of an Accelerator-driven Fuel Regenerator and a number of LWRs serviced by it, is the subject of this study, in view of supposed safety and partitioning avoidance advantages. The design premises leading to this concept are widely discussed. 7 refs, 7 figs

  9. Nuclear waste management in Switzerland - concept and plan of realisation

    International Nuclear Information System (INIS)

    1992-12-01

    This reports begins by discussing some basic principles of the nuclear waste management concept, the boundary conditions imposed by social considerations, and technical, economic and organisational parameters. The overall concept will then be presented as it applies to the two disposal strategies for short-lived wastes and for high-level and long-lived intermediate-level wastes and spent fuel. The current status of project work is discussed and future plans, objectives and time schedules are presented. (author) figs., tabs., 20 refs

  10. Factors of site selection for nuclear power plants in selected industrial states

    International Nuclear Information System (INIS)

    Hoffmann, L.; Obermair, G.; Ringler, W.; Romahn, B.; Sanders, H.

    1978-01-01

    The range of the tasks within the project consists of working out an optimal catalogue of criteria for the site selection for nuclear power plants; establishing a structured documentation system for the criteria and licensing procedures used by selected industrial countries when selecting sites for nuclear power plants; analyzing and evaluating the documented material with the aim of supplying the basis for decisions concerning land use. The tasks are being realized within a technological ring of data (for the period until 1990, reactor types, cooling, power-heat coupling, special sites, block sizes, local concentration) and a set politico-economical ring of data for the following countries: F.R. Germany, Belgium, Switzerland, Great Britain, Sweden, Denmark, Austria, France, Netherlands, USA, Japan, Yougoslavia. (HP) [de

  11. Applications of Nuclear Physics

    OpenAIRE

    Hayes, Anna C.

    2017-01-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that und...

  12. Selection of Possible Candidate Area for Nuclear Power Plant in Johor, Malaysia

    International Nuclear Information System (INIS)

    Nor Afifah Basri; Ahmad Termizi Ramli

    2012-01-01

    Nuclear power is considered as one of the best option for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation, commissioning the first nuclear power plant needs tremendous effort in various aspects. Site selection is one of important step in nuclear power plant commissioning process. This paper proposes candidate sites for nuclear power plant in Mersing, Kota Tinggi, Muar and Batu Pahat district in Johor, Malaysia. The candidate selection process uses the IAEA document and AELB guideline as main reference, supported by site selection procedure by various countries. MapInfo Professional software was used to simulate the selection process for candidate areas for the nuclear power plant. This paper concluded that Tenggaroh and Jemaluang area are the most suitable area for nuclear power plant facilities in Johor, Malaysia. (Author)

  13. Selection of possible candidate area for nuclear energy facility in Johor, Malaysia

    International Nuclear Information System (INIS)

    Nor Afifah Basri; Ahmad Termizi Ramli

    2012-01-01

    Nuclear power is considered as one of the best option for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation, commissioning the first nuclear power plant needs tremendous effort in various aspects. Site selection is one of important step in nuclear power plant commissioning process. This paper proposes candidate sites for nuclear power plant in Mersing, Kota Tinggi, Muar and Batu Pahat district in Johor, Malaysia. The candidate selection process uses the IAEA document and AELB guideline as main reference, supported by site selection procedure by various countries. MapInfo Professional software was used to stimulate the selection process for candidate areas for the nuclear power plant. This paper concluded that Tenggaroh and Jemaluang area are the most suitable area for nuclear power plant facilities in Johor, Malaysia. (Author)

  14. 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

  15. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 3

    International Nuclear Information System (INIS)

    Johansen, K.; Donnelly, K.J.; Gee, J.H.; Green, B.J.; Nathwani, J.S.; Quinn, A.M.; Rogers, B.G.; Stevenson, M.A.; Dunford, W.E.; Tamm, J.A.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was completed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This, the third volume of the report, summarizes the pre-closure environmental and safety assessments completed by Ontario Hydro for Atomic Energy of Canada Limited. The preliminary results and their sigificance are discussed. 85 refs

  16. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 4

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Gillespie, P.A.; Mehta, K.K.; Henrich, W.F.; LeNeveu, D.M.; Guvanasen, V.M.; Sherman, G.R.; Donahue, D.C.; Goodwin, B.W.; Andres, T.H.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was performed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This volume, entitled Post-Closure Assessment, describes the methods, models and data used to perform the second post-closure assessment. The results are presented and their significance is discussed. Conclusions and planned improvements are listed. 72 refs

  17. Application of GIS in site selection for nuclear waste disposal facility

    International Nuclear Information System (INIS)

    Sheng, G.; Luginaah, I.N.; Sorrell, J.

    1996-01-01

    Whether designing a new facility or investigating, potential contaminant migration at an existing site, proper characterization of the subsurface conditions and their interaction with surface features is critical to the process. The Atomic Energy Control Board, states in its regulatory document R-104 that, open-quotes For the long-term management of radioactive wastes, the preferred approach is disposal, a permanent method of management in which there is no intention of retrieval and which, ideally uses techniques and designs that do not rely for their success on long-term institutional control beyond a reasonable period of timeclose quotes. Thus although storage is safe, eventually disposal is necessary to avoid long-term reliance on continuing care and attention, such as monitoring and maintenance. In Canada, the concept being proposed by Atomic Energy of Canada Limited (AECL) involves disposal in deep underground repositories in intrusive igneous rock. The aim of this concept as a disposal method is to build multiple barriers that would protect humans and the natural environment from contaminants in the radioactive waste. The multiple barriers include the geosphere, which consists of the rock, any sediments overlying the rock, and the groundwater. Nevertheless, immediate, as well as long-term, consequences, including, risk involved with technological systems and the inherent uncertainty of any forecast, make the prediction and analysis tasks of increasing importance. This uncertainty in the area of nuclear waste disposal is leading to growing concerns about nuclear waste site selection

  18. Perspectives in high energy nuclear collisions

    International Nuclear Information System (INIS)

    Rafelski, J.

    1983-08-01

    This report gives an overview of some aspects of hadronic physics relevant for the conception of a research facility devoted to the study of high energy nuclear collisions. Several concepts to be studied in nuclear collisions are selected, with emphasis placed on the properties and nature of the quark-gluon plasma, the formation of the plasma state in the central region and its anticipated lifetime, and the observability, through strangeness content of this new form of nuclear matter. (orig.)

  19. Operator psychological selection system for nuclear power plant

    International Nuclear Information System (INIS)

    He Xuhong; Huang Xiangrui

    2004-01-01

    Based on a detailed job analysis of nuclear power plant operator including operation procedures analysis, interview with personnel familiar with operator job, and 9 events happened in the past in the plant involved operator error analysis, several operator work characteristics and performance influence factors are obtained. According to these specific characteristics and factors, referring to the psychological selection research results in the other related critical occupational fields, a full psychological selection system of nuclear power plant operator is forwarded in this paper, including 21 dimensions in 3 facets as general psychological ability, personality and psychological healthy. Practical measurement methods for the proposed selection dimensions are discussed in the end

  20. Closures for underground nuclear power plants

    International Nuclear Information System (INIS)

    1981-10-01

    This study demonstrates that, with the appropriate selection of an access concept on the underground nuclear power plant, it is possible to design a gate complying with the increased requirements of the construction of an underground nuclear power plant. The investigations revealed that a comparison leakage of 42 mm in diameter for the failure of seals is too conservative. When selecting suitable seals a leakage being more extensive than the above mentioned one can be prevented even in case of disturbance lasting several months. The closure structures of the personnel and material accesses do not represent any weak point within the concept of the construction method for underground nuclear power plants. (orig./HP)

  1. Comparison between dispersed nuclear power plants and a nuclear energy center at a hypothetical site on Kentucky Lake, Tennessee. Volume I. Summary

    International Nuclear Information System (INIS)

    Burwell, C.C.; Reister, D.B.; Rosemarin, C.S.; Sisman, O.; Suffern, J.S.

    1976-05-01

    A brief summary is presented of the surrogate site concept used to compare the Nuclear Energy Center (NEC) concept with the present method of dispersed siting of nuclear power plants. Included are data on power transmission, environmental considerations, and a discussion of a site selection methodology

  2. Status Of Nuclear Heat And Hydrogen Systems Concept Study

    International Nuclear Information System (INIS)

    Lee, Won Jae; Choi, Yoon Ho; Han, Jae Mun; Ham, Jin Ki; Choi, Su Jin; Lee, Sang Il; Park, Je Ho; Koo, Jae Sak

    2014-01-01

    A three-year national research and development project, “Nuclear Heat and Hydrogen (NuH_2) Systems Concept Study” was launched in 2012 as a pre-project in preparation of a demonstration plant construction and subsequent commercialization. Korea Atomic Energy Research Institute (KAERI) leads the project, and domestic industry partners, POSCO, HDEC, HHI, HEC and STX, as potential vendors and users share the costs and works. The main tasks are to develop the functional and design requirements, to optimize the system concepts and layouts, and to develop the demonstration plan and business model of the NuH_2 systems. This paper addresses the current status of the project and outcomes. (author)

  3. Selection of materials in nuclear fuel: present and future

    International Nuclear Information System (INIS)

    Munoz-Reja, C.; Fuentes, L.; Garcia de la Infanta, J. M.; Munoz Sicilia, A.

    2013-01-01

    One of the main aspects of the nuclear fuel is the selection of materials for the components. The operating conditions of the fuel elements impose a major challenge to materials: high temperature, corrosive aqueous environment, high mechanical properties, long periods of time under these extreme conditions and what is the differentiating factor; the effect of irradiation. The materials are selected to fulfill these severe requirements and also to be able to control and to predict its behavior in the working conditions. Their development, in terms of composition and processing, is based on the continuous follow-up of the operation behavior. Many of these materials are specific of the nuclear industry, such as the uranium dioxide and the zirconium alloys. This article presents the selection and development of the nuclear fuel materials as a function of the services requirements. It also includes a view of the new nuclear fuels materials that are being raised after Fukushima accident. (Author)

  4. Development of the job concept of a nuclear power plant operator

    International Nuclear Information System (INIS)

    Alpeev, A.S.; Bukrinskii, A.M.

    1994-01-01

    An important conclusion drawn in the aftermath of the 1979 accident at Three Mile Island 2 in the USA, in particular, in discussions, held in Stockholm in 1980 at the International Conference on Safety Problems, of the causes of this accident, was that the plant-operator concept employed at the time in western countries had to be changed. The concept presupposed that the operator's actions must be strictly limited by instructions which supposedly encompass all possible situations associated with the accidents. The principal problem facing the operator in this concept is to identify the situation in which the appropriate instruction can be selected for immediate execution. An error in identifying the situation could influence decisively the evolution of further events in the power block of the nuclear plant, and this is precisely what happened at Three Mile Island 2. For this reason, operator training was based mainly on identifying the initial events, which corresponded to a definite sequence of the further developments owing to the technical scheme and laws of thermophysical processes. Such operator training is based on an event tree which gives a graphical representation of the probable consequences of the development of events in an accident with a given initial event. It is believed that approximately 20 initial events (tree roots) form the basic collection of events, each of which has three to seven branches, i.e., an accident can evolve in several possible directions. Every branch point on each tree is identified by a definite collection of technological parameters, according to which the operator must be able to identify the situation. Under the present concept, when the situation is identified correctly, the search for the required control instruction and its execution is a secondary process

  5. Information management for nuclear power stations: System Design Concept

    International Nuclear Information System (INIS)

    Halpin, D.W.

    1978-03-01

    A study of the information management structure required to support nuclear power plant construction was performed by a joint university-industry group under the sponsorship of the Department of Energy (DOE), formerly the Energy Research and Development Administration (ERDA). The purpose of this study was (1) to study methods for the control of information during the construction and start-up of nuclear power plants, and (2) identify those data elements intrinsic to nuclear power plants which must be maintained in a structured format for quick access and retrieval. Maintenance of the massive amount of data needed for control of a nuclear project during design, procurement, construction, start-up/testing, and operational phases requires a structuring which allows immediate update and retrieval based on a wide variety of access criteria. The objective of the research described has been to identify design concepts which support the development of an information control system responsive to these requirements. A conceptual design of a Management Information Data Base System which can meet the project control and information exchange needs of today's large nuclear power plant construction projects has been completed and an approach recommended for development and implementation of a complete operational system

  6. The concept of radioactive waste and spent nuclear fuel management in the Czech Republic

    International Nuclear Information System (INIS)

    Suransky, F.; Duda, V.

    2003-01-01

    The article briefly comments on the status of nuclear waste and spent nuclear fuel management in the Czech Republic in the context of the document entitled 'The Concept of Radioactive Waste and Spent Nuclear Fuel Management in the Czech Republic', which was adopted by the Czech Government in May 2002 as a national strategy in this field. (author)

  7. Linguistic fuzzy selection of liquid levelmeters in nuclear facilities

    International Nuclear Information System (INIS)

    Ghyym, S. H.

    1999-01-01

    In this work, a selection methodology of liquid levelmeters, especially, level sensors in non-nuclear category, to be installed in nuclear facilities is developed using a linguistic fuzzy approach. Depending on defuzzification techniques, the linguistic fuzzy methodology leads to either linguistic (exactly, fully-linguistic) or cardinal (i.e., semi-linguistic) evaluation. In the case of the linguistic method, for each alternative, fuzzy preference index is converted to linguistic utility value by means of a similarity measure determining the degree of similarity between fuzzy index and linguistic ratings. For the cardinal method, the index is translated to cardinal overall utility value. According to these values, alternatives of interest are linguistically or numerically evaluated and a suitable alternative can be selected. Under given selection criteria, the suitable selections out of some liquid levelmeters for nuclear facilities are dealt with using the linguistic fuzzy methodology proposed. Then, linguistic fuzzy evaluation results are compared with numerical results available in the literature. It is found that as to a suitable option the linguistic fuzzy selection is in agreement with the crisp numerical selection. In addition, this comparison shows that the fully-linguistic method facilitates linguistic interpretation regarding evaluation results

  8. Linguistic fuzzy selection of liquid levelmeters in nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ghyym, S. H. [KEPRI, Taejon (Korea, Republic of)

    1999-10-01

    In this work, a selection methodology of liquid levelmeters, especially, level sensors in non-nuclear category, to be installed in nuclear facilities is developed using a linguistic fuzzy approach. Depending on defuzzification techniques, the linguistic fuzzy methodology leads to either linguistic (exactly, fully-linguistic) or cardinal (i.e., semi-linguistic) evaluation. In the case of the linguistic method, for each alternative, fuzzy preference index is converted to linguistic utility value by means of a similarity measure determining the degree of similarity between fuzzy index and linguistic ratings. For the cardinal method, the index is translated to cardinal overall utility value. According to these values, alternatives of interest are linguistically or numerically evaluated and a suitable alternative can be selected. Under given selection criteria, the suitable selections out of some liquid levelmeters for nuclear facilities are dealt with using the linguistic fuzzy methodology proposed. Then, linguistic fuzzy evaluation results are compared with numerical results available in the literature. It is found that as to a suitable option the linguistic fuzzy selection is in agreement with the crisp numerical selection. In addition, this comparison shows that the fully-linguistic method facilitates linguistic interpretation regarding evaluation results.

  9. Concept of underground nuclear power plant

    International Nuclear Information System (INIS)

    Onishi, Sotoaki

    1976-01-01

    The concept of constructing nuclear power plants on the sea or underground as the future sitting is based on moving the present power plants on the ground with actual results to the sea or underground without changing the design. The underground nuclear power plants have many similar points to underground hydro-electric power stations with many achievements in the construction viewpoint, though they have their proper difficult problems. Of course, it requires to excavate larger underground caves than the case of underground hydro-electric power plants. The maximum dimensions of the caves have been determined through experience in practice. Therefore the developments of design theory and construction technique are desirable in this field. In discussing underground construction, two evaluating methods are considered for the shielding effect of base rocks. The minimum vertical distance up to ground surface from the center of the cave differs depending upon the in-cave pressure, and the conditions of base rock, soil and underground water in case of the accident assumed in the design, and is approximately 60m, if the cave is assumed to be an indefinite cylindrical shape, by the safer side calculation in the above two evaluations. (Wakatsuki, Y.)

  10. A new concept for accelerator driven transmutation of nuclear wastes

    International Nuclear Information System (INIS)

    Arthur, E.D.

    1991-01-01

    A new concept for an accelerator-driven transmutation system is described. The central feature of the concept is generation of intense fluxes of thermal neutrons. In the system all long-lived radionuclides comprising high-level nuclear waste can be transmuted efficiently. Transmutation takes place in a unique, low material inventory environment. Presently two principal areas are being investigated for application of the concept. The first is associated with cleanup of defense high-level waste at DOE sites such as Hanford. The second, longer term area involves production of electric power using a coupled accelerator-multiplying blanket system. This system would utilize natural thorium or uranium and would transmute long-lived components of high-level waste concurrently during operation. 5 refs., 5 figs

  11. Selected topics in nuclear structure

    International Nuclear Information System (INIS)

    Stachura, Z.

    1984-09-01

    19. winter school in Zakopane was devoted to selected topics in nuclear structure such as: production of spin resonances, heavy ions reactions and their applications to the investigation of high spin states, octupole deformations, excited states and production of new elements etc. The experimental data are ofen compared with theoretical predictions. Report contains 28 papers. (M.F.W.)

  12. Selection/licensing of nuclear power plant operators

    International Nuclear Information System (INIS)

    Saari, L.M.

    1983-07-01

    An important aspect of nuclear power plant (NPP) safety is the reactor operator in the control room. The operators are the first individuals to deal with an emergency situation, and thus, effective performance on their part is essential for safe plant operations. Important issues pertaining to NPP reactor operators would fall within the personnel subsystem of our safety system analysis. While there are many potential aspects of the personnel subsystem, a key first step in this focus is the selection of individuals - attempting to choose individuals for the job of reactor operator who will safely perform the job. This requires a valid (job-related) selection process. Some background information on the Nuclear Regulatory Commission (NRC) licensing process used for selecting NPP reactor operators is briefly presented and a description of a research endeavor now underway at Battelle for developing a valid reactor operator licensing examination is included

  13. Conception of a computer for the nuclear medical department of the Augsburg hospital center

    International Nuclear Information System (INIS)

    Graf, G.; Heidenreich, P.

    1984-01-01

    A computer system based on the Siemens R30 process computer has been employed at the Institute of Nuclear Medicine of the Augsburg Hospital Center since early 1981. This system, including the development and testing of organ-specific evaluation programs, was used as a basis for the conception of the new computer system for the department of nuclear medicine of the Augsburg Hospital Center. The computer system was extended and installed according to this conception when the new 1400-bed hospital was opened in the 3rd phase of construction in autumn 1982. (orig.) [de

  14. The concept of nuclear-weapon-free zones, with special reference to East Asia

    International Nuclear Information System (INIS)

    Prawitz, J.

    1997-01-01

    The concept of nuclear-weapon-free zone, as it has developed from political deliberation since mid-1950s, today covers a spectrum of arrangements, geographically ranging from whole continent like Latin America to a corridor in central Europe, and functionally serving the purposes of preventing the spread of nuclear weapons and avoiding nuclear war. Among the nuclear-weapon-free zones proposed but not established, one is now being negotiated and two are subject to investigations published in official reports. These are the proposed zones in ASEAN area, The Middle East and Nordic Europe

  15. Regulatory requirements for nuclear power plant site selection in Malaysia-a review.

    Science.gov (United States)

    Basri, N A; Hashim, S; Ramli, A T; Bradley, D A; Hamzah, K

    2016-12-01

    Malaysia has initiated a range of pre-project activities in preparation for its planned nuclear power programme. Clearly one of the first steps is the selection of sites that are deemed suitable for the construction and operation of a nuclear power plant. Here we outline the Malaysian regulatory requirements for nuclear power plant site selection, emphasizing details of the selection procedures and site characteristics needed, with a clear focus on radiation safety and radiation protection in respect of the site surroundings. The Malaysia Atomic Energy Licensing Board (AELB) site selection guidelines are in accord with those provided in International Atomic Energy Agency (IAEA) and United Stated Nuclear Regulatory Commission (USNRC) documents. To enhance the suitability criteria during selection, as well as to assist in the final decision making process, possible assessments using the site selection characteristics and information are proposed.

  16. Applications of nuclear physics

    Science.gov (United States)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  17. Applications of nuclear physics

    International Nuclear Information System (INIS)

    Hayes-Sterbenz, Anna Catherine

    2017-01-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  18. From Nucleons to Nucleus Concepts of Microscopic Nuclear Theory

    CERN Document Server

    Suhonen, Jouni

    2007-01-01

    From Nucleons to Nucleus deals with single-particle and collective features of spherical nuclei. Each nuclear model is introduced and derived in detail. The formalism is then applied to light and medium-heavy nuclei in worked-out examples, and finally the acquired skills are strengthened by a wide selection of exercises, many relating the models to experimental data. Nuclear properties are discussed using particles, holes and quasiparticles. A large number of matrix elements of standard operators have been tabulated for reference. From Nucleons to Nucleus is based on lectures on nuclear physics given by the author. Its main scope is thus to serve as a textbook for advanced students. But also researchers will appreciate it as wellbalanced reference to theoretical nuclear physics.

  19. Repository sealing concepts for the Nevada nuclear waste storage Investigations Project

    International Nuclear Information System (INIS)

    Fernandez, J.A.; Freshley, M.D.

    1984-08-01

    This report describes concepts for sealing a nuclear waste repository in an unsaturated tuff environment. The repository site under consideration is Yucca Mountain, which is on and adjacent to the Nevada Test Site. The hydrogeology of Yucca Mountain, preliminary repository concepts, functional requirements and performance criteria for sealing, federal and state regulations, and hydrological calculations are considered in developing the sealing concepts. Water flow through the unsaturated zone is expected to be small and generally vertically downward with some potential to occur through discrete fault and fracture zones. These assumptions are used in developing sealing concepts for shafts, ramps, and boreholes. Sealing of discrete, water-producing faults and fracture zones encountered in horizontal emplacement holes and in access and emplacement drifts is also described. 49 references, 21 figures, 6 tables

  20. The crucial role of nomothetic and idiographic conceptions of time: interdisciplinary collaboration in nuclear waste management.

    Science.gov (United States)

    Moser, Corinne; Stauffacher, Michael; Krütli, Pius; Scholz, Roland W

    2012-01-01

    The disposal of nuclear waste involves extensive time scales. Technical experts consider up to 1 million years for the disposal of spent fuel and high-level waste in their safety assessment. Yet nuclear waste is not only a technical but also a so-called sociotechnical problem and, therefore, requires interdisciplinary collaboration between technical, natural, social sciences, and the humanities in its management. Given that these disciplines differ in their language, epistemics, and interests, such collaboration might be problematic. Based on evidence from cognitive psychology, we suggest that, in particular, a concept like time is presumably critical and can be understood differently. This study explores how different scientific disciplines understand extensive time scales in general and then focuses on nuclear waste. Eighteen qualitative exploratory interviews were conducted with experts for time-related phenomena of different disciplines, among them experts working in nuclear waste management. Analyses revealed two distinct conceptions of time corresponding to idiographic and nomothetic research approaches: scientists from the humanities and social sciences tend to have a more open, undetermined conception of time, whereas natural scientists tend to focus on a more determined conception that includes some undetermined aspects. Our analyses lead to reflections on potential difficulties for interdisciplinary teams in nuclear waste management. We focus on the understanding of the safety assessment, on potential implications for communication between experts from different disciplines (e.g., between experts from the humanities and engineering for risk assessment and risk communication), and we reflect on the roles of different disciplines in nuclear waste management. © 2011 Society for Risk Analysis.

  1. Canada's high-level nuclear waste disposal concept and its evaluation process

    International Nuclear Information System (INIS)

    Sheng, Grant; Shemilt, L.W.

    2004-01-01

    The concept of disposing high-level nuclear waste in granitic rocks in the Canadian Shield, developed by Atomic Energy of Canada Limited (AECL), is anticipated to undergo a national public review within two years. The disposal concept, its documentation, and its process of evaluation, including the role of the public, government and the scientific/engineering community, are summarized. A Technical Advisory Committee (TAC) has provided external peer review of the Program since 1979 and its findings are published in annual reports which are publicly available. (author)

  2. Advanced Nuclear Power Concepts for Human Exploration Missions

    International Nuclear Information System (INIS)

    Robert L. Cataldo; Lee S. Mason

    2000-01-01

    The design reference mission for the National Aeronautics and Space Administration's (NASA's) human mission to Mars supports a philosophy of living off the land in order to reduce crew risk, launch mass, and life-cycle costs associated with logistics resupply to a Mars base. Life-support materials, oxygen, water, and buffer gases, and the crew's ascent-stage propellant would not be brought from Earth but rather manufactured from the Mars atmosphere. The propellants would be made over ∼2 yr, the time between Mars mission launch window opportunities. The production of propellants is very power intensive and depends on type, amount, and time to produce the propellants. Closed-loop life support and food production are also power intensive. With the base having several habitats, a greenhouse, and propellant production capability, total power levels reach well over 125 kW(electric). The most mass-efficient means of satisfying these requirements is through the use of nuclear power. Studies have been performed to identify a potential system concept, described in this paper, using a mobile cart to transport the power system away from the Mars lander and provide adequate separation between the reactor and crew. The studies included an assessment of reactor and power conversion technology options, selection of system and component redundancy, determination of optimum separation distance, and system performance sensitivity to some key operating parameters

  3. Executive summary of safeguards systems concepts for nuclear material transportation. Final report

    International Nuclear Information System (INIS)

    Baldonado, O.C.; Kevany, M.; Rodney, D.; Pitts, D.; Mazur, M.

    1977-09-01

    The U.S. Nuclear Regulatory Commission contracted with System Development Corporation to develop integrated system concepts for the safeguard of special strategic nuclear materials (SSNM), which include plutonium, uranium 233 and uranium 235 of at least 20 percent enrichment, against malevolent action during interfacility transport. This executive summary outlines the conduct and findings of the project. The study was divided into three major subtasks: (1) The development of adversary action sequences; (2) The assessment of the vulnerability of the transport of nuclear materials to adversary action; (3) The development of conceptual safeguards system design requirements to reduce vulnerabilities

  4. Argentinian experience in selecting sites for nuclear power stations

    International Nuclear Information System (INIS)

    Csik, B.J.

    1975-01-01

    One nuclear power station is in operation in the Republic of Argentina, a second is under construction, and the decision to build a third has been taken. According to existing plans, about ten nuclear power stations should go into operation during the next decade. The present paper analyses the experience acquired in selecting sites for the first units, commenting on the criteria and methods applied, the studies that were carried out, the specific problems encountered and the solutions adopted, as well as on the question of acceptance of the chosen sites by the public. It goes on to describe the current programme of selection and study of sites for future nuclear power stations

  5. Theoretical studies on nuclear spin selective quantum dynamics of non-linear molecules; Theoretische Untersuchung zur Quantendynamik der Kernspinisomere nicht-linearer Molekuele

    Energy Technology Data Exchange (ETDEWEB)

    Grohmann, Thomas

    2012-05-31

    In this thesis the wave packet dynamics of nuclear spin isomers of polyatomic molecules after interaction with static and time-dependent magnetic fields and moderate intense nonresonant laser pulses is investigated. In particular, the process of inducing (internal) molecular rotation as well as alignment of molecules by manipulating their rotational or rotational-torsional degrees of freedom is studied. In the first part of the thesis all theoretical concepts for identifying nuclear spin isomers and for describing their quantum dynamics will be discussed. Especially the symmetrization postulate and themolecular symmetry group will be introduced and illustrated for some examples of molecules. These concepts will be extended to the case of identifying nuclear spin isomers in the presence of an external field. In the second part it is shown for nitromethane that magnetic fields are able to induce unidirectional rotations in opposite directions for different nuclear spin isomers of molecules containing methyl groups if the dipolar interaction is included. Additionally, it is demonstrated that different nuclear spin isomers of a chemical compound may show different alignment after the interaction with a moderate intense laser pulse. As shown for the rigid symmetric top propadien and the rigid asymmetric tops ethene and analogues, distinct pairs of nuclear spin isomers show at certain points in time a complementary behavior: while one isomer is showing alignment the partner isomer is showing anti-alignment. Moreover, it is illustrated that not every nuclear spin isomer can be aligned equally efficient. The alignment of non-rigid molecules is considered as well. As an example for a molecule with feasible torsion in the electronic ground state, the alignment of diboron tetrafluoride is investigated. It becomes apparent that not only rotational but also the torsional dynamics of the molecules is nuclear spin selective; different nuclear spin isomers have at distinct points

  6. Nuclear power: accident probabilities, risks, and benefits. A bibliography

    International Nuclear Information System (INIS)

    1976-02-01

    This report is a selected listing of 396 documents pertaining to nuclear accident probability and nuclear risk. Because of the attention focused on these concepts by the recent (August 1974) publication of the draft of WASH-1400, ''Reactor Safety Study,'' it is intended that this bibliography make conveniently available the existence of relevant literature on these concepts. Such an awareness will enhance an understanding of probability and risk as applied to nuclear power plants and is essential to their further development and/or application. This bibliography includes first a listing of the selected documents with abstracts and keywords, followed by three indexes: (1) keyword, (2) author, and (3) permuted title

  7. The users manual and concepts of nuclear materials accounting system

    International Nuclear Information System (INIS)

    Lee, Byung Du; Jeon, In

    1996-03-01

    This report is to describe the concepts, operation status and user's manuals of nuclear materials accounting system which was developed to not only make out, report and manage the IAEA accounting reports but also maintain the accounting information. Therefore, facility operator could effectively make use of the accounting system without a special training by using this report. 3 tabs., 15 figs., (Author) .new

  8. The self-consistent energy system with an enhanced non-proliferated core concept for global nuclear energy utilization

    International Nuclear Information System (INIS)

    Kawashima, Masatoshi; Arie, Kazuo; Araki, Yoshio; Sato, Mitsuyoshi; Mori, Kenji; Nakayama, Yoshiyuki; Nakazono, Ryuichi; Kuroda, Yuji; Ishiguma, Kazuo; Fujii-e, Yoichi

    2008-01-01

    A sustainable nuclear energy system was developed based on the concept of Self-Consistent Nuclear Energy System (SCNES). Our study that trans-uranium (TRU) metallic fuel fast reactor cycle coupled with recycling of five long-lived fission products (LLFP) as well as actinides is the most promising system for the sustainable nuclear utilization. Efficient utilization of uranium-238 through the SCNES concept opens the doors to prolong the lifetime of nuclear energy systems towards several tens of thousand years. Recent evolution of the concept revealed compatibility of fuel sustainability, minor actinide (MA) minimization and non-proliferation aspects for peaceful use of nuclear energy systems through the discussion. As for those TRU compositions stabilized under fast neutron spectra, plutonium isotope fractions are remained in the range of reactor grade classification with high fraction of Pu240 isotope. Recent evolution of the SCNES concept has revealed that TRU recycling can cope with enhancing non-proliferation efforts in peaceful use with the 'no-blanket and multi-zoning core' concept. Therefore, the realization of SCNES is most important. In addition, along the process to the goals, a three-step approach is proposed to solve concurrent problems raised in the LWR systems. We discussed possible roles and contribution to the near future demand along worldwide expansion of LWR capacities by applying the 1st generation SCNES. MA fractions in TRU are more than 10% from LWR discharged fuels and even higher up to 20% in fuels from long interim storages. TRU recycling in the 1st generation SCNES system can reduce the MA fractions down to 4-5% in a few decades. This capability significantly releases 'MA' pressures in down-stream of LWR systems. Current efforts for enhancing capabilities for energy generation by LWR systems are efficient against the global warming crisis. In parallel to those movements, early realization of the SCNES concept can be the most viable decision

  9. Results from the second Galaxy Serpent web-based table top exercise utilizing the concept of nuclear forensics libraries

    International Nuclear Information System (INIS)

    Borgardt, James; Canaday, Jodi; Chamberlain, David

    2017-01-01

    Galaxy Serpent is a unique, virtual, web-based international tabletop series of exercises designed to mature the concept of National Nuclear Forensics Libraries (NNFLs). Teams participating in the second version of the exercise were provided synthetic sealed radioactive source data used to compile a model NNFL which then served as a comparative instrument in hypothetical scenarios involving sources out of regulatory control, allowing teams to successfully down-select and determine whether investigated sources were consistent with holdings in their model library. The methodologies utilized and aggregate results of the exercise will be presented, along with challenges encountered and benefits realized. (author)

  10. Prescriptive concepts for advanced nuclear materials control and accountability systems

    International Nuclear Information System (INIS)

    Whitty, W.J.; Strittmatter, R.B.; Ford, W.; Tisinger, R.M.; Meyer, T.H.

    1987-06-01

    Networking- and distributed-processing hardware and software have the potential of greatly enhancing nuclear materials control and accountability (MC and A) systems, from both safeguards and process operations perspectives, while allowing timely integrated safeguards activities and enhanced computer security at reasonable cost. A hierarchical distributed system is proposed consisting of groups of terminal and instruments in plant production and support areas connected to microprocessors that are connected to either larger microprocessors or minicomputers. These micros and/or minis are connected to a main machine, which might be either a mainframe or a super minicomputer. Data acquisition, preliminary input data validation, and transaction processing occur at the lowest level. Transaction buffering, resource sharing, and selected data processing occur at the intermediate level. The host computer maintains overall control of the data base and provides routine safeguards and security reporting and special safeguards analyses. The research described outlines the distribution of MC and A system requirements in the hierarchical system and distributed processing applied to MC and A. Implications of integrated safeguards and computer security concepts for the distributed system design are discussed. 10 refs., 4 figs

  11. Nuclear propulsion for the space exploration initiative

    International Nuclear Information System (INIS)

    Stanley, M.L.

    1991-01-01

    President Bush's speech of July 20, 1989, outlining a goal to go back to the moon and then Mars initiated the Space Exploration Initiative (SEI). The US Department of Defense (DOD), US Department of Energy (DOE), and NASA have been working together in the planning necessary to initiate a program to develop a nuclear propulsion system. Applications of nuclear technology for in-space transfer of personnel and cargo between Earth orbit and lunar or Martian orbit are being considered as alternatives to chemical propulsion systems. Mission and system concept studies conducted over the past 30 yr have consistently indicated that use of nuclear technology can substantially reduce in-space propellant requirements. A variety of nuclear technology options are currently being studied, including nuclear thermal rockets, nuclear electrical propulsion systems, and hybrid nuclear thermal rockets/nuclear electric propulsion concepts. Concept performance in terms of thrust, weight, power, and efficiency are dependent, and appropriate concept application is mission dependent (i.e., lunar, Mars, cargo, personnel, trajectory, transit time, payload). A comprehensive evaluation of mission application, technology performance capability and maturity, technology development programmatics, and safety characteristics is required to optimize both technology and mission selection to support the Presidential initiative

  12. Research on professional adaptability psychological selection indices of nuclear power plant operators

    International Nuclear Information System (INIS)

    Liu Jingquan; Li Zhe; Li Maoyou

    2010-01-01

    Based on the analysis of the work characteristics of nuclear power plant operators and the comparison of professional psychological selection indices for different occupations, the indices of psychological selection system which is applicable to nuclear power plant operators are proposed in this paper, using the method named 'taking classes,cross-comparison'. The index results of the suggested psychological selection system reflects all the professional requirements on the nuclear power plant operators, which can also be used for the recruitment, training and the retraining programs for operators. (authors)

  13. Robotics and remote handling concepts for disposal of high-level nuclear waste

    International Nuclear Information System (INIS)

    McAffee, Douglas; Raczka, Norman; Schwartztrauber, Keith

    1997-01-01

    This paper summarizes preliminary remote handling and robotic concepts being developed as part of the US Department of Energy's (DOE) Yucca Mountain Project. The DOE is currently evaluating the Yucca Mountain Nevada site for suitability as a possible underground geologic repository for the disposal of high level nuclear waste. The current advanced conceptual design calls for the disposal of more than 12,000 high level nuclear waste packages within a 225 km underground network of tunnels and emplacement drifts. Many of the waste packages may weigh as much as 66 tonnes and measure 1.8 m in diameter and 5.6 m long. The waste packages will emit significant levels of radiation and heat. Therefore, remote handling is a cornerstone of the repository design and operating concepts. This paper discusses potential applications areas for robotics and remote handling technologies within the subsurface repository. It also summarizes the findings of a preliminary technology survey which reviewed available robotic and remote handling technologies developed within the nuclear, mining, rail and industrial robotics and automation industries, and at national laboratories, universities, and related research institutions and government agencies

  14. CONCEPT computer code

    International Nuclear Information System (INIS)

    Delene, J.

    1984-01-01

    CONCEPT is a computer code that will provide conceptual capital investment cost estimates for nuclear and coal-fired power plants. The code can develop an estimate for construction at any point in time. Any unit size within the range of about 400 to 1300 MW electric may be selected. Any of 23 reference site locations across the United States and Canada may be selected. PWR, BWR, and coal-fired plants burning high-sulfur and low-sulfur coal can be estimated. Multiple-unit plants can be estimated. Costs due to escalation/inflation and interest during construction are calculated

  15. Laser enhanced radioactive decay and selective transmutation of nuclear waste

    International Nuclear Information System (INIS)

    Saloman, R.; Aarnio, P.; Ala-Heikkila, J.; Hakola, A.; Santala, M.

    2007-01-01

    We have investigated narrow-band coherent laser radiation - ranging from visible to X- and to gamma-ray wave length region - and their interactions both directly with photon-nuclear couplings and indirectly through the photon-electron and electron-nucleus interactions. In particular we discuss various means of selective excitation of nuclear resonance states by narrowband lasers. During the relaxation process the active nucleus may return to its initial ground-state or find another final state. In the latter case the nucleus is transmuted into a state which may have beneficial properties for instance concerning radioactivity. One ideal case would be the destruction of long-lived nuclear waste isotopes into faster decaying ones. The essential presumption is that the excitation process is selective and efficient as regards background processes due to unwanted excitation channels of the primary isotope and due to other surrounding nuclides. The paper consists of 1) a short review of generating short-wave length coherent light sources, 2) a survey of potential photon-induced nuclear states and their decay channels, and 3) a determination of the selectivity of the transmutation process

  16. Particle bed reactor nuclear rocket concept

    International Nuclear Information System (INIS)

    Ludewig, H.

    1991-01-01

    The particle bed reactor nuclear rocket concept consists of fuel particles (in this case (U,Zr)C with an outer coat of zirconium carbide). These particles are packed in an annular bed surrounded by two frits (porous tubes) forming a fuel element; the outer one being a cold frit, the inner one being a hot frit. The fuel element are cooled by hydrogen passing in through the moderator. These elements are assembled in a reactor assembly in a hexagonal pattern. The reactor can be either reflected or not, depending on the design, and either 19 or 37 elements, are used. Propellant enters in the top, passes through the moderator fuel element and out through the nozzle. Beryllium used for the moderator in this particular design to withstand the high radiation exposure implied by the long run times

  17. From conception to decommissioning-servicing nuclear power

    International Nuclear Information System (INIS)

    Burbridge, R.N.

    1988-01-01

    In any utility, or integrated group of utilities, there is a need for an identified body charged with being the guardians of the design database. This is essential with nuclear stations. Within the CEGB (Central Electricity Generating Board), the Generation Development and Construction Division (GDCD) acts as that guardian and performs the triple role of Client (specifying the requirements and procuring new stations), of Architect-Engineer (defining systems and plant layouts and performing effective project management), and of Consultant (for servicing operating stations). Long-term plant developments are pursued until they can be securely incorporated into station proposals. Planning Inquiries for new stations are supported technically until the proposed station is approved and the proposal becomes a project which is managed to be completed on programme and within budget to the required standards. Once complete and commissioned, the station is handed over to the operators and the designers and constructors take on their role of Independent Assessors of proposed design changes. At the end of its life, the decommissioning of the station becomes another project requiring effective management. Nuclear power requires servicing from conception to decommissioning. 1 fig

  18. 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.

  19. 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

  20. Nuclear steelmaking in Europe

    International Nuclear Information System (INIS)

    Barnes, R.S.

    1975-01-01

    The European Nuclear Steelmaking Club has decided initially to pursue the concept of a steel works separated from the nuclear reactor generating the gases needed for reducing the iron ore. The energy requirements for the various alternative process routes and the issues involved in the selection of the optimum reforming temperature are discussed, taking into account the availability of the various hydrocarbon feedstocks within Europe. A scenario for the eventual introduction of nuclear steelmaking is outlined. (author)

  1. NN-Es Fault Diagnosis Method in Nuclear Power Equipment Based on Concept Lattice

    International Nuclear Information System (INIS)

    Liu Yongkuo; Xie Chunli; Xia Hong

    2010-01-01

    In order to improve the fault diagnosis accuracy of nuclear power plant,neural network and expert systems were combined to give full play to their advantages. In this paper, the concept lattice was applied to get the object properties, extracting the core attributes, dispensable attributes and relative necessary attributes from a large number raw data of fault symptoms.Based on these attributes, neural networks with different levels of importance were designed to improve the learning speed and diagnosis accuracy, and the diagnosis results of the neural networks were verified by using rule-based reasoning expert system. To verify the accuracy of this method, some simulation experiments about the typical faults of nuclear power plant were conducted. And the simulation results show that it is feasible to diagnose nuclear power plant faults with the confederation diagnosis methods combined the neural networks based on the concept lattice theory and expert system, with the distinctive features such as the efficiency of neural network learning, less calculation and reliability of diagnosis results and so on. (authors)

  2. The risks of nuclear energy technology. Safety concepts of light water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Raskob, Wolfgang; Landman, Claudia; Paesler-Sauer, Juergen [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Inst. fuer Kern- und Energietechnk (IKET); Kessler, Guenter; Veser, Anke; Schlueter, Franz-Hermann

    2014-11-01

    Analyses the risks of nuclear power stations. Discusses the security concept of reactors. Analyzes possible crash of air planes on a reactor containment. Presents measures against the spread of radioactivity after a severe accident. Written in engaging style for professionals and policy makers. The book analyses the risks of nuclear power stations. The security concept of reactors is explained. Measures against the spread of radioactivity after a severe accident, accidents of core melting and a possible crash of an air plane on a reactor containment are discussed. The book covers three scientific subjects of the safety concepts of Light Water Reactors: - A first part describes the basic safety design concepts of operating German Pressurized Water Reactors and Boiling Water Reactors including accident management measures introduced after the reactor accidents of Three Mile Island and Chernobyl. These safety concepts are also compared with the experiences of the Fukushima accidents. In addition, the safety design concepts of the future modern European Pressurized Water Reactor (EPR) and of the future modern Boiling Water Reactor SWR-1000 (KERENA) are presented. These are based on new safety research results of the past decades. - In a second, part the possible crash of military or heavy commercial air planes on a reactor containment is analyzed. It is shown that reactor containments can be designed to resist to such an airplane crash. - In a third part, an online decision system is presented. It allows to analyze the distribution of radioactivity in the atmosphere and to the environment after a severe reactor accident. It provides data for decisions to be taken by authorities for the minimization of radiobiological effects to the population. This book appeals to readers who have an interest in save living conditions and some understanding for physics or engineering.

  3. Use of computer simulations for the early introduction of nuclear engineering concepts

    International Nuclear Information System (INIS)

    Ougouag, A.M.; Zerguini, T.H.

    1985-01-01

    A sophomore level nuclear engineering (NE) course is being introduced at the University of Illinois. Via computer simulations, this course presents materials covering the most important aspects of the field. It is noted that computer simulations in nuclear engineering are cheaper and safer than experiments yet they provide an effective teaching tool for the early introduction of advanced concepts. The new course material can be used as a tutorial and for remedial learning. The use of computer simulation motivates learning since students associate computer activities with games. Such a course can help in the dissemination of the proper information to students from different fields, including liberal arts, and eventually increase undergraduate student enrollment in nuclear engineering

  4. Concept of a computer network architecture for complete automation of nuclear power plants

    International Nuclear Information System (INIS)

    Edwards, R.M.; Ray, A.

    1990-01-01

    The state of the art in automation of nuclear power plants has been largely limited to computerized data acquisition, monitoring, display, and recording of process signals. Complete automation of nuclear power plants, which would include plant operations, control, and management, fault diagnosis, and system reconfiguration with efficient and reliable man/machine interactions, has been projected as a realistic goal. This paper presents the concept of a computer network architecture that would use a high-speed optical data highway to integrate diverse, interacting, and spatially distributed functions that are essential for a fully automated nuclear power plant

  5. Quality assurance considerations for nuclear power system selection

    International Nuclear Information System (INIS)

    Bender, M.

    1977-01-01

    The key quality assurance principle to be applied in nuclear system selection is to establish that the technological basis is understood and used properly. Knowledgeable and capable personnel with experience in the application are needed, and they must have access to appropriate engineering, laboratory, and manufacturing facilities. A suitable balance must be maintained between the responsibilities of the seller-supplier and the purchaser-owner to assure an even-handed treatment of the implementation program. Safety and reliability must be inherent to the regulatory framework. There must be flexibility in the purchaser-owner resources to overcome unanticipated adversity. Given these quality assurance elements, the nuclear system selection process should result in a high probability that the performance objectives will be satisfied

  6. The evolution of the break preclusion concept for nuclear power plants in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Koeln (Germany)

    1997-04-01

    In the updating of the Guidelines for PWR`s of the {open_quotes}Reaktor-Sicherheitskommission{close_quotes} (RSK) in 1981 the requirements on the design have been changed with respect to the postulated leaks and breaks in the primary pressure boundary. The major change was a revision in the requirements for pipe whip protection. As a logical consequence of the {open_quotes}concept of basic safety{close_quotes} a guillotine type break or any other break type resulting in a large opening is not postulated any longer for the calculation of reaction and jet forces. As an upper limit for a leak an area of 0, 1 A (A = open cross section of the pipe) is postulated. This decision was based on a general assessment of the present PWR system design in Germany. Since then a number of piping systems have been requalified in the older nuclear power plants to comply with the break preclusion concept. Also a number of extensions of the concept have been developed to cover also leak-assumptions for branch pipes. Furthermore due considerations have been given to other aspects which could contribute to a leak development in the primary circuit, like vessel penetrations, manhole covers, flanges, etc. Now the break preclusion concept originally applied to the main piping has been developed into an integrated concept for the whole pressure boundary within the containment and will be applied also in the periodic safety review of present nuclear power plants.

  7. Selection of candidate container materials for the conceptual waste package design for a potential high level nuclear waste repository at Yucca Mountain

    Energy Technology Data Exchange (ETDEWEB)

    Van Konynenburg, R.A.; Halsey, W.G.; McCright, R.D.; Clarke, W.L. Jr. [Lawrence Livermore National Lab., CA (United States); Gdowski, G.E. [KMI, Inc., Albuquerque, NM (United States)

    1993-02-01

    Preliminary selection criteria have been developed, peer-reviewed, and applied to a field of 41 candidate materials to choose three alloys for further consideration during the advanced conceptual design phase of waste package development for a potential high level nuclear waste repository at Yucca Mountain, Nevada. These three alloys are titanium grade 12, Alloy C-4, and Alloy 825. These selections are specific to the particular conceptual design outlined in the Site Characterization Plan. Other design concepts that may be considered in the advanced conceptual design phase may favor other materials choices.

  8. Selection of candidate container materials for the conceptual waste package design for a potential high level nuclear waste repository at Yucca Mountain

    International Nuclear Information System (INIS)

    Van Konynenburg, R.A.; Halsey, W.G.; McCright, R.D.; Clarke, W.L. Jr.; Gdowski, G.E.

    1993-02-01

    Preliminary selection criteria have been developed, peer-reviewed, and applied to a field of 41 candidate materials to choose three alloys for further consideration during the advanced conceptual design phase of waste package development for a potential high level nuclear waste repository at Yucca Mountain, Nevada. These three alloys are titanium grade 12, Alloy C-4, and Alloy 825. These selections are specific to the particular conceptual design outlined in the Site Characterization Plan. Other design concepts that may be considered in the advanced conceptual design phase may favor other materials choices

  9. Essentials of nuclear chemistry

    International Nuclear Information System (INIS)

    Arniker, H.J.

    1982-01-01

    Theories of nuclear structure, stability, and radioactivity; nuclear reactions including fission, fusion, and reactors; and the applications of radioactivity, are covered. A non-mathematical treatment of the higher concepts are presented. The use of SI units, with cgs equivalents and ample clarifications in the form of worked examples; original examples investigated by the author in the applications of radioactivity; and selected problems are included

  10. Concept selection of car bumper beam with developed hybrid bio-composite material

    International Nuclear Information System (INIS)

    Davoodi, M.M.; Sapuan, S.M.; Ahmad, D.; Aidy, A.; Khalina, A.; Jonoobi, Mehdi

    2011-01-01

    Highlights: → We simulate the low impact test by Abaqus Ver16R9 using the same material model. → Six different weighted criteria were discussed to nominate the best concept. → Double Hat Profile showed the best concept to fulfil the defined PDS. → Geometric parameters may overcome the weak inherent properties of bio composite. → Toughened bio-composite material may employ in structural automotive components. -- Abstract: Application of natural fibre composites is going to increase in different areas caused by environmental, technical and economic advantages. However, their low mechanical properties have limited their particular application in automotive structural components. Hybridizations with other reinforcements or matrices can improve mechanical properties of natural fibre composite. Moreover, geometric optimizations have a significant role in structural strength improvement. This study focused on selecting the best geometrical bumper beam concept to fulfill the safety parameters of the defined product design specification (PDS). The mechanical properties of developed hybrid composite material were considered in different bumper beam concepts with the same frontal curvature, thickness, and overall dimensions. The low-speed impact test was simulated under the same conditions in Abaqus V16R9 software. Six weighted criteria, which were deflection, strain energy, mass, cost, easy manufacturing, and the rib possibility were analyzed to form an evaluation matrix. Topsis method was employed to select the best concept. It is concluded that double hat profile (DHP) with defined material model can be used for bumper beam of a small car. In addition, selected concept can be strengthened by adding reinforced ribs or increasing the thickness of the bumper beam to comply with the defined PDS.

  11. Selection, qualification and training of personnel for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This standard provides criteria for the selection, qualification and training of personnel for stationary nuclear power plants. Qualifications, responsibilities, and training of personnel in operating and support organizations appropriate for the safe and efficient operation of nuclear power plants are addressed

  12. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Nuttall, K.

    1987-01-01

    Canada has established an extensive research program to develop and demonstrate the technology for safely disposing of nuclear fuel waste from Canadian nuclear electric generating stations. The program focuses on the concept of disposal deep in plutonic rock, which is abundant in the province of Ontario, Canada's major producer of nuclear electricity. Research is carried out at field research areas in the Canadian Precambrian Shield, and in government and university laboratories. The schedule calls for a document assessing the disposal concept to be submitted to regulatory and environmental agencies in late 1988. This document will form the basis for a review of the concept by these agencies and by the public. No site selection will be carried out before this review is completed. 10 refs.; 2 figs

  13. Site selection and evaluation of nuclear power units in Egypt

    International Nuclear Information System (INIS)

    Bonnefille, R.

    1980-01-01

    The selection of sites for nuclear power units in Egypt by SOFRATOME for Nuclear Plants Authority is carried on using a method based on interaction between different criteria. The method and the main results on criterion 'radio-ecological impact' are sketched briefly [fr

  14. The design features and safety concepts of the nuclear heating reactor developed in China

    International Nuclear Information System (INIS)

    Zheng Wenxiang; Wang Dazhong

    1995-01-01

    Based on the specific conditions of the nuclear heat applications and the development objectives of the advanced reactors, the nuclear heating reactor (NHR) exploited in China has adhered to the new safety concepts and been designed with a number of advanced features, including the integrated arrangement, full power natural circulation capacity, self-pressurized performance, dynamically-hydraulic control rod drive and passive safety systems, so that higher standard of safety as well as simplification in the plant systems and improvement in economic viability has been achieved. This paper describes the special consideration in the design as well as the main design features and safety concepts of the NHR. Some experimental and analytical results are also presented to demonstrate the NHR safety features

  15. Concept and structure of instrumentation and control of the Atucha II nuclear power plant

    International Nuclear Information System (INIS)

    Garzon, D.; Roca, J.L.

    1987-01-01

    The general structure of instrumentation and control of Atucha II nuclear power plant as well as the technologies used, are described: concepts of functional decentralization and physical centralization; concept of functional group and functional complex; description of the technologies used (physical support) in the project of plant instrumentation and control; description of the different automation levels on the basis of concepts of control interface, automatism, regulation, group and subgroup controls; principles of signal conditioning; concept of announcement of alarms and state: supervisory computer, description of HAS (Hard wired Alarm System) and CAS (Computer Alarm System); application of the above mentioned structure to the project of another type of plants. (Author)

  16. Remotex: a new concept for efficient remote operation and maintenance in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Feldman, M.J.; White, J.R.

    1980-01-01

    Remotex is a concept of remote operation and maintenance that utilizes advanced manipulator design to improve plant operating efficiency, reduce personnel exposure, and improve safeguards and diversion resistance. It is a concept developed over the past two years in the conceptual design of the Hot Experimental Facility (HEF), a mechanically intense pilot plant facility designed to demonstrate reprocessng technology for early US breeder demonstration reactors. The Remotex concept is directly applicable to all segments of nuclear and nonnuclear industries where work tasks or conditions exist that are hazardous to the health of man

  17. Summary of International Waste Management Programs (LLNL Input to SNL L3 MS: System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW)

    Energy Technology Data Exchange (ETDEWEB)

    Greenberg, Harris R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Blink, James A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Halsey, William G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sutton, Mark [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2011-08-11

    The Used Fuel Disposition Campaign (UFDC) within the Department of Energy’s Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation’s spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. This Lessons Learned task is part of a multi-laboratory effort, with this LLNL report providing input to a Level 3 SNL milestone (System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW). The work package number is: FTLL11UF0328; the work package title is: Technical Bases / Lessons Learned; the milestone number is: M41UF032802; and the milestone title is: “LLNL Input to SNL L3 MS: System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW”. The system-wide integration effort will integrate all aspects of waste management and disposal, integrating the waste generators, interim storage, transportation, and ultimate disposal at a repository site. The review of international experience in these areas is required to support future studies that address all of these components in an integrated manner. Note that this report is a snapshot of nuclear power infrastructure and international waste management programs that is current as of August 2011, with one notable exception. No attempt has been made to discuss the currently evolving world-wide response to the tragic consequences of the earthquake and tsunami that devastated Japan on March 11, 2011, leaving more than 15,000 people dead and more than 8,000 people missing, and severely damaging the Fukushima Daiichi nuclear power complex. Continuing efforts in FY 2012 will update the data, and summarize it in an Excel spreadsheet for easy comparison and assist in the knowledge management of the study cases.

  18. Nuclear power plant site selection: a case study

    International Nuclear Information System (INIS)

    Lugasi, Y.; Mehrez, A.; Sinuany-Stern, Z.

    1985-01-01

    Selecting the site for a nuclear power plant involves the evaluation of numerous criteria and the professional judgment of various experts. The Israel Atomic Energy Commission has been concerned with the problem of selecting a site for a nuclear power station. Previous studies have been performed by the commission to identify potential sites. There were initial screenings where potential sites were chosen according to various minimal criteria and international standards. Only sites that met all the criteria were chosen. A study was made to find the most preferred site among the potential sites that met all the criteria. Two mathematical approaches were used: Keeney's multiattribute utility function and Saaty's eigenvalue prioritization technique. Both models ranked the same site as the most desirable; however, the models differed in their ranking of the other sites

  19. Evaluation of the Ventilation and Air Cleaning System Design Concepts for Safety Requirements during Fire Conditions in Nuclear Applications

    International Nuclear Information System (INIS)

    Rashad, S.; El-Fawal, M.; Kandil, M.

    2013-01-01

    evaluates different design concepts or approaches for the ventilation and air cleaning system (VACS) that can be used to achieve safety and adequate protection in nuclear applications facilities during fire and accidental criticality conditions. Various anticipated events or accidents causing hazards in nuclear fuel cycle facilities, e.g. routine hazards, fires, accidental criticality and iodine release have been reviewed and discussed. Also it describes the possible fire protection approaches with their functional classifications and their engineered and administrative safety features. Finally a conclusion on the selection of the best design concept is recommended.

  20. Nuclear synergism of the light elements

    International Nuclear Information System (INIS)

    Harms, A.A.

    1983-05-01

    Some basic issues concerning accelerator initiated and fusion sustained nuclear energy systems are examined. For this purpose we identify selected nuclear fusion reactions characterized by a variable ion-to-neutron content and explore their intrinsic couplings and regenerative features. These are then related to particular systems concepts which emphasize fusion physics and accelerator technology. It is concluded that several light-element reaction systems possess appealing and interesting properties and can further be associated with selected advanced nuclear technologies. Their eventual implementation as nuclear energy systems requires further research in fusion physics, accelerator technology and mathematical physics. Because of the substantial potential benefits of such nuclear energy systems, it is concluded that research in this area should be pursued with much vigour. (orig.)

  1. Nuclear safeguards control in nuclear power stations

    International Nuclear Information System (INIS)

    Boedege, R.; Braatz, U.; Heger, H.

    1976-01-01

    The execution of the Non-Proliferation Treaty (NPT) has initiated a third phase in the efforts taken to ensure peace by limiting the number of atomic powers. In this phase it is important, above all, to turn into workable systems the conditions imposed upon technology by the different provisions of the Verification Agreement of the NPT. This is achieved mainly by elaborating annexes to the Agreement specifically geared to certain model plants, typical representatives selected for LWR power stations being the plants at Garigliano, Italy (BWR), and Stade, Federal Republic of Germany (PWR). The surveillance measures taken to prevent any diversion of special nuclear material for purposes of nuclear weapons manufacture must be effective in achieving their specific objective and must not impede the circumspect management of operations of the plants concerned. A VDEW working party has studied the technical details of the planned surveillance measures in nuclear power stations in the Federal Republic of Germany and now presents a concept of material balancing by units which meets the conditions imposed by the inspection authority and could also be accepted by the operators of nuclear power stations. The concept provides for uninterrupted control of the material balance areas of the nuclear power stations concerned, allows continuous control of the whole nuclear fuel cycle, is based exclusively on existing methods and facilities, and can be implemented at low cost. (orig.) [de

  2. Interval-valued intuitionistic fuzzy multi-criteria model for design concept selection

    Directory of Open Access Journals (Sweden)

    Daniel Osezua Aikhuele

    2017-09-01

    Full Text Available This paper presents a new approach for design concept selection by using an integrated Fuzzy Analytical Hierarchy Process (FAHP and an Interval-valued intuitionistic fuzzy modified TOP-SIS (IVIF-modified TOPSIS model. The integrated model which uses the improved score func-tion and a weighted normalized Euclidean distance method for the calculation of the separation measures of alternatives from the positive and negative intuitionistic ideal solutions provides a new approach for the computation of intuitionistic fuzzy ideal solutions. The results of the two approaches are integrated using a reflection defuzzification integration formula. To ensure the feasibility and the rationality of the integrated model, the method is successfully applied for eval-uating and selecting some design related problems including a real-life case study for the selec-tion of the best concept design for a new printed-circuit-board (PCB and for a hypothetical ex-ample. The model which provides a novel alternative, has been compared with similar computa-tional methods in the literature.

  3. Scientific-technical cooperation with foreign (esp. Europe and INSC partner countries) nuclear regulatory authorities and their technical support organizations in the fields of nuclear safety of operating nuclear power plants and on the concept evaluation of generation 3+ plants. Final report

    International Nuclear Information System (INIS)

    Wolff, Holger

    2016-09-01

    The BMUB/BfS-Project 3614I01512 forms the frame of the GRS for the scientific-technical cooperation with Technical Support Organisations and Nuclear Regulatory Authorities in the field of nuclear safety in operating NPPs and for the concept evaluation of generation 3 + plants in Europe and INSC Partner Countries. In the present final project report results are described which were gained within the project duration 15.10.2014 up to the 30.09.2016 in the following working packages: Investigations following the catastrophe of Fukushima Daiichi, Evaluation of selected National Action Plans, DBA and severe accident analyses for NPP with PWR (WWER-440, WWER-1000), cooperation with INSC partner countries on DBA, BDBA and severe accident analyses for WWER plants of generation 3 + and building NRA and safety evaluation capacities and decommissioning of nuclear facilities and disposal of radioactive waste. The results are preceded by an outline on the activities related to the project management and to the planning of the bilateral work.

  4. Concept of automated system for spent fuel utilization ('Reburning') from compact nuclear reactors

    International Nuclear Information System (INIS)

    Ianovski, V.V.; Lozhkin, O.V.; Nesterov, M.M.; Tarasov, N.A.; Uvarov, V.I.

    1997-01-01

    On the basic concept of an automated system of nuclear power installation safety is developed the utilization project of spent fuel from compact nuclear reactors. The main features of this project are: 1. design and creation of the mobile model-industrial installation; 2. development of the utilization and storage diagram of the spent fuel from compact nuclear reactors, with the specific recommendation for the natatorial means using both for the nuclear fuel reburning, for its transportation in places of the storage; 3. research of an opportunity during the utilization process to obtain additional power resources, ozone and others to increase of justifying expenses at the utilization; 4. creation of new generation engineering for the automation of remote control processes in the high radiation background conditions. 7 refs., 1 fig

  5. Nuclear Power Plant project site selection geotechnical considerations

    International Nuclear Information System (INIS)

    Katti, V.J.; Banerjee, D.C.

    1997-01-01

    During the selection of a site for Nuclear Power Plant (NPP) and Radioactive Waste Plant (RWP), geotechnical investigations play a significant role in deciding merits and demerits of the sites. Any accidents in these units can play havoc on mankind and may leave bitter imprints on generations to come. Hence proper care has to be taken at the early stage for selecting the sites. Site selection procedure is a complicated one, because it involves experts from various disciplines like geology, geophysics, civil, mechanical electrical engineering, health-physics and other fields

  6. Technical concepts of further improvement of nuclear power plant safety

    International Nuclear Information System (INIS)

    Sochor, R.

    1983-01-01

    The following technical concepts are described which secure the integrity of the containment in case of an accident whose scale exceeds the so-called design basis accident: siting nuclear power plants underground which raises construction costs by 20 - 25%; completing the containment with equipment preventing the outflow of molten corium; completing the containment with emergency pressure space for discharging overpressure - this emergency space is filled with gravel which will trap approximately 50% of fission waste. (Ha)

  7. Nuclear thermal propulsion transportation systems for lunar/Mars exploration

    International Nuclear Information System (INIS)

    Clark, J.S.; Borowski, S.K.; Mcilwain, M.C.; Pellaccio, D.G.

    1992-09-01

    Nuclear thermal propulsion technology development is underway at NASA and DoE for Space Exploration Initiative (SEI) missions to Mars, with initial near-earth flights to validate flight readiness. Several reactor concepts are being considered for these missions, and important selection criteria will be evaluated before final selection of a system. These criteria include: safety and reliability, technical risk, cost, and performance, in that order. Of the concepts evaluated to date, the Nuclear Engine for Rocket Vehicle Applications (NERVA) derivative (NDR) is the only concept that has demonstrated full power, life, and performance in actual reactor tests. Other concepts will require significant design work and must demonstrate proof-of-concept. Technical risk, and hence, development cost should therefore be lowest for the concept, and the NDR concept is currently being considered for the initial SEI missions. As lighter weight, higher performance systems are developed and validated, including appropriate safety and astronaut-rating requirements, they will be considered to support future SEI application. A space transportation system using a modular nuclear thermal rocket (NTR) system for lunar and Mars missions is expected to result in significant life cycle cost savings. Finally, several key issues remain for NTR's, including public acceptance and operational issues. Nonetheless, NTR's are believed to be the next generation of space propulsion systems - the key to space exploration

  8. Concept of assistance of the Federal Office for Rdiation Protection with regard to serious cases of prevention of nuclear hazards

    International Nuclear Information System (INIS)

    Becker, D.E.

    1998-01-01

    For the defence against the threats through radioactive substances, a general concept is presently being elaborated under the overall control of the Federal Government. A number of competent organisations are involved in this, for example the Federal Office of Criminal Investigation, the Federal Armed Forces, and the Federal Office for Radiation Protection. In Germany, the 16 Federal States are responsible for the prevention of nuclear hazards. In the case of hazards through radioactive material, experts from the competent radiation protection authorities are consulted. For serious cases of prevention of nuclear hazards (nuclear fuels, criticality, danger of dispersion), the Federal Office for Radiation Protection - a subordinate authority of the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety responsible for radiation protection - was given order to elaborate a concept for assistance to those Federal States. This concept is presented in the following. (author)

  9. Defense nuclear energy systems selection methodology for civil nuclear power applications

    International Nuclear Information System (INIS)

    Scarborough, J.C.

    1986-01-01

    A methodology developed to select a preferred nuclear power system for a US Department of Defense (DOD) application has been used to evaluate preferred nuclear power systems for a remote island community in Southeast Asia. The plant would provide ∼10 MW of electric power, possibly low-temperature process heat for the local community, and would supplement existing island diesel electric capacity. The nuclear power system evaluation procedure was evolved from a disciplined methodology for ranking ten nuclear power designs under joint development by the US Department of Energy (DOE) and DOD. These included six designs proposed by industry for the Secure Military Power Plant Program (now termed Multimegawatt Terrestrial Reactor Program), the SP-100 Program, the North Warning System Program, and the Modular Advanced High-Temperature Gas-Cooled Reactor (HTGR) and Liquid-Metal Reactor (LMR) programs. The 15 evaluation criteria established for the civil application were generally similar to those developed and used for the defense energy systems evaluation, except that the weighting factor applied to each individual criterion differed. The criteria and their weighting (importance) functions for the civil application are described

  10. SP-100 space nuclear power system

    International Nuclear Information System (INIS)

    Given, R.W.; Morgan, R.E.; Chi, J.W.H.; Westinghouse Electric Corp., Madison, PA)

    1984-01-01

    A baseline design concept for a 100 kWe nuclear reactor space power system is described. The concept was developed under contract from JPL as part of a joint program of the DOE, DOD, and NASA. The major technical and safety constraints influencing the selection of reactor operating parameters are discussed. A lithium-cooled compact fast reactor was selected as the best candidate system. The material selected for the thermoelectric conversion system was silicon germanium (SiGe) with gallium phosphide doping. Attention is given to the improved safety of the seven in-core control rod configuration

  11. Selected aspects of fusion reactions

    International Nuclear Information System (INIS)

    Lacroix, D.

    2003-01-01

    In this lecture, we present selected aspects of nuclear fusion. The importance of the initial geometry of the reaction and its relation to fusion barrier are first discussed. The effect of deformation leading to the notion of barrier distribution is then illustrated. After a brief overview of the advantages of macroscopic theories, the dynamics of nuclear system under large amplitude motion is reviewed. The di-nuclear concept is presented to understand the competition between fusion and quasi-fission. This concept is then generalized to account for the dissipative dynamics in multidimensional collective space. The last part of this lecture is devoted to new aspects encountered with radioactive beams specific properties of very extended neutron rich system, influence of pygmy or soft dipole resonances and charge exchange far from stability are discussed. (author)

  12. International meeting 'Selected topics on nuclear methods for non-nuclear applications'. Proceedings

    International Nuclear Information System (INIS)

    Stoyanov, Ch.

    2007-01-01

    The volume includes the presentations given on the International Meeting 'Selected Topics on Nuclear Methods for Non-nuclear Applications'. The meeting was organized by the Project CECOA. The Project 'CEnter for COoerative Activities' (CECOA) of the Institute for Nuclear Research and Nuclear Energy (INRNE) of Bulgarian Academy of Sciences is part of the Program 'Creating of Infrastructure' of Bulgarian Ministry of Science and Education. The CECOA-project unifies the groups of INRNE doing research in the field of nuclear methods. Four Laboratories of INRNE are members of CECOA-project: Moessbauer Spectroscopy and Low Radioactivity Measurements, High-Resolution Gamma-Spectroscopy, Neutron Methods in Condensed Matter, Neutron Optics and Structure Analysis. Taking into account the leading role of education on nuclear physics the Project includes program devoted to the training on nuclear physics. The presented volume contains 23 contributed papers. The contributions are separated in 6 sections. The section 'Nano technology' includes 5 papers. The activity in this field within the Project reveals the collaboration with other Institutes of Bulgarian Academy of Sciences as well as large international contacts. The section 'Radioecology and Radioactive Waste' is two fold. Part of the contributions of the section manifests the connection of the CECOA with small enterprises. The contacts are on the level of common projects concerning the investigations, remediation and release of radioactively contaminated terrain, soils, water, buildings and materials around the former uranium processing industry. Another part of the section is devoted to the application of nuclear methods to the treatment of radioactive waste produced by nuclear power stations. The section 'Neutron Physics' reveals the activity within the Project connected with the study of new materials using polarized neutrons and neutron diffraction methods. The section 'Nuclear Physics' is an introduction to some

  13. MITEE: A new nuclear engine concept for ultra fast, lightweight solar system exploration missions

    Science.gov (United States)

    Powell, James; Paniagua, John; Ludewig, Hans; Maise, George; Todosow, Michael

    1998-01-01

    A new ultra compact nuclear engine concept, MITEE (MIniature R_eactor E_nginE_), is described, and its performance evaluated for various solar system exploration missions. The MITEE concept is based on the Particle Bed Reactor (PBR), with modifications that enable a smaller, lighter nuclear engine. A range of MITEE Engine designs is described. Representative design parameters for the baseline MITEE reactor are: 75MW(th) power level, 1000 second Isp, 100 kilogram mass, 10 MW/Liter fuel element power density, 39 cm core diameter/height. Total engine mass, including turbo pump assembly, nozzles, controls, and contingency, is estimated to be 200 kilograms. Using the MITEE engine, ultra fast, lightweight solar system exploration missions are enabled. A range of such missions has been analyzed using the MULIMP code, and are described.

  14. Selected articles translated from Jadernye Konstanty (Nuclear Constants) volume 1, 1996

    International Nuclear Information System (INIS)

    1997-08-01

    This report contains selected articles translated from Jedernye Konstanty (Nuclear Constants). Eight papers are included and each one is separately indexed. Nuclear data libraries, Neutron Reactions, Low energy Photofission etc. are dealt with. Refs, figs, tabs

  15. Recent advances and design options of the aseismic bearing pad concept for reduction of seismic loading

    International Nuclear Information System (INIS)

    Vaidya, N.R.; Musacchio, J.M.; Rizzo, P.C.

    1985-01-01

    The intent of this paper is to: briefly review the developed concepts from a mechanics standpoint; summarize the results of recent testing and applications; discuss the complexities and subtleties of differences between concepts, and highlight the effectiveness of each within selected frequency ranges. On this basis, the paper will provide a forum for application of each concept within the nuclear design community. The potential licensing implications of incorporating the ABP concept into nuclear plant design are be discussed in light of actual experience extrapolated to several dominant regulatory processes; namely the French, German, Japanese, Canadian and American. The intent is to identify potential licensing issues, spur additional research and development in these areas, and continue to bring the concept to the attention of the nuclear community to facilitate acceptance and application. (orig./HP)

  16. Selecting of key safety parameters in reactor nuclear safety supervision

    International Nuclear Information System (INIS)

    He Fan; Yu Hong

    2014-01-01

    The safety parameters indicate the operational states and safety of research reactor are the basis of nuclear safety supervision institution to carry out effective supervision to nuclear facilities. In this paper, the selecting of key safety parameters presented by the research reactor operating unit to National Nuclear Safety Administration that can express the research reactor operational states and safety when operational occurrence or nuclear accident happens, and the interrelationship between them are discussed. Analysis shows that, the key parameters to nuclear safety supervision of research reactor including design limits, operational limits and conditions, safety system settings, safety limits, acceptable limits and emergency action level etc. (authors)

  17. Fast nuclear reactors. Associated international projects. State of the art and assessment of the concepts

    International Nuclear Information System (INIS)

    Azpitarte, O.; Ramilo, L.

    2013-01-01

    The recognition of the strategic importance of nuclear energy as a source of sustainable energy may be perceived in the continuous development, in many countries, of the technology of fast nuclear reactors with an associated closed fuel cycle, assuming that these Generation IV innovative systems will be required in the future. These reactors fulfill international requirements for safety and reliability, economic competitiveness, sustainability and proliferation resistance. They have the potential of using more efficiently the natural resources of Uranium and of reducing the volume and radiotoxicity of the nuclear waste by partitioning and transmutation of Minor Actinides. The national and international programs being carried out today are concentrated in the following concepts: Sodium Fast Reactor (SFR), Lead Fast Reactor (LFR), Gas Fast Reactor (GFR), Super Critical Water Reactor (SCWR) and Molten Salt Reactor (MSR). This article presents a short review of the technology of the mentioned concepts and details the current state of the main national and international related projects. (author)

  18. Proposal on experience learning of a nuclear reactor for children in future. A basic concept on a nuclear reactor facility for demonstration and education

    International Nuclear Information System (INIS)

    Murata, Takashi; Yoshiki, Nobuya; Kinehara, Yoshiki; Nakagawa, Haruo

    2001-01-01

    The Science Council of Japan indicates in a proposal on R and D on nuclear energy forward the 21st Century that it is important to expand the educational object on nuclear energy from colleges and gradual schools to elementary, middle high schools. And, the Committee of Japan Nuclear Energy Industries also proposed that as an effort forward security of reliability and popularization of knowledge, completeness of learning chance on energy and nuclear energy in education such as usage of general learning time, concept on establishment of educational reactor for demonstration and experience, is essential. Here was described on a concept on establishment of nuclear reactor for demonstration and experience at objectives of common national peoples, which was based on results of searches and investigations carried out by authors and aimed to supply to a field to grow up a literary adequately and widely capable of judging various information on the peoples by focusing to effectiveness of empirical learning as a method of promoting corrective understanding of common citizens on high class technical system and by establishment of the reactor aiming at general education on nuclear energy at a place easily accessible by common citizens, such as large city. (G.K.)

  19. Proposal on experience learning of a nuclear reactor for children in future. A basic concept on a nuclear reactor facility for demonstration and education

    Energy Technology Data Exchange (ETDEWEB)

    Murata, Takashi [Kyoto Univ., Graduate School of Energy Science, Kyoto (Japan); Yoshiki, Nobuya; Kinehara, Yoshiki; Nakagawa, Haruo

    2001-12-01

    The Science Council of Japan indicates in a proposal on R and D on nuclear energy forward the 21st Century that it is important to expand the educational object on nuclear energy from colleges and gradual schools to elementary, middle high schools. And, the Committee of Japan Nuclear Energy Industries also proposed that as an effort forward security of reliability and popularization of knowledge, completeness of learning chance on energy and nuclear energy in education such as usage of general learning time, concept on establishment of educational reactor for demonstration and experience, is essential. Here was described on a concept on establishment of nuclear reactor for demonstration and experience at objectives of common national peoples, which was based on results of searches and investigations carried out by authors and aimed to supply to a field to grow up a literary adequately and widely capable of judging various information on the peoples by focusing to effectiveness of empirical learning as a method of promoting corrective understanding of common citizens on high class technical system and by establishment of the reactor aiming at general education on nuclear energy at a place easily accessible by common citizens, such as large city. (G.K.)

  20. Design concepts to enhance nuclear power plant protection

    International Nuclear Information System (INIS)

    Ericson, D.M. Jr.; Varnado, G.B.

    1980-01-01

    Using a modern design for a nuclear power plant as a point of departure, this study examines the enhancement of protection which may be achieved by changes to the design. These changes include concepts such as complete physical separation of redundant trains of safety equipment, hardened enclosures for water storage tanks, and hardened shutdown heat removal systems. The degree of enhancement (value) is examined in terms such as the potential reduction in the number of vital areas and the increase in probability of adversary sequence interruption. The impacts considered include constraints imposed upon operations and maintenance personnel and increased capital and operating costs. The study concludes that structural design changes alone do not provide significant increases in protection

  1. Concept of assistance of the Federal Office for Radiation Protection with regard to prevention of serious cases of nuclear hazards

    Energy Technology Data Exchange (ETDEWEB)

    Becker, D.E. [Federal Office for Radiation Protection, Salzgitter (Germany)

    2000-05-01

    For the defence against the threats caused by radioactive substances, a general concept was elaborated under the overall control of the Federal Government. A number of competent organisations are involved in this, for example the Federal Office of Criminal Investigation, the Federal Armed Forces, and the Federal Office for Radiation Protection. In Germany, the 16 Federal States are responsible for the prevention of nuclear hazards. In the case of hazards caused by radioactive material, experts from the competent radiation protection authorities are consulted. For the prevention of serious cases of nuclear hazards (nuclear fuels, criticality, danger of dispersion), the Federal Office for Radiation Protection - a subordinate authority of the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety responsible for radiation protection, nuclear safety, and waste management - was given order to elaborate a concept for assistance to those Federal States. The field of prevention of nuclear hazards ranges from combatting illegal trade with radioactive test sources up to the defence of nuclear fuels with the possibility to construct critical assemblies or the threatening by the distribution of airborne material which might enter the lungs. The latter are considered as serious cases of nuclear hazards. Since the expenditures for devices and personal to be trained would be inadequately high, the Federal Office for Radiation Protection (BfS) is prepared to support the Federal States if it becomes necessary. The concept includes a stand-by service, the search for radioactive material by helicopter or a ground team, analysis of the activity and the type of nuclides, risk assessment, and also measures to steam the risk. This concept will be presented. (author)

  2. Concept of assistance of the Federal Office for Radiation Protection with regard to prevention of serious cases of nuclear hazards

    International Nuclear Information System (INIS)

    Becker, D.E.

    2000-01-01

    For the defence against the threats caused by radioactive substances, a general concept was elaborated under the overall control of the Federal Government. A number of competent organisations are involved in this, for example the Federal Office of Criminal Investigation, the Federal Armed Forces, and the Federal Office for Radiation Protection. In Germany, the 16 Federal States are responsible for the prevention of nuclear hazards. In the case of hazards caused by radioactive material, experts from the competent radiation protection authorities are consulted. For the prevention of serious cases of nuclear hazards (nuclear fuels, criticality, danger of dispersion), the Federal Office for Radiation Protection - a subordinate authority of the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety responsible for radiation protection, nuclear safety, and waste management - was given order to elaborate a concept for assistance to those Federal States. The field of prevention of nuclear hazards ranges from combatting illegal trade with radioactive test sources up to the defence of nuclear fuels with the possibility to construct critical assemblies or the threatening by the distribution of airborne material which might enter the lungs. The latter are considered as serious cases of nuclear hazards. Since the expenditures for devices and personal to be trained would be inadequately high, the Federal Office for Radiation Protection (BfS) is prepared to support the Federal States if it becomes necessary. The concept includes a stand-by service, the search for radioactive material by helicopter or a ground team, analysis of the activity and the type of nuclides, risk assessment, and also measures to steam the risk. This concept will be presented. (author)

  3. Norm of nuclear weapons non-use and deterrence: interaction of the conceptions in case of usa

    OpenAIRE

    Bladaitė, Neringa

    2016-01-01

    Norm of Nuclear Weapons Non-use and Deterrence: Interaction of the Conceptions in Case of USA The problem that is analyzed in this master thesis is formed according the paradox. Although, US is thought to be the county that maintains norm of non-use, in the practice US forms the strategy according nuclear deterrence. The object of this master thesis is nuclear weapons posture of US during the period of 2009-2015. The main aim of this thesis is to explore posture of US nuclear weapons use base...

  4. The incentive concept as developed in the nuclear safety conventions and its possible extension to other sectors

    International Nuclear Information System (INIS)

    Wright, T. de

    2007-01-01

    This paper seeks to analyse the incentive concept, initially adopted in the C.N.S. (convention on nuclear safety) and later developed in the Joint Convention, as the innovation credited with encouraging both participation in , and compliance with, the nuclear safety conventions. It then seeks to examine the possibilities for the introduction of that concept into other sectors of international law. In the first part of the paper, the essential features of the concept and the mechanisms used in the conventions to bring it into effect will be discussed. the second part of the paper will focus on the different aspects of the conventions which have been described as integral to the concept. The third part of the paper will identify certain apprehensions regarding the effectiveness of such 'soft' treaty provisions and explain why the ' incentive' concept may be particularly well suited to certain specific situations. The final part of the paper will address the potential application of the concept and related treaty provisions to other fields of law, particularly to international environmental law. in addition, some suggestions will be made as to how provisions implementing the incentive concept into a treaty may be slightly modified to increase their effectiveness. (N.C.)

  5. Overview of nuclear safety activities performed by JRC-IE on Gen IV fast reactor concepts

    Energy Technology Data Exchange (ETDEWEB)

    Tsige-Tamirat, H.; Ammirabile, L.; D' Agata, E.; Fuetterer, M.; Ranguelova, V. [European Commission, Joint Research Centre, Institute for Energy, Westerduinweg 3, 1755LE Petten (Netherlands)

    2010-07-01

    The European Strategic Energy Technology (SET) Plan recognizes the need to develop new energy technologies, in order to reduce greenhouse gas emissions and secure energy supply in Europe. Besides renewable energy and improved energy efficiency, a new generation of nuclear power plants and innovative nuclear power applications can play a significant role to achieve this goal. The JRC Institute for Energy 'Safety of Future Nuclear Reactors' (SFNR) Unit is engaged in experimental research, numerical simulation and modelling, scientific, feasibility and engineering studies on innovative nuclear reactor systems. This also represents a significant EURATOM contribution to the Generation IV International Forum. Its activities deal with, among others, the performance assessment of innovative fuels and materials, development of new reactor core concepts and safety solutions, and knowledge management and preservation. Special attention is given to fast reactor concepts, namely the sodium (SFR) and lead (LFR) cooled reactors. Recognizing the maturity of the SFR technology, the European Sustainable Nuclear Energy Technology Platform (SNETP) considers a prototype SFR to be built as a next-step towards the deployment of a first-of-a-kind Gen IV SFR. This paper gives an overview of current research preformed at JRC-IE with emphasis on the work performed in the Collaborative Project on European Sodium Fast Reactor (CP-ESFR) within the European Commission's Seventh Framework Program. (authors)

  6. Overview of nuclear safety activities performed by JRC-IE on Gen IV fast reactor concepts

    International Nuclear Information System (INIS)

    Tsige-Tamirat, H.; Ammirabile, L.; D'Agata, E.; Fuetterer, M.; Ranguelova, V.

    2010-01-01

    The European Strategic Energy Technology (SET) Plan recognizes the need to develop new energy technologies, in order to reduce greenhouse gas emissions and secure energy supply in Europe. Besides renewable energy and improved energy efficiency, a new generation of nuclear power plants and innovative nuclear power applications can play a significant role to achieve this goal. The JRC Institute for Energy 'Safety of Future Nuclear Reactors' (SFNR) Unit is engaged in experimental research, numerical simulation and modelling, scientific, feasibility and engineering studies on innovative nuclear reactor systems. This also represents a significant EURATOM contribution to the Generation IV International Forum. Its activities deal with, among others, the performance assessment of innovative fuels and materials, development of new reactor core concepts and safety solutions, and knowledge management and preservation. Special attention is given to fast reactor concepts, namely the sodium (SFR) and lead (LFR) cooled reactors. Recognizing the maturity of the SFR technology, the European Sustainable Nuclear Energy Technology Platform (SNETP) considers a prototype SFR to be built as a next-step towards the deployment of a first-of-a-kind Gen IV SFR. This paper gives an overview of current research preformed at JRC-IE with emphasis on the work performed in the Collaborative Project on European Sodium Fast Reactor (CP-ESFR) within the European Commission's Seventh Framework Program. (authors)

  7. Generalized concepts for measures in case of nuclear and radiological emergencies; Generalisierte Konzepte fuer Massnahmen bei nuklearen und radiologischen Notfaellen

    Energy Technology Data Exchange (ETDEWEB)

    Sogalla, Martin; Buettner, Uwe; Schnadt, Horst

    2015-05-15

    In the frame of the project 3610S60014 GRS has developed a generalized concept of measures for an improved availability of support and information systems for emergency purposes and the planning of press and public relations that shall be applicable for the complete spectrum of nuclear end radiological emergencies. The concept allows the derivation of criteria and clear procedures for the situation evaluation and decision making. The project is aimed to integrate all available measure concepts from external emergency preparedness, prevention of ABD hazards and specific nuclear emergency plans.

  8. Supplier selection based on improved MOGA and its application in nuclear power equipment procurement

    International Nuclear Information System (INIS)

    Yan Zhaojun; Wang Dezhong; Zhou Lei

    2007-01-01

    Considering the fact that there are few objective and available methods supporting the supplier selection in nuclear power equipment purchasing process, a supplier selection method based on improved multi-objective genetic algorithm (MOGA) is proposed. The simulation results demonstrate the effectiveness and efficiency of this method for the supplier selection in nuclear power equipment procurement process. (authors)

  9. Selection of sites for nuclear power plants in The Netherlands. Pt. A

    International Nuclear Information System (INIS)

    1985-01-01

    In this report a policy proposal is presented concerning the selection of location sites for new nuclear power plants in the Netherlands. Firstly it is investigated which of the 29 already selected location sites are not to be taken into further account because of obvious obstructions (close vicinity of a big city etc.). The remaining sites are judged on the base of local population magnitude. The sites that pass the last criteria are relatively compared from a large number of viewpoints. To round off the selection procedure the government will explain why they consider the finally selected sites to be suitable for location of new nuclear power plants. Steps are indicated to prevent the decrease of planologic suitability of the selected location sites. (Auth.)

  10. In-reactor testing of the closed cycle gas core reactor---the nuclear light bulb concept

    International Nuclear Information System (INIS)

    Gauntt, R.O.; Slutz, S.A.; Harms, G.A.; Latham, T.S.; Roman, W.C.; Rodgers, R.J.

    1993-01-01

    The Nuclear Light Bulb (NLB) concept is an advanced closed cycle space propulsion rocket engine design that offers unprecidented performance characteristics in terms of specific impulse (>1800 s) and thrust (>445 kN). The NLB is a gas-core nuclear reactor making use of thermal radiation from a high temperature U-plasma core to heat the hydrogen propellant to very high temperatures (∼4000 K). The following paper describes analyses performed in support of the design of in-reactor tests that are planned to be performed in the Annular Core Research Reactor (ACRR) at Sandia National Laboratories in order to demonstrate the technical feasibility of this advanced concept. The tests will examine the stability of a hydrodynamically confined fissioning U-plasma under steady and transient conditions. Testing will also involve study of propellant heating by thermal radiation from the plasma and materials performance in the nuclear environment of the NLB. The analyses presented here include neutronic performance studies and U-plasma radiation heat-transport studies of small vortex-confined fissioning U-plasma experiments that are irradiated in the ACRR. These analyses indicate that high U-plasma temperatures (4000 to 9000 K) can be sustained in the ACRR for periods of time on the order of 5 to 20 s. These testing conditions are well suited to examine the stability and performance requirements necessary to demonstrate the feasibility of this concept

  11. Auto type-selection of constant supporting in nuclear power stations

    International Nuclear Information System (INIS)

    Liu Hu; Wang Fujun; Liu Wei; Li Zhaoqing

    2013-01-01

    To solve the type-selection of constant supporting in nuclear power stations, combining the characteristics of constant supporting which can adjust in the certain scope and the rules of load-displacement, the requirements and process for the type-selection of constant supporting is proposed, and the process of type-selection is optimized by Visual Basic. After inputting of the known parameters, the process can automatically select the most economical and reasonable constant supporting by array and function. (authors)

  12. High School Biology Students' Transfer of the Concept of Natural Selection: A Mixed-Methods Approach

    Science.gov (United States)

    Pugh, Kevin J.; Koskey, Kristin L. K.; Linnenbrink-Garcia, Lisa

    2014-01-01

    The concept of natural selection serves as a foundation for understanding diverse biological concepts and has broad applicability to other domains. However, we know little about students' abilities to transfer (i.e. apply to a new context or use generatively) this concept and the relation between students' conceptual understanding and transfer…

  13. Site selection - siting of the final repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    2011-03-01

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  14. Site selection - siting of the final repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  15. Investigations of possibilities to dispose of spent nuclear fuel in Lithuania: a model case. Volume 2, Concept of Repository in Crystalline Rocks

    International Nuclear Information System (INIS)

    Motiejunas, S.; Poskas, P.

    2005-01-01

    The aim is to present the generic repository concept in crystalline rocks in Lithuania and cost assessment of the disposal of spent nuclear fuel and long-lived intermediate level waste in this repository. Due to limited budget of this project the repository concept development for Lithuania was based mostly on the experience of foreign countries. In this Volume a review of the existing information on disposal concept in crystalline rocks from various countries is presented. Described repository concept for crystalline rocks in Lithuania covers repository layout, backfill, canister, construction materials and auxiliary buildings. Costs calculations for disposal of spent nuclear fuel and long-lived intermediate-level wastes from Ignalina NPP are presented too. Thermal, criticality and other important disposal evaluations for RBMK-1500 spent nuclear fuel emplaced in copper canister were performed and described

  16. Nuclear heat generating plants - technical concepts and market potentials. Chapter 11

    International Nuclear Information System (INIS)

    Hasenkopf, O.; Erhard, W.D.; Nonnenmacher, A.; Hanselmann, M.

    1988-01-01

    Within the framework of a case study under the Federal Ministry of Research and Technology project 'Nuclear heat generating plants - technological concepts and market potentials', the possible applications of such plants were studied giving the district heat supply network of the Technische Werke der Stadt Stuttgart AG (Technical Works of the City of Stuttgart, Inc.) as an example. The use of district heating systems concentrated specifically on areas identified for economical supply because of their topographical position, existing heat density, distance from power plants, and a reasonable delimination from the available gas network. Based on the results of optimization calculations made by the Stuttgart Institute for Nuclear Technology and Energy Conversion, the required investment capital can be estimated as a function of the amount of fuel savings under the Stuttgart case study. (orig./UA) [de

  17. Evaluation of the basic concepts of approaches for the coexistence of nuclear energy and people/local community

    International Nuclear Information System (INIS)

    Kondo, Shunsuke; Kuroki, Shinichi; Nakagiri, Yuko

    2007-01-01

    In November 2007, the Policy Evaluation Committee compiled the report, which evaluated the basic concepts of approaches to the coexistence of nuclear energy and people/local community, specified in the Framework for Nuclear Energy Policy. The report states that the 'concerned administrative bodies are carrying out measures related to the coexistence of nuclear energy and people/local communities in line with these basic concept' and summarizes fifteen proposals conductive to the betterment and improvement of these measures, which were classified as 1) secure transparency and promotion of mutual understanding with the public, 2) development and enrichment of learning opportunities and public participation, 3) relationship between the government and local governments and 4) coexistence with local residents. The Japan Atomic Energy Commission (JAEC) considers this report to be reasonable. This article presented an overview of this activity. (T. Tanaka)

  18. Selectivity in multiple quantum nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Warren, W.S.

    1980-11-01

    The observation of multiple-quantum nuclear magnetic resonance transitions in isotropic or anisotropic liquids is shown to give readily interpretable information on molecular configurations, rates of motional processes, and intramolecular interactions. However, the observed intensity of high multiple-quantum transitions falls off dramatically as the number of coupled spins increases. The theory of multiple-quantum NMR is developed through the density matrix formalism, and exact intensities are derived for several cases (isotropic first-order systems and anisotropic systems with high symmetry) to shown that this intensity decrease is expected if standard multiple-quantum pulse sequences are used. New pulse sequences are developed which excite coherences and produce population inversions only between selected states, even though other transitions are simultaneously resonant. One type of selective excitation presented only allows molecules to absorb and emit photons in groups of n. Coherent averaging theory is extended to describe these selective sequences, and to design sequences which are selective to arbitrarily high order in the Magnus expansion. This theory and computer calculations both show that extremely good selectivity and large signal enhancements are possible

  19. Selectivity in multiple quantum nuclear magnetic resonance

    Energy Technology Data Exchange (ETDEWEB)

    Warren, Warren Sloan [Univ. of California, Berkeley, CA (United States). Dept. of Chemistry; Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). Materials Sciences Division

    1980-11-01

    The observation of multiple-quantum nuclear magnetic resonance transitions in isotropic or anisotropic liquids is shown to give readily interpretable information on molecular configurations, rates of motional processes, and intramolecular interactions. However, the observed intensity of high multiple-quantum transitions falls off dramatically as the number of coupled spins increases. The theory of multiple-quantum NMR is developed through the density matrix formalism, and exact intensities are derived for several cases (isotropic first-order systems and anisotropic systems with high symmetry) to shown that this intensity decrease is expected if standard multiple-quantum pulse sequences are used. New pulse sequences are developed which excite coherences and produce population inversions only between selected states, even though other transitions are simultaneously resonant. One type of selective excitation presented only allows molecules to absorb and emit photons in groups of n. Coherent averaging theory is extended to describe these selective sequences, and to design sequences which are selective to arbitrarily high order in the Magnus expansion. This theory and computer calculations both show that extremely good selectivity and large signal enhancements are possible.

  20. Selecting safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    Today, many thousands of documents are available describing the requirements, guidelines, and industrial standards which can be used as bases for a nuclear power plant programme. Many of these documents relate to nuclear safety which is currently the focus of world-wide attention. The multitude of documents available on the subject, and their varying status and emphasis, make the processes of selection and implementation very important. Because nuclear power plants are technically intricate and advanced, particularly in relation to the technological status of many developing countries, these processes are also complicated. These matters were the subject of a seminar held at the Agency's headquarters in Vienna last December. The IAEA Nuclear Safety Standards (NUSS) programme was outlined and explained at the Seminar. The five areas of the NUSS programme for nuclear power plants cover, governmental organization, siting, design; operation; quality assurance. In each area the Agency has issued Codes of Practice and is developing Safety Guides. These provide regulatory agencies with a framework for safety. The Seminar recognized that the NUSS programme should enable developing countries to identify priorities in their work, particularly the implementation of safety standards. The ISO activities in the nuclear field are carried out in the framework of its Technical Committee 85 (ISO/TC85). The work is distributed in sub-committees. Seminar on selection and implementation of safety standards for nuclear power plants, jointly organized by the IAEA and the International Organization for Standardization (ISO), and held in Vienna from 15 to 18 December 1980 concerned with: terminology, definitions, units and symbols (SC-1), radiation protection (SC-2), power reactor technology (SC-3), nuclear fuel technology (SC-5). There was general agreement that the ISO standards are complementary to the NUSS codes and guides. ISO has had close relations with the IAEA for several years

  1. Environmental implications of thorium use in selected nuclear fuel cycles. Final

    International Nuclear Information System (INIS)

    Buckley, D.W.; Simmons, G.L.; Ziskind, R.A.

    1978-01-01

    The objective of this study was to assess the environmental implications of the nuclear fuel cycle associated with the highly enriched uranium concept of the High Temperature Gas Cooled Reactor. Model fuel cycles were constructed for the HTGR and a reference light water reactor (LWR) cycle. Mass flows were developed, control technology cases proposed and costed, effluents determined, and population doses calculated. Emphasis was given to the intercomparison of the fuel cycles to delineate areas which show pronounced departure. The dose commitment received by the population both within and outside a radius of 50 miles of each facility was determined. The 100 year population dose commitments due to a single year's plant operation was selected to facilitate intercomparison among fuel cycle components. No account was taken for long term waste sources associated with the fuel cycle such as mill tailing piles or terminal waste storage (study groundrule). The resource utilization and radionuclide activity of various fuel cycle options for using thorium in a Pressurized Water Reactor were studied. These data were contrasted with similar results obtained for a uranium fuel PWR

  2. Blended learning concept for the support of know-how transfer in a nuclear company

    International Nuclear Information System (INIS)

    Langenberger, Nina

    2010-01-01

    AREVA is the largest growing nuclear company. Development and construction of new power plants, sustainment and maintenance of existing installations require many professionally trained personnel, more than 800 new appointments per year trigger the in-plant training and education. The AREVA NP Training Center is in charge of the education and training of the personnel. The contribution deals with the applied blended learning concept and the know-how transfer within AREVA NP. Web-based training and the virtual class room are part of the concept.

  3. DESIGN AND LAYOUT CONCEPTS FOR COMPACT, FACTORY-PRODUCED, TRANSPORTABLE, GENERATION IV REACTOR SYSTEMS

    Energy Technology Data Exchange (ETDEWEB)

    Mynatt Fred R.; Townsend, L.W.; Williamson, Martin; Williams, Wesley; Miller, Laurence W.; Khan, M. Khurram; McConn, Joe; Kadak, Andrew C.; Berte, Marc V.; Sawhney, Rapinder; Fife, Jacob; Sedler, Todd L.; Conway, Larry E.; Felde, Dave K.

    2003-11-12

    The purpose of this research project is to develop compact (100 to 400 MWe) Generation IV nuclear power plant design and layout concepts that maximize the benefits of factory-based fabrication and optimal packaging, transportation and siting. The reactor concepts selected were compact designs under development in the 2000 to 2001 period. This interdisciplinary project was comprised of three university-led nuclear engineering teams identified by reactor coolant type (water, gas, and liquid metal) and a fourth Industrial Engineering team. The reactors included a Modular Pebble Bed helium-cooled concept being developed at MIT, the IRIS water-cooled concept being developed by a team led by Westinghouse Electric Company, and a Lead-Bismuth-cooled concept developed by UT. In addition to the design and layout concepts this report includes a section on heat exchanger manufacturing simulations and a section on construction and cost impacts of proposed modular designs.

  4. DESIGN AND LAYOUT CONCEPTS FOR COMPACT, FACTORY-PRODUCED, TRANSPORTABLE, GENERATION IV REACTOR SYSTEMS

    International Nuclear Information System (INIS)

    Mynatt, Fred R.; Townsend, L.W.; Williamson, Martin; Williams, Wesley; Miller, Laurence W.; Khan, M. Khurram; McConn, Joe; Kadak, Andrew C.; Berte, Marc V.; Sawhney, Rapinder; Fife, Jacob; Sedler, Todd L.; Conway, Larry E.; Felde, Dave K.

    2003-01-01

    The purpose of this research project is to develop compact (100 to 400 MWe) Generation IV nuclear power plant design and layout concepts that maximize the benefits of factory-based fabrication and optimal packaging, transportation and siting. The reactor concepts selected were compact designs under development in the 2000 to 2001 period. This interdisciplinary project was comprised of three university-led nuclear engineering teams identified by reactor coolant type (water, gas, and liquid metal) and a fourth Industrial Engineering team. The reactors included a Modular Pebble Bed helium-cooled concept being developed at MIT, the IRIS water-cooled concept being developed by a team led by Westinghouse Electric Company, and a Lead-Bismuth-cooled concept developed by UT. In addition to the design and layout concepts this report includes a section on heat exchanger manufacturing simulations and a section on construction and cost impacts of proposed modular designs

  5. A methodology for semiautomatic taxonomy of concepts extraction from nuclear scientific documents using text mining techniques

    International Nuclear Information System (INIS)

    Braga, Fabiane dos Reis

    2013-01-01

    This thesis presents a text mining method for semi-automatic extraction of taxonomy of concepts, from a textual corpus composed of scientific papers related to nuclear area. The text classification is a natural human practice and a crucial task for work with large repositories. The document clustering technique provides a logical and understandable framework that facilitates the organization, browsing and searching. Most clustering algorithms using the bag of words model to represent the content of a document. This model generates a high dimensionality of the data, ignores the fact that different words can have the same meaning and does not consider the relationship between them, assuming that words are independent of each other. The methodology presents a combination of a model for document representation by concepts with a hierarchical document clustering method using frequency of co-occurrence concepts and a technique for clusters labeling more representatives, with the objective of producing a taxonomy of concepts which may reflect a structure of the knowledge domain. It is hoped that this work will contribute to the conceptual mapping of scientific production of nuclear area and thus support the management of research activities in this area. (author)

  6. New reactor concepts

    International Nuclear Information System (INIS)

    Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A.

    1998-11-01

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

  7. Comparison and selection of client computer in nuclear instrument

    International Nuclear Information System (INIS)

    Ma Guizhen; Xie Yanhui; Peng Jing; Xu Feiyan

    2012-01-01

    The function of modern new nuclear instrument is very much. And the information degree is high requested. Through close matching for host computer and client computer, the data processing function can be carried out. This article puts forward a few of projects for the client computer of general nuclear instrument. The function and features of several common client computers, such as FPGA, ARM and DSP, are analyzed and compared. The applied scope is discussed also. At the same time, using a practical design as an example, the selection ideas of client computer are described. This article can be used for reference for the hardware design of data acquisition processing unit in nuclear instrument. (authors)

  8. CONCEPT-5, Cost and Economics Analysis for Nuclear Fuel or Fossil Fuel Power Plant

    International Nuclear Information System (INIS)

    Bowers, H.I.; Gratteau, J.E.; Zielsinki, T.J.

    1992-01-01

    1 - Description of problem or function: The CONCEPT computer code system was developed to provide conceptual capital cost estimates for nuclear and coal-fired power plants. Cost estimates can be made as a function of plant type, size, location, and date of initial operation. The output includes a detailed breakdown of the estimate into direct and indirect costs similar to the accounting system described in document NUS-531. Cost models are provided in CONCEPT5, the fifth generation in the development of the CONCEPT package, for single-unit coal-fired plants, pressurized-water reactors, boiling- water reactors, liquid-metal-cooled reactors, and multi-unit coal- fired plants based on today's average or best operating experience. Costs may be obtained for any of twenty U.S. cities, a hypothetical Middletown site, and two Canadian cities. CONCEPT5 models are updated models of those available in CONCEPT3 and, in addition, this edition contains historical factory equipment cost data for the generation of cost indices and escalation rates; indirect costs are calculated as a function of unit size rather than a function of direct costs; and an indirect cost account for owner's costs and an improved time-dependent escalation feature are included. The CONCEPT3 models and cost data are outdated; the package is being retained in the library since it is the only UNIVAC1108 machine version of CONCEPT available and could prove helpful in converting the latest IBM release. 2 - Method of solution: CONCEPT is based on the premise that any central station power plant involves approximately the same major cost components regardless of location or date of initial operation. The program has detailed cost models for each plant type at a reference condition. Through use of size, time, and location- dependent cost adjustments, a reference cost model is modified to produce a specific capital cost estimate. CONCEPT is supported by two auxiliary programs--CONTAC, which generates and maintains

  9. Delegated democracy. Siting selection for the Swedish nuclear waste

    International Nuclear Information System (INIS)

    Johansson, Hanna Sofia

    2008-11-01

    The present study concerns the siting of the Swedish nuclear waste repository. Four cases are examined: the feasibility studies in Nykoeping and Tierp (cases 1 and 2), as well as three public consultation meetings with conservationist and environmental organisations, and two study visits to nuclear facilities in Oskarshamn and Oesthammar, which were held during what is called the site-investigation phase (cases 3 and 4). The Swedish Nuclear Fuel and Waste Management Co (SKB) began the search for a nuclear waste site in the 1970s. Since 1992 SKB has conducted feasibility studies in eight municipalities, including in the four municipalities mentioned above. At the present time more comprehensive site investigations are underway in Oskarshamn and Oesthammar, two municipalities that already host nuclear power plants as well as storages for nuclear waste. In addition to SKB and the municipalities involved in the site-selection process, politicians, opinion groups, concerned members of the public, and oversight bodies are important actors. The analysis of the cases employs the concepts of 'sub-politics', 'boundary work', and 'expertise', together with the four models of democracy 'representative democracy', participatory democracy', 'deliberative democracy', and 'technocracy'. The aim of the study is to describe the characteristics of Swedish democracy in relation to the disposal of Swedish nuclear waste. The main questions of the study are: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? and Which democratic ideals were influential during the feasibility studies and in the consultation process? The study is based on qualitative methods, and the source materials consist of documents, interviews, and participant observations. In summary, the form of democracy that emerges in the four case studies can be described as delegated democracy. This means that a large

  10. Noticeable aspects of selecting intervention measures for nuclear accidents

    International Nuclear Information System (INIS)

    Guo Yong; Shi Yuanming

    1993-01-01

    Referring to the experience of intervention measures taken for protecting the public after Chernobyl accident and to recent knowledge of source terms of reactor accidents, the noticeable aspects of selecting of intervention measures for nuclear accidents is discussed

  11. Utilizing reliability concepts in the development of IEEE recommended good practices for nuclear plant maintenance

    International Nuclear Information System (INIS)

    Gradin, L.P.

    1986-01-01

    This paper presents information describing the concern for nuclear power plant electrical equipment maintenance and the IEEE Nuclear Power Engineering Committee's method to address that concern. That method includes the creation of Working Group 3.3, ''Maintenance Good Practices'' which is developing specific maintenance good practice documents, supporting technical information exchange, and providing a vehicle to promote practices which can reduce cost and enhance plant safety. The foundation for that effort is the utilization of Reliability concepts

  12. Selected Topics in Nuclear Theory. Lectures Given at the International Summer School on Selected Topics in Nuclear Theory

    Energy Technology Data Exchange (ETDEWEB)

    Janouch, F. [ed.

    1963-01-15

    An International Summer School on Selected Topics in Nuclear Theory was held during the period 20 August to 9 September 1962 in the Low Tatra Mountains, Czechoslovakia, under the auspices of the Nuclear Research Institute of the Czechoslovak Academy of Sciences, with financial support from the International Atomic Energy Agency. In view of the wide interest of the seven topics considered there and of the speed with which the field of theoretical physics is developing, the Agency decided to make available its facilities for rapid publication and to publish the lectures under its own imprint; however, all editorial and composition work has been performed under the supervision of the general editor. Dr. F. Janouch of the Nuclear Research Institute of the Czechoslovak Academy of Sciences. The problem of keeping in touch with the rapidly changing but fundamental field of theoretical physics is a difficult one, particularly for scientists in the developing countries. It is hoped that such publications as the present one and the companion volume containing the lectures presented at the Agency's Seminar on Theoretical Physics at Trieste w ill help, at least in a modest fashion, to overcome these difficulties.

  13. Proposal on concept of security of energy supply with nuclear energy

    International Nuclear Information System (INIS)

    Ujita, Hiroshi; Matsui, Kazuaki; Yamada, Eiji

    2009-01-01

    Security of energy supply (SoS) was a major concern for OECD governments in the early 1970s. Since then, successive oil crises, volatility of hydrocarbon prices, as well as terrorist risks and natural disasters, have brought the issue back to the centre stage of policy agendas. SoS concept has been proposed which is defined by time frame and space frame as well. Wide meaning SoS consists of narrow meaning SoS of short-term energy crisis, which is the traditional concept, and long-term global energy problem, which has become important recently. Three models have been proposed here for evaluating SoS. A method to estimate energy security level in a quantitative manner by comparing with various measures has been also proposed, in which nuclear energy contribution onto SoS can be further measured. (author)

  14. Solid Catalyst with Ionic Liquid Layer (SCILL). A concept to improve the selectivity of selective hydrogenations

    Energy Technology Data Exchange (ETDEWEB)

    Jess, A.; Korth, W. [Bayreuth Univ. (Germany). Chair of Chemical Engineering

    2011-07-01

    Catalytic hydrogenations are important for refinery processes, petrochemical applications as well as for numerous processes of the fine chemicals industry. In some cases, hydrogenations consist of a sequence of consecutive reactions, and the desired product is the intermediate. An important goal is then a high yield and selectivity to the intermediate, if possible at a high conversion degree. The selectivity to an intermediate primarily depends on the chemical nature of the catalyst, but may also be influenced by diffusion processes. Ionic liquids (ILs) are low melting salts (< 100 C) and represent a promising solvent class. This paper focuses on the concept of a Solid Catalyst with Ionic Liquid Layer (SCILL), where the solid catalyst is coated with a thin IL layer to improve the selectivity. (orig.)

  15. Nuclear heat source component design considerations for HTGR process heat reactor plant concept

    International Nuclear Information System (INIS)

    McDonald, C.F.; Kapich, D.; King, J.H.; Venkatesh, M.C.

    1982-05-01

    The coupling of a high-temperature gas-cooled reactor (HTGR) and a chemical process facility has the potential for long-term synthetic fuel production (i.e., oil, gasoline, aviation fuel, hydrogen, etc) using coal as the carbon source. Studies are in progress to exploit the high-temperature capability of an advanced HTGR variant for nuclear process heat. The process heat plant discussed in this paper has a 1170-MW(t) reactor as the heat source and the concept is based on indirect reforming, i.e., the high-temperature nuclear thermal energy is transported [via an intermediate heat exchanger (IHX)] to the externally located process plant by a secondary helium transport loop. Emphasis is placed on design considerations for the major nuclear heat source (NHS) components, and discussions are presented for the reactor core, prestressed concrete reactor vessel (PCRV), rotating machinery, and heat exchangers

  16. Preparation and concept of geodesy work on the Temelin nuclear power plant site

    International Nuclear Information System (INIS)

    Vincik, K.; Zdobinsky, J.

    1989-01-01

    Listed are the main partners in the Temelin nuclear power plant construction (investor, general designer, building and equipment parts suppliers), the main specifications of the power plant, the layout of buildings, the types of construction documentation, and the concept of geodesy work. A network was laid out comprising 9 points and a local coordinate system and an elevation system for design work were determined. Within the layout, a network of basic elevation points with depth stabilization and a starting 6-point level network were proposed. The updating is described of the layout network and of the organization of geodesy work during the construction of the Temelin nuclear power plant. (E.J.)

  17. Biological Principles and Threshold Concepts for Understanding Natural Selection. Implications for Developing Visualizations as a Pedagogic Tool

    Science.gov (United States)

    Tibell, Lena A. E.; Harms, Ute

    2017-11-01

    Modern evolutionary theory is both a central theory and an integrative framework of the life sciences. This is reflected in the common references to evolution in modern science education curricula and contexts. In fact, evolution is a core idea that is supposed to support biology learning by facilitating the organization of relevant knowledge. In addition, evolution can function as a pivotal link between concepts and highlight similarities in the complexity of biological concepts. However, empirical studies in many countries have for decades identified deficiencies in students' scientific understanding of evolution mainly focusing on natural selection. Clearly, there are major obstacles to learning natural selection, and we argue that to overcome them, it is essential to address explicitly the general abstract concepts that underlie the biological processes, e.g., randomness or probability. Hence, we propose a two-dimensional framework for analyzing and structuring teaching of natural selection. The first—purely biological—dimension embraces the three main principles variation, heredity, and selection structured in nine key concepts that form the core idea of natural selection. The second dimension encompasses four so-called thresholds, i.e., general abstract and/or non-perceptual concepts: randomness, probability, spatial scales, and temporal scales. We claim that both of these dimensions must be continuously considered, in tandem, when teaching evolution in order to allow development of a meaningful understanding of the process. Further, we suggest that making the thresholds tangible with the aid of appropriate kinds of visualizations will facilitate grasping of the threshold concepts, and thus, help learners to overcome the difficulties in understanding the central theory of life.

  18. Concept of object-oriented intelligent support for nuclear reactor designing

    International Nuclear Information System (INIS)

    Yoshikawa, H.; Gofuku, A.

    1991-01-01

    A concept of object-oriented intelligent CAD/CAE environment is proposed for the conceptual designing of advanced nuclear reactor system. It is composed of (i) object-oriented frame-structure database which represents the hierarchical relationship of the composite elements of reactor core and the physical properties, and (ii) object-oriented modularization of the elementary calculation processes, which are needed for reactor core design analysis. As an example practise, an object-oriented frame structure is constructed for representing a 3D configuration of a special fuel element of a space reactor design, by using a general-purpose expert system shell ESHELL/X. (author)

  19. Outline of research proposals selected in the Nuclear Energy Research Initiative (NERI) program

    International Nuclear Information System (INIS)

    Iwamura, Takamichi; Okubo, Tsutomu; Usui, Shuji

    1999-08-01

    The U.S. Department of Energy (DOE) created a new R and D program called Nuclear Energy Research Initiative (NERI)' in FY 1999 with the appropriation of $19 million. The major objectives of the NERI program is to preserve the nuclear science and engineering infrastructure in the U.S. and to maintain a competitive position in the global nuclear market in the 21st century. In may, 1999, the DOE selected 45 research proposals for the first year of the NERI program. The proposals are classified into the following five R and D areas: Proliferation Resistant Reactors and/or Fuel Cycles, New Reactor Designs, Advanced Nuclear Fuel, New Technology for Management of Nuclear Waste, Fundamental Nuclear Science. Since the NERI is a very epoch-making and strategic nuclear research program sponsored by the U.S. government, the trend of the NERI is considered to affect the future R and D programs in Japanese nuclear industries and research institutes including JAERI. The present report summarizes the analyzed results of the selected 45 research proposals. Staffs comments are made on each proposal in connection with the R and D activities in JAERI. (author)

  20. The importante of physical and mathematical models for nuclear power plants site selection

    International Nuclear Information System (INIS)

    Rios, J.L.P.

    1989-01-01

    The importance of the release of effluents from nuclear installations for the site selection of nuclear power plants is discussed. The main available analysis methods, physical and mathematical, is presented [pt

  1. Concept of Operations for Nuclear Warhead Embedded Sensors

    Energy Technology Data Exchange (ETDEWEB)

    Rockett, P D; Koncher, T R

    2012-05-16

    Embedded arms-control-sensors provide a powerful new paradigm for managing compliance with future nuclear weapons treaties, where deployed warhead numbers will be reduced to 1000 or less. The CONOPS (Concept of Operations) for use with these sensors is a practical tool with which one may help define design parameters, including size, power, resolution, communications, and physical structure. How frequently must data be acquired and must a human be present? Will such data be acquired for only stored weapons or will it be required of deployed weapons as well? Will tactical weapons be subject to such monitoring or will only strategic weapons apply? Which data will be most crucial? Will OSI's be a component of embedded sensor data management or will these sensors stand alone in their data extraction processes? The problem space is massive, but can be constrained by extrapolating to a reasonable future treaty regime and examining the bounded options this scenario poses. Arms control verification sensors, embedded within the warhead case or aeroshell, must provide sufficient but not excessively detailed data, confirming that the item is a nuclear warhead and that it is a particular warhead without revealing sensitive information. Geolocation will be provided by an intermediate transceiver used to acquire the data and to forward the data to a central processing location. Past Chain-of-Custody projects have included such devices and will be primarily responsible for adding such indicators in the future. For the purposes of a treaty regime a TLI will be verified as a nuclear warhead by knowledge of (a) the presence and mass of SNM, (b) the presence of HE, and (c) the reporting of a unique tag ID. All of these parameters can be obtained via neutron correlation measurements, Raman spectroscopy, and fiber optic grating fabrication, respectively. Data from these sensors will be pushed out monthly and acquired nearly daily, providing one of several verification layers in

  2. Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

    International Nuclear Information System (INIS)

    Chen Xiaoqiu

    2009-01-01

    Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

  3. A model selection support system for numerical simulations of nuclear thermal-hydraulics

    International Nuclear Information System (INIS)

    Gofuku, Akio; Shimizu, Kenji; Sugano, Keiji; Yoshikawa, Hidekazu; Wakabayashi, Jiro

    1990-01-01

    In order to execute efficiently a dynamic simulation of a large-scaled engineering system such as a nuclear power plant, it is necessary to develop intelligent simulation support system for all phases of the simulation. This study is concerned with the intelligent support for the program development phase and is engaged in the adequate model selection support method by applying AI (Artificial Intelligence) techniques to execute a simulation consistent with its purpose and conditions. A proto-type expert system to support the model selection for numerical simulations of nuclear thermal-hydraulics in the case of cold leg small break loss-of-coolant accident of PWR plant is now under development on a personal computer. The steps to support the selection of both fluid model and constitutive equations for the drift flux model have been developed. Several cases of model selection were carried out and reasonable model selection results were obtained. (author)

  4. Variable selection in multivariate calibration based on clustering of variable concept.

    Science.gov (United States)

    Farrokhnia, Maryam; Karimi, Sadegh

    2016-01-01

    Recently we have proposed a new variable selection algorithm, based on clustering of variable concept (CLoVA) in classification problem. With the same idea, this new concept has been applied to a regression problem and then the obtained results have been compared with conventional variable selection strategies for PLS. The basic idea behind the clustering of variable is that, the instrument channels are clustered into different clusters via clustering algorithms. Then, the spectral data of each cluster are subjected to PLS regression. Different real data sets (Cargill corn, Biscuit dough, ACE QSAR, Soy, and Tablet) have been used to evaluate the influence of the clustering of variables on the prediction performances of PLS. Almost in the all cases, the statistical parameter especially in prediction error shows the superiority of CLoVA-PLS respect to other variable selection strategies. Finally the synergy clustering of variable (sCLoVA-PLS), which is used the combination of cluster, has been proposed as an efficient and modification of CLoVA algorithm. The obtained statistical parameter indicates that variable clustering can split useful part from redundant ones, and then based on informative cluster; stable model can be reached. Copyright © 2015 Elsevier B.V. All rights reserved.

  5. Selecting strategies for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2006-01-01

    This status report on Selecting Strategies for the Decommissioning of Nuclear Facilities is based on the viewpoints and materials presented at the Tarragona seminar as well as the experience of the WPDD. It identifies, reviews and analyses factors influencing decommissioning strategies and addresses the challenges associated with balancing these factors in the process of strategy selection. It gives recognition to the fact that, in addition to technical characteristics, there are many other factors that influence the selection of a decommissioning strategy and that cannot be quantified, such as policy, regulatory and socio-economic factors and aspects that reach far into the future. Uncertainties associated with such factors are a challenge to those who have to take decisions on a decommissioning strategy. (author)

  6. Innovative nuclear thermal rocket concept utilizing LEU fuel for space application

    International Nuclear Information System (INIS)

    Nam, Seung Hyun; Venneri, Paolo; Choi, Jae Young; Jeong, Yong Hoon; Chang, Soon Heung

    2015-01-01

    Space is one of the best places for humanity to turn to keep learning and exploiting. A Nuclear Thermal Rocket (NTR) is a viable and more efficient option for human space exploration than the existing Chemical Rockets (CRs) which are highly inefficient for long-term manned missions such as to Mars and its satellites. NERVA derived NTR engines have been studied for the human missions as a mainstream in the United States of America (USA). Actually, the NERVA technology has already been developed and successfully tested since 1950s. The state-of-the-art technology is based on a Hydrogen gas (H_2) cooled high temperature reactor with solid core utilizing High-Enriched Uranium (HEU) fuel to reduce heavy metal mass and to use fast or epithermal neutron spectrums enabling simple core designs. However, even though the NTR designs utilizing HEU is the best option in terms of rocket performance, they inevitably provoke nuclear proliferation obstacles on all Research and Development (R and D) activities by civilians and non-nuclear weapon states, and its eventual commercialization. To surmount the security issue to use HEU fuel for a NTR, a concept of the innovative NTR engine, Korea Advanced NUclear Thermal Engine Rocket utilizing Low-Enriched Uranium fuel (KANUTER-LEU) is presented in this paper. The design goal of KANUTER-LEU is to make use of a LEU fuel for its compact reactor, but does not sacrifice the rocket performance relative to the traditional NTRs utilizing HEU. KANUTER-LEU mainly consists of a fission reactor utilizing H_2 propellant, a propulsion system and an optional Electricity Generation System as a bimodal engine. To implement LEU fuel for the reactor, the innovative engine adopts W-UO_2 CERMET fuel to drastically increase uranium density and thermal neutron spectrum to improve neutron economy in the core. The moderator and structural material selections also consider neutronic and thermo-physical characteristics to reduce non-fission neutron loss and

  7. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    International Nuclear Information System (INIS)

    1995-01-01

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system

  8. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  9. DECISION SUPPORT CONCEPT TO MANAGEMENT OF CONSTRUCTION PROJECTS - PROBLEM OF CONSTRUCTION SITE SELECTION

    Directory of Open Access Journals (Sweden)

    Nikša Jajac

    2013-02-01

    Full Text Available The aim of this paper is to present Decision Support Concept (DSC for management of construction projects. Focus of our research is in application of multicritera methods (MCM to decision making in planning phase of construction projects (related to the problem of construction sites selection. The problem is identified as a significant one from many different aspects such as economic aspect, civil engineering aspect, etc. what indicates the necessity for evaluation of multiple sites by several different criteria. Therefore, DSC for construction site selection based on PROMETHEE method is designed. In order to define the appropriate criteria, their weights and preference functions for the concept, three groups of stakeholders are involved (investors, construction experts and experts for real estate market in its design. AHP method has been used for determination of criteria weights. The model has been tested on the problem of site selection for construction of residential-commercial building in four largest cities in Croatia.

  10. Strategy selection for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2004-01-01

    As modern nuclear power programmes mature and large, commercial nuclear power plants and fuel cycle facilities approach the end of their useful life by reason of age, economics or change of policy on the use of nuclear power, new challenges associated with decommissioning and dismantling come to the fore. Politicians and the public may expect there to be a 'right answer' to the choice of strategy for a particular type of facility, or even all facilities. Both this seminar and wider experience show that this is not the case. Local factors and national political positions have a significant input and often result in widely differing strategy approaches to broadly similar decommissioning projects. All facility owners represented at the seminar were able to demonstrate a rational process for strategy selection and compelling arguments for the choices made. In addition to the papers that were presented, these proceedings include a summary of the discussions that took place. (author)

  11. Selection of planes in nuclear magnetic resonance tomography

    International Nuclear Information System (INIS)

    Bonagamba, T.J.

    1986-01-01

    A prototype aiming to obtain images in nuclear magnetic resonance tomography was developed, by adjusting NMR spectrometer in the IFQSC Laboratory. The techniques for selecting planes were analysed by a set of computer codes, which were elaborated from Bloch equation solutions to simulate the spin system behaviour. Images were obtained using planes with thickness inferior to 1 cm. (M.C.K.)

  12. 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.

  13. Nuclear Fuel Cycle Introductory Concepts

    Energy Technology Data Exchange (ETDEWEB)

    Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-02-02

    The nuclear fuel cycle is a complex entity, with many stages and possibilities, encompassing natural resources, energy, science, commerce, and security, involving a host of nations around the world. This overview describes the process for generating nuclear power using fissionable nuclei.

  14. Nuclear Fuel Cycle Introductory Concepts

    International Nuclear Information System (INIS)

    Karpius, Peter Joseph

    2017-01-01

    The nuclear fuel cycle is a complex entity, with many stages and possibilities, encompassing natural resources, energy, science, commerce, and security, involving a host of nations around the world. This overview describes the process for generating nuclear power using fissionable nuclei.

  15. Site selection of nuclear power plants

    International Nuclear Information System (INIS)

    Schnappauf, W.

    1982-01-01

    A stock report of the development of the extent as well as the fundamentals of the conflict about nuclear energy shows that the effective law is both another cause and a mirror of the discussions about it. In total the investigation shows that the planning of site selection suffers from a number of legal problems. They are mainly of structural kind and are concerned with the issues of citizens' participation and graduation of procedures which are central for the management of the conflict. Therefore the present set of instruments is hardly able to contribute to increasing the acceptancy. The kind and extent of issues on one hand as well as the dimension of the conflict on the other make clear that the executive power itself is overtaxed. In this situation the legislative authorities are called up to take responsibility upon themselves. There are no objections from the constitutional or other aspects to legal site selection. (orig./HSCH) [de

  16. Nuclear safety criteria applied in site selection - the practice in France

    International Nuclear Information System (INIS)

    Candes, P.; Aussourd, Ph.

    1975-01-01

    In France, the safety of nuclear facilities is the responsibility of the Ministry for Industry and Research (Central Department for the Safety of Nuclear Facilities). The first part of the paper deals with the conception and contents of the site studies which are included in a safety report with the object of obtaining authorization to go ahead with work on the establishment of a facility. The conception is governed by the following two considerations: (a) the site is a place where the natural elements and living organisms occur and which is characterized by the permanent presence of the human factor, while the proposed nuclear facility will - like any industrial facility - present risks and have an impact on the site, particularly through the discharge of radioactive effluent and potentially in consequence of a nuclear accident; (b) the site exercises an influence - in fact, it even imposes constraints - on the nuclear facility. The site study as submitted by the operators to the authorities responsible for the safety evaluation traditionally consists of six sections, covering: (I) description and history of the site; (II) meteorological conditions; (III) hydrology of the area; (IV) geological and seismological conditions; (V) ecological factors; (VI) natural and/or previous radioactivity at the site. These six sections contain the data which serve as a basis for applying the two considerations spelled out above. However, the two corresponding directions of study and analysis do not settle the fundamental problem of the distribution of the population around the site. Methods for dealing with this problem are suggested in the second part of the paper; they take into account the efforts made so far at the international level. The authors consider that limiting criteria should not be based solely on the radioactive effluent discharges associated with normal operation but on the radioactivity releases associated with accidents. The methods proposed by them constitute

  17. Feasibility study on application of new concept of environmental assessment to nuclear energy

    International Nuclear Information System (INIS)

    Lee, Young Eal; Lee, Kun Jai

    2000-01-01

    The existing environmental assessments of nuclear energy are focused on the two kinds of issues such as prevention of green house gas emission and radiological impact assessment. So, the comparative assessment of the other resources such as fossil fuels has been the main part and this result has been the side of nuclear power as the clean energy resource. However, now is when to develop the methodology that approaches to environmental assessment of energy in terms of the various environmental categories. Life Cycle Assessment (LCA) would be the effective environmental assessment tool, which is able to meet the necessity mentioned above. Also classification of the radiological impact and calculation of the environmental impact from the radioactive substances are indispensable as long as the nuclear energy is considered in the application of LCA for the utilization of energy in the industry. However, direct introduction of LCA to the nuclear energy is difficult more or less due to the absence of the methodology for the radiological impact assessment within the LCA framework. Therefore, this study suggests the new concept of environmental assessment. Also current status of development for the classification factor of radiological impact is introduced and investigates the feasibility of application of it to nuclear power generation system

  18. Nuclear heat generating plants - technical concepts and market potentials. Chapter 8

    International Nuclear Information System (INIS)

    Thoene, E.

    1988-01-01

    To determine the advantages and disadvantages of different heat generating systems, a comparison is made between nuclear heat generating plants and competing heat generating systems. Nuclear heat generating plant concepts in practice have to compete with a wide range of existing and new fossil heat generating technologies of the most different capacities, ranging from combined heat and power generation to individual heating in one-family houses. Heat generation costs are calculated by means of a dynamic annuity method from an economic point of view. The development of real prices of fossil energy sources is based on two scenarios characterized as follows: scenario I - insignificant price increase by the year 2000, then stagnant; scenario II - moderate price increase by the year 2010, then stagnant. As a result of that systems comparison it can be stated that the considered nuclear heat generating plants may be an interesting competitive heat generation option, provided the assumptions on which the study is based can be implemented. This applies especially to investment costs. At the same time those plants contribute to a diversification of energy source options on the heat market. Their use leads to a reduction of fossil fuel imports, increasing at the same time short- and long-term supply guarantees. If nuclear heat generating plants substitute fossil heat generating plants, or render the construction of new ones superfluous, they contribute to avoiding chemical air pollutants. (orig./UA) [de

  19. Concept of a new method for fatigue monitoring of nuclear power plant components

    International Nuclear Information System (INIS)

    Zafosnik, M.; Cizelj, L.

    2007-01-01

    Fatigue is one of the well-understood aging mechanisms affecting mechanical components in many industrial facilities including nuclear power plants. Operational experience of nuclear power plants worldwide to date confirmed adequate design of safety related components against fatigue. In some cases however, for example when the plant life extension is envisioned, it may be very useful to monitor the remaining fatigue life of safety related components. Nuclear power plants components are classified into safety classes regarding their importance in mitigating the consequences of hypothetic accidents. Service life of components subjected to fatigue loading can be estimated with Usage Factor uk. A concept of the new method aiming both at monitoring the current state of the component and predicting its remaining lifetime in the life-extension conditions is presented. The method is based on determination of partial Usage Factor of components in which operating transients will be considered and compared to design transients. (author)

  20. An overview of microbial research related to high-level nuclear waste disposal with emphasis on the Canadian concept for the disposal of nuclear fuel waste

    International Nuclear Information System (INIS)

    Stroes-Gascoyne, S.; West, J.M.

    1995-01-01

    Current research on the effects of microbiology on nuclear waste disposal, carried out in a number of countries, is summarized. Atomic Energy of Canada Limited has developed a concept for the permanent disposal of nuclear fuel waste in Canada. A program was initiated in 1991 to address and quantify the potential effects of microbial action on the integrity of the multibarrier system on which the disposal concept is based. This microbial program focuses on answering specific questions in areas such as the survival of bacteria under relevant radiation and desiccation conditions; growth and mobility of microbes in compacted clay buffer materials and the potential consequences for container corrosion and microbial gas production; the presence and activity of microbes in deep granitic groundwaters; and the effects of biofilms on radionuclide migration in the geosphere. (author)

  1. Computational concept for the containment liner for a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Nagelstutz, Franz; Anders, Nils [Babcock Noell GmbH, Wuerzburg (Germany). Abt. Berechnung

    2010-05-15

    The determination of the optimal design of the Containment Liner considering amount of material, manufacturing and erection was the challenge for the engineering team of Babcock Noell GmbH. Several load cases for normal operation and accidental conditions as well as severe accidents have been analyzed. A realistic consideration of impacts by accidents was especially difficult. The special load cases in the vicinity of penetrations and anchor plates have been calculated. The results of theses analyses have been considered in the actual design of the liner. An integrated concept from planning, manufacturing and erection of this large component has been implemented, which is the topic of the speech 'ENGINEERING AND INNOVATIVE ERECTION CONCEPT FOR THE CONTAINMENT LINER FOR AN EPR trademark ' given by Dr. Rainer Goehring, Babcock Noell GmbH, Division Nuclear Technology Projects, Wuerzburg. He demonstrates that within the given time frame, with the required quality and within the required tolerances the containment liner can be erected. (orig.)

  2. Panning for SNuRMs: using cofactor profiling for the rational discovery of selective nuclear receptor modulators.

    Science.gov (United States)

    Kremoser, Claus; Albers, Michael; Burris, Thomas P; Deuschle, Ulrich; Koegl, Manfred

    2007-10-01

    Drugs that target nuclear receptors are clinically, as well as commercially, successful. Their widespread use, however, is limited by an inherent propensity of nuclear receptors to trigger beneficial, as well as adverse, pharmacological effects upon drug activation. Hence, selective drugs that display reduced adverse effects, such as the selective estrogen receptor modulator (SERM) Raloxifene, have been developed by guidance through classical cell culture assays and animal trials. Full agonist and selective modulator nuclear receptor drugs, in general, differ by their ability to recruit certain cofactors to the receptor protein. Hence, systematic cofactor profiling is advancing into an approach for the rationally guided identification of selective NR modulators (SNuRMs) with improved therapeutic ratio.

  3. Basic concept of the nuclear emergency preparedness and response in Japan after the accident of the Fukushima Dai-ichi Nuclear Power Station. The plain explanation for regional officials and emergency workers

    International Nuclear Information System (INIS)

    Sato, Sohei; Yamamoto, Kazuya

    2013-07-01

    After the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station occurred on March 11, 2011, actions for controlling the accident and protective actions for the residents like evacuation were taken. In parallel with this, it has been developed to reform the nuclear regulatory systems and the emergency preparedness and response systems in Japan. Especially the Nuclear Regulation Authority's Nuclear Emergency Preparedness and Response Guidelines were adopted with the introducing the basic concepts and the criteria on the basis of the IAEA's safety standards and differed greatly from the prior guidelines. Thus the arrangement of emergency response systems, resources and the operational procedures will be developed complying with according to the guidelines in municipalities around the nuclear power station sites. This work attempts to provide a plain explanation as possible for the regional officials and emergency workers about the basic concepts of the new guidelines. (author)

  4. Some concepts of future nuclear ship

    International Nuclear Information System (INIS)

    Fujino, Masataka

    2000-01-01

    Characteristic features of nuclear power generation are as follows: (1) Thermal energy can be continuously extracted for a long time without fuel feed, (2) Nuclear energy is suitable for generating huge power, (3) Oxygen is unnecessary for combustion of fuel, and (4) Unlike fossil fuel, nuclear power generation does not exhaust NOx, SOx, and CO 2 : it can be considered environmentally friendly. In view of these features, the Japan Atomic Energy Research Institute commissioned the Shipbuilding Research Association of Japan (JSRA) to survey what kinds of nuclear ship would be put to practical use in the near future. For this purpose, a research committee was organized in 1992 by the JSRA, and concluded its investigation in 1996. The main aim of this research was to clarify the requirements of ship performance as nuclear ships, and then to extract the technical issues of the marine reactor installed in nuclear ships to be solved. As a result of the survey, it was suggested that displacement-type large high-speed container ship would be one of the promising future nuclear merchant ships, and 6500 m deep-sea and 600 m undersea scientific research submersibles would be other promising nuclear special purpose ships. At the same time, various requirements of marine reactors, which are expected to be installed in these ships, were clarified mainly from the technical viewpoints. (author)

  5. Evolution of systems concepts for a 100 kWe class space nuclear power system

    International Nuclear Information System (INIS)

    Katucki, R.; Josloff, A.; Kirpich, A.; Florio, F.

    1985-01-01

    Conceptual designs for the SP-100 space nuclear power system have been prepared that meet baseline, backup and growth program scenarios. Near-term advancement in technology was considered in the design of the baseline concept. An improved silicon-germanium thermoelectric technique is used to convert the heat from a fast-spectrum, liquid lithium cooled reactor. This system produces a net power of 100 kWe with a 10-year end of life, under the specific constraints of area and volume. Output of the backup concept is estimated to be 60 kWe for a 10-year end of life. This system differs from the naseline concept because currently available thermoelectric conversion is used from energy supplied by a liquid sodium cooled reactor. The growth concept uses Stirling engine conversion to produce 100 kWe within the constraints of mass and volume. The growth concept can be scaled up to produce a 1 MWe output that uses the same type reactor developed for the baseline concept. Assessments made for each of the program scenarios indicate the key development efforts needed to initiate detailed design and hardware program phases. Development plans were prepared for each scenario that detail the work elements and show the program activities leading to a state of flight readiness

  6. Evolution of systems concepts for a 100 kWe class Space Nuclear Power System

    Science.gov (United States)

    Katucki, R.; Josloff, A.; Kirpich, A.; Florio, F.

    1985-01-01

    Conceptual designs for the SP-100 Space Nuclear Power System have been prepared that meet baseline, backup and growth program scenarios. Near-term advancement in technology was considered in the design of the Baseline Concept. An improved silicon-germanium thermoelectric technique is used to convert the heat from a fast-spectrum, liquid lithium cooled reactor. This system produces a net power of 100 kWe with a 10-year end of life, under the specific constraints of area and volume. Output of the Backup Concept is estimated to be 60 kWe for a 10-year end of life. This system differs from the Baseline Concept because currently available thermoelectric conversion is used from energy supplied by a liquid sodium cooled reactor. The Growth Concept uses Stirling engine conversion to produce 100 kWe within the constraints of mass and volume. The Growth Concept can be scaled up to produce a 1 MWe output that uses the same type reactor developed for the Baseline Concept. Assessments made for each of the program scenarios indicate the key development efforts needed to initiate detailed design and hardware program phases. Development plans were prepared for each scenario that detail the work elements and show the program activities leading to a state of flight readiness.

  7. Questions raised by the concept of nuclear damage in the ambit of the nuclear Conventions with particular regard to the German viewpoint

    International Nuclear Information System (INIS)

    Steinkemper, H.

    1985-01-01

    An important consequence of the amendment of the Paris Convention and the Brussels Supplementary Convention by the Protocols of 16 November 1982 is the replacement of the European Monetary Agreement unit of account by the International Monetary Fund's Special Drawing Right. The increase by a factor of 2.5 of the maximum amounts under the Brussels Convention is also an essential aspect of the revision. The question of damage covered by the nuclear third party liability regime was not affected by the 1982 amendments. This is why the author considers it appropriate to examine in further detail a number of important questions in this field. The paper deals with the following aspects: the scope and limits of the concept of nuclear damage; the right to be indemnified for disamenities and costs arising from evacuation and prevention measures; and the problem of the nuclear link of causality for damage likely to be attributed also to non-nuclear causes. (NEA) [fr

  8. Nuclear Power Options Viability Study. Volume 3. Nuclear discipline topics

    Energy Technology Data Exchange (ETDEWEB)

    Trauger, D B; White, J D; Bowers, H I; Braid, R B; Cantor, R A; Daniels, L; Davis, R M; Delene, J G; Gat, U; Hood, T C

    1986-09-01

    Innovative reactor concepts are described and evaluated in accordance with criteria established in the study. The reactors to be studied were chosen on the basis of three ground rules: (1) the potential for commercialization between 2000-2010, (2) economic competiveness with coal-fired plants, and (3) the degree of passive safety in the design. The concepts, classified by coolants, were light water reactors, liquid metal reactors, and high temperature reactors, and most were of modular design. All the concepts appear to be potentially viable in the time frame selected, but the information available is not adequate for a definitive evaluation of their economic competitiveness. This volume primarily reports in greater detail on several topics from the study. These are: Construction, Economics, Regulation, Safety and Economic Risk, Nuclear Waste Transportation and Disposal, and Market Acceptance. Although treated generically, the topics are presented in the context of the reactor concepts of the study.

  9. Nuclear Power Options Viability Study. Volume 3. Nuclear discipline topics

    International Nuclear Information System (INIS)

    Trauger, D.B.; White, J.D.; Bowers, H.I.

    1986-09-01

    Innovative reactor concepts are described and evaluated in accordance with criteria established in the study. The reactors to be studied were chosen on the basis of three ground rules: (1) the potential for commercialization between 2000-2010, (2) economic competiveness with coal-fired plants, and (3) the degree of passive safety in the design. The concepts, classified by coolants, were light water reactors, liquid metal reactors, and high temperature reactors, and most were of modular design. All the concepts appear to be potentially viable in the time frame selected, but the information available is not adequate for a definitive evaluation of their economic competitiveness. This volume primarily reports in greater detail on several topics from the study. These are: Construction, Economics, Regulation, Safety and Economic Risk, Nuclear Waste Transportation and Disposal, and Market Acceptance. Although treated generically, the topics are presented in the context of the reactor concepts of the study

  10. The recharge area concept: A strategy for siting nuclear waste repositories

    International Nuclear Information System (INIS)

    Sheng, G.; Toth, J.

    2000-01-01

    The Recharge Area Concept is the proposition that in Canadian-Shield type natural environments recharge areas of regional groundwater flow systems are superior for high-level nuclear waste repositories to other types of groundwater flow regimes, especially to areas of groundwater discharge. This conclusion is reached from an analysis of basinal groundwater flow models. The calculations were made for a two-dimensional flank of a fully saturated topographic basin, 20 km long and 4 km deep, in which groundwater is driven by gravity. Variants of hydraulic-conductivity distributions were considered: 1) homogeneous; 2) stratified; and 3) stratified-faulted. The faults attitudes were changed by steps from vertical to horizontal for different variants. The model is assumed conceptually to represent the crystalline-rock environment of the Canadian Shield. The hydrogeologic performances of hypothetical repositories placed 500 m deep in the recharge and discharge areas were characterized by thirteen parameters. The principal advantages of recharge- over discharge-area locations are: 1) longer travel paths and return-flow times from repository to surface; 2) robustness of predicted values of performance parameters; 3) field-verifiability of favourable hydrogeologic conditions (amounting to an implicit validation of the calculated minimum values of return-flow times); 4) site acceptance based on quantifiable and observable flow-controlling parameters; and 5) simple logistics and favourable economics of site selection and screening. As a by-product of modeling, it is demonstrated that the presence of old water is not an indication of stagnancy. (author)

  11. Selective application of revised source terms to operating nuclear power plants

    International Nuclear Information System (INIS)

    Moon, Joo Hyun; Song, Jae Hyuk; Lee, Young Wook; Ko, Hyun Seok; Kang, Chang Sun

    2001-01-01

    More than 30 years later since 1962 when TID-14844 was promulgated, there has been big change of the US NRC's regulatory position in using accident source terms for radiological assessment following a design basis accident (DBA). To replace the instantaneous source terms of TID-14844, the time-dependent source terms of NUREG-1465 was published in 1995. In the meantime, the radiological acceptance criteria for reactor site evaluation in 10 CFR Part 100 were also revised. In particular, the concept of total effective dose equivalent has been incorporated in accordance with the radiation protection standards set forth in revised 10 CFR Part 20. Subsequently, the publication of Regulatory Guide 1.183 and the revision of Standard Review Plan 15.0.1 followed in 2000, which provided the licensee of operating nuclear power reactor with the acceptable guidance of applying the revised source term. The guidance allowed the holder of an operating license issued prior to January 10, 1997 to voluntarily revise the accident source terms used in the radiological consequence analyses of DBA. Regarding to its type of application, there suggested full and selective applications, Whether it is full or selective, based upon the scope and nature of associated plant modifications being proposed, the actual application of the revised source terms to an operating plant is expected to give a large impact on its facility design basis. Considering scope and cost of the analyses required for licensing, selective application is seemed to be more appealing to an licensee of the operating plant rather than full application. In this paper, hence, the selective application methodology is reviewed and is actally applied to the assessment of offsite radiological consequence following a LOCA at Ulchin Unit 3 and 4, in order to identify and analyze the potential impacts due to application of revised source terms and to assess the considerations taken in each application prior to its actual

  12. Ecological aspects of the nuclear age: selected readings in radiation ecology

    International Nuclear Information System (INIS)

    Schultz, V.; Whicker, F.W.

    1971-01-01

    A compilation of selected readings is presented in the areas of radiation ecology, radionuclide cycling, ionizing radiation effects, radioisotope tracer techniques in ecology, and military and peaceful uses of nuclear energy

  13. Advances in nuclear fuel cycle materials and concepts. Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

    El-Sayed, A A [Materials Division, Nuclear Research Centre, Atomic Energy Authority, Cairo (Egypt)

    1996-03-01

    This presentation gives an overview of the new trends in the materials used in various steps of the nuclear fuel cycle. This will cover fuels for various types of reactors (PWRs, HTRs, ... etc.) cladding materials, control rod materials, reactor structural materials, as well as materials used in the back end of the fuel cycle. Problems associated with corrosion of fuel cladding materials as well as those in control rod materials (B{sub 4} C swelling...etc.), and approaches for combating these influences are reviewed. For the case of reactor pressure vessel materials issues related to the influences of alloy composition, design approaches including the use of more forged parts and minimizing, as for as possible, longitudinal welds especially in the central region, are discussed. Furthermore the application of techniques for recovery of pre-irradiation mechanical properties of PVS components is also covered. New candidate materials for the construction of high level waste containers including modified types of stainless steel (high Ni and high MO), nickel-base alloys and titanium alloys are also detailed. Finally, nuclear fuel cycle concepts involving plutonium and actinides recycling shall be reviewed. 28 figs., 6 tabs.

  14. Advances in nuclear fuel cycle materials and concepts. Vol. 1

    International Nuclear Information System (INIS)

    El-Sayed, A.A.

    1996-01-01

    This presentation gives an overview of the new trends in the materials used in various steps of the nuclear fuel cycle. This will cover fuels for various types of reactors (PWRs, HTRs, ... etc.) cladding materials, control rod materials, reactor structural materials, as well as materials used in the back end of the fuel cycle. Problems associated with corrosion of fuel cladding materials as well as those in control rod materials (B 4 C swelling...etc.), and approaches for combating these influences are reviewed. For the case of reactor pressure vessel materials issues related to the influences of alloy composition, design approaches including the use of more forged parts and minimizing, as for as possible, longitudinal welds especially in the central region, are discussed. Furthermore the application of techniques for recovery of pre-irradiation mechanical properties of PVS components is also covered. New candidate materials for the construction of high level waste containers including modified types of stainless steel (high Ni and high MO), nickel-base alloys and titanium alloys are also detailed. Finally, nuclear fuel cycle concepts involving plutonium and actinides recycling shall be reviewed. 28 figs., 6 tabs

  15. METHOD FOR SELECTION OF PROJECT MANAGEMENT APPROACH BASED ON FUZZY CONCEPTS

    Directory of Open Access Journals (Sweden)

    Igor V. KONONENKO

    2017-03-01

    Full Text Available Literature analysis of works that devoted to research of the selection a project management approach and development of effective methods for this problem solution is given. Mathematical model and method for selection of project management approach with fuzzy concepts of applicability of existing approaches are proposed. The selection is made of such approaches as the PMBOK Guide, the ISO21500 standard, the PRINCE2 methodology, the SWEBOK Guide, agile methodologies Scrum, XP, and Kanban. The number of project parameters which have a great impact on the result of the selection and measure of their impact is determined. Project parameters relate to information about the project, team, communication, critical project risks. They include the number of people involved in the project, the customer's experience with this project team, the project team's experience in this field, the project team's understanding of requirements, adapting ability, initiative, and others. The suggested method is considered on the example of its application for selection a project management approach to software development project.

  16. A feasibility assessment of nuclear reactor power system concepts for the NASA Growth Space Station

    Science.gov (United States)

    Bloomfield, H. S.; Heller, J. A.

    1986-01-01

    A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth Space Station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of Space Station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination.

  17. A feasibility assessment of nuclear reactor power system concepts for the NASA growth Space Station

    International Nuclear Information System (INIS)

    Bloomfield, H.S.; Heller, J.A.

    1986-01-01

    A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth space station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of space station related concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination

  18. Method of generating intense nuclear polarized beams by selective photodetachment of negative ions

    International Nuclear Information System (INIS)

    Hershcovitch, A.

    1986-01-01

    A novel method for production of nuclear polarized negative hydrogen ions by selective neutralization with a laser of negative hydrogen ions in a magnetic field is described. This selectivity is possible since a final state of the neutralized atom, and hence the neutralization energy, depends on its nuclear polarization. The main advantages of this scheme are the availability of multi-ampere negative ion sources and the possibility of neutralizing negative ions with very high efficiency. An assessment of the required laser power indicates that this method is in principle feasible with today's technology

  19. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  20. Knowledge management for the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Kirschnick, F.; Engelhardt, S.

    2004-01-01

    This paper describes background, objectives and select conceptual components of knowledge management for the decommissioning of nuclear power plants. The concept focuses on the transfer of personal practice experience within and between nuclear power plants. The conceptual insights embrace aspects of knowledge content, structure, KM processes, organization, cooperation, culture, persuasion, leadership, technology, infrastructure, business impact and resilience. Key challenges are discussed, and related advice is provided for KM practitioners with similar endeavours in the field of nuclear power plant decommissioning. (author)

  1. Engineering and innovative erection concept for the containment liner for a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Goehring, Rainer [Babcock Noell GmbH, Wuerzburg (Germany). Abt. Nukleare Projekte; Anders, Nils; Nagelstutz, Franz [Babcock Noell GmbH, Wuerzburg (Germany). Abt. Berechnung

    2010-04-15

    The determination of the optimal design of the containment liner considering amount of material, manufacturing and erection was the challenge for the engineering team of Babcock Noell GmbH. Several load cases for normal operation and accidental conditions as well as severe accidents have been analysed. The special load cases in the vicinity of penetrations and anchor plates have been calculated. The results of theses analyses have been considered in the actual design of the liner. The construction costs of a Nuclear Power Plant are also impacted by the erection time of components. Therefore, it is necessary to optimize the erection times and consequently essentially to shorten. One possibility has been demonstrated by Babcock Noell GmbH with the erection concept of a containment liner. The liner is preassembled on the pre-assembly place in rings of up to 12 meter height, with the nominal diameter of 47 meter and a weight of approximately up to 200 tonnes. These rings, as well as the containment cup and the dome, are lifted with a heavy load crane into the reactor building. With this concept, the construction activities on the inner containment wall are only five times disrupted by the welding and coating of the circumferential weld (approx. 25 calendar days). In comparison with the common known erection concept of welding of liner shells in situ, at least 20 weeks are saved on the schedule. An integrated concept from planning, manufacturing and erection of this large component has been implemented. It could be demonstrated that within the given time frame, with the required quality and within the required tolerances the containment liner for the Nuclear Power Plant can be delivered to the Client. (orig.)

  2. Engineering and innovative erection concept for the containment liner for a nuclear power plant

    International Nuclear Information System (INIS)

    Goehring, Rainer; Anders, Nils; Nagelstutz, Franz

    2010-01-01

    The determination of the optimal design of the containment liner considering amount of material, manufacturing and erection was the challenge for the engineering team of Babcock Noell GmbH. Several load cases for normal operation and accidental conditions as well as severe accidents have been analysed. The special load cases in the vicinity of penetrations and anchor plates have been calculated. The results of theses analyses have been considered in the actual design of the liner. The construction costs of a Nuclear Power Plant are also impacted by the erection time of components. Therefore, it is necessary to optimize the erection times and consequently essentially to shorten. One possibility has been demonstrated by Babcock Noell GmbH with the erection concept of a containment liner. The liner is preassembled on the pre-assembly place in rings of up to 12 meter height, with the nominal diameter of 47 meter and a weight of approximately up to 200 tonnes. These rings, as well as the containment cup and the dome, are lifted with a heavy load crane into the reactor building. With this concept, the construction activities on the inner containment wall are only five times disrupted by the welding and coating of the circumferential weld (approx. 25 calendar days). In comparison with the common known erection concept of welding of liner shells in situ, at least 20 weeks are saved on the schedule. An integrated concept from planning, manufacturing and erection of this large component has been implemented. It could be demonstrated that within the given time frame, with the required quality and within the required tolerances the containment liner for the Nuclear Power Plant can be delivered to the Client. (orig.)

  3. Advanced concepts for waste management and nuclear energy production in the EURATOM 5. framework programme

    International Nuclear Information System (INIS)

    Hugon, M.; Bhatnagar, V.P.; Martin Bermejon, J.

    2002-01-01

    This paper summarises the objectives of the research projects on partitioning and transmutation (P and T) of long-lived radionuclides in nuclear waste and advanced systems for nuclear energy production in the key action on nuclear fission of the EURATOM 5. Framework Programme (FP5) (1998-2002). As these FP5 projects cover the main aspects of P and T, they should provide a basis for evaluating the practicability, on an industrial scale, of P and T for reducing the amount of long-lived radionuclides to be disposed of. Concerning advanced concepts, a cluster of projects is addressing the key technical issues to be solved before implementing high-temperature reactors (HTRs) commercially for energy production. Finally, the European Commissions proposal fora New Framework Programme (2002-2006) is briefly outlined. (authors)

  4. Advanced concepts for waste management and nuclear energy production in the EURATOM fifth framework programme

    International Nuclear Information System (INIS)

    Hugon, M.; Bhatnagar, V.P.; Martin Bermejo, J.

    2001-01-01

    This paper summarises the objectives of the research projects on Partitioning and Transmutation (P and T) of long lived radionuclides in nuclear waste and advanced systems for nuclear energy production in the key action on nuclear fission of the EURATOM Fifth Framework Programme (FP5) (1998-2002). As these FP5 projects cover the main aspects of P and T, they should provide a basis for evaluating the practicability, on an industrial scale, of P and T for reducing the amount of long lived radionuclides to be disposed of. Concerning advanced concepts, a cluster of projects is addressing the key technical issues to be solved before implementing High Temperature Reactors (HTRs) commercially for energy production. Finally, the European Commission(tm)s proposal for a New Framework Programme (2002-2006) is briefly outlined. (author)

  5. Nuclear energy: public controversies and the analysis of risks

    International Nuclear Information System (INIS)

    Sills, D.L.

    1984-01-01

    Energy is a social concept, the product of social, economic, and political processes that define certain raw materials as resources and thus convert them into usable energy. Like all social concepts, energy is controversial. Out of a wide range of controversies, three are selected for analysis here: (1) the relationship of nuclear power systems to nuclear weapons proliferation; (2) the risks of terrorism and sabotage associated with the operation of nuclear power facilities, including threats to civil liberties; and (3) the problems associated with the long-term management of radioactive wastes. The final section of the paper describes various modes of analyzing risks and the perception of risks. It is concluded that it may take many decades to learn whether nuclear energy is as natural a source of electrical power as wells are of drinking water, or whether nuclear energy is a horror that mankind in the 1980s or 1990s took a hard look at and then backed away. (author)

  6. Regulatory Aspects for Site Selection for Radiological and Nuclear Installations

    International Nuclear Information System (INIS)

    Sirag, N.M.

    2016-01-01

    The purpose of this research is to check in one of the considerations necessary for any new nuclear facility. A previous study that was conducted using a questionnaire reported that general admission to the public, aesthetic considerations, and characteristics associated with the site are able to adequately accept the existence of new nuclear facilities. The findings of this research revealed that public involvement in the process of site selection and in the design of nuclear power plants, an understanding of their point of view is an important aspect of a participatory approach. An important factor for any new nuclear program is to improve confidence in the energy choices in the future. A survey was conducted on 1304 adults to, to get the main goal. The study concluded showed that the prevalence of culture of safety reflected on the public acceptance of the site, especially if it takes into account the aesthetic and environmental considerations.

  7. A new advanced safe nuclear reactor concept

    International Nuclear Information System (INIS)

    Sefidvash, Farhang

    1999-01-01

    The reactor design is based on fluidized bed concept and utilizes pressurized water reactor technology. The fuel is automatically removed from the reactor by gravity under any accident condition. The reactor demonstrates the characteristics of inherent safety and passive cooling. Here two options for modification to the original design are proposed in order to increase the stability and thermal efficiency of the reactor. A modified version of the reactor involves the choice of supercritical steam as the coolant to produce a plant thermal efficiency of about 40%. Another is to modify the shape of the reactor core to produce a non-fluctuating bed and consequently guarantee the dynamic stability of the reactor. The mixing of Tantalum in the fuel is also proposed as an additional inhibition to power excursion. The spent fuel pellets may not be considered nuclear waste since they are in the shape and size that can easily be used as a a radioactive source for food irradiation and industrial applications. The reactor can easily operate with any desired spectrum by varying the porosity in order to be a plutonium burner or utilize a thorium fuel cycle. (author)

  8. Decree of the State Office for Nuclear Safety No. 147/1997 of 17 June 1997 specifying lists of selected nuclear-related items and dual-use nuclear-related items

    International Nuclear Information System (INIS)

    1997-01-01

    The core of the Decree consists of 2 lists, viz (a) the List of Selected Items (selected nuclear-related materials, equipment and technologies) which are subject to control regimes during imports, exports and transit; and (b) the List of Dual-Use Items (dual-use nuclear-related materials, equipment and technologies) which are subject to control regimes during imports and exports. Both Lists are based on the IAEA document INFCIRC/254/Rev.2/Part 2/Mod.1. (P.A.)

  9. Liabilities for the decommissioning and disposal in the nuclear area. Analysis and concept of reformation

    International Nuclear Information System (INIS)

    Meyer, Bettina

    2012-01-01

    The contribution under consideration examines the adequacy of the reserves for decommissioning / dismantling and disposal in order to finance long-term tasks. A reform concept is presented. The two key components of the reformation are the establishment of a public fund for the long-term obligations and a stronger insolvency protection of medium-term nuclear liabilities.

  10. Nuclear heat source component design considerations for HTGR process heat reactor plant concept

    International Nuclear Information System (INIS)

    McDonald, C.F.; Kapich, D.; King, J.H.; Venkatesh, M.C.

    1982-01-01

    Using alternate energy sources abundant in the U.S.A. to help curb foreign oil imports is vitally important from both national security and economic standpoints. Perhaps the most forwardlooking opportunity to realize national energy goals involves the integrated use of two energy sources that have an established technology base in the U.S.A., namely nuclear energy and coal. The coupling of a high-temperature gas-cooled reactor (HTGR) and a chemical process facility has the potential for long-term synthetic fuel production (i.e., oil, gasoline, aviation fuel, hydrogen, etc.) using coal as the carbon source. Studies are in progress to exploit the high-temperature capability of an advanced HTGR variant for nuclear process heat. The process heat plant discussed in this paper has a 1170-MW(t) reactor as the heat source and the concept is based on indirect reforming, i.e., the high-temperature nuclear thermal energy is transported (via an intermediate heat exchanger (IHX)) to the externally located process plant by a secondary helium transport loop. Emphasis is placed on design considerations for the major nuclear heat source (NHS) components, and discussions are presented for the reactor core, prestressed concrete reactor vessel (PCRV), rotating machinery, and heat exchangers

  11. Analyses of the double-layed repository concepts for spent nuclear fuels

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Youl; Kim, Hyeona; Lee, Min Soo; Choi, Heui Joo; Kim, Kyung Su [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-06-15

    A deep geological disposal at a depth of 500 m in stable host rock is considered to be the safest method with current technologies for disposal of spent fuels classified as high-level radioactive waste. The most important requirement is that the temperature of the bentonite buffer, which is a component of the engineered barrier, should not exceed 100℃. In Korea, the amount of spent fuel generated by nuclear power generation, which accounts for about 30% of the total electricity, is continuously increasing and accumulating. Accordingly, the area required to dispose of it is also increasing. In this study, various duplex disposal concepts were derived for the purpose of improving the disposal efficiency by reducing the disposal area. Based on these concepts, thermal analyses were carried out to confirm whether the critical disposal system requirements were met, and the thermal stability of the disposal system was evaluated by analyzing the results. The results showed that upward 75 m or downward 75 m apart from the reference disposal system location of 500 m depth would qualify for the double layered disposal concept. The results of this study can be applied to the establishment of spent fuel management policy and the design of practical commercial disposal system. Detailed analyses with data of a real disposal site are necessary.

  12. Selection and verification of safety parameters in safety parameter display system for nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Yuangfang

    1992-02-01

    The method and results for safety parameter selection and its verification in safety parameter display system of nuclear power plants are introduced. According to safety analysis, the overall safety is divided into six critical safety functions, and a certain amount of safety parameters which can represent the integrity degree of each function and the causes of change are strictly selected. The verification of safety parameter selection is carried out from the view of applying the plant emergency procedures and in the accident man oeuvres on a full scale nuclear power plant simulator

  13. Improving versus maintaining nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    The concept of improving nuclear safety versus maintaining it has been discussed at a number of nuclear regulators meetings in recent years. National reports have indicated that there are philosophical differences between NEA member countries about whether their regulatory approaches require licensees to continuously improve nuclear safety or to continuously maintain it. It has been concluded that, while the actual level of safety achieved in all member countries is probably much the same, this is difficult to prove in a quantitative way. In practice, all regulatory approaches require improvements to be made to correct deficiencies and when otherwise warranted. Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publication provides an overview of current nuclear regulatory philosophies and approaches, as well as insights into a selection of public perception issues. This publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

  14. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  15. Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

    Energy Technology Data Exchange (ETDEWEB)

    Malbasa, N [Ekonerg, Zagreb (Croatia)

    2008-07-01

    A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

  16. Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

    International Nuclear Information System (INIS)

    Malbasa, N.

    2008-01-01

    A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

  17. Microbial issues pertaining to the Canadian concept for the disposal of nuclear fuel waste

    International Nuclear Information System (INIS)

    Stroes-Gascoyne, S.; West, J.M.

    1994-03-01

    AECL Research is developing a concept for the permanent disposal of nuclear fuel waste in plutonic rock of the Canadian Shield. The Federal Environmental Assessment Review Panel has issued a set of guidelines to be used by AECL Research in preparing an Environmental Impact Statement (EIS) for this concept. These guidelines require that the EIS address a number of microbiological factors and their potential to affect the integrity of the multiple barrier system on which the disposal concept is based. This report formulates a number of views and positions on microbiological factors that could influence the performance of a disposal vault in plutonic rock. Microbiological factors discussed include the presence and survival of microbes, biofilms, corrosion, biodegradation (of emplaced materials), gas production, geochemical changes, radionuclides migration, colloid formation, mutation, pathogens and methylation. Not all issues can be fully resolved with the current state of knowledge. Studies being performed to underscore and strengthen current knowledge are briefly discussed. (author). 92 refs., 1 tab

  18. Retrievability - a matter of public acceptance? Reflections on the public review of the proposed nuclear fuel waste disposal concept in Canada

    International Nuclear Information System (INIS)

    Riverin, G.

    2000-01-01

    Environmental assessment has been used as a planning tool in Canada for almost three decades. Public participation, one of its fundamental principles, is at the heart of environmental assessment in our country. To date, approximately 12 large projects related to nuclear energy have been the subject of public reviews by independent panels of experts appointed by the Government of Canada. These include: the development of uranium mines in Northern Saskatchewan; the construction and operation of two CANDU reactors in New-Brunswick, the second of which was never constructed; proposed uranium hexafluoride refineries in Ontario and Saskatchewan; expansion of a dry storage facility for nuclear spent fuel in Quebec; and decommissioning of uranium mine tailings areas in Ontario. All of the assessments mentioned above were conducted under the environmental assessment regimes of 1975 and 1984 that preceded the Canadian Environmental Assessment Act (1995). One of the public reviews of particular interest to this workshop is that of the proposed concept for deep geological disposal of nuclear fuel waste in Canada. This paper focuses exclusively on the public review of the Nuclear Fuel Waste Disposal Concept developed by Atomic Energy of Canada Limited (AECL), particularly as it relates to public acceptance of retrievability. The paper first describes the historical context in which AECL's concept was developed prior to the public review. It then briefly outlines the changes in the societal context that occurred between the time when decisions were made to proceed with the development of the concept in 1978 and the time when public hearings were held in 1996-1997 and the panel report was presented to the government in 1998. It also provides a short description of the concept itself. The paper then presents a discussion of the arguments used by the public in the panel review, arguments, which demonstrate a decrease in confidence in a concept lacking effective postclosure

  19. Safety concept of nuclear power plants in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schnurer, H.L.; Seipel, H.G.

    1983-01-01

    The safety philosophy of the Federal Republic of Germany (FRG) pertaining to nuclear power plants is presented. Its general approach makes much use of research and experience in other countries, especially the United States, but the FRG has also evolved approaches and aspects unique to itself. The article discusses the institutional interrelationships of the entities affecting German nuclear power plant safety and presents the resulting German safety philosophy. This philosophy is based, as in the United States, on multilevel defenses but with greater reliance on a number of accident-prevention and/or -mitigation concepts, including: (1) automated responses to off-normal conditions, (2) an operating-limit system that acts before initiation of protective actions by the reactor protection system, (3) multistrand independent safety trains, and (4) long-term self-contained safety under accident conditions without operator intervention. The practical realization of this philosophy in the design and operation of the chief reactor systems is described

  20. Site selection and evaluation for nuclear power plants with respect to population distribution

    International Nuclear Information System (INIS)

    1980-01-01

    This safety guide, relating population distribution to site selection and evaluation, for nuclear power plants, forms part of the IAEA's programme, referred to as the NUSS programme (Nuclear Safety Standards). The guide presents population distribution data, requirements, examples of site screening methods, and an overview of radiological impact assessment with respect to population distribution

  1. Selected topics in nuclear electronics

    International Nuclear Information System (INIS)

    1988-03-01

    The IAEA training courses in the field of nuclear electronics heavily rely upon practical work in the laboratory. Accordingly, the IAEA has produced and published the Nuclear Electronics Laboratory Manual (TECDOC 309) where the experience on organizing the efficient practical training in nuclear electronics was compiled. The present publication is focused on the theoretical understanding of basic electronic circuits and is of particular importance to the attendees of the IAEA training course. The present publication does not copy any available book on nuclear electronics and instrumentation. On purpose, it does not describe the elementary electronics circuits as applied in nuclear instruments; they can be found in books. It starts the nuclear electronics study on the instruments level, continues to describe the technology and circuitries on the board level, and only in some exceptional cases investigates the circuits on the components level. It is believed that such an approach better reflects the advanced status of nuclear electronics and the philosophy of the modern design of nuclear instruments. For illustration, and wherever it appeared useful, some commercial instruments are described and analyzed. Figs and tabs

  2. Selected topics in nuclear electronics

    International Nuclear Information System (INIS)

    1986-01-01

    The IAEA training courses in the field of nuclear electronics heavily rely upon practical work in the laboratory. Accordingly, the IAEA has produced and published the Nuclear Electronics Laboratory Manual (TECDOC 309) where the experience on organizing the efficient practical training in nuclear electronics was compiled. The present publication is focused on the theoretical understanding of basic electronic circuits and is of particular importance to the attendees of the IAEA training course. The present publication does not copy any available book on nuclear electronics and instrumentation. On purpose, it does not describe the elementary electronics circuits as applied in nuclear instruments; they can be found in books. It starts the nuclear electronics study on the instruments level, continues to describe the technology and circuitries on the board level, and only in some exceptional cases investigates the circuits on the components level. It is believed that such an approach better reflects the advanced status of nuclear electronics and the philosophy of the modern design of nuclear instruments. For illustration, and wherever it appeared useful, some commercial instruments are described and analyzed

  3. An Investigation of Self-Concept, Clothing Selection, and Life Satisfaction among Disabled Consumers

    Science.gov (United States)

    Chang, Hyo Jung

    2012-01-01

    This dissertation investigates the relationships between various aspects of self-concept (i.e., generalized self-efficacy, public self-consciousness, state hope, and self-esteem), clothing selection (i.e., clothing that expresses individuality, clothing that improves the emotional state, clothing that camouflages the body), and life satisfaction…

  4. Nuclear power safety

    International Nuclear Information System (INIS)

    1991-11-01

    This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

  5. The Establishment of Object Selection Criteria for Effect Analysis of Electromagnetic Pulse (EMP) in Operating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Ye, Song Hae; Ryu, Hosun; Kim, Minyi; Lee, Euijong [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The electromagnetic pulse (EMP) can be used as a strategic weapon by inducing damaging voltage and currents that the electrical circuits are not designed to withstand. EMPs are lethal to electronic systems. All EMP events have three common components: a source, coupling path, and receptor. It can also travel across power grids, destroying electronics as it passes in less than a second. There have been no research studies on the effect analysis for EMP in domestic nuclear power plants and power grids. To ensure the safety of operating nuclear power plants in this environment, the emission of EMP is needed for the effect analysis and safety measures against EMPs. Actually, it is difficult and inefficient to conduct the effect analysis of EMP with all the equipment and systems in nuclear power plants (NPPs). Therefore, this paper presents the results of establishing the object selection criteria for the effect analysis of EMP in operating nuclear power plants through reviewing previous research in the US and the safety related design concepts in domestic NPPs. It is not necessary to ensure the continued operation of the plant in intense multiple EMP environments. The most probable effect of EMP on a modern nuclear power plant is an unscheduled shutdown. EMP may also cause an extended shutdown by the unnecessary activation of some safety related systems. In general, EMP can be considered a nuisance to nuclear plants, but it is not considered a serious threat to plant safety. The results of EMP effect analysis show less possibility of failure in the tested individual equipment. It was also confirmed that there is no possibility of simultaneous failure for devices in charge of the safety shutdown in the NPP.

  6. Hanford Nuclear Energy Center: a conceptual study

    Energy Technology Data Exchange (ETDEWEB)

    Harty, H. (comp.)

    1978-09-30

    The objective of the study is to develop an improved understanding of the nuclear energy center (NEC) concept and to identify research and development needed to evaluate the concept fully. A specific context was selected for the study--the Hanford site. Thus, the study primarily addresses the HNEC concept, but the findings are extrapolated to generic NECs where possible. The major emphasis in the HNEC study was to explore potential technical and environmental problems in a specific context and in sufficient detail to evaluate potential problems and propose practical solutions. The areas of concern are typical of those considered in preparing environmental and safety analysis reports, including: topics dealing with engineering choices (e.g., site selection, heat sink management, electrical transmission, and reliability of generation); environmental matters (e.g., terrestrial and radiological effects); socioeconomic factors (e.g., community impacts); and licensing considerations.

  7. Site selection for Canada's national repository for used nuclear fuel

    International Nuclear Information System (INIS)

    Ben Belfadhel, M.; Watts, B.; Facella, J.

    2015-01-01

    In 2007, the Government of Canada selected Adaptive Phased Management as Canada's plan for the long-term management of Canada's used nuclear fuel. The approach provides for containment and isolation of the material in a deep geological repository at a safe site with an informed and willing host. The Nuclear Waste Management Organization is tasked through federal legislation with selecting the site and developing and managing all aspects of the plan. In May 2010, the organization published and initiated the site selection process that serves as a road map for decision making on the location for the deep geological repository. It continues to lead the site selection process for the repository and an associated Centre of Expertise. The screening process is advancing and, from an initial starting point of 22 communities expressing interest in learning about the project; as of September 2015, 9 communities are the focus of more detailed technical and community well-being studies. Preliminary Assessments, the third step in the 9-step site selection process are underway in these communities. The Assessments involve preliminary technical and social desktop and field assessments, engagement activities within and beyond each interested community, and involvement of Indigenous peoples and nearby municipalities in the planning and conduct of the work. This paper provides an update on the advancement of the site selection process. It describes the nature of the technical and social studies being conducted at this phase of work, including the progressively more detailed field studies that are the focus of technical work at the current stage, the approach to engagement and collaboration with communities to direct these studies, and the work underway to ensure the framework used for this assessment and engagement includes the range of priorities and perspectives of First Nations and Metis peoples and communities in the broader area. (author)

  8. AECB staff response to the environmental impact statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1995-07-01

    The Environmental Impact Statement (EIS) on the Concept for Disposal of Canada's Nuclear Fuel Waste was released in October 1994 (AECL,1994) in response to the guidelines issued in 1992 by a Panel formed to evaluate this concept (Federal Environmental Assessment Review Panel, 1992). This response is primarily a statement of deficiencies and thus focuses on the negative aspects of the EIS. The staff review of the EIS was based on the AECB mandate, which is to protect human health and the environment and as such was focused on technical issues in the EIS. These were performance assessment of the multiple barrier system, environmental impacts, concept feasibility, siting, transport and safety as well as general issues of regulatory policy and criteria. The EIS and its supporting documentation have been the sole basis used to judge whether AECB staff expectations of the EIS have been met. The staff response (Part II) considers whether an issue is addressed appropriately and adequately, while taking account of the generic and preliminary nature of the concept. The overall conclusion that AECB staff have drawn from the technical review of the EIS is that the EIS, by itself, does not adequately demonstrate the case for deep geological disposal for nuclear fuel waste. However, AECB staff believe that the EIS information, in combination with a variety of generic national and international assessments, has provided confidence that the deep geological disposal concept is safe and viable. 74 refs

  9. Cation-selective extraction column study for the conception of nuclear medical radionuclide generators; Untersuchung kationenselektiver Extraktionssaeulen zur Konzeption nuklearmedizinischer Radionuklidgeneratoren

    Energy Technology Data Exchange (ETDEWEB)

    Streng, Roman

    2012-07-09

    The topic of the present work is the conception of a Yttrium-90 radionuclide generator for nuclear medicine applications. Due to its physical properties Yttrium-90 is considered as one of the most useful nuclides for radiotherapeutic cancer treatment. The parent nuclide Strontium-90 is gained during reprocessing of fission products. Thus, the sustained availability of large quantities of Yttrium-90 is limited to a number of research facilities. A radionuclide generator provides an independent Yttrium-90 source and enhances the capacities for radiopharmaceutical research and biomedical applications. The present work focussed on the identification of appropriate column materials for the separation of Strontium and Yttrium. The results for two materials are reported: AnaLig {sup registered} Sr-01 and crystalline antimonic acid. Based on the mode of operation of the Technetium-99m generator the aim was to enable the construction of a compact, enclosed apparatus. The projected device comprises a reservoir for the eluant, the ion-exchange column, pipings and radiation shielding. Elution of Yttrium-90 could then be easily performed by connecting evacuated vials to the outlet tube. The prospected concept involves physical and chemical confinements that exclude most of the known processes for Strontium-Yttrium separation. For example no ligands, no oxidizing reactants (e.g. nitric acid) and no organic solvents are to be used, but small volumes of isotonic or buffer solutions and dilute acids respectively. AnaLig {sup registered} Sr-01 is a commercially available resin used in extraction chromatography. Its high selectivity for Strontium cations results from the strictly defined cavity of the imbedded cryptand. Determination of weight distribution coefficients, elution studies and pre-generator experiments were carried out. Quantitative separation of Yttrium from Strontium and Zirconium is possible using small volumes of 0,05 M hydrochloric acid as eluant. Furthermore, high

  10. Concept of Lunar Energy Park

    Science.gov (United States)

    Niino, Masayuki; Kisara, Katsuto; Chen, Lidong

    1993-10-01

    This paper presents a new concept of energy supply system named Lunar Energy Park (LEP) as one of the next-generation clean energy sources. In this concept, electricity is generated by nuclear power plants built on the moon and then transmitted to receiving stations on the earth by laser beam through transporting systems situated in geostationary orbit. The lunar nuclear power plants use a high-efficiency composite energy conversion system consisting of thermionic and thermoelectric generators to change nuclear thermal energy into electricity directly. The nuclear resources are considered to be available from the moon, and nuclear fuel transport from earth to moon is not necessary. Because direct energy conversion systems are employed, the lunar nuclear plants can be operated and controlled by robots and are maintenance-free, and so will cause no pollution to humans. The key technologies for LEP include improvements of conversion efficiency of both thermionic and thermoelectric converters, and developments of laser-beam power transmission technology as well. The details, including the construction of lunar nuclear plants, energy conversion and energy transmission systems, as well as the research plan strategies for this concept are reviewed.

  11. Concept of voltage monitoring for a nuclear power plant emergency power supply system (PWR 1300 MWe)

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1988-01-01

    Voltage monitoring concept for a Nuclear Power Plant Emergency Power Supply Systems (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and 3 NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  12. Conventional and Bimodal Nuclear Thermal Rocket (NTR) Artificial Gravity Mars Transfer Vehicle Concepts

    Science.gov (United States)

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

    2016-01-01

    A variety of countermeasures have been developed to address the debilitating physiological effects of zero-gravity (0-g) experienced by cosmonauts and astronauts during their approximately 0.5 to 1.2 year long stays in low Earth orbit (LEO). Longer interplanetary flights, combined with possible prolonged stays in Mars orbit, could subject crewmembers to up to approximately 2.5 years of weightlessness. In view of known and recently diagnosed problems associated with 0-g, an artificial gravity (AG) spacecraft offers many advantages and may indeed be an enabling technology for human flights to Mars. A number of important human factors must be taken into account in selecting the rotation radius, rotation rate, and orientation of the habitation module or modules. These factors include the gravity gradient effect, radial and tangential Coriolis forces, along with cross-coupled acceleration effects. Artificial gravity Mars transfer vehicle (MTV) concepts are presented that utilize both conventional NTR, as well as, enhanced bimodal nuclear thermal rocket (BNTR) propulsion. The NTR is a proven technology that generates high thrust and has a specific impulse (Isp) capability of approximately 900 s-twice that of today's best chemical rockets. The AG/MTV concepts using conventional Nuclear Thermal Propulsion (NTP) carry twin cylindrical International Space Station (ISS)- type habitation modules with their long axes oriented either perpendicular or parallel to the longitudinal spin axis of the MTV and utilize photovoltaic arrays (PVAs) for spacecraft power. The twin habitat modules are connected to a central operations hub located at the front of the MTV via two pressurized tunnels that provide the rotation radius for the habitat modules. For the BNTR AG/MTV option, each engine has its own closed secondary helium(He)-xenon (Xe) gas loop and Brayton Rotating Unit (BRU) that can generate 10s of kilowatts (kWe) of spacecraft electrical power during the mission coast phase

  13. Nuclear substructure reorganization during late stageerythropoiesis is selective and does not involve caspase cleavage ofmajor nuclear substructural proteins

    Energy Technology Data Exchange (ETDEWEB)

    Krauss, Sharon Wald; Lo, Annie J.; Short, Sarah A.; Koury, MarkJ.; Mohandas, Narla; Chasis, Joel Anne

    2005-04-06

    Enucleation, a rare feature of mammalian differentiation, occurs in three cell types: erythroblasts, lens epithelium and keratinocytes. Previous investigations suggest that caspase activation functions in lens epithelial and keratinocyte enucleation, as well as in early erythropoiesis encompassing BFU-E differentiation to proerythroblast. To determine whether caspase activation contributes to later erythropoiesis and whether nuclear substructures other than chromatin reorganize, we analyzed distributions of nuclear subcompartment proteins and assayed for caspase-induced cleavage of subcompartmental target proteins in mouse erythroblasts. We found that patterns of lamin B in the filamentous network interacting with both the nuclear envelope and DNA, nuclear matrix protein NuMA, and splicing factors Sm and SC35 persisted during nuclear condensation, consistent with effective transcription of genes expressed late in differentiation. Thus nuclear reorganization prior to enucleation is selective, allowing maintenance of critical transcriptional processes independent of extensive chromosomal reorganization. Consistent with these data, we found no evidence for caspase-induced cleavage of major nuclear subcompartment proteins during late erythropoiesis, in contrast to what has been observed in early erythropoiesis and in lens epithelial and keratinocyte differentiation. These findings imply that nuclear condensation and extrusion during terminal erythroid differentiation involve novel mechanisms that do not entail major activation of apoptotic machinery.

  14. Analytical hierarchy process for the selection of nuclear reactors for Mexico

    International Nuclear Information System (INIS)

    Martin-Del-Campo, C.; Nelson, P. F.; Francois, J. L.

    2008-01-01

    The Analytical Hierarchy Process (AHP) was applied as a decision making technique to select the next new nuclear power reactor for Mexico. The main objective is to select the most suitable nuclear reactor technology for Mexico, to start the bidding process within one or two years, and the reactor to initiate commercial operation by 2016. Four alternatives which comply with these specific restrictions were compared: the Advanced Boiling Water Reactor (AB WR) from General Electric, Hitachi and Toshiba; the European Pressurized Water Reactor (ERR) from AREVA; the pressurized water reactor - advanced passive plant, AP1000, from Westinghouse; and the Economic Simplified Boiling Water Reactor (ESBWR) from General Electric. The evaluation criteria include economic and safety indicator, some of them quantitative and others qualitative. Additional complexity to the solution of this problem is that there are stakeholders that can be involved in the definition of the evaluation criteria and in the definition of relative importance between them, according to each stakeholder interests or benefits. Only the two main stakeholders were considered, these are the Federal Commission of Electricity (Comision Federal de Electricidad, CFE) and the National Commission of Nuclear Safety and Safeguards (Comision Nacional de Seguridad Nuclear y Salvaguardias, CNSNS). Considering the evaluation criteria used and the authors' assessment of their importance, the ABWR was ranked the highest. Sensitivity analyses were performed in order to define the most suitable reactor for the needs of Mexico. (authors)

  15. Feasibility study of a zone approach concept for the nuclear fuel cycle of Argentina

    International Nuclear Information System (INIS)

    Saavedra, Analia D.; Castro, Laura B.; Mairal, M.L.; Maceiras, Elena; Fernandez Moreno, Sonia; Vicens, Hugo E.; Llacer, Carlos D.; Valentino, Lucia I.

    1999-01-01

    An important part of the nuclear material inventory in Argentina is placed in the nuclear fuel cycle devoted to nuclear power generation, with a high frequency of transfers of such material amongst the nuclear facilities involved. These facilities mostly handle natural uranium. At present, the safeguards systems for these facilities is based on 'Facility Approach' concept. Therefore, for each one of them an independent safeguards approach is applied. However, there are specific procedures that while maintaining or increasing safeguards effectiveness may reduce the inspection resources required in the field. One of these procedures is the 'Zone Approach', by means of which there is a reduction in the need for verifying inventory changes amongst the involved facilities and provides assurance against borrowing of nuclear material within the zone. This paper describes the features of the facilities included in the study, the present safeguards approach applied to them and a feasibility analysis of a zone approach scheme. The comparison between 'facility specific approach' and a 'zone approach' would allow determining whether a reduction of the inspection effort currently applied to fulfil the quantitative safeguards criteria in force for these facilities is obtained. On the other hand, a result showing a relevant reduction on the inspection effort while maintaining safeguards effectiveness would permit to re-orient these resources for an optimum application of the 'Strengthened Safeguards System'. (author)

  16. Selective separation of radionuclides from nuclear waste solutions with inorganic ion exchangers

    International Nuclear Information System (INIS)

    Lehto, J.; Harjula, R.

    1999-01-01

    Nuclear industry produces and stores large volumes of radioactive waste solutions. Removal of radionuclides from the solutions is an important and challenging task for two main reasons: reductions in the volumes of solidified waste, which have to be disposed of, and reductions in the radioactive discharges into the environment. Since the radioactive elements in most waste solutions are in trace concentrations and the waste solutions contain large excesses of inactive metal ions, highly selective separation methods are needed for the removal of radionuclides. A number of inorganic ion exchange materials are very selective to key radionuclides and they can play an important role in solving these problems. The spectrum of nuclear waste solutions is rather wide considering their radionuclide contents, concentrations of interfering salts and acidity/alkalinity. Therefore, several inorganic ions exchangers are needed for the removal of most harmful radionuclides from a variety of solutions. This paper discusses the use and requirements of inorganic ion exchange materials in nuclear waste management. Special attention is paid to the novel ion exchange materials developed in the Laboratory of Radiochemistry, University of Helsinki. (orig.)

  17. Accelerator-driven sub-critical target concept for transmutation of nuclear wastes

    International Nuclear Information System (INIS)

    Van Tuyle, G.J.; Todosow, M.; Aronson, A.L.; Takahashi, H.; Geiger, M.J.

    1991-01-01

    A means of transmuting key long-lived nuclear wastes, primarily the minor actinides (Np, Am, Cm) and iodine, using a hybrid proton accelerator and sub-critical lattice, is proposed. By partitioning the components of the light water reactor (LWR) spent fuel and by transmuting key elements, such as the plutonium, the minor actinides, and a few of the long-lived fission products, some of the most significant challenges in building a waste repository can be substantially reduced. The proposed machine, based on the described PHOENIX Concept, would transmute the minor actinides and the iodine produced by 75 LWRs, and would generate usable electricity (beyond that required to run the large accelerator) of 850 MW e . 19 refs., 20 figs

  18. Concept of the development of new type reactor and other nuclear technology in which nuclear-proliferation resistivity is taken into consideration

    International Nuclear Information System (INIS)

    Chang, Yoon I.

    2000-01-01

    As we start a new century in a new millennium, it is timely to look back at the last 50 years of nuclear energy development, and take a pause here to formulate the directions we need to take in the nuclear energy development for the next 50 years and beyond. The proliferation resistivity should be given a priority in the development of next-generation advanced reactor concepts, and there are three important principles to be considered in such efforts. The proliferation resistivity should be considered as a part of broader objectives, rather than a design goal by itself; the proliferation resistivity should be considered within the context of global institutional framework; and any technical proliferation resistivity features designed into the reactor system should be made intrinsic in nature. (author)

  19. Personnel planning and employment: Organizational concepts for safer power plant operation

    International Nuclear Information System (INIS)

    Mueller, K.H.

    1984-01-01

    Well thought out plant-specific organisation, proper staff selection, careful training, far-sighted management and an optimum man-machine relationship; this together guarantees problem-free operation of nuclear power plants. Organizational concepts must not be considered as statistical values. The management must maintain the capacity of re-thinking and, if necessary, leaving the beaten track of organizational routines. (orig./HSCH) [de

  20. Can the acceptance of nuclear reactors be raised by a simpler, more transparent safety concept employing improved containments?

    International Nuclear Information System (INIS)

    Krieg, R.

    1993-01-01

    Sociological and psychological findings are presented which describe problems society faces with risky technologies. It turns out that for a small but influential group of the society not only the risk, but also the transparency of the technology and the engineered safeguards are important. For this group an improvement of the transparency should raise the acceptance of the technology. However, for the majority of the public, broad discussions about a different more transparent safety concept could generate a feeling of insecurity, especially concerning existing nuclear power plants. In order to improve the transparency in engineered safeguards of nuclear reactors, four basic principles are introduced. Nuclear containments, which remain intact after failure of all emergency cooling systems resulting in a core meltdown accident with steam and hydrogen explosions, are in line with these principles. Such containments are under investigation in Germany right now. It is pointed out that the public should be informed prudently about this work to improve the containments, and the required transparency of the engineered safeguards should be underlined as a major goal. Vague descriptions, providing only superficially information about safer reactors, could easily cause misunderstandings. If one goes along this line a simpler and more transparent safety concept employing improved containments will have the potential to raise the acceptance of nuclear reactors. (orig.)

  1. Selected concrete spent fuel storage cask concepts and the DOE/PSN Cooperative Cask Testing Program

    International Nuclear Information System (INIS)

    Creer, J.M.; McKinnon, M.A.; Collantes, C.E.

    1990-01-01

    To date, water pools, metal casks, horizontal concrete modules, and modular vaults have been used to store the major quantity of commercial light water reactor spent nuclear fuel. Recently, vertical concrete dry storage casks have received consideration for storage of spent nuclear fuel. This paper reviews the evolution of the development of selected vertical concrete dry storage casks and outlines a cooperative cask testing (heat transfer and shielding) program involving the US Department of Energy and Pacific Sierra Nuclear Associates. Others participating in the cooperative program are Pacific Northwest Laboratory; EG ampersand G Idaho, Inc.; Wisconsin Electric Power Company; and the Electric Power Research Institute. 28 refs., 14 figs

  2. Space nuclear reactor concepts for avoidance of a single point failure

    International Nuclear Information System (INIS)

    El-Genk, M. S.

    2007-01-01

    This paper presents three space nuclear reactor concepts for future exploration missions requiring electrical power of 10's to 100's kW, for 7-10 years. These concepts avoid a single point failure in reactor cooling; and they could be used with a host of energy conversion technologies. The first is lithium or sodium heat pipes cooled reactor. The heat pipes operate at a fraction of their prevailing capillary or sonic limit. Thus, when a number of heat pipes fail, those in the adjacent modules remove their heat load, maintaining reactor core adequately cooled. The second is a reactor with a circulating liquid metal coolant. The reactor core is divided into six identical sectors, each with a separate energy conversion loop. The sectors in the reactor core are neurotically coupled, but hydraulically decoupled. Thus, when a sector experiences a loss of coolant, the fission power generated in it will be removed by the circulating coolant in the adjacent sectors. In this case, however, the reactor fission power would have to decrease to avoid exceeding the design temperature limits in the sector with a failed loop. These two reactor concepts are used with energy conversion technologies, such as advanced Thermoelectric (TE), Free Piston Stirling Engines (FPSE), and Alkali Metal Thermal-to- Electric Conversion (AMTEC). Gas cooled reactors are a better choice to use with Closed Brayton Cycle engines, such as the third reactor concept to be presented in the paper. It has a sectored core that is cooled with a binary mixture of He-Xe (40 gm/mole). Each of the three sectors in the reactor has its own CBC and neutronically, but not hydraulically, coupled to the other sectors

  3. The surface water submodel for the assessment of Canada's nuclear fuel waste management concept

    International Nuclear Information System (INIS)

    Bird, G.A.; Stephenson, M.; Cornett, R.J.

    1992-12-01

    A requirement in assessing the safety of Canada's nuclear fuel waste management concept is the prediction of radiological doses to humans and other biota, which may occur far in the future as a result of releases of nuclides to the biosphere. A biosphere model has been developed, consisting of four integrated submodels describing surface water, soil, atmosphere, and food-dose components. This report documents the surface water submodel, which is a simple, generic mass balance model of a Canadian Shield lake. Nuclide input to the lake is the time-dependent mass output from the geosphere model. Nuclides enter the lake from compacted sediments. The surface water submodel calculates nuclide concentrations in lake water and sediment. These concentrations are used in the other biosphere submodels to predict the radiological dose to biota. Selection of parameter values for the model is based on the literature, our own data, and conservative assumptions to ensure that doses are not underestimated. MOst parameters are represented by log normal. This probabilistic approach of using distributed parameter values accounts for variability and uncertainty in parameter values, and short-term environmental fluctuations. Long-term environmental changes, such as glaciation, are not considered in the model. Sensitivity analysis indicates that nuclide concentrations in lake water and sediment are governed primarily by hydrological flushing, with lake catchment area being the most important parameter. When catchment area is held constant, as would occur at a specific site, lake area and nuclide transfer rate from water to sediment strongly influence concentrations in both water and sediment. Sediment accumulation rate also strongly influences sediment nuclide concentrations. Validation of model predictions using published studies and other data demonstrates that our model is realistic and suitable for assessing Canada's disposal concept. (Author)

  4. Method to assist conception of collimators in nuclear medicine

    International Nuclear Information System (INIS)

    Gantet, P.; Esquerre, J.P.; Danet, B.; Roux, G.; Guiraud, R.

    1990-01-01

    Designing a collimator should begin by an accurate computation of its performances in order to minimize the usual expensive and time consuming phase of trial and error. The authors briefly describe several methods currently used, and present a method of simulation of the percussional response of collimators. The computation takes into account the attenuation of photons by the collimator septas. An other benefit is its ability to be used whatever the geometric specifications of the collimator. The program computes spatial resolution, geometric efficiency, septal penetration, as well as slice thickness when the collimator is used with a SPECT device. The study presents the results concerning two collimators: a general purpose parallel hole commercially available and a focused parallel one dedicated to a single slice SPECT system. In conclusion, this deterministic method which takes attenuation into account for collimators performances computation should be useful tool to assist conception of new collimators in nuclear medicine [fr

  5. Study about the integrated treatment of chemical and radioactive effluents, introducing the zero release concept

    International Nuclear Information System (INIS)

    Mierzwa, Jose Carlos

    1996-01-01

    An Integrated System to the treatment of Chemical and Radioactive Effluents to the Centro Experimental Aramar is proposed and evaluated, introducing the Effluent Zero Release concept, where factors related to the environmental regulation in vigor in the country, as well as the availability of hydrological resources in the place where CEA have been implanted, are considered. Through a literature analysis of the main effluents treatment techniques available nowadays and after a case of study selection, take into account two industrial installations that will be implanted at CEA, it was defined an arrangement to compose the Integrated System to the Treatment of Chemicals and Radioactive Effluents, focusing the Zero Release concept consolidation. A defined arrangement uses a combination among three treatment processes, it means chemical precipitation, reverse osmosis and evaporation, that were experimentally evaluated. The proposed arrangement was evaluated using synthetic effluents, that were prepared based on data from literature and conception documents of the installation considered in this work. Three kinds of effluents were simulated, one arising from a nuclear reactor laundry, one arising from the water refrigeration system and demineralized water production to the nuclear reactor and the other one arising from a nuclear material production laboratory. Each effluent were individually submitted to the selected treatment processes, to get the best operational conditions for each treatment process. The results got during the laboratory assays show that the proposed Integrated System to the Treatment of Chemicals and Radioactive Effluents is feasible, consolidating the Effluent Zero Release concept, which is the proposition of this work. (author)

  6. The Swr 1000: a nuclear power plant concept with boiling water reactor for maximum safety and economy of operation

    International Nuclear Information System (INIS)

    Brettschuh, W.

    2001-01-01

    The SWR 1000 is a design concept for a light water reactor nuclear power plant that meets all requirements regarding plant safety, economic efficiency and environ-mental friendliness. As a result of the plant's safety concept, the occurrence of core damage can, for all practical intents and purposes, be ruled out. If a core melt accident should nevertheless occur, the molten core can be retained inside the RPV, thus ensuring that all consequences of such an accident remain restricted to the plant itself. The power generating costs of the SWR 1000 are lower than with those of coal-fired and combined-cycle power plants. Power generation using nuclear energy does not release carbon dioxide to the environment, thus meeting the need for sustainable protection of our global climate. (author)

  7. Generic repository design concepts and thermal analysis (FY11)

    International Nuclear Information System (INIS)

    Howard, Robert; Dupont, Mark; Blink, James A.; Fratoni, Massimiliano; Greenberg, Harris; Carter, Joe; Hardin, Ernest L.; Sutton, Mark A.

    2011-01-01

    the disposal system. Clay/shale, salt, and crystalline rock media are selected as the basis for reference mined geologic disposal concepts in this study, consistent with advanced international repository programs, and previous investigations in the U.S. The U.S. pursued deep geologic disposal programs in crystalline rock, shale, salt, and volcanic rock in the years leading up to the Nuclear Waste Policy Act, or NWPA (Rechard et al. 2011). The 1987 NWPA amendment act focused the U.S. program on unsaturated, volcanic rock at the Yucca Mountain site, culminating in the 2008 license application. Additional work on unsaturated, crystalline rock settings (e.g., volcanic tuff) is not required to support this generic study. Reference disposal concepts are selected for the media listed above and for deep borehole disposal, drawing from recent work in the U.S. and internationally. The main features of the repository concepts are discussed in Section 4.5 and summarized in Table ES-1. Temperature histories at the waste package surface and a specified distance into the host rock are calculated for combinations of waste types and reference disposal concepts, specifying waste package emplacement modes. Target maximum waste package surface temperatures are identified, enabling a sensitivity study to inform the tradeoff between the quantity of waste per disposal package, and decay storage duration, with respect to peak temperature at the waste package surface. For surface storage duration on the order of 100 years or less, waste package sizes for direct disposal of SNF are effectively limited to 4-PWR configurations (or equivalent size and output). Thermal results are summarized, along with recommendations for follow-on work including adding additional reference concepts, verification and uncertainty analysis for thermal calculations, developing descriptions of surface facilities and other system details, and cost estimation to support system-level evaluations.

  8. Generic repository design concepts and thermal analysis (FY11).

    Energy Technology Data Exchange (ETDEWEB)

    Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); Dupont, Mark (Savannah River Nuclear Solutions, Aiken, SC); Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Fratoni, Massimiliano (Lawrence Livermore National Laboratory, Livermore, CA); Greenberg, Harris (Lawrence Livermore National Laboratory, Livermore, CA); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Hardin, Ernest L.; Sutton, Mark A. (Lawrence Livermore National Laboratory, Livermore, CA)

    2011-08-01

    disposal system. Clay/shale, salt, and crystalline rock media are selected as the basis for reference mined geologic disposal concepts in this study, consistent with advanced international repository programs, and previous investigations in the U.S. The U.S. pursued deep geologic disposal programs in crystalline rock, shale, salt, and volcanic rock in the years leading up to the Nuclear Waste Policy Act, or NWPA (Rechard et al. 2011). The 1987 NWPA amendment act focused the U.S. program on unsaturated, volcanic rock at the Yucca Mountain site, culminating in the 2008 license application. Additional work on unsaturated, crystalline rock settings (e.g., volcanic tuff) is not required to support this generic study. Reference disposal concepts are selected for the media listed above and for deep borehole disposal, drawing from recent work in the U.S. and internationally. The main features of the repository concepts are discussed in Section 4.5 and summarized in Table ES-1. Temperature histories at the waste package surface and a specified distance into the host rock are calculated for combinations of waste types and reference disposal concepts, specifying waste package emplacement modes. Target maximum waste package surface temperatures are identified, enabling a sensitivity study to inform the tradeoff between the quantity of waste per disposal package, and decay storage duration, with respect to peak temperature at the waste package surface. For surface storage duration on the order of 100 years or less, waste package sizes for direct disposal of SNF are effectively limited to 4-PWR configurations (or equivalent size and output). Thermal results are summarized, along with recommendations for follow-on work including adding additional reference concepts, verification and uncertainty analysis for thermal calculations, developing descriptions of surface facilities and other system details, and cost estimation to support system-level evaluations.

  9. An integrated approach to site selection for nuclear power plants

    International Nuclear Information System (INIS)

    Hassan, E.M.A.

    1975-01-01

    A method of analysing and evaluating the large number of factors influencing site selection is proposed, which can interrelate these factors and associated problems in an integrated way and at the same time establish a technique for site evaluation. The objective is to develop an integrated programme that illustrates the complexity and dynamic interrelationships of the various factors to develop an improved understanding of the functions and objectives of siting nuclear power plants and would aim finally at the development of an effective procedure and technique for site evaluation and/or comparative evaluation for making rational site-selection decisions. (author)

  10. Nuclear site selection and environmental protection. The decision making methods

    International Nuclear Information System (INIS)

    Bresson, G.; Lacourly, G.; Fitoussi, L.

    1975-01-01

    The selection of the site of a nuclear plant most often comes to seek out and compound between two trends: that of the operator who will try and reduce the cost price of his product to the lowest and that of the protectionist who will try and reduce to the minimum the hazards resulting from the plant operation. Such a compromise is the result of a more or less empirical choice, which enters within the frame of a cost-benefit analysis, in which theoretically, the choice between several possible solutions is made of the selection giving the higher advantage [fr

  11. Development of generation IV nuclear energy systems

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Oka, Yoshiaki; Ogawa, Masuro; Ichimiya, Masakazu; Noda, Hiroshi

    2003-01-01

    The fifth 'Generation IV International Forum (GIF), Policy Group Meetings' was held at the Zen-Nikku Hotel in Tokyo, on September 19-20, 2002, under participations of Abraham, Secretary of DOE in U.S.A., Columbani, Secretary of CEA in France, Fujiie, Chairman of CAE in Japan, Kano, Parliamental Minister of MIS in Japan, and so on. Ten nations entering GIF (Argentina, Brazil, Canada, France, Japan, Korea, South Africa, Switzerland, U.K., and U.S.A.) selected six next generation nuclear energy concepts for objects of international cooperative research and development aiming at its practice by 2030. These concepts applicable to not only power generation, but also hydrogen production, sea water purification, and so on, are sodium liquid metal cooled reactor (Japan), high temperature gas cooled reactor (France), Super-critical pressure water cooled reactor (SCWR: Canada), Lead metal cooled reactor (Switzerland), Gas cooled fast reactor (U.S.A.), and molten salts reactor. On the generation IV nuclear reactor systems aiming to further upgrade their sustainability, safety, economical efficiency, and nuclear non proliferation, the 'Plans on Technical Development' (Road-map) to decide priority of their R and Ds has been cooperatively discussed under frameworks of international research cooperation by the GIF members nations. Here were shared descriptions on nuclear fuel cycle as a remise of technical evaluation and adopted concepts by Japanese participants contributing to making up the Road-map. (G.K.)

  12. Overall plant concept for a tank-type fast reactor

    International Nuclear Information System (INIS)

    Yamaki, Hideo; Davies, S.M.; Goodman, L.

    1984-01-01

    Japanese nuclear industries are expressing interest in the merits of the tank-type FBR as a large plant (demonstration) after JOYO (experimental, in operation) and MONJU (prototype, under construction). In response to this growing interest in a tank-type FBR demonstration plant, Hitachi has initiated a conceptual study of a 1000 MWe tank plant concept in collaboration with GE and Bechtel. Key objectives of this study have been: to select reliable and competitive tank plant concepts, with emphases on a seismic-resistant and compact tank reactor system;to select reliable shutdown heat removal system;and to identify R and D items needed for early 1990s construction. Design goals were defined as follows: capital costs must be less than twice, and as close as practical to 1.5 those of equivalent LWR plants;earthquake resistant structures to meet stringent Japanese seismic conditions must be as simple and reliable as practical;safety must be maintained at LWR-equivalent risks;and R and D needs must be limited to minimum cost for the limited time allowed. This paper summarizes the overall plant concepts with some selected topics, whereas detailed descriptions of the reactor assembly and the layout design are found in separate papers

  13. Vault submodel for the second interim assessment of the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    LeNeveu, D.M.

    1986-02-01

    The consequences to man and the environment of the disposal of nuclear fuel waste are being studied within the Canadian Nuclear Fuel Waste Management Program. The concept being assessed is that of a sealed disposal vault at a depth of 1000 m in plutonic rock in the Canadian Shield. To determine the consequences, the vault and its environment are simulated using a SYstem Variability Analysis Code (SYVAC), a stochastic model of the disposal system. SYVAC contains three submodels that represent the three major parts of the disposal system: the vault, the geosphere and the biosphere. This report documents the conceptual and mathematical framework of the vault submodel

  14. Concepts of nuclear liability revisited: a post-Chernobyl assessment of the Paris and the Vienna Conventions

    International Nuclear Information System (INIS)

    Pelzer, Norbert

    1988-01-01

    The accident at Chernobyl caused evident damage to third parties. Nuclear third party liability law was applicable. It is thus timely to reassess the concept of the international civil nuclear liability regulations, with special reference to the accident and the proceedings which resulted from it. The first section deals with the basis of liability - the origin and development of the Paris and Vienna Conventions, various aspects of liability and international implementation of the Convention. The second part considers the limitations on the liability and the third part looks at recent developments and future prospects which include the draft of a joint protocol. (U.K.)

  15. Coupled Multi-physical Simulations for the Assessment of Nuclear Waste Repository Concepts: Modeling, Software Development and Simulation

    Science.gov (United States)

    Massmann, J.; Nagel, T.; Bilke, L.; Böttcher, N.; Heusermann, S.; Fischer, T.; Kumar, V.; Schäfers, A.; Shao, H.; Vogel, P.; Wang, W.; Watanabe, N.; Ziefle, G.; Kolditz, O.

    2016-12-01

    As part of the German site selection process for a high-level nuclear waste repository, different repository concepts in the geological candidate formations rock salt, clay stone and crystalline rock are being discussed. An open assessment of these concepts using numerical simulations requires physical models capturing the individual particularities of each rock type and associated geotechnical barrier concept to a comparable level of sophistication. In a joint work group of the Helmholtz Centre for Environmental Research (UFZ) and the German Federal Institute for Geosciences and Natural Resources (BGR), scientists of the UFZ are developing and implementing multiphysical process models while BGR scientists apply them to large scale analyses. The advances in simulation methods for waste repositories are incorporated into the open-source code OpenGeoSys. Here, recent application-driven progress in this context is highlighted. A robust implementation of visco-plasticity with temperature-dependent properties into a framework for the thermo-mechanical analysis of rock salt will be shown. The model enables the simulation of heat transport along with its consequences on the elastic response as well as on primary and secondary creep or the occurrence of dilatancy in the repository near field. Transverse isotropy, non-isothermal hydraulic processes and their coupling to mechanical stresses are taken into account for the analysis of repositories in clay stone. These processes are also considered in the near field analyses of engineered barrier systems, including the swelling/shrinkage of the bentonite material. The temperature-dependent saturation evolution around the heat-emitting waste container is described by different multiphase flow formulations. For all mentioned applications, we illustrate the workflow from model development and implementation, over verification and validation, to repository-scale application simulations using methods of high performance computing.

  16. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

    International Nuclear Information System (INIS)

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power - generating capability and one without

  17. Similar Efficacies of Selection Shape Mitochondrial and Nuclear Genes in Both Drosophila melanogaster and Homo sapiens.

    Science.gov (United States)

    Cooper, Brandon S; Burrus, Chad R; Ji, Chao; Hahn, Matthew W; Montooth, Kristi L

    2015-08-21

    Deleterious mutations contribute to polymorphism even when selection effectively prevents their fixation. The efficacy of selection in removing deleterious mitochondrial mutations from populations depends on the effective population size (Ne) of the mitochondrial DNA and the degree to which a lack of recombination magnifies the effects of linked selection. Using complete mitochondrial genomes from Drosophila melanogaster and nuclear data available from the same samples, we reexamine the hypothesis that nonrecombining animal mitochondrial DNA harbor an excess of deleterious polymorphisms relative to the nuclear genome. We find no evidence of recombination in the mitochondrial genome, and the much-reduced level of mitochondrial synonymous polymorphism relative to nuclear genes is consistent with a reduction in Ne. Nevertheless, we find that the neutrality index, a measure of the excess of nonsynonymous polymorphism relative to the neutral expectation, is only weakly significantly different between mitochondrial and nuclear loci. This difference is likely the result of the larger proportion of beneficial mutations in X-linked relative to autosomal loci, and we find little to no difference between mitochondrial and autosomal neutrality indices. Reanalysis of published data from Homo sapiens reveals a similar lack of a difference between the two genomes, although previous studies have suggested a strong difference in both species. Thus, despite a smaller Ne, mitochondrial loci of both flies and humans appear to experience similar efficacies of purifying selection as do loci in the recombining nuclear genome. Copyright © 2015 Cooper et al.

  18. AECB staff response to the environmental impact statement on the concept for disposal of Canada`s nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The Environmental Impact Statement (EIS) on the Concept for Disposal of Canada`s Nuclear Fuel Waste was released in October 1994 (AECL,1994) in response to the guidelines issued in 1992 by a Panel formed to evaluate this concept (Federal Environmental Assessment Review Panel, 1992). This response is primarily a statement of deficiencies and thus focuses on the negative aspects of the EIS. The staff review of the EIS was based on the AECB mandate, which is to protect human health and the environment and as such was focused on technical issues in the EIS. These were performance assessment of the multiple barrier system, environmental impacts, concept feasibility, siting, transport and safety as well as general issues of regulatory policy and criteria. The EIS and its supporting documentation have been the sole basis used to judge whether AECB staff expectations of the EIS have been met. The staff response (Part II) considers whether an issue is addressed appropriately and adequately, while taking account of the generic and preliminary nature of the concept. The overall conclusion that AECB staff have drawn from the technical review of the EIS is that the EIS, by itself, does not adequately demonstrate the case for deep geological disposal for nuclear fuel waste. However, AECB staff believe that the EIS information, in combination with a variety of generic national and international assessments, has provided confidence that the deep geological disposal concept is safe and viable. 74 refs.

  19. Evaluation of concepts for monitored retrievable storage of spent nuclear fuel and high-level radioactive waste

    International Nuclear Information System (INIS)

    Triplett, M.B.; Smith, R.I.

    1984-04-01

    The primary mission selected by DOE for the monitored retrieval storage (MRS) system is to provide an alternative means of storage in the event that the repository program is delayed. The MRS concepts considered were the eight concepts included in the MRS Research and Development Report to Congress (DOE 1983). These concepts are: metal cask (stationary and transportable); concrete cask (sealed storage cask); concrete cask-in-trench; field drywell; tunnel drywell; open cycle vault; closed cycle vault; and tunnel rack vault. Conceptual design analyses were performed for the candidate concepts using a common set of design requirements specified in consideration of the MRS mission

  20. The selection of probabilistic safety assessment techniques for non-reactor nuclear facilities

    International Nuclear Information System (INIS)

    Vail, J.

    1992-01-01

    Historically, the probabilistic safety assessment (PSA) methodology of choice is the well known event tree/fault tree inductive technique. For reactor facilities is has stood the test of time. Some non-reactor nuclear facilities have found inductive methodologies difficult to apply. The stand-alone fault tree deductive technique has been used effectively to analyze risk in nuclear chemical processing facilities and waste handling facilities. The selection between the two choices suggest benefits from use of the deductive method for non-reactor facilities

  1. The selection of embedded computer using in the nuclear physics instruments

    International Nuclear Information System (INIS)

    Zhang Jianchuan; Nan Gangyang; Wang Yanyu; Su Hong

    2010-01-01

    It introduces the requirement for embedded PC and the benefits of using it in the experimental nuclear physics instrument developing and improving project. A cording to the specific requirements in the project of improving laboratory instruments. several kinds of embedded computer are compared and specifically tested. Thus, a x86 architecture embedded computer, which have ultra-low-power consumption and a small in size, is selected to be the main component of the controller using in the nuclear physics instrument, and this will be used in the high-speed data acquisition and electronic control system. (authors)

  2. Review of the safety concept for fusion reactor concepts and transferability of the nuclear fission regulation to potential fusion power plants

    Energy Technology Data Exchange (ETDEWEB)

    Raeder, Juergen; Weller, Arthur; Wolf, Robert [Max-Planck-Institut fuer Plasmaphysik (IPP), Garching (Germany); Jin, Xue Zhou; Boccaccini, Lorenzo V.; Stieglitz, Robert; Carloni, Dario [Karlsruher Institute fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany); Pistner, Christoph [Oeko-Institut e.V., Darmstadt (Germany); Herb, Joachim [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Koeln (Germany)

    2016-01-15

    This paper summarizes the current state of the art in science and technology of the safety concept for future fusion power plants (FPPs) and examines the transferability of the current nuclear fission regulation to the concepts of future fusion power plants. At the moment there exist only conceptual designs of future fusion power plants. The most detailed concepts with regards to safety aspects were found in the European Power Plant Conceptual Study (PPCS). The plant concepts discussed in the PPCS are based on magnetic confinement of the plasma. The safety concept of fusion power plants, which has been developed during the last decades, is based on the safety concepts of installations with radioactive inventories, especially nuclear fission power plants. It applies the concept of defence in depth. However, there are specific differences between the implementations of the safety concepts due to the physical and technological characteristics of fusion and fission. It is analysed whether for fusion a safety concept is required comparable to the one of fission. For this the consequences of a purely hypothetical release of large amounts of the radioactive inventory of a fusion power plant and a fission power plant are compared. In such an event the evacuation criterion outside the plant is exceeded by several orders of magnitude for a fission power plant. For a fusion power plant the expected radiological consequences are of the order of the evacuation criterion. Therefore, a safety concept is also necessary for fusion to guarantee the confinement of the radioactive inventory. The comparison between the safety concepts for fusion and fission shows that the fundamental safety function ''confinement of the radioactive materials'' can be transferred directly in a methodical way. For a fusion power plant this fundamental safety function is based on both, physical barriers as well as on active retention functions. After the termination of the fusion

  3. Some consideration on the relevance of concepts based on the probability distribution of words reminded by stimulus terms concerning atomic energy and radiation utilization

    International Nuclear Information System (INIS)

    Urabe, Itsumasa

    2002-01-01

    The relevance of concepts brought to mind by stimulus terms concerning atomic energy and radiation utilization has been investigated to learn how people understand the present status of nuclear technology. The relevance of concepts was defined as the frequency distribution of words that came to mind immediately after seeing selected terms needed for present-day life as well as for nuclear engineering. An analysis of knowledge structure shows that a concept of atomic energy has a close relation with that of electric power generation; an understanding of nuclear power utilization may be promoted in relation to an understanding of energy and environmental problems because the concepts of energy, atomic energy, electric power generation, and natural environment have closer relations with one another; a concept of radiation has various relations with harmful radiological health effects, but little relation with industrial, agricultural, and other beneficial uses except of nuclear power generation or medical applications. It also became clear from the investigation that studies on natural radiation may be important to promote an understanding of radiation utilization because a concept of the natural environment does not yet relate to that of natural radiation. (author)

  4. A Resource for Eliciting Student Alternative Conceptions: Examining the Adaptability of a Concept Inventory for Natural Selection at the Secondary School Level

    Science.gov (United States)

    Lucero, Margaret M.; Petrosino, Anthony J.

    2017-01-01

    The Conceptual Inventory of Natural Selection (CINS) is an example of a research-based instrument that assesses conceptual understanding in an area that contains well-documented alternative conceptions. Much of the CINS's use and original validation has been relegated to undergraduate settings, but the information learned from student responses on…

  5. Concept and optimization of burning and transmutation reactor in nuclear fuel recycle system

    International Nuclear Information System (INIS)

    Marsodi; Mulyanto; Kitamoto, Asashi.

    1994-01-01

    Basic concept of B/T reactor, not only produces thermal energy but also performs burning and/or transmutation of MA and long-lived FPs, was introduced here based on numerical computation model. The advantage of nuclear reaction by thermal or fast neutron was combined conceptually with each other in order to maximize the overall B/T rate obtained by a composite system of fast and thermal reactor. According to the mass balance analysis of B/T reactors with P-T treatment, fast reactor hardened neutron energy may be effective for MA burning. Furthermore, a high flux reactor operated by fast or thermal neutron could be different from a reactor with high B/T rate or high capacity for loading of MA and/or long-lived FPs. The purpose of this study is to make clear the concept and the performance of fast and thermal B/T reactor designed under high neutron utilization for HLW disposal. (author)

  6. Current concepts in nuclear pore electrophysiology.

    Science.gov (United States)

    Bustamante, José Omar

    2006-01-01

    Over 4 decades ago, microelectrode studies of in situ nuclei showed that, under certain conditions, the nuclear envelope (NE) behaves as a barrier opposing the nucleocytoplasmic flow of physiological ions. As the nuclear pore complexes (NPCs) of the NE are the only pathways for direct nucleocytoplasmic flow, those experiments implied that the NPCs are capable of restricting ion flow. These early studies validated electrophysiology as a useful approach to quantify some of the mechanisms by which NPCs mediate gene activity and expression. Since electron microscopy (EM) and other non-electrophysiological investigations, showed that the NPC lumen is a nanochannel, the opinion prevailed that the NPC could not oppose the flow of ions and, therefore, that electrophysiological observations resulted from technical artifacts. Consequently, the initial enthusiasm with nuclear electrophysiology faded out in less than a decade. In 1990, nuclear electrophysiology was revisited with patch-clamp, the most powerful electrophysiological technique to date. Patch-clamp has consistently demonstrated that the NE has intrinsic ion channel activity. Direct demonstrations of the NPC on-off ion channel gating behavior were published for artificial conditions in 1995 and for intact living nuclei in 2002. This on-off switching/gating behavior can be interpreted in terms of a metastable energy barrier. In the hope of advancing nuclear electrophysiology, and to complement the other papers contained in this special issue of the journal, here I review some of the main technical, experimental, and theoretical issues of the field, with special focus on NPCs.

  7. Constor steel concrete sandwich cask concept for transport and storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Diersch, R.; Dreier, G.; Gluschke, K.; Zubkov, A.; Danilin, B.; Fromzel, V.

    1998-01-01

    A spent nuclear fuel transport and storage sandwich cask concept has been developed together with the Russian company CKTI. Special consideration was given to an economical and effective way of manufacturing by using conventional mechanical engineering technologies and common materials. The main objective of this development was to fabricate these casks in countries not having highly specialized industries. Nevertheless, this sandwich cask concept fulfills both the internationally valid IAEA criteria for transportation and the German criteria for long-term intermediate storage. The basic cask concept has been designed for adaptation to different spent fuel specifications as well as handling conditions in the NPP. Recently, adaptations have been made for spent fuel from the RBMK and VVER reactors, and also for BWR spent fuel. The analyses of nuclear and thermal behaviour as well as of strength according to IAEA examination requirements (9-m-drop, 1-m-pin drop, 800 deg. C-fire test) and of the behaviour during accident scenarios at the storage site (drop, fire, gas cloud explosion, side impact) were carried out by means of recognized calculation methods and programmes. In a special experimental programme, the mechanical and thermodynamic properties of heavy concrete were examined and the reference values required for safety analyses were determined. The results of the safety analysis after drop tests according to IAEA-regulations as well as after 1 m-drops at the storage site were confirmed by means of a test programme using a scale model. The fabrication technology has been tested with help of a half scale cask model. The model has been prefabricated in Russia and completed in Germany. It has been shown that the CONSTOR cask can be fabricated in an effective and economic way. (authors)

  8. Simultaneous nuclear data target accuracy study for innovative fast reactors

    International Nuclear Information System (INIS)

    Aliberti, G.; Palmiotti, G.; Salvatores, M.

    2007-01-01

    The present paper summarizes the major outcomes of a study conducted within a Nuclear Energy Agency Working Party on Evaluation Cooperation (NEA WPEC) initiative aiming to investigate data needs for future innovative nuclear systems, to quantify them and to propose a strategy to meet them. Within the NEA WPEC Subgroup 26 an uncertainty assessment has been carried out using covariance data recently processed by joint efforts of several US and European Labs. In general, the uncertainty analysis shows that for the wide selection of fast reactor concepts considered, the present integral parameters uncertainties resulting from the assumed uncertainties on nuclear data are probably acceptable in the early phases of design feasibility studies. However, in the successive phase of preliminary conceptual designs and in later design phases of selected reactor and fuel cycle concepts, there will be the need for improved data and methods, in order to reduce margins, both for economic and safety reasons. It is then important to define as soon as possible priority issues, i.e. which are the nuclear data (isotope, reaction type, energy range) that need improvement, in order to quantify target accuracies and to select a strategy to meet the requirements needed (e.g. by some selected new differential measurements and by the use of integral experiments). In this context one should account for the wide range of high accuracy integral experiments already performed and available in national or, better, international data basis, in order to indicate new integral experiments that will be needed to account for new requirements due to innovative design features, and to provide the necessary full integral data base to be used for validation of the design simulation tools.

  9. Westinghouse Nuclear Core Design Training Center - a design simulator

    International Nuclear Information System (INIS)

    Altomare, S.; Pritchett, J.; Altman, D.

    1992-01-01

    The emergence of more powerful computing technology enables nuclear design calculations to be done on workstations. This shift to workstation usage has already had a profound effect in the training area. In 1991, the Westinghouse Electric Corporation's Commercial Nuclear Fuel Division (CNFD) developed and implemented a Nuclear Core Design Training Center (CDTC), a new concept in on-the-job training. The CDTC provides controlled on-the-job training in a structured classroom environment. It alllows one trainer, with the use of a specially prepared training facility, to provide full-scope, hands-on training to many trainees at one time. Also, the CDTC system reduces the overall cycle time required to complete the total training experience while also providing the flexibility of individual training in selected modules of interest. This paper provides descriptions of the CDTC and the respective experience gained in the application of this new concept

  10. Selection of nuclear reactor coolant materials

    International Nuclear Information System (INIS)

    Shi Lisheng; Wang Bairong

    2012-01-01

    Nuclear material is nuclear material or materials used in nuclear industry, the general term, it is the material basis for the construction of nuclear power, but also a leader in nuclear energy development, the two interdependent and mutually reinforcing. At the same time, nuclear materials research, development and application of the depth and breadth of science and technology reflects a nation and the level of the nuclear power industry. Coolant also known as heat-carrier agent, is an important part of the heart nuclear reactor, its role is to secure as much as possible to the economic output in the form fission energy to heat the reactor to be used: the same time cooling the core, is controlled by the various structural components allowable temperature. This paper described the definition of nuclear reactor coolant and characteristics, and then addressed the requirements of the coolant material, and finally were introduced several useful properties of the coolant and chemical control. (authors)

  11. The next nuclear power station generation: Beyond-design accident concepts, methods, and action sequence

    International Nuclear Information System (INIS)

    Asmolov, V.G.; Khakh, O.Ya.; Shashkov, M.G.

    1993-01-01

    The problem of beyond-design accidents at nuclear stations will not be solved unless a safety culture becomes a basic characteristic of all lines of activity. Only then can the danger of accidents as an objective feature of nuclear stations be eliminated by purposive skilled and responsible activities of those implementing safety. Nuclear-station safety is provided by the following interacting and complementary lines of activity: (1) the design and construction of nuclear stations by properly qualified design and building organizations; (2) monitoring and supervision of safety by special state bodies; (3) control of the station by the exploiting organization; and (4) scientific examination of safety within the above framework and by independent organizations. The distribution of the responsibilities, powers, and right in these lines should be defined by a law on atomic energy, but there is not such law in Russian. The beyond-design accident problem is a key one in nuclear station safety, as it clear from the serious experience with accidents and numerous probabilistic studies. There are four features of the state of this topic in Russia that are of major significance for managing accidents: the lack of an atomic energy law, the inadequacy of the technical standards, the lack of a verified program package for nuclear-station designs in order to calculate the beyond-design accidents and analyze risks, and a lack of approach by designers to such accidents on the basis of international recommendations. This paper gives a brief description of three-forming points in the scientific activity: the general concept of nuclear-station safety, methods of analyzing and providing accident management, and the sequence of actions developed by specialists at this institute in recent years

  12. Evaluating the attractiveness of nuclear material for proliferation-resistance and nuclear security

    International Nuclear Information System (INIS)

    Choi, Jor-Shan; Ikegame, Kou; Kuno, Yusuke

    2011-01-01

    The attractiveness of nuclear material, defined as a function of the isotopic composition of the nuclear material in formulas expressing the material's intrinsic properties, is of considerably debate in recent developments of proliferation-resistance measures of a nuclear energy system. A reason for such debate arises from the fact that the concept of nuclear material attractiveness can be confusing because the desirability of a material for nuclear explosive use depends on many tangible and intangible factors including the intent and capability of the adversary. In addition, a material that is unattractive to an advanced nation (in the case of proliferation) may be very attractive to a terrorist (in the case of physical protection and nuclear security). Hence, the concept of 'Nuclear Material Attractiveness' for different nuclear materials must be considered in the context of safeguards and security. The development of a ranking scheme on the attractiveness of nuclear materials could be a useful concept to start-off the strategies for safeguards and security on a new footing (i.e., why and how nuclear material is attractive, and what are the quantifiable basis). Japan may benefit from such concept regarding the attractiveness of nuclear materials when recovering nuclear materials from the damaged cores in Fukushima because safety, security, and safeguards (3S) would be a prominent consideration for the recovery operation, and it would be the first time such operation is performed in a non-nuclear weapons state. (author)

  13. Evolvability Is an Evolved Ability: The Coding Concept as the Arch-Unit of Natural Selection.

    Science.gov (United States)

    Janković, Srdja; Ćirković, Milan M

    2016-03-01

    Physical processes that characterize living matter are qualitatively distinct in that they involve encoding and transfer of specific types of information. Such information plays an active part in the control of events that are ultimately linked to the capacity of the system to persist and multiply. This algorithmicity of life is a key prerequisite for its Darwinian evolution, driven by natural selection acting upon stochastically arising variations of the encoded information. The concept of evolvability attempts to define the total capacity of a system to evolve new encoded traits under appropriate conditions, i.e., the accessible section of total morphological space. Since this is dependent on previously evolved regulatory networks that govern information flow in the system, evolvability itself may be regarded as an evolved ability. The way information is physically written, read and modified in living cells (the "coding concept") has not changed substantially during the whole history of the Earth's biosphere. This biosphere, be it alone or one of many, is, accordingly, itself a product of natural selection, since the overall evolvability conferred by its coding concept (nucleic acids as information carriers with the "rulebook of meanings" provided by codons, as well as all the subsystems that regulate various conditional information-reading modes) certainly played a key role in enabling this biosphere to survive up to the present, through alterations of planetary conditions, including at least five catastrophic events linked to major mass extinctions. We submit that, whatever the actual prebiotic physical and chemical processes may have been on our home planet, or may, in principle, occur at some time and place in the Universe, a particular coding concept, with its respective potential to give rise to a biosphere, or class of biospheres, of a certain evolvability, may itself be regarded as a unit (indeed the arch-unit) of natural selection.

  14. Assessing and addressing increased stakeholder and operator information needs in nuclear fuel cycle facilities: two concepts

    Energy Technology Data Exchange (ETDEWEB)

    Saltiel, David H. [Sandia National Laboratories, Albuquerque (United States)

    2007-12-15

    Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the 'designing-in' of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance.

  15. Assessing and addressing increased stakeholder and operator information needs in nuclear fuel cycle facilities: two concepts

    International Nuclear Information System (INIS)

    Saltiel, David H.

    2007-01-01

    Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the 'designing-in' of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance

  16. A Non-Ventilated Solar Façade Concept Based on Selective and Transparent Insulation Material Integration: An Experimental Study

    Directory of Open Access Journals (Sweden)

    Miroslav Čekon

    2017-06-01

    Full Text Available A new solar façade concept based on transparent insulation and a selective absorber is proposed, tested and compared with conventional insulation and a non-selective type of absorber, respectively. The presented study focuses on an experimental non-ventilated solar type of façade exposed to solar radiation both in the laboratory and in outdoor tests. Due to the high solar absorbance level of the façade, high- and low-emissivity contributions were primarily analysed. All of the implemented materials were contrasted from the thermal and optical point of view. An analysis was made of both thermodynamic and steady state procedures affecting the proposed solar façade concept. Experimental full scale tests on real building components were additionally involved during summer monitoring. An indicator of the temperature response generated by solar radiation exposure demonstrates the outdoor performance of the façade is closely related to overheating phenomena. From the thermal point of view, the proposed transparent insulation and selective absorber concept corresponds to the performance of conventional thermal insulation of identical material thickness; however, the non-selective prototype only provides 50% thermal performance. The results of the solar-based experiments show that with a small-scale experimental prototype, approximately no significant difference is measured when compared with a non-selective absorber type. The only difference was achieved at the maximum of 2.5 K, when the lower temperature was obtained in the solar selective concept. At the full-scale outdoor mode, the results indicate a maximum of 3.0 K difference, however the lower temperature achieves a non-selective approach. This solar façade can actively contribute to the thermal performance of building components during periods of heating.

  17. Cultivation of nuclear safety culture in Guangdong Nuclear Power Station (GNPS)

    International Nuclear Information System (INIS)

    Lu Wei; Tang Yanzhao

    2004-01-01

    Probed into the concept and developing phases of safety couture in the management of nuclear power station, especially analyzed the background and the road of cultivating nuclear safety culture in GNPS, highlighted the core concept of GNPS nuclear safety culture, presented GNPS safety culture indicators, summarized the major measures taken by GNPS, depicted the propagandizing process of transparency in GNPS, and systematically appraised the effect of GNPS in implementing nuclear safety culture. (authors)

  18. Selection of a new nuclear unit for Slovakia: possibilities and key technical issues

    International Nuclear Information System (INIS)

    Misak, J.

    2009-01-01

    Plans for construction of new nuclear unit at Jaslovske Bohunice brings forward the issue of selection of reactor design. This paper compares technical characteristics (safety and operational) of pressurized water reactors that are at present available in the market, such as AP 1000 (WEC), EPR (AREVA), AES 2006 (ASE), APWR 1700 (Mitsubishi) and APR 1400 (Korea Hydro and Nuclear). Selected parameters that require close attention in future negotiations with potential suppliers are discussed in detail. Compared are parameters as type of the reactor, reactor output power, quantified level of safety, compliance with national legislature and international safety requirements, operational flexibility in meeting requirements of the grid, using of verified technology, measures for coping with severe accidents, resistance against extreme external conditions etc. (authors)

  19. Using marketing research concepts to investigate specialty selection by medical students.

    Science.gov (United States)

    Weissman, Charles; Schroeder, Josh; Elchalal, Uriel; Weiss, Yoram; Tandeter, Howard; Zisk-Rony, Rachel Y

    2012-10-01

    This study was intended to examine whether a marketing research approach improves understanding of medical specialty selection by medical students. This approach likens students to consumers who are deciding whether or not to purchase a product (specialty). This approach proposes that when consumers' criteria match their perceptions of a product's features, the likelihood that they will purchase it (select the specialty) increases. This study examines whether exploring students' selection criteria and perceptions of various specialties provides additional insights into the selection process. Using a consumer behaviour model as a framework, a questionnaire was designed and administered to Year 6 (final-year) students in 2008 and 2009 to elicit information on their knowledge about and interests in various specialties, the criteria they used in specialty selection, and their perceptions of six specialties. A total of 132 (67%) questionnaires were returned. In many instances, consistency between selection criteria and perceptions of a specialty was accompanied by interest in pursuing the specialty. Exceptions were noted and pointed to areas requiring additional research. For example, although > 70% of female students replied that the affordance of a controllable lifestyle was an important selection criterion, many were interested in obstetrics and gynaecology despite the fact that it was not perceived as providing a controllable lifestyle. Minimal overlap among students reporting interest in primary specialties that possess similar characteristics (e.g. paediatrics and family medicine) demonstrated the need to target marketing (recruitment) efforts for each specialty individually. Using marketing research concepts to examine medical specialty selection may precipitate a conceptual shift among health care leaders which acknowledges that, to attract students, specialties must meet students' selection criteria. Moreover, if consumers (students) deem a product (specialty

  20. Human health considerations in the assessment of Canadian concept for the disposal of nuclear fuel wastes

    International Nuclear Information System (INIS)

    Baweja, A.S.; Tracy, B.L.; Ahier, B.; Bartlett, S.

    1996-01-01

    In 1978, AECL was mandated by the government of Ontario and the federal government to find a permanent disposal solution for spent nuclear fuels. Canada opted for disposal in plutonic rocks of the Canadian shield. The Canadian concept calls for disposal in crystalline rocks at a depth of 500 to 1000 m below the surface. The spent fuel would be contained in a canister, the canister would be emplaced in a vault containing clay-based buffer materials, and the cavity would be backfilled and sealed with natural materials. A Federal Environmental Assessment Review Panel was formed in 1992 to assess the concept for disposal of the spent fuel. In this paper a brief discussion of the human health impacts of the proposed concept is presented. Our assessment is based on the information provided by AECL, namely, the main EIS document, a summary and nine other supporting documents

  1. ORNL R and D on advanced small and medium power reactors: selected topics

    International Nuclear Information System (INIS)

    White, J.D.; Trauger, D.B.

    1989-01-01

    From 1984-1985, ORNL studied several innovative small and medium power nuclear concepts with respect to viability. Criteria for assessment of market attractiveness were developed and are described here. Using these criteria and descriptions of selected advanced reactor concepts, an assessment of their projected market viability in the time period 2000-2010 was made. All of these selected concepts could be considered as having the potential for meeting the criteria but, in most cases, considerable R and D would be required to reduce uncertainties. This work and later studies of safety and licensing of advanced, passively safe reactor concepts by ORNL are described. The results of these studies are taken into account in most of the current (FY 1989) work at ORNL on advanced reactors. A brief outline of this current work is given. One of the current R and D efforts at ORNL which addresses the operability and safety of advanced reactors is the Advanced Controls Program. Selected topics from this Program are described

  2. ORNL R and D on advanced small and medium power reactors: Selected topics

    International Nuclear Information System (INIS)

    White, J.D.; Trauger, D.B.

    1988-01-01

    From 1984-1985, ORNL studied several innovative small and medium power nuclear concepts with respect to viability. Criteria for assessment of market attractiveness were developed and are described here. Using these criteria and descriptions of selected advanced reactor concepts, and assessment of their projected market viability in the time period 2000-2010 was made. All of these selected concepts could be considered as having the potential for meeting the criteria but, in most cases, considerable RandD would be required to reduce uncertainties. This work and later studies of safety and licensing of advanced, passively safe reactor concepts by ORNL are described. The results of these studies are taken into account in most of the current (FY 1989) work at ORNL on advanced reactors. A brief outline of this current work is given. One of the current RandD efforts at ORNL which addresses the operability and safety of advanced reactors is the Advanced Controls Program. Selected topics from this Program are described. 13 refs., 1 fig

  3. Site selection for nuclear power plants and geologic seismologia influence

    International Nuclear Information System (INIS)

    Castro Feitosa, G. de.

    1985-01-01

    The site selection for nuclear power plants is analised concerning to the process, methodology and the phases in an overall project efforts. The factors affecting are analised on a general viewpoint, showing the considerations given to every one. The geologic and seismologic factors influence on the foundation design are more detailed analised, with required investigation and procedures accordingly sub-soil conditions in the site [pt

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

    International Nuclear Information System (INIS)

    Fittje, James E.; Buehrle, Robert J.

    2006-01-01

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

  5. Evaluation of potential blanket concepts for a Demonstration Tokamak Hybrid Reactor

    International Nuclear Information System (INIS)

    Chapin, D.L.; Chi, J.W.H.; Kelly, J.L.

    1978-01-01

    An evaluation has been made of several different blanket concepts for use in a near-term Demonstration Tokamak Hybrid Reactor (DTHR), whose main objective would be to produce a significant amount of fissile fuel while demonstrating the feasibility of the tokamak hybrid reactor concept. The desirability of a simple design using proven technology plus a proliferation resistant fuel cycle led to the selection of a low temperature and pressure water-cooled, zircaloy clad ThO 2 blanket concept to breed 233 U. The nuclear performance and thermal-hydraulics characteristics of the blanket were evaluated to arrive at a consistent design. The blanket was found to be feasible for producing a significant amount of fissile fuel even with the limited operating conditions and blanket coverage in the DTHR

  6. Reagan's concept of federalism and nuclear power

    International Nuclear Information System (INIS)

    Axelrod, R.S.; Wilson, H.A.

    1991-01-01

    The 'New Federation' of the Reagan Administration was a doctrine to reduce regulations and devolve government functions to State and local governments. However, when these goals competed with other substantive goals, eg the promotion of nuclear power, the Administration chose to advance the latter. State and local governments utilized the NRC requirement for their participation in the planning and implementation of an evacuation plan to prevent the licensing of the Shoreham nuclear power plant. This strategy was contested by the national Administration which insisted on licensing the plant. The licensing of the Long Island Lighting Company's Shoreham nuclear power plant provides an opportunity to examine the role of nuclear power in highlighting the contradictions in Reagan's 'New Federation'. (author)

  7. Nuclear Power Options Viability Study. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    Trauger, D.B.; White, J.D.; Booth, R.S.

    1986-09-01

    Innovative reactor concepts are described and evaluated in accordance with criteria established in the study. The reactors to be studied were selected on the basis of three ground rules: (1) the potential for commercialization between 2000 to 2010, (2) economic competitiveness with coal, and (3) the degree of passive safety in the design. The concepts, classified by coolants, were light water reactors, liquid metal reactors, and high-temperature reactors, and most were of modular design. Although the information available is not adequate for a definitive evaluation of economic competitiveness, all of the concepts appear to be potentially viable in the time frame selected. Public and institutional acceptance of nuclear power was found to be affected primarily by four issues: (1) operational safety, (2) waste handling and disposal, (3) construction and operating costs, and (4) the adequacy of management and regulatory controls

  8. Accelerator-driven system design concept for disposing of spent nuclear fuels

    International Nuclear Information System (INIS)

    Gohar, Y.; Cao, Y.; Kellogg, R.; Merzari, E.

    2015-01-01

    At present, the US SNF (Spent Nuclear Fuel) inventory is growing by about 2,000 metric tonnes (MT) per year from the current operating nuclear power plants to reach about 70,000 MT by 2015. This SNF inventory contains about 1% transuranics (700 MT), which has about 115 MT of minor actinides. Accelerator-driven systems utilising proton accelerators with neutron spallation targets and subcritical blankets can be utilised for transmuting these transuranics, simultaneously generating carbon free energy, and significantly reducing the capacity of the required geological repository storage facility for the spent nuclear fuels. A fraction of the SNF plutonium can be used as a MOX fuel in the current/future thermal power reactors and as a starting fuel for future fast power reactors. The uranium of the spent nuclear fuel can be recycled for use in future nuclear power plants. This paper shows that only four to five accelerator-driven systems operating for less than 33 full power years can dispose of the US SNF inventory expected by 2015. In addition, a significant fraction of the long-lived fission products will be transmuted at the same time. Each system consists of a proton accelerator with a neutron spallation target and a subcritical assembly. The accelerator beam parameters are 1 GeV protons and 25 MW beam power, which produce 3 GWt in the subcritical assembly. A liquid metal (lead or lead-bismuth eutectic) spallation target is selected because of design advantages. This target is located at the centre of the subcritical assembly to maximise the utilisation of spallation neutrons. Because of the high power density in the target material, the target has its own coolant loop, which is independent of the subcritical assembly coolant loop. Mobile fuel forms with transuranic materials without uranium are considered in this work with liquid lead or lead-bismuth eutectic as fuel carrier

  9. The Need to Assess Public Values in a Site Selection Process

    International Nuclear Information System (INIS)

    Sheng, Grant; Fortier, Michael

    2001-01-01

    Siting a nuclear fuel waste disposal facility is highly problematic for both technical and nontechnical reasons. The majority of countries using nuclear energy and many in the scientific community favour burying the spent fuel deep in a stable geological formation. It is our contention that site selection of a disposal facility must consider social, political, spatial and scientific perspectives in a comprehensive and integrated fashion in order to achieve a successful process. Moreover, we submit that people's values must be explicitly recognized and be taken into account through a formalized process during deliberations on the disposal concept, the process of evaluation of the concept, and the site selection process. The purpose of this paper is: (1) to identify the importance of recognizing people's values in the process of determining 'public acceptability', (2) to outline a possible framework by which public acceptability can be gauged through a formalized process of value elicitation, and (3) to introduce a novel method by which a web-based geographic information systems (GIS) application can be used as a tool for value elicitation. In order to assess effectively the public acceptability of Canada's nuclear waste disposal concept, we submit that such a process must examine the underlying values that are held by the public. Moreover, the evaluation process of Canada's concept demonstrates that an acceptable process is a pre-condition for an acceptable result, although such a process does not necessarily guarantee an acceptable result. However, the consequences of a flawed process can be very significant, as shown by Canada's experience. This paper also provides a brief overview of a value elicitation process that, in our opinion, could be used to assess the public acceptability of the Concept. We also describe how a web-based GIS application could be used to infer some of the underlying values held by the public

  10. Materials for generation-IV nuclear reactors

    International Nuclear Information System (INIS)

    Alvarez, M. G.

    2009-01-01

    Materials science and materials development are key issues for the implementation of innovative reactor systems such as those defined in the framework of the Generation IV. Six systems have been selected for Generation IV consideration: gas-cooled fast reactor, lead-cooled fast reactor, molten salt-cooled reactor, sodium-cooled fast reactor, supercritical water-cooled reactor, and very high temperature reactor. The structural materials need to resist much higher temperatures, higher neutron doses and extremely corrosive environment, which are beyond the experience of the current nuclear power plants. For this reason, the first consideration in the development of Generation-IV concepts is selection and deployment of materials that operate successfully in the aggressive operating environments expected in the Gen-IV concepts. This paper summarizes the Gen-IV operating environments and describes the various candidate materials under consideration for use in different structural applications. (author)

  11. Systems selection methodology for civil nuclear power applications

    International Nuclear Information System (INIS)

    Scarborough, J.

    1988-01-01

    A methodology for evaluation and selection of a preferred Advanced Small or Medium Power Reactor (SMPR) for commercial electric power generation is discussed, and an illustrative example is presented with five US Advanced SMPR power plants. The evaluation procedure was developed from a methodology for ranking small, advanced nuclear power plant designs under development by the US Department of Energy (DOE) and Department of Defense (DOD). The methodology involves establishing numerical probability distributions for each of fifteen evaluation criteria for each Advanced SMPR plant. A resultant single probability distribution with its associated numerical mean value is then developed for each Advanced SMPR plant by Monte Carlo sampling techniques in order that each plant may be ranked with an associated statement of certainty. The selection methodology is intended as a screening procedure for commercial offerings to preclude detailed technical and commercial assessments from being conducted for those offerings which do not meet the initial screening criteria

  12. Systems selection methodology for civil nuclear power applications

    International Nuclear Information System (INIS)

    Scarborough, J.C.

    1987-01-01

    A methodology for evaluation and selection of a preferred Advanced Small or Medium Power Reactor (SMPR) for commercial electric power generation is discussed, and an illustrative example is presented with five U.S. Advanced SMPR power plants. The evaluation procedure was developed from a methodology for ranking small. advenced nuclear power plant designs under development by the U.S. Department of Energy (DOE) and Department of Defense (DOD). The methodology involves establishing numerical probability distributions for each of fifteen evaluation criteria for each Advanced SMPR plant. A resultant single probability distribution with its associated numerical mean value is then developed for each Advanced SMPR plant by Monte Carlo sampling techniques in order that each plant may be ranked with an associated statement of certainty. The selection methodology is intended as a screening procedure for commercial offerings to preclude detailed technical and commercial assessments from being conducted for those offerings which do not meet the initial screening criteria. (auhtor)

  13. AECB staff response to the environmental impact statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1995-07-01

    The Environmental Impact Statement on the Concept for Disposal of Canada's Nuclear Fuel Waste was released in October 1994 in response to the guidelines issued in 1992 by a panel formed to evaluate this concept (Federal Environmental Assessment Review Panel, 1992). This response is primarily a statement of deficiencies and thus focuses on the negative aspects of the Environmental Impact Statement (EIS). The staff review of the EIS was based on the AECB mandate, which is to protect human health and the environment and as such was focused on technical issues in the EIS. These were performance assessment of the multiple barrier system, environmental impacts, concept feasibility, siting, transport and safety as well as general issues o f regulatory policy and criteria. 30 refs

  14. Decision support for selecting exportable nuclear technology using the analytic hierarchy process: A Korean case

    International Nuclear Information System (INIS)

    Lee, Deok Joo; Hwang, Jooho

    2010-01-01

    The Korean government plans to increase strategically focused R and D investment in some promising nuclear technology areas to create export opportunities of technology in a global nuclear market. The purpose of this paper is to present a decision support process for selecting promising nuclear technology with the perspective of exportability by using the AHP based on extensive data gathered from nuclear experts in Korea. In this study, the decision criteria for evaluating the export competitiveness of nuclear technologies were determined, and a hierarchical structure for the decision-making process was systematically developed. Subsequently relative weights of decision criteria were derived using AHP methodology and the export competitiveness of nuclear technology alternatives was quantified to prioritize them. We discuss the implications of our results with a viewpoint toward national nuclear technology policy.

  15. Advanced nuclear reactor and nuclear fusion power generation

    International Nuclear Information System (INIS)

    2000-04-01

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

  16. Physical protection concepts of nuclear materials. The French experience

    International Nuclear Information System (INIS)

    Arnaud, G.; Artaud, R.

    1995-01-01

    As the nuclear energy was being developed, it appeared necessary to set up protections against its potential hazards, that should be more complete and elaborate than those implemented on the other industrial installations. This had to be done both in the safety field to prevent the environment and the populations from the consequences of severe casualties, and in the security field to avoid the risk of proliferation and limit to an acceptable level the results of voluntarily provoked accidents and sabotages. Taking advantage of the gathered experience, this document gives consideration to the concepts used in France in order to ensure the physical protection of the nuclear materials. The following topics are tackled: context inside which are envisaged the specific measures, coherence with the general dispositions taken to protect industrial installations, importance and limitations of the part played by the regulations, respective responsibilities of the plant operators and the public authorities, compromise between objectives in view and means to implement, adjustment between the physical protection system and the operating requirements. In addition, the ways in which these systems should be implemented are discussed, underlining the necessity to make progressive steps under a permanent will, in order, first, to update and bring under conformity the old installations, and second, to ensure the maintenance of the systems, taking account of the evolutions of needs and techniques. Those points are commented on examples taken among the different types of installations to be found in France, showing the differences in approach coming from the type and the age of the facilities, and giving the present trends for the new plants. (authors). 1 annexe

  17. Building concept of cooling towers for WWER-1000 nuclear power plants

    International Nuclear Information System (INIS)

    Bucha, V.; David, M.

    1984-01-01

    A project is described of cooling towers with natural draught for the Temelin nuclear power plant. The concept proceeds from the classical design of the so-called Itterson type, i.e., the outer cladding of the draught stack is made of a monolithic reinforced concrete unit in the shape of a hyperboloid of revolution supported by a system of oblique supports mounted along the edge of the cooled water tank. The procedure is explained of the thermal calculation for the given operating conditions. The basic alternatives are considered of the choice of material and design of the cooling system. Questions are discussed relating to the design of the eliminator, the windwart wall and the shape of the shell of the draught stack and its loading by wind and seismic effects. (E.S.)

  18. Nuclear law and new legal concepts

    International Nuclear Information System (INIS)

    Atias, Ch.; Warusfel, B.; Byk, Ch.

    2003-01-01

    The articles on this topic have been written from three of the papers of the Conference organized on January 14, in Paris by the 'Law and Insurance' Section of the French Nuclear Energy Society together with the French Section of the International Nuclear Law Association. The first two articles deal with transparency, its justifications and limits. The third article analyses the rights of the future generations and our duties towards them. (authors)

  19. Conceptions of nuclear threshold status

    International Nuclear Information System (INIS)

    Quester, G.H.

    1991-01-01

    This paper reviews some alternative definitions of nuclear threshold status. Each of them is important, and major analytical confusions would result if one sense of the term is mistaken for another. The motives for nations entering into such threshold status are a blend of civilian and military gains, and of national interests versus parochial or bureaucratic interests. A portion of the rationale for threshold status emerges inevitably from the pursuit of economic goals, and another portion is made more attraction by the derives of the domestic political process. Yet the impact on international security cannot be dismissed, especially where conflicts among the states remain real. Among the military or national security motives are basic deterrence, psychological warfare, war-fighting and, more generally, national prestige. In the end, as the threshold phenomenon is assayed for lessons concerning the role of nuclear weapons more generally in international relations and security, one might conclude that threshold status and outright proliferation coverage to a degree in the motives for all of the states involved and in the advantages attained. As this paper has illustrated, nuclear threshold status is more subtle and more ambiguous than outright proliferation, and it takes considerable time to sort out the complexities. Yet the world has now had a substantial amount of time to deal with this ambiguous status, and this may tempt more states to exploit it

  20. Architectural Design of a Nuclear Research Center with Radiation Safety Considerations, in North Western Coast of Egypt (Using Auto CAD and 3ds Max Programs)

    International Nuclear Information System (INIS)

    Farahat, M.A.Z.

    2016-01-01

    This research discusses the design of nuclear research centers to help architects and engineers who will design these centers. Also, the research covers the site characteristics which are used in site selection of nuclear research centers. It covers the principles and standards used in design and planning of nuclear research centers. The master plan of a nuclear research center should be designed based on the system of segregation according to the level of radioactivity. Radiation safety is an important aspect in the design of nuclear research centers. The Egyptian Atomic Energy Authority consists of three nuclear research centers, namely, the Nuclear Research Center in Inshas (Grid Planning Concept), the Hot Laboratories and Waste Management Center in Inshas (Grid Planning Concept) and The National Center for Radiation Research and Technology in Nasr City (Linear Planning Concept). The Radial Planning Concept is the best among all the Planning Concepts as regard radiation safety considerations. Therefore, an architectural design of a new nuclear research center was proposed in a suitable site in North Western Coast of Egypt (Radial Planning Concept) using Auto CAD and 3ds Max programs. This site is suitable and satisfies many of the site requirements. It is recommended that the architectural design of nuclear research centers should be supervised by an architectural engineer experienced in architectural design of nuclear facilities

  1. Fission Surface Power System Initial Concept Definition

    Science.gov (United States)

    2010-01-01

    Under the NASA Exploration Technology Development Program (ETDP) and in partnership with the Department of Energy (DOE), NASA has embarked on a project to develop Fission Surface Power (FSP) technology. The primary goals of the project are to 1) develop FSP concepts that meet expected surface power requirements at reasonable cost with added benefits over other options, 2) establish a hardwarebased technical foundation for FSP design concepts and reduce overall development risk, 3) reduce the cost uncertainties for FSP and establish greater credibility for flight system cost estimates, and 4) generate the key products to allow NASA decision-makers to consider FSP as a preferred option for flight development. The FSP project was initiated in 2006 as the Prometheus Program and the Jupiter Icy Moons Orbiter (JIMO) mission were phased-out. As a first step, NASA Headquarters commissioned the Affordable Fission Surface Power System Study to evaluate the potential for an affordable FSP development approach. With a cost-effective FSP strategy identified, the FSP team evaluated design options and selected a Preliminary Reference Concept to guide technology development. Since then, the FSP Preliminary Reference Concept has served as a point-of-departure for several NASA mission architecture studies examining the use of nuclear power and has provided the foundation for a series of "Pathfinder" hardware tests. The long-term technology goal is a Technology Demonstration Unit (TDU) integrated system test using full-scale components and a non-nuclear reactor simulator. The FSP team consists of Glenn Research Center (GRC), Marshall Space Flight Center (MSFC) and the DOE National Laboratories at Los Alamos (LANL), Idaho (INL), Oak Ridge (ORNL), and Sandia (SNL). The project is organized into two main elements: Concept Definition and Risk Reduction. Under Concept Definition, the team performs trade studies, develops analytical tools, and formulates system concepts. Under Risk

  2. Liquid fuel concept benefits

    International Nuclear Information System (INIS)

    Hron, M.

    1996-01-01

    There are principle drawbacks of any kind of solid nuclear fuel listed and analyzed in the first part of the paper. One of the primary results of the analyses performed shows that the solid fuel concept, which was to certain degree advantageous in the first periods of a nuclear reactor development and operation, has guided this branch of a utilization of atomic nucleus energy to a death end. On the background of this, the liquid fuel concept and its benefits are introduced and briefly described in the first part of the paper, too. As one of the first realistic attempts to utilize the advantages of liquid fuels, the reactor/blanket system with molten fluoride salts in the role of fuel and coolant simultaneously, as incorporated in the accelerator-driven transmutation technology (ADTT) being proposed and currently having been under development in the Los Alamos National Laboratory, will be studied both theoretically and experimentally. There is a preliminary design concept of an experimental assembly LA-O briefly introduced in the paper which is under preparation in the Czech Republic for such a project. Finally, there will be another very promising concept of a small low power ADTT system introduced which is characterized by a high level of safety and economical efficiency. In the conclusion, the overall survey of principal benefits which may be expected by introducing liquid nuclear fuel in nuclear power and research reactor systems is given and critically analyzed. 7 refs, 4 figs

  3. Asia nuclear-test-ban network for nuclear non-proliferation

    International Nuclear Information System (INIS)

    Shinohara, Nobuo; Kokaji, Lisa; Ichimasa, Sukeyuki

    2010-01-01

    In Global Center of Excellence Program of The University of Tokyo, Non- Proliferation Study Committee by the members of nuclear industries, electricity utilities, nuclear energy institutes and universities has initiated on October 2008 from the viewpoints of investigating a package of measures for nuclear non-proliferation and bringing up young people who will support the near-future nuclear energy system. One of the non-proliferation issues in the Committee is the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Objective of this treaty is to cease all nuclear weapon test explosions and all other nuclear explosion. This purpose should be contributed effectively to the political stability of the Asian region by continuous efforts to eliminate the nuclear weapons. In the Committee, by extracting several issues related to the CTBT, conception of 'Asia nuclear-test-ban network for nuclear non-proliferation' has been discussed with the aim of the nuclear-weapon security in Asian region, where environmental nuclear-test monitoring data is mainly treated and utilized. In this paper, the conception of the 'network' is presented in detail. (author)

  4. Drug efficiency: a new concept to guide lead optimization programs towards the selection of better clinical candidates.

    Science.gov (United States)

    Braggio, Simone; Montanari, Dino; Rossi, Tino; Ratti, Emiliangelo

    2010-07-01

    As a result of their wide acceptance and conceptual simplicity, drug-like concepts are having a major influence on the drug discovery process, particularly in the selection of the 'optimal' absorption, distribution, metabolism, excretion and toxicity and physicochemical parameters space. While they have an undisputable value when assessing the potential of lead series or in evaluating inherent risk of a portfolio of drug candidates, they result much less useful in weighing up compounds for the selection of the best potential clinical candidate. We introduce the concept of drug efficiency as a new tool both to guide the drug discovery program teams during the lead optimization phase and to better assess the developability potential of a drug candidate.

  5. On the road to new nuclear safety

    International Nuclear Information System (INIS)

    Kovacs, Zoltan; Novakova, Helena; Spenlinger, Robert

    2013-01-01

    The article describes the issue of nuclear safety of nuclear power plants and major factors affecting nuclear safety, discusses the consequences of the Fukushima-Daiichi accident, and outlines the advanced concept of nuclear safety which extends the current regulatory requirements for plant safety. This new concept should be adopted globally to prevent occurrences having similar consequences worldwide. The tasks of this new nuclear safety concept are discussed. (orig.)

  6. Exploring the Relationship between Secondary Science Teachers' Subject Matter Knowledge and Knowledge of Student Conceptions While Teaching Evolution by Natural Selection

    Science.gov (United States)

    Lucero, Margaret M.; Petrosino, Anthony J.; Delgado, Cesar

    2017-01-01

    The fundamental scientific concept of evolution occurring by natural selection is home to many deeply held alternative conceptions and considered difficult to teach. Science teachers' subject matter knowledge (SMK) and the pedagogical content knowledge (PCK) component of knowledge of students' conceptions (KOSC) can be valuable resources for…

  7. Selection of sites for nuclear power plants in The Netherlands. Pt. B

    International Nuclear Information System (INIS)

    1986-01-01

    In this report the headlines are presented of the participation of the Dutch people in the policy resolution with regard to the selection of sites of nuclear power plants. In Ch. 1 it is indicated how this participation is organized and the quantitative results are given. In the other chapters the results of the people's participation are treated qualitatively with restriction to the headlines. In Ch. 3 the remarks about the procedure and its precedents are reported. Ch. 4 reflects the public opinion with regard to the (nuclear) energy problem. In Ch. 5 finally the problems concerning the sites of nuclear power plants are treated. The criteria are discussed used by the participants in the judgement of the locations on their aptitude, in general as well as by possible site. (Auth.)

  8. System of selective disemination of information at ININ

    International Nuclear Information System (INIS)

    Martinez G, M.A.

    1981-01-01

    A study of the systems of selective dissemination of information (SDI) is presented, the concepts for such systems outlined, and their developments traced in advanced countries, its forms of operation and implications for the special libraries. Also the operation of INIS at CIDN (Centro de Informacion y Documentacion Nuclear) is presented, together with recommendations and conclusions to improve the development of this service in Mexico. (author)

  9. The atmosphere submodel for the assessment of Canada's nuclear fuel waste management concept

    International Nuclear Information System (INIS)

    Amiro, B.D.

    1992-09-01

    Canada's Nuclear Fuel Waste Management Program is researching a concept for disposal of immobilized nuclear fuel waste in a vault mined deep in stable plutonic rock. When protective barriers are eventually breached, radioactive and chemically toxic nuclides, carried by groundwater, may migrate from the vault to the biosphere. They may cycle through surface waters, soil, the atmosphere and the food chain. One of the objectives of the program is to assess the movement of nuclides using modelling techniques to calculate the radiological dose to humans and concentrations of contaminants in the environment. To achieve these goals a biosphere model, comprising four submodels, has been developed. This report describes the atmosphere submodel and the pathways through which nuclides may move through the atmosphere. The model describes the processes of nuclide suspension, dispersion and deposition. Surface water and soil are considered as primary sources of nuclide fluxes to the atmosphere. Some nuclides may be attached to contaminated suspended particulate matter, whereas others are mobile as gases. The model considers natural phenomena such as wind erosion of soil, forest fires, gaseous emissions from soil, and bubble bursting at lake surfaces. Anthropogenic processes such as wood burning for energy are also modelled, and nuclide concentrations in both outdoor and indoor air are calculated. The model combines a variety of techniques, including mass loading concepts, flux density estimates, numerical dispersion models and specific activity relationships. The model is probabilistic; transport is modelled using simple mass transfer equations, and variability is incorporated by distributing values for parameters. This report documents the model equations, the parameter values, and comparisons of pathways. (Author)

  10. Natural analogs in support of the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Cramer, Jan.

    1994-08-01

    The assessment of the long-term safety and performance of the Canadian concept for disposal of nuclear fuel waste is a unique and challenging undertaking, because the predictions have to be made for time periods in the range of 10 4 to 10 6 a into the future. The data used for the assessment modelling is in large part based on observations from short-term laboratory and field experiments. Natural analogs can provide a reference for the safety assessment, providing both useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU (CANada Deuterium Uranium) fuel. The introduction gives a definition of natural analogs and an overview of the various types of analogs and analog studies. The review is broken down into sections pertaining to the major components of the disposal system: the vault, the geosphere and the biosphere. Specific examples are given for each. In addition, a section deals with several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by a number of countries as part of their waste management programs. (author). 224 refs., 11 tabs., 2 figs

  11. Natural analogs in support of the Canadian concept for nuclear fuel waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Cramer, Jan

    1994-08-01

    The assessment of the long-term safety and performance of the Canadian concept for disposal of nuclear fuel waste is a unique and challenging undertaking, because the predictions have to be made for time periods in the range of 10{sup 4} to 10{sup 6} a into the future. The data used for the assessment modelling is in large part based on observations from short-term laboratory and field experiments. Natural analogs can provide a reference for the safety assessment, providing both useful data and a qualitative illustration of the interaction of processes and materials in complex natural systems. This report reviews the available natural analog information used in support of the Canadian concept, with particular emphasis on the disposal of used CANDU (CANada Deuterium Uranium) fuel. The introduction gives a definition of natural analogs and an overview of the various types of analogs and analog studies. The review is broken down into sections pertaining to the major components of the disposal system: the vault, the geosphere and the biosphere. Specific examples are given for each. In addition, a section deals with several comprehensive natural systems that contain a number of features and processes similar to the disposal concept and that are under study by a number of countries as part of their waste management programs. (author). 224 refs., 11 tabs., 2 figs.

  12. Selection of Nuclear Desalination Technology in East Kalimantan Province

    International Nuclear Information System (INIS)

    Siti Alimah; Sudi Ariyanto; Erlan Dewita; Budiarto; Geni R Sunaryo

    2009-01-01

    Nowadays, electricity demand in East Kalimantan increases with a rate of 12% per annum. Since the electricity supply produced by PT PLN increases 8,5% per annum, then it can consequently an occurrence of electricity shortage in the region. NPP may be regarded as one viable option to overcome the problem. In case of fresh water availability, the supply is also less than the demand. Therefore, a serious effort is necessary. Nuclear desalination, which is a process of separating dissolved salts of seawater or brackish water, can be coupled to the NPP to produce fresh water. There are some desalination technology commonly used in the world i.e. MSF (Multi-Stage Flash Distillation), MED (Multi-Effect Distillation) and RO (Reverse Osmosis). This paper shows the study result of selection for desalination technology to obtain the optimum solution. The selection is done based on the thirteen important parameters, which are estimated to affect on determine technology option on the nuclear desalination with a weighing factor with ranges from 1 to 4. The most favourable technology is that with the highest point. The result show that MED has highest weighing factor that is 39, followed 36 for RO and 33 for MSF. Since the water quality requirement to supply NPP is about 1 ppm and to supply public demand is below 1000 ppm, so a hybrid system of MED-RO is optimum option to produce fresh water. (author)

  13. The role of nuclear research centres in the introduction of a nuclear power programme

    International Nuclear Information System (INIS)

    Afgan, N.; Anastasijevic, P.; Kolar, D.; Strohal, P.

    1977-01-01

    Full development of nuclear energy has imposed a new role on nuclear energy centres. Nuclear technology for different reactor concepts is also now in a phase of high development. Several reactor concepts have been developed for industrial use and electric power production. Development of fast reactors is still under way and needs further research efforts. Having in mind these two main guidelines, research programmes in nuclear energy centres should be geared to the development of the activities vital to the implementation of national nuclear energy programmes. In this respect, national nuclear centres should devote their attention to three major tasks. First, to establish a background for the introduction of nuclear energy into the national energy system and to support a national safety system. Secondly, to support the national programme by skilled manpower, to provide the basic training in nuclear technology for future staff of nuclear power stations and to assist the universities in establishing the necessary educational programme in nuclear energy. Thirdly, to follow the development of nuclear energy technology for fast breeder reactor concepts. (author)

  14. Creating broad acceptance of novel nuclear concepts (A progress report on relevant ISTC programs)

    Energy Technology Data Exchange (ETDEWEB)

    Tocheny, Lev V. [ISTC - International Science and Technology Center, Krasnoproletarskaya 32-34, POBox 20, 127473 Moscow (Russian Federation)

    2008-07-01

    The International Science and Technology Center (ISTC) is a unique international organization created in Moscow more than twelve years ago by Russia, USA, EU and Japan. Later Korea and Canada, and several CIS countries as well acceded to ISTC. The basic idea behind establishing the ISTC was to support non-proliferation of the mass destruction weapons technologies by re-directing former Soviet weapons scientists to peaceful research thus preventing the drain of dangerous knowledge and expertise from Russia and other CIS countries. Numerous science and technology projects are realized with the ISTC support in different areas, from bio-technologies and environmental problems to all aspects of nuclear studies, including those focused on the development of effective innovative concepts and technologies in the nuclear field, in general, and for improvement of nuclear safety, in particular. Presently, the ISTC has 40 member countries (27 from EU), representing the CIS, Europe, Asia, and North America. The Partner list includes over 180 organizations and leading industrial companies from all ISTC parties. ISTC Activities to the end of 2007 above 2500 projects approved for funding. More than 350 institutions and 35,000 specialists received grants from ISTC. The presentation addresses some consequences of the ISTC projects and programs, related to nuclear science and technologies, as well as methods and approaches employed by the ISTC to foster close international collaboration and joint manage projects towards fruitful results. (authors)

  15. Creating broad acceptance of novel nuclear concepts (A progress report on relevant ISTC programs)

    International Nuclear Information System (INIS)

    Tocheny, Lev V.

    2008-01-01

    The International Science and Technology Center (ISTC) is a unique international organization created in Moscow more than twelve years ago by Russia, USA, EU and Japan. Later Korea and Canada, and several CIS countries as well acceded to ISTC. The basic idea behind establishing the ISTC was to support non-proliferation of the mass destruction weapons technologies by re-directing former Soviet weapons scientists to peaceful research thus preventing the drain of dangerous knowledge and expertise from Russia and other CIS countries. Numerous science and technology projects are realized with the ISTC support in different areas, from bio-technologies and environmental problems to all aspects of nuclear studies, including those focused on the development of effective innovative concepts and technologies in the nuclear field, in general, and for improvement of nuclear safety, in particular. Presently, the ISTC has 40 member countries (27 from EU), representing the CIS, Europe, Asia, and North America. The Partner list includes over 180 organizations and leading industrial companies from all ISTC parties. ISTC Activities to the end of 2007 above 2500 projects approved for funding. More than 350 institutions and 35,000 specialists received grants from ISTC. The presentation addresses some consequences of the ISTC projects and programs, related to nuclear science and technologies, as well as methods and approaches employed by the ISTC to foster close international collaboration and joint manage projects towards fruitful results. (authors)

  16. Bibliography on the defense in depth (DiD) approach for nuclear safety

    International Nuclear Information System (INIS)

    Wielenberg, Andreas

    2016-07-01

    This report is a bibliography on references related to the concept of defence-in-depth (DiD), particularly in the field of nuclear reactor safety. In addition, selected publications on the application of DiD outside of the field of nuclear reactor safety are referenced. For each reference, the main data of the publication, an assignment of key words, a short summary of the relation to DiD and, if applicable, a link to an internet resource for the document is provided. The bibliography report aims at covering all the major sources of regulatory documents and texts related to DiD in nuclear reactor safety for major international organisation on nuclear reactor safety and regulators in the Europe, North America, and selected Asian countries. In order to manage the scope of the work, more recent publications have received precedence by the authors, outdated versions or superseded documents might not be included in this report. Since there are a lot of publications on the concept on DiD in a number of contexts, producing a comprehensive listing beyond the context of regulatory publications was not possible for this publication. There are, therefore, a lot of textbooks, publications in scientific journals, conference contributions, etc. related to the concept of DiD, which are not included into this report. Their omission is due to the constraints for the production of this report and is in no way intended as a negative statement on either their relevance or their technical quality. Publications after 2014 are not reflected in this report. (authors)

  17. Concept of voltage and frequency monitoring for a nuclear power plant normal power supply system - PWR 1300 MWe

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1990-01-01

    Voltage and frequency monitoring concept for a Nuclear Power Plant Normal Power Supply System (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and e NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  18. Nuclear waste package design for the Vadose zone in tuff

    International Nuclear Information System (INIS)

    O'Neal, W.C.; Ballou, L.B.; Gregg, D.W.; Russell, E.W.

    1984-02-01

    This report presents an overview of the selection and analysis of conceptual waste package designs that will be used by the Nevada Nuclear Waste Storage Investigations (NNWSI) project for disposal of high-level nuclear waste (HLW) at the proposed Yucca Mountain, Nevada Site. The design requirements that the waste packages are required to meet are listed. Concept drawings for the reference designs and one alternative package design are shown. Four metal alloys; 304L SS, 321 SS, 316L SS and Incoloy 825 have been selected for candidate canister/overpack materials, and 1020 carbon steel has been selected as the reference metal for the borehole liners. A summary of the results of technical and economic analysis supporting the selection of the conceptual waste package designs is included. Post-closure containment and release rates are not discussed in this paper. 17 references, 2 figures, 2 tables

  19. Concept Design and Risk Assessment of Nuclear Propulsion Ship

    International Nuclear Information System (INIS)

    Gil, Youngmi; Yoo, Seongjin; Kim, Yeontae; Oh, June; Byun, Yoonchul; Woo, Ilguk; Kim, Jiho; Choi, Suhn

    2014-01-01

    The nuclear propulsion ships (hereinafter referred to as 'nuclear ships') have been considered as an eco-friendly ship. There have historically been warship and submarine with the source of nuclear power. The use of nuclear ships has been recently extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, we evaluated the economics of various types of ships and concluded that the container ship could be appropriate for the nuclear propulsion. In order to verify its safety, we performed the ship calculation based on the optimal arrangement of the nuclear reactor. Finally, we verified its safety by the HAZID. In the former research, we confirmed the applicability of the nuclear propulsion system for the large container ship. In this study, we verified the safety of the nuclear ships according to the HAZID analysis. We expect that this research will lead to safe design of the nuclear ships

  20. Concept Design and Risk Assessment of Nuclear Propulsion Ship

    Energy Technology Data Exchange (ETDEWEB)

    Gil, Youngmi; Yoo, Seongjin; Kim, Yeontae; Oh, June; Byun, Yoonchul; Woo, Ilguk [Daewoo Shipbuilding and Marine Engineering Co. Ltd., Seoul (Korea, Republic of); Kim, Jiho; Choi, Suhn [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The nuclear propulsion ships (hereinafter referred to as 'nuclear ships') have been considered as an eco-friendly ship. There have historically been warship and submarine with the source of nuclear power. The use of nuclear ships has been recently extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, we evaluated the economics of various types of ships and concluded that the container ship could be appropriate for the nuclear propulsion. In order to verify its safety, we performed the ship calculation based on the optimal arrangement of the nuclear reactor. Finally, we verified its safety by the HAZID. In the former research, we confirmed the applicability of the nuclear propulsion system for the large container ship. In this study, we verified the safety of the nuclear ships according to the HAZID analysis. We expect that this research will lead to safe design of the nuclear ships.

  1. Next Generation Nuclear Plant System Requirements Manual

    International Nuclear Information System (INIS)

    Not Listed

    2008-01-01

    System Requirements Manual for the NGNP Project. The Energy Policy Act of 2005 (H.R. 6; EPAct), which was signed into law by President George W. Bush in August 2005, required the Secretary of the U.S. Department of Energy (DOE) to establish a project to be known as the Next Generation Nuclear Plant (NGNP) Project. According to the EPAct, the NGNP Project shall consist of the research, development, design, construction, and operation of a prototype plant (to be referred to herein as the NGNP) that (1) includes a nuclear reactor based on the research and development (R and D) activities supported by the Generation IV Nuclear Energy Systems initiative, and (2) shall be used to generate electricity, to produce hydrogen, or to both generate electricity and produce hydrogen. The NGNP Project supports both the national need to develop safe, clean, economical nuclear energy and the Nuclear Hydrogen Initiative (NHI), which has the goal of establishing greenhouse-gas-free technologies for the production of hydrogen. The DOE has selected the helium-cooled High Temperature Gas-Cooled Reactor (HTGR) as the reactor concept to be used for the NGNP because it is the only near-term Generation IV concept that has the capability to provide process heat at high-enough temperatures for highly efficient production of hydrogen. The EPAct also names the Idaho National Laboratory (INL), the DOE's lead national laboratory for nuclear energy research, as the site for the prototype NGNP

  2. Selection and construction of nuclear and radiation emergency medical center in a region

    International Nuclear Information System (INIS)

    Wang Guojun; He Xu; Liao Li; Gao Dong

    2014-01-01

    Three level of first-class comprehensive hospital is an important force of nuclear and radiation accident rescue, has a very rich experience in response to nuclear and radiation accidents and deal with large quantities of the sick and wounded. With the foundation and the ability of the construction and operation of medical emergency rescue center. This paper according to the median model location theory of emergency center, combined with the specific situation of the nuclear and radiation accident in Hunan Province, reference location, rescue experience, emergency allocation of resources, teaching and research capacity, establish regional medical emergency center of nuclear and radiation accidents based on three level of first-class comprehensive hospital, break the traditional concept that the center must be provincial capital,form a multi-level, three-dimensional, network of emergency hospital rescue system. The main duties of the center are accident emergency response, on-site treatment and technical guidance of accident, psychological grooming. The author propose building measures according to the duties of the center: increase national and provincial financial investment, carry out training, drills and first aid knowledge missionaries regularly, innovative materials management, speed up the construction of information platform, establish and improve the hospital rescue system, improve organization institution and system of plans, reengineering rescue process. (authors)

  3. ENTNEA: A concept for enhancing regional atomic energy cooperation for securing nuclear transparency in northeast Asia

    Energy Technology Data Exchange (ETDEWEB)

    Shin, S. T. [Korea Institute for Defence Analyses, Seoul (Korea)

    2000-11-01

    Nuclear energy continues to be a strong and growing component of economic development in Northeast Asia. A broad range of nuclear energy systems already exists across the region and vigorous growth is projected. Associated with these capabilities and plans are various concerns about operational safety, environmental protection, and accumulation of spent fuel and other nuclear materials. We consider cooperative measures that might address these concerns. The confidence building measures suggested here center on the sharing of information to lessen concerns about nuclear activities or to solve technical problems. These activities are encompassed by an Enhanced Nuclear Transparency in Northeast Asia (ENTNEA) concept that would be composed of near-term, information-sharing activities and an eventual regional institution. The near-term activities would address specific concerns and build a tradition of cooperation; examples include radiation measurements for public safety and emergency response, demonstration of safe operations at facilities and in transportation, and material security in the back end of the fuel cycle. Linkages to existing efforts and organizations would be sought to maximize the benefits of cooperation. In the longer term, the new cooperative tradition might evolve into an ENTNEA institution. In institutional form, ENTNEA could combine the near-term activities and new cooperative activities, which might require an institutional basis, for the mutual benefit and security of regional parties. 28 refs., 23 figs., 5 tabs. (Author)

  4. Civil liability for nuclear damage: selected questions connected with the revision of the Vienna Convention

    International Nuclear Information System (INIS)

    Lopuski, J.

    1993-01-01

    This paper concentrates on certain issues raised by the revision of the Vienna Convention. After a general theoretical review of the risk of and the responsibility for nuclear activities in the existing international civil liability regime, the author analyzes the concept of liability, its extent - whether nuclear liability can be absolute and refers to the possible exonerations - and the channelling of risk and liability in this field. The potential sources of compensation and funds for the operator's liability are also taken into consideration. The author also proposes several solutions taking into account the similar systems already established by other international conventions in force, mainly in the maritime field. 14 refs

  5. New reactor concepts; Nieuwe rectorconcepten - nouveaux reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A

    1998-11-01

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost.

  6. Program SYVAC, for stochastic assessment of nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Sherman, G.R.; Hoffman, K.J.; Donahue, D.C.

    1985-01-01

    In this paper, the computer program SYVAC, used to assess concepts for the disposal of nuclear fuel waste, is described with regard to the development approach, the basic program structure, and quality assurance. The interrelationships of these aspects are illustrated by detailed descriptions of two concepts of fundamental importance to the program: the method of selecting parameter values from input probability density functions, and the numerical evaluation of the convolution integral. Quality assurance procedures, including different types of comparisons and peer review, are presented

  7. Site selection for Canada's national repository for used nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Ben Belfadhel, M.; Watts, B.; Facella, J., E-mail: mbenbelfadhel@nwmo.ca [Nuclear Waste Management Organization (NWMO), Toronto, Ontario (Canada)

    2015-12-15

    In 2007, the Government of Canada selected Adaptive Phased Management as Canada's plan for the long-term management of Canada's used nuclear fuel. The approach provides for containment and isolation of the material in a deep geological repository at a safe site with an informed and willing host. The Nuclear Waste Management Organization is tasked through federal legislation with selecting the site and developing and managing all aspects of the plan. In May 2010, the organization published and initiated the site selection process that serves as a road map for decision making on the location for the deep geological repository. It continues to lead the site selection process for the repository and an associated Centre of Expertise. The screening process is advancing and, from an initial starting point of 22 communities expressing interest in learning about the project; as of September 2015, 9 communities are the focus of more detailed technical and community well-being studies. Preliminary Assessments, the third step in the 9-step site selection process are underway in these communities. The Assessments involve preliminary technical and social desktop and field assessments, engagement activities within and beyond each interested community, and involvement of Indigenous peoples and nearby municipalities in the planning and conduct of the work. This paper provides an update on the advancement of the site selection process. It describes the nature of the technical and social studies being conducted at this phase of work, including the progressively more detailed field studies that are the focus of technical work at the current stage, the approach to engagement and collaboration with communities to direct these studies, and the work underway to ensure the framework used for this assessment and engagement includes the range of priorities and perspectives of First Nations and Metis peoples and communities in the broader area. (author)

  8. The encapsulated nuclear heat source reactor for proliferation-resistant nuclear energy

    International Nuclear Information System (INIS)

    Brown, N.W.; Hossain, Q.; Carelli, M.D.; Conway, L.; Dzodzo, M.; Greenspan, E.; Saphier, D.

    2001-01-01

    The encapsulated nuclear heat source (ENHS) is a modular reactor that was selected by the 1999 DOE NERI program as a candidate ''Generation-IV'' reactor concept. It is a fast neutron spectrum reactor cooled by Pb-Bi using natural circulation. It is designed for passive load following, for high level of passive safety, and for 15 years without refueling. One of the unique features of the ENHS is that the fission-generated heat is transferred from the primary coolant to the secondary coolant across the reactor vessel wall by conduction-providing for an essentially sealed module that is easy to install and replace. Because the fuel is encapsulated within a heavy steel container throughout its life it provides a unique improvement to the proliferation resistance of the nuclear fuel cycle. This paper presents the innovative technology of the ENHS. (author)

  9. Inherent safe design of advanced high temperature reactors - concepts for future nuclear power plants

    International Nuclear Information System (INIS)

    Hodzic, A.; Kugeler, K.

    1997-01-01

    This paper discusses the applicable solutions for a commercial size High Temperature Reactor (HTR) with inherent safety features. It describes the possible realization using an advanced concept which combines newly proposed design characteristics with some well known and proven HTR inherent safety features. The use of the HTR technology offers the conceivably best solution to meet the legal criteria, recently stated in Germany, for the future reactor generation. Both systems, block and pebble bed ,reactor, could be under certain design conditions self regulating in terms of core nuclear heat, mechanical stability and the environmental transfer. 23 refs., 7 figs

  10. Nuclear energy an introduction to the concepts, systems, and applications of nuclear processes

    CERN Document Server

    Murray, Raymond

    2001-01-01

    Nuclear Energy, Fifth Edition provides nuclear engineers, plant designers and radiation physicists with a comprehensive overview of nuclear energy and its uses, discusses potential problems and provides an outlook for the futureNew and important trends are discussed including probabilistic safety analysis (PSA), deregulation of the electric power industry to permit competition in the supply of electricity; improvements in performance characteristics of nuclear power plants, such as capacity factor, production costs, and safety factors; storage and disposal of all types of radioactive w

  11. Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mecartnery, Martha [Univ. of California, Irvine, CA (United States); Graeve, Olivia [Univ. of California, San Diego, CA (United States); Patel, Maulik [Univ. of Liverpool (United Kingdom)

    2017-05-25

    The goal of this research is to help develop new fuels for higher efficiency, longer lifetimes (higher burn-up) and increased accident tolerance in future nuclear reactors. Multiphase nanocrystalline ceramics will be used in the design of simulated advanced inert matrix nuclear fuel to provide for enhanced plasticity, better radiation tolerance, and improved thermal conductivity

  12. Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel

    International Nuclear Information System (INIS)

    Mecartnery, Martha; Graeve, Olivia; Patel, Maulik

    2017-01-01

    The goal of this research is to help develop new fuels for higher efficiency, longer lifetimes (higher burn-up) and increased accident tolerance in future nuclear reactors. Multiphase nanocrystalline ceramics will be used in the design of simulated advanced inert matrix nuclear fuel to provide for enhanced plasticity, better radiation tolerance, and improved thermal conductivity

  13. Nuclear weapons, scientists, and the post-Cold War challenge selected papers on arms control

    CERN Document Server

    Drell, Sidney D

    2007-01-01

    This volume includes a representative selection of Sidney Drell's recent writings and speeches (circa 1993 to the present) on public policy issues with substantial scientific components. Most of the writings deal with national security, nuclear weapons, and arms control and reflect the author's personal involvement in such issues dating back to 1960. Fifteen years after the demise of the Soviet Union, the gravest danger presented by nuclear weapons is the spread of advanced technology that may result in the proliferation of nuclear weapons. Of most concern would be their acquisition by hostile governments and terrorists who are unconstrained by accepted norms of civilized behavior. The current challenges are to prevent this from happening and, at the same time, to pursue aggressively the opportunity to escape from an outdated nuclear deterrence trap.

  14. Concepts for space nuclear multi-mode reactors

    International Nuclear Information System (INIS)

    Myrabo, L.; Botts, T.E.; Powell, J.R.

    1983-01-01

    A number of nuclear multi-mode reactor power plants are conceptualized for use with solid core, fixed particle bed and rotating particle bed reactors. Multi-mode systems generate high peak electrical power in the open cycle mode, with MHD generator or turbogenerator converters and cryogenically stored coolants. Low level stationkeeping power and auxiliary reactor cooling (i.e., for the removal of reactor afterheat) are provided in a closed cycle mode. Depending on reactor design, heat transfer to the low power converters can be accomplished by heat pipes, liquid metal coolants or high pressure gas coolants. Candidate low power conversion cycles include Brayton turbogenerator, Rankine turbogenerator, thermoelectric and thermionic approaches. A methodology is suggested for estimating the system mass of multi-mode nuclear power plants as a function of peak electric power level and required mission run time. The masses of closed cycle nuclear and open cycle chemical power systems are briefly examined to identify the regime of superiority for nuclear multi-mode systems. Key research and technology issues for such power plants are also identified

  15. Selected topics in nuclear structure

    International Nuclear Information System (INIS)

    Faessler, A.

    1990-01-01

    Today's dream of nuclear structure physics is to calculate the properties of nuclei starting from Quantum-Chromodynamics (QCD). However, we are definitely not able to do that today and may be even in the future one would wish only to show in principle that this is possible. It probably will never be a daily approach to study excitation energies, transitions probabilities and other properties of nuclei. This paper discusses the possibility of coming from the shore of QCD to the other side of the river, to nuclear structure, not in one great arch buy like medieval bridges in several arches grounded each solidly on pillars going down to the river floor and by that connecting theory with the solid ground of experiments. The first arch is meant to connect QCD and the nucleon-nucleon phase shifts with the help to the nucleon-nucleon phase shifts with the experimentally fitted effective interactions for the final model spaces used in nuclear structure calculations. This is at the moment still by far the weakest arch although a large amount of work and ideas have been invested since about the middle of the 60's to derive a theory of effective interactions and to establish the connection of the effective interaction fitted to nuclear structure data with the bare interaction between nucleons in the vacuum. The last arch is connecting the effective nucleon-nucleon interaction with nuclear structure properties

  16. Proof-of-concept study of a marine ion-selective optical sensing instrument

    Science.gov (United States)

    Sobron, P.; Thompson, C.; Bamsey, M.

    2013-12-01

    We have developed a proof-of-concept instrument for real-time in-situ characterization of the ion chemistry of the ocean. Our instrument uses optical sensors equipped with ion-selective membranes which exhibit a change in an optical property that can be correlated with the concentration of a specific ion. We have implemented a system for multi-ion sensing that includes the use of a single spectrometer in tandem with a fiber optic multiplexer that is capable of reading a suite of attached optrodes, each of them dedicated to a unique ion. In this abstract we report the experimental characterization of calcium and potassium optrodes as a template for ion-selective optrodes and their application to the characterization of the oceans. The tests were performed at the Controlled Environment Systems Research Facility of the University of Guelph. Guelph's optrode housing was tested by immersing it in a 1/2 strength Hoagland's hydroponic solution to test functionality of the K+ and Ca2+ optrodes in this environment. Our results demonstrate the feasibility of recording spectral information in sub-minute times from more than one optrode simultaneously in a given aqueous system. This proof-of-concept study has allowed us to measure parameters of interest and comparison to analytical predictions for critical subsystems of a deployable system, and demonstrates maturity of the multi-ion sensing optrode technology. Critical advantages of our optrode system are that it: (1) enables concurrent measurements of multiple ionic species relevant in ocean sciences; (2) has high time and spatial resolution; (3) has low limits of detection; (4) uses low-cost, low-mass, energy efficient optoelectronics. Our system has the potential for facilitating new observational, experimental, and analytic capabilities in ocean sciences, including: (a) health and environment monitoring; (b) aquaculture; (c) global change, e.g. ocean acidification; and (d) origin of life research. Proof-of-concept setup at

  17. The role of nuclear research centers for the introduction of a nuclear power programme

    International Nuclear Information System (INIS)

    Perovic, B.; Frlec, B.; Kundic, V.

    1977-01-01

    Full development of nuclear energy has imposed a new role on nuclear energy centers. Nuclear technology for different reactor concepts is also now in a phase of high development. Several reactor concepts have been developed for industrial use and electric power production. Development of fast reactors is still under way and needs further research efforts. Having in mind these two main guidelines, research programmes in nuclear energy centers should be geared to the development of the activities vital to the implementation of national nuclear energy programmes. In this respect, national nuclear centers should devote their attention to three major tasks. First, to establish a background for the introduction of nuclear energy into the national energy system and to support a national safety system. Second, to support the national programme by skilled manpower, to provide the basic training in nuclear technology for future staff of nuclear power stations and to assist the universities in establishing the necessary educational programme in nuclear energy. Third, to follow the development of nuclear energy technology for the fast breeder reactor concepts. This paper describes some experience in introducing a new programme to the national nuclear energy centers in Yugoslavia. Recently, Yugoslavia has started building its first nuclear power station. Further introduction of nuclear power stations in the national electric energy system is also planned. This implies the need to reconsider the current nuclear energy programme in the nuclear energy centers. It has been decided to evaluate past experience and further needs for research activities regarding the nuclear power programme. Yugoslavia has three main nuclear energy centers whose activities are devoted to the development of national manpower in the field of nuclear sciences. Besides these three organizations, there are several others whose activities are concentrated on specific tasks in nuclear technology. In the

  18. Role of mine ventilation in site selection for a nuclear waste repository

    International Nuclear Information System (INIS)

    McPherson, M.J.

    1984-01-01

    The application of mine ventilation practice and theory to the measurement of groundwater flow for the purpose of the selection of sites for underground storage of nuclear spent fuel is described. The discipline of mine ventilation has an important part to play not only in the design and operation of an underground nuclear waste repository but also during the early stages of potential site characterization. One of the most vital factors in the selection of a suitable site is the rate at which groundwater can flow through the native rock. The effects of repository heat on groundwater migration are highlighted and a description of a major experiment in an underground test site is included. Detailed monitoring of airflow and its psychrometric properties enabled quantification of very low rates of water seepage into an isolated heading. The results indicated the relationship between permeability of a fractured rock and temperature. The transient phenomena that govern evaporation of water from fissured rock surfaces in the test chamber are also examined. (author)

  19. Final repository for spent nuclear fuel in granite - the KBS-3V concept in Sweden and Finland

    International Nuclear Information System (INIS)

    Pettersson, Stig; Loennerberg, Bengt

    2008-01-01

    Both Sweden and Finland has advanced plans for design, construction and operation of the final repositories for direct disposal of spent nuclear fuel. Both countries have the same type of host rock - granite. They are also investigating alternative concept for disposal, vertical or horizontal disposal of the canisters with encapsulated spent nuclear fuel, normally called KBS-3V or the KBS-3H disposal concept. The development of the KBS-3V concept started around 1980 and is the reference method for both SKB in Sweden and Posiva in Finland. However, extensive development work is ongoing since 2001 with KBS-3H in order to bring that concept to the same maturity as KBS-3V. This presentation deals with the design and operation of the KBS-3V based on the work done within Sweden and SKB but the development is Finland is identical and it is a close cooperation between SKB in Sweden and Posiva in Finland. In Sweden, the site investigation for location of the repository has been concentrated on two sites, in the Oskarshamn area, about 350 km south of Stockholm, and the Forsmark area, about 180 km north of Stockholm. For information it can be mentioned that Finland plans to locate their repository in the vicinity of the Olkiluoto nuclear power plant site, about 300 km north of Helsinki. The site investigation is completed and the selection of site is scheduled to mid 2009 and sending in the application for location and construction of the repository is scheduled to end 2009. After receiving all necessary permits, construction time and commissioning will take about 7 to 8 years and operation is expected to start about 2020. The KBS-3 system is based on a multi barrier concept and the work with compiling the design requirements for the underground part of the deep repository has been ongoing for some time within the SKB organisation. Today the design requirements for the underground part are documented in a big number of reports that has been produced by specialists and working

  20. Nuclear energy technology: theory and practice of commercial nuclear power

    International Nuclear Information System (INIS)

    Knief, R.A.

    1982-01-01

    Reviews Nuclear Energy Technology: Theory and Practice of Commercial Nuclear Power by Ronald Allen Knief, whose contents include an overview of the basic concepts of reactors and the nuclear fuel cycle; the basics of nuclear physics; reactor theory; heat removal; economics; current concerns at the front and back ends of the fuel cycle; design descriptions of domestic and foreign reactor systems; reactor safety and safeguards; Three Mile Island; and a brief overview of the basic concepts of nuclear fusion. Both magnetic and inertial confinement techniques are clearly outlined. Also reviews Nuclear Fuel Management by Harry W. Graves, Jr., consisting of introductory subjects (e.g. front end of fuel cycle); core physics methodology required for fuel depletion calculations; power capability evaluation (analyzes physical parameters that limit potential core power density); and fuel management topics (economics, loading arrangements and core operation strategies)

  1. Accelerator technology for Los Alamos nuclear-waste-transmutation and energy-production concepts

    International Nuclear Information System (INIS)

    Lawrence, G.P.; Jameson, R.A.; Schriber, S.O.

    1991-01-01

    Powerful proton linacs are being studied at Los Alamos as drivers for high-flux neutron sources that can transmute long-lived fission products and actinides in defense nuclear waste, and also as drivers of advanced fission-energy systems that could generate electric power with no long-term waste legacy. A transmuter fed by an 800-MeV, 140-mA cw conventional copper linac could destroy the accumulated 99 Tc and 129 I at the DOE's Hanford site within 30 years. A high-efficiency 1200-MeV, 140-mA niobium superconducting linac could drive an energy-producing system generating 1-GWe electric power. Preliminary design concepts for these different high-power linacs are discussed, along with the principal technical issues and the status of the technology base. 9 refs., 5 figs., 4 tabs

  2. The IAEA concept of detection of diversion through nuclear material accountancy (2)

    International Nuclear Information System (INIS)

    Akiba, Mitsunori

    2005-01-01

    Diversion into D (falsification of accounting report) and diversion into MUF could be detected by the Inspectorate through nuclear material accountancy. The Inspectorate designs inspection activities to detect diversion into D in cost effective ways. As a result, detection of diversion into D is divided into two statistics, one is item difference statistics which could detect major defects and the other is material balance statistics which could detect remaining small defects. MUF statistics could detect Diversion into MUF. Item statistics has many useful characteristics from safeguards view points, so it is examined in details. Material balance statistics and MUF statistics stem from measurement error associated with equipment inevitably. The above-mentioned concept is called 'IAEA decision structure'. Hereafter, designing safeguards (inspection activities) approach will be based on the IAEA decision structure. (author)

  3. Advanced display concepts in nuclear control rooms

    International Nuclear Information System (INIS)

    Clark, M.T.; Banks, W.W.; Blackman, H.S.; Gertman, D.I.

    1982-01-01

    Precursors necessary for the development of a full-scale predictor display/control system have been under development since the mid 1940's. The predictor display itself has been available for use in manual control systems since 1958. However, the nuclear industry has not yet explored the uses and benefits of predictor systems. The purpose of this paper is to provide information on the application of this technology to the nuclear industry. The possibility of employing a simulation-based control system for nuclear plant systems that currently use conventional auto/manual schemes is discussed. By employing simulation-based systems, a predictor display could be made available to the operator during manual operations, thus facilitating control without outwardly affecting the overall control scheme

  4. Human factor as nuclear safety element

    International Nuclear Information System (INIS)

    Valeca, S.C.; Preda, M.; Valeca, M.; Ana, E. M.; Popescu, D.

    2008-01-01

    National nuclear power system is based on western technology, it covers almost 20% from national need and could be briefly described by: - Safety and economic performances of Cernavoda NPP Unit 1; - Reduced influence on environment, population and workers; - Excellent ranking (place 4) among CANDU units from all over the world. Also, the national nuclear power system plays a major role in Romanian power policy accomplishment: - Energy safety and independence assurance; - Decrease of production of greenhouse effect gases; - Preserve the stability and adequacy of energy cost. 'Nuclear Safety' concept covers all the activities resulting from nuclear fuel cycle. By taking into account the international experience, the related activities are estimated to last around 70 years in Romania: - 10 years for site description and selection, design, manufacturing and commissioning activities; - 40 years for Nuclear Power Plant operation, maintenance and modernization activities; - 20 years for preservation and decommissioning activities. The above mentioned activities requires human resources, qualified and specialized in the following areas: - research and development; - equipment design, manufacturing and operation; - components construction and assembly, operation and maintenance. (authors)

  5. Integrated logistic support concept in the design of nuclear power plants

    International Nuclear Information System (INIS)

    Martin-Onraet, M.; Degrave, C.; Meuwisse, C.

    1996-01-01

    Considering its plant operating experience, the analysis of foreign practice and the development of new design approaches and tools, Electricite de France (EDF) is convinced that it is possible to improve new plant design, operation and maintenance without increasing too much investment costs. To remain competitive it is necessary to maintain the kWh production cost of the future unit at a level close to those of the latest unit under construction (N4 series), while raising the Safety level. To minimize the kWh cost EDF has decided to implement the CIDEM project (French acronym for Design Integrating Availability, Operating Experience and Maintenance), an analytic and systematic process for studying new projects, aiming at a design optimization including investment, maintenance, availability and radiation exposure objectives. This approach aims at a single goal: to minimize the kWh production cost incorporating investment operation and fuel cost, based on experience from French and foreign units. This process, already widely practiced in other industries or services (aerospace, defense, ...), uses concepts known by the acronyms RAM (Reliability, Availability, Maintainability) RCM (Reliability, Centered Maintenance) and ILS (Integrated Logistic Support). The first CIDEM application is centered on the future French nuclear unit construction program, known as the REP 2000 program but the approach could be applied to other Reactor type or fossil-fired units in particular for its methodological aspect. The purpose of this paper is to introduce the EDF ILS concept

  6. Selected topics in special nuclear materials safeguard system design

    International Nuclear Information System (INIS)

    King, L.L.; Thatcher, C.D.; Clarke, J.D.; Rodriguez, M.P.

    1991-01-01

    During the past two decades the improvements in circuit integration have given rise to many new applications in digital processing technology by continuously reducing the unit cost of processing power. Along with this increase in processing power a corresponding decrease in circuit volume has been achieved. Progress has been so swift that new classes of applications become feasible every 2 or 3 years. This is especially true in the application of proven new technology to special nuclear materials (SNM) safeguard systems. Several areas of application were investigated in establishing the performance requirements for the SNM safeguard system. These included the improvements in material control and accountability and surveillance by using multiple sensors to continuously monitor SNM inventory within the selected value(s); establishing a system architecture to provide capabilities needed for present and future performance requirements; and limiting operating manpower exposure to radiation. This paper describes two selected topics in the application of state-of-the-art, well-proven technology to SNM safeguard system design

  7. Development of probabilistic evaluation methodology for structural integrity of nuclear components

    International Nuclear Information System (INIS)

    Lee, Gang Yong; Yang, Jee Hyeok; Shin, Jeong Woo; Hong, Soon Won; Lee, Won Gyu; Kim, Goo Yeong

    1999-03-01

    Since integrity is very important in Nuclear Power Plants, there have been a lot of researches and several rules are provided. But these are mostly based on the concept of the deterministic fracture mechanics and in many cases, those rules are unrealistic or conservative. Therefore, the concept of the probabilistic fracture mechanics considering the realistic failure of the structure and the quantitative failure probability is introduced in many fields. There have been many researches on the probabilistic fracture mechanics in world, but a few in Korea. The final object of our research os to develop the code years. In the first year study, we obtained the concept of the probabilistic fracture mechanics by reviewing the papers about the integrity evaluation of the nuclear pressure vessel on the base of the probabilistic fracture mechanics and selected the important random variables by comparing the effects of random variables on the failure probability using the existing code

  8. New concept of siting in the 21st century

    International Nuclear Information System (INIS)

    Nakayama, Katsuma; Otsubo, Fumiharu; Kumagai, Shigeru

    1995-01-01

    The New Concept of Siting in the 21st Century -- the theme of this paper -- is the concept of a new siting technology which combines the application of man - made islands (offshore), underground (steep mountains along the sea), and quaternary ground with the symbiosis with local communities. It is intended not only for promotion of the construction of nuclear power plants but also for the development of a 'new community', including the inducement of enterprises to the construction site and the promotion of new industries at the site. In studying the new concept, it is necessary to select model areas, discuss design and construction methods, and make a rough calculation of construction cost. In addition, we plan to estimate economic effects of the new concept on the construction site area. During 1993, we discussed appropriate physical conditions (topographic feature, geological structure, etc.) and geographical conditions (population density, national parks, fishing right, etc.) for the application of the siting technology giving consideration to the concept symbiosis with local communities. At present, the estimations of construction cost and future effects of new siting technology on local communities are carried on to study the new concept of siting in the 21st century. (author)

  9. Nuclear power plants: selected references

    International Nuclear Information System (INIS)

    Stewart, A.W.

    1982-01-01

    Books, articles, and US government documents cited in this bibliography cover the political, economic, environmental, scientific, and legal aspects of nuclear power. Because the question of safety has been such an important issue in the debate over nuclear power, safety aspects are treated in a substantial number of the publications cited. All material listed was published in the past 15 years, with the majority appearing since 1975

  10. Identification of potential nuclear reprogramming and differentiation factors by a novel selection method for cloning chromatin-binding proteins

    International Nuclear Information System (INIS)

    Wang Liu; Zheng Aihua; Yi Ling; Xu Chongren; Ding Mingxiao; Deng Hongkui

    2004-01-01

    Nuclear reprogramming is critical for animal cloning and stem cell creation through nuclear transfer, which requires extensive remodeling of chromosomal architecture involving dramatic changes in chromatin-binding proteins. To understand the mechanism of nuclear reprogramming, it is critical to identify chromatin-binding factors specify the reprogramming process. In this report, we have developed a high-throughput selection method, based on T7 phage display and chromatin immunoprecipitation, to isolate chromatin-binding factors expressed in mouse embryonic stem cells using primary mouse embryonic fibroblast chromatin. Seven chromatin-binding proteins have been isolated by this method. We have also isolated several chromatin-binding proteins involved in hepatocyte differentiation. Our method provides a powerful tool to rapidly and selectively identify chromatin-binding proteins. The method can be used to study epigenetic modification of chromatin during nuclear reprogramming, cell differentiation, and transdifferentiation

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

    Science.gov (United States)

    Bobrowski, Krzysztof; Skotnicki, Konrad; Szreder, Tomasz

    2016-10-01

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

  12. Nuclear waste processing

    International Nuclear Information System (INIS)

    Nienhuys, K.; Noordegraaf, D.

    1977-04-01

    This report is composed with a view to the discussions around the selection of a site in F.R.Germany near the Netherlands' border for a fuel reprocessing plant. Most of the scientific data available are placed side by side, especially those which are contradictory in order to promote better judgement of affairs before governmental decisions are made. The report comprises a brief introduction to nuclear power plants, fuel cycle, radioactive materials and their properties. Next the transportation of wastes from the nuclear power plants to the reprocessing plants is dealt with more extensively, including the processing and the effluents of as well as the experiences with operational reprocessing plants. The hazards from manipulation of radioactive materials accidents and theft are outlined in each case, followed by a problem discussion. The appendix illustrates the German concept of 'industrial park for after-treatment and disposal'

  13. The Need to Assess Public Values in a Site Selection Process

    Energy Technology Data Exchange (ETDEWEB)

    Sheng, Grant; Fortier, Michael [York Univ., Toronto, ON (Canada). Faculty of Environmental Studies; Collins, Alison [York Centre for Applied Sustainability, Toronto, ON (Canada)

    2001-07-01

    Siting a nuclear fuel waste disposal facility is highly problematic for both technical and nontechnical reasons. The majority of countries using nuclear energy and many in the scientific community favour burying the spent fuel deep in a stable geological formation. It is our contention that site selection of a disposal facility must consider social, political, spatial and scientific perspectives in a comprehensive and integrated fashion in order to achieve a successful process. Moreover, we submit that people's values must be explicitly recognized and be taken into account through a formalized process during deliberations on the disposal concept, the process of evaluation of the concept, and the site selection process. The purpose of this paper is: (1) to identify the importance of recognizing people's values in the process of determining 'public acceptability', (2) to outline a possible framework by which public acceptability can be gauged through a formalized process of value elicitation, and (3) to introduce a novel method by which a web-based geographic information systems (GIS) application can be used as a tool for value elicitation. In order to assess effectively the public acceptability of Canada's nuclear waste disposal concept, we submit that such a process must examine the underlying values that are held by the public. Moreover, the evaluation process of Canada's concept demonstrates that an acceptable process is a pre-condition for an acceptable result, although such a process does not necessarily guarantee an acceptable result. However, the consequences of a flawed process can be very significant, as shown by Canada's experience. This paper also provides a brief overview of a value elicitation process that, in our opinion, could be used to assess the public acceptability of the Concept. We also describe how a web-based GIS application could be used to infer some of the underlying values held by the public.

  14. Quality indexes for selecting control materials of the nuclear reactors

    International Nuclear Information System (INIS)

    Martinez-Val, J.M.; Pena, J.; Esteban Naudin, A.

    1981-01-01

    Quality indexes are established and valued for selecting control materials, The requirements for accomplishing such purposes are explained with detailed analysis: absortion cross section must be as high as possible, adequate reactivity evolution versus depletion, good resistance to radiation, appropiate thermal stability, mechanical resistance and ductility, chemical compatibility with the environment, good heat transfer properties, abundant in the nature and low costs. At present Westinghouse desire to commercialize hafnium as control material shows the exciting task of looking for new materials controlling nuclear reactors. (auth.)

  15. How is it possible to measure a nuclear temperature

    International Nuclear Information System (INIS)

    Tamain, B.

    1989-01-01

    Several methods for the measurement of nuclear temperatures are summarized. The concepts of hot nuclei and temperature are defined. The nuclear equation of state is presented. The statistical theory of hot nuclei decay properties is analyzed. The obtention of the excitation energy from the recoil velocity measurement is considered in the case of complete and incomplete fusion. The measurements of temperature and excitation energy from the properties of decay products are reviewed. The study shows that no measurement method is perfect. Moreover, it is necessary to select events for which the degree of dissipation of the incident energy is estimated

  16. Nuclear law and new legal concepts; Droit nucleaire et concepts juridiques nouveaux

    Energy Technology Data Exchange (ETDEWEB)

    Atias, Ch.; Warusfel, B. [Paris-5 Univ., 75 (France); Byk, Ch. [Association Internationale droit, ethique et science, 75 - Paris (France)

    2003-02-01

    The articles on this topic have been written from three of the papers of the Conference organized on January 14, in Paris by the 'Law and Insurance' Section of the French Nuclear Energy Society together with the French Section of the International Nuclear Law Association. The first two articles deal with transparency, its justifications and limits. The third article analyses the rights of the future generations and our duties towards them. (authors)

  17. Nuclear safety culture and nuclear safety supervision

    International Nuclear Information System (INIS)

    Chai Jianshe

    2013-01-01

    In this paper, the author reviews systematically and summarizes up the development process and stage characteristics of nuclear safety culture, analysis the connotation and characteristics of nuclear safety culture, sums up the achievements of our country's nuclear safety supervision, dissects the challenges and problems of nuclear safety supervision. This thesis focused on the relationship between nuclear safety culture and nuclear safety supervision, they are essential differences, but there is a close relationship. Nuclear safety supervision needs to introduce some concepts of nuclear safety culture, lays emphasis on humanistic care and improves its level and efficiency. Nuclear safety supervision authorities must strengthen nuclear safety culture training, conduct the development of nuclear safety culture, make sure that nuclear safety culture can play significant roles. (author)

  18. Evaluation of scaling concepts for integral system test facilities

    International Nuclear Information System (INIS)

    Condie, K.G.; Larson, T.K.; Davis, C.B.

    1987-01-01

    A study was conducted by EG and G Idaho, Inc., to identify and technically evaluate potential concepts which will allow the U.S. Nuclear Regulatory Commission to maintain the capability to conduct future integral, thermal-hydraulic facility experiments of interest to light water reactor safety. This paper summarizes the methodology used in the study and presents a rankings for each facility concept relative to its ability to simulate phenomena identified as important in selected reactor transients in Babcock and Wilcox and Westinghouse large pressurized water reactors. Established scaling methodologies are used to develop potential concepts for scaled integral thermal-hydraulic experiment facilities. Concepts selected included: full height, full pressure water; reduced height, reduced pressure water; reduced height, full pressure water; one-tenth linear, full pressure water; and reduced height, full scaled pressure Freon. Results from this study suggest that a facility capable of operating at typical reactor operating conditions will scale most phenomena reasonably well. Local heat transfer phenomena is best scaled by the full height facility, while the reduced height facilities provide better scaling where multi-dimensional phenomena are considered important. Although many phenomena in facilities using Freon or water at nontypical pressure will scale reasonably well, those phenomena which are heavily dependent on quality can be distorted. Furthermore, relation of data produced in facilities operating with nontypical fluids or at nontypical pressures to large plants will be a difficult and time-consuming process

  19. Dynamic nuclear polarization and optimal control spatial-selective 13C MRI and MRS

    DEFF Research Database (Denmark)

    Vinding, Mads Sloth; Laustsen, Christoffer; Maximov, Ivan I.

    2013-01-01

    . This is achieved through the development of spatial-selective single-shot spiral-readout MRI and MRS experiments combined with dynamic nuclear polarization hyperpolarized [1-13C]pyruvate on a 4.7T pre-clinical MR scanner. The method stands out from related techniques by facilitating anatomic shaped region...

  20. Nuclear friction and chaotic motion

    International Nuclear Information System (INIS)

    Srokowski, T.; Szczurek, A.; Drozdz, S.

    1990-01-01

    The concept of nuclear friction is considered from the point of view of regular versus chaotic motion in an atomic nucleus. Using a realistic nuclear Hamiltonian it is explicitly shown that the frictional description of the gross features of nuclear collisions is adequate if the system behaves chaotically. Because of the core in the Hamiltonian, the three-body nuclear system already reveals a structure of the phase space rich enough for this concept to be applicable

  1. Selected exercises in particle and nuclear physics

    CERN Document Server

    Bianchini, Lorenzo

    2018-01-01

    This book presents more than 300 exercises, with guided solutions, on topics that span both the experimental and the theoretical aspects of particle physics. The exercises are organized by subject, covering kinematics, interactions of particles with matter, particle detectors, hadrons and resonances, electroweak interactions and flavor physics, statistics and data analysis, and accelerators and beam dynamics. Some 200 of the exercises, including 50 in multiple-choice format, derive from exams set by the Italian National Institute for Nuclear Research (INFN) over the past decade to select its scientific staff of experimental researchers. The remainder comprise problems taken from the undergraduate classes at ETH Zurich or inspired by classic textbooks. Whenever appropriate, in-depth information is provided on the source of the problem, and readers will also benefit from the inclusion of bibliographic details and short dissertations on particular topics. This book is an ideal complement to textbooks on experime...

  2. Improved best estimate plus uncertainty methodology including advanced validation concepts to license evolving nuclear reactors

    International Nuclear Information System (INIS)

    Unal, Cetin; Williams, Brian; McClure, Patrick; Nelson, Ralph A.

    2010-01-01

    Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M and S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for

  3. Improved best estimate plus uncertainty methodology including advanced validation concepts to license evolving nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Unal, Cetin [Los Alamos National Laboratory; Williams, Brian [Los Alamos National Laboratory; Mc Clure, Patrick [Los Alamos National Laboratory; Nelson, Ralph A [IDAHO NATIONAL LAB

    2010-01-01

    Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M&S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for cost

  4. Process for selecting a site for Canada's deep geological repository for used nuclear fuel

    International Nuclear Information System (INIS)

    Facella, J.; Belfadhel, M.B.

    2011-01-01

    The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management, the approach selected by the Government of Canada for long-term management of used nuclear fuel waste generated by Canadian nuclear reactors. The ultimate objective of Adaptive Phased Management is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable crystalline or sedimentary rock formation at a depth of about 500m. The repository will consist of a series of access and service shafts and a series of tunnels leading to placement rooms where used fuel will be placed and sealed in competent rock using a multi-barrier system which includes long lived specially designed containers, sealing materials such as bentonite and the rock itself. The used fuel will be monitored throughout all phases of implementation and will also remain retrievable for an extended period of time. In May 2010, the NWMO published the site selection process that serves as the road map to decision-making on the location for the deep geological repository. NWMO initiated the process with a first stage that invites communities to learn more about the project and the site selection process. NWMO is actively building awareness of the project and, on request of communities, is delivering briefings, supporting community capacity building and undertaking high-level screenings of site suitability. The paper provides a brief description of: Adaptive Phased Management including the deep geological repository which is its ultimate goal, and the design of the site selection process, and importantly the approach to assessing the suitability of sites from both a social and technical perspective. The paper will outline how NWMO sought to develop a socially-acceptable site selection process as a firm foundation for future decisions on siting. Through a two-year collaborative process, NWMO sought to understand the expectations of

  5. Selection, competency development and assessment of nuclear power plant managers

    International Nuclear Information System (INIS)

    1998-06-01

    This publication provides information on proven methods and good practices with respect to the selection, development and assessment of nuclear power plant (NPP) managers. The report is organized into four sections, a glossary, two appendices, and several annexes. The Introduction (Section 1) provides the framework for the report. Section 2 describes how appropriate management competencies can be used for the selection, development and assessment of NPP managers, including: -Selection which includes recruitment, promotion and succession management. -Management development programmes including formal training, job rotation, on the job training, mentoring, and outside assignments. -Assessment of individual performance. Section 3 describes a systematic process for identifying the competencies needed by NPP managers. This section culminates in a set of suggested core competencies for NPP managers which are further expanded in Appendix A. The annexes included provide specific examples of competency-based management selection, development, and assessment programmes in several Member States. -Annex A is one method to organize and display competencies. -Annex B is an example of using competencies for selection of first line managers. -Annex C is an example of using management competencies for succession management. -Annexes -H are examples of management development programmes. -Annexes I and J are examples of management assessment programmes. A glossary of terms is provided at the end of the report to explain the use of some key terms explain the use of some key terms

  6. Final disposal of spent nuclear fuel - basis for site selection

    International Nuclear Information System (INIS)

    Anttila, P.

    1995-05-01

    International organizations, e.g. IAEA, have published several recommendations and guides for the safe disposal of radioactive waste. There are three major groups of issues affecting the site selection process, i.e. geological, environmental and socioeconomic. The first step of the site selection process is an inventory of potential host rock formations. After that, potential study areas are screened to identify sites for detailed investigations, prior to geological conditions and overall suitability for the safe disposal. This kind of stepwise site selection procedure has been used in Finland and in Sweden. A similar approach has been proposed in Canada, too. In accordance with the amendment to the Nuclear Energy Act, that entered into force in the beginning of 1995, Imatran Voima Oy has to make preparations for the final disposal of spent fuel in the Finnish bedrock. Relating to the possible site selection, the following geological factors, as internationally recommended and used in the Nordic countries, should be taken into account: topography, stability of bedrock, brokenness and fracturing of bedrock, size of bedrock block, rock type, predictability and natural resources. The bedrock of the Loviisa NPP site is a part of the Vyborg rapakivi massif. As a whole the rapakivi granite area forms a potential target area, although other rock types or areas cannot be excluded from possible site selection studies. (25 refs., 7 figs.)

  7. Concepts of particle physics

    International Nuclear Information System (INIS)

    Gottfried, K.; Weisskopf, V.F.

    1984-01-01

    This volume elucidates basic and well-established concepts of particle physics for the autodidact who is curious about recent developments in fundamental physics. Elementary quantum mechanics is a background must. Contents, abridged: The evolution of the particle concept before the advent of quantum mechanics. Nonrelativistic quantum mechanics and atomic physics. Relativistic quantum theory. Nuclear phenomena. Subnuclear phenomena. Index

  8. Calculations and selection of a TRIGA core for the Nuclear Reactor IAN-R1

    International Nuclear Information System (INIS)

    Castiblanco, L.A.; Sarta, J.A.

    1997-01-01

    The Reactor Group used the code WIMS reduced to five groups of energy, together with the code CITATION, and evaluated four configurations for a core, according to the grid actually installed. The four configurations were taken from the two proposals presented to the Instituto de Ciencias Nucleares y Energias Alternativas by General Atomics Company. In this paper, the Authors selected the best configuration according to the performance of flux distribution and excess reactivity, for a TRIGA core to be installed in the Nuclear Reactor IAN-R1

  9. The Effect of Using a Proposed Teaching Strategy Based on the Selective Thinking on Students' Acquisition Concepts in Mathematics

    Science.gov (United States)

    Qudah, Ahmad Hassan

    2016-01-01

    This study aimed at identify the effect of using a proposed teaching strategy based on the selective thinking in acquire mathematical concepts by Classroom Teacher Students at Al- al- Bayt University, The sample of the study consisted of (74) students, equally distributed into a control group and an experimental group. The selective thinking…

  10. Status of Progress Made Toward Preliminary Design Concepts for the Inventory in Select Media for DOE-Managed HLW/SNF

    Energy Technology Data Exchange (ETDEWEB)

    Matteo, Edward N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hardin, Ernest L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Park, Heeho Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rigali, Mark J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jove-Colon, Carlos F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-30

    As the title suggests, this report provides a summary of the status and progress for the Preliminary Design Concepts Work Package. Described herein are design concepts and thermal analysis for crystalline and salt host media. The report concludes that thermal management of defense waste, including the relatively small subset of high thermal output waste packages, is readily achievable. Another important conclusion pertains to engineering feasibility, and design concepts presented herein are based upon established and existing elements and/or designs. The multipack configuration options for the crystalline host media pose the greatest engineering challenges, as these designs involve large, heavy waste packages that pose specific challenges with respect to handling and emplacement. Defense-related Spent Nuclear Fuel (DSNF) presents issues for post-closure criticality control, and a key recommendation made herein relates to the need for special packaging design that includes neutron-absorbing material for the DSNF. Lastly, this report finds that the preliminary design options discussed are tenable for operational and post-closure safety, owing to the fact that these concepts have been derived from other published and well-studied repository designs.

  11. Process for selecting a site for Canada's deep geological repository for used nuclear fuel

    International Nuclear Information System (INIS)

    Facella, J.; Ben Belfadhel, M.; Patton, P.

    2012-01-01

    'Full Text:' The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management, the approach selected by the Government of Canada for long-term management of used nuclear fuel waste generated by Canadian nuclear reactors. The ultimate objective of Adaptive Phased Management is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable crystalline or sedimentary rock formation at a depth of about 500m. The repository will consist of a series of access and service shafts and a series of tunnels leading to placement rooms where used fuel will be placed and sealed in competent rock using a multi-barrier system which includes long lived specially designed containers, sealing materials such as bentonite and the rock itself. The used fuel will be monitored throughout all phases of implementation and will also remain retrievable for an extended period of time. In May 2010, the NWMO published the site selection process that serves as the road map to decision-making on the location for the deep geological repository. NWMO initiated the process with a first stage that invites communities to learn more about the project and the site selection process. NWMO is actively building awareness of the project and, on request of communities, is delivering briefings, supporting community capacity building and undertaking screenings of site suitability. This panel presentation provides a brief description of: Adaptive Phased Management including the deep geological repository which is its ultimate goal, and the design of the site selection process, and importantly the approach to assessing the suitability of sites from both a social and technical perspective. The panel presentation will be conducted in three parts: site selection process and engagement, Aboriginal engagement and Technical evaluations, followed by a discussion. The presentation will outline how NWMO sought

  12. Analysis of the portfolio of sites to characterize for selecting a nuclear repository

    International Nuclear Information System (INIS)

    Keeney, R.L.

    1987-01-01

    The US Department of Energy has selected three sites, from five nominated, to characterize for a nuclear repository to permanently dispose of nuclear waste. This decision was made without the benefit of an analysis of this portfolio problem. This paper analyzes different portfolios of three sites for simultaneous characterization and strategies for sequential characterization. Characterization of each site, which involves significant subsurface excavation, is now estimated to cost $1 billion. Mainly because of the high characterization costs, sequential characterization strategies are identified which are the equivalent of $1.7-2.0 billion less expensive than the selected DOE simultaneous characterization of the three sites. If three sites are simultaneously characterized, one portfolio is estimated to be the equivalent of $100-400 million better than the selected DOE portfolio. Because of these potential savings and several other complicating factors that may influence the relative desirability of characterization strategies, a thorough analysis of characterization strategies that addresses the likelihood of finding disqualifying conditions during site characterization, uncertainties, and dependencies in forecast site repository costs, preclosure and postclosure health and safety impacts, potential delays of both sequential and simultaneous characterization strategies, and the environmental, socioeconomic, and health and safety impacts of characterization activities is recommended

  13. Nuclear R and D program in Indonesia and selection of future research reactor to support it

    International Nuclear Information System (INIS)

    Baiquni, A.; Subki, I.

    1981-01-01

    The nuclear R and D program selection decision is described as a phased program, each phase having its specific objective. The elements of each phase are identified and related with the objective, from which the activities of each element are also broadly outlined. To support the nuclear R and D program and to realize the objectives in each phase, the research facilities are also developed. A new nuclear development center housing a multipurpose reactor (MPR) and various laboratories are also described. The choice of the MPR and its criteria are also described briefly

  14. The technological conception

    International Nuclear Information System (INIS)

    Parrochia, D.

    1998-01-01

    The 'technological conception' examines how a project can be concretized or how it is possible to 'conceive', i.e. to produce operative ideas that can be directly use. The first part of this book, called 'concepts and methods', analyzes the logics of conceiving and its philosophy in the construction of its objects and in the management of its programs or projects. The second part is devoted to some exemplary technologies: roads, tunnels, bridges, dams, nuclear power plants, aerospace constructions, and analyzes different concrete logics of technological conception. Finally, the author shows how todays conception faces the risks and complexity increase of systems and considers the possibility of an entirely automated manufacturing shop in the future. (J.S.)

  15. Public attitudes to nuclear and coal power in site selection for a future energy centre

    International Nuclear Information System (INIS)

    Baril, R.G.; Dobson, J.K.

    This paper discusses the results of a 1977 public attitude survey carried out as part of an Ontario Hydro generating site selection program along the North Channel of Lake Huron. The results of the survey are compared with those of two similar surveys conducted in 1974 and 1975. The main topics discussed include local citizen attitudes to a generating site in the area, nuclear power, attitude changes over three years, differences in attitudes to nuclear and to coal fired generation and the underlying reasons given for favouring or opposing nuclear power. The results of other surveys which have been conducted recently in Canada and internationally are discussed and compared with this survey. Most longitudinal studies point to a trend of declining public acceptance regarding nuclear power. If this trend continues, there are important implications for the nuclear power industry: they are discussed from a sociological and political perspective. (author)

  16. Small ex-core heat pipe thermionic reactor concept (SEHPTR)

    International Nuclear Information System (INIS)

    Jacox, M.G.; Bennett, R.G.; Lundberg, L.B.; Miller, B.G.; Drexler, R.L.

    1991-01-01

    The Idaho National Engineering Laboratory (INEL) has developed an innovative space nuclear power concept with unique features and significant advantages for both Defense and Civilian space missions. The Small Ex-core Heat Pipe Thermionic Reactor (SEHPTR) concept was developed in response to Air Force needs for space nuclear power in the range of 10 to 40 kilowatts. This paper describes the SEHPTR concept and discusses the key technical issues and advantages of such a system

  17. Idaho national laboratory - a nuclear research center

    International Nuclear Information System (INIS)

    Zaidi Mohammed, K.

    2006-01-01

    Full text: The Idaho National Laboratory (INL) is committed to providing international nuclear leadership for the 21st Century, developing and demonstrating compelling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multi program national laboratories. INL runs three major programs - Nuclear, Security and Science. Nuclear programs covers the Advanced test reactor, Six Generation IV technology concepts selected for Rand D, targeting tumors - Boron Neutron Capture therapy. Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (INSE) under the Center for Advanced Energy Studies (CAES) and the Idaho State University (ISU). INSE will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer INSE is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'. (author)

  18. Mars power system concept definition study. Volume 1: Study results

    Science.gov (United States)

    Littman, Franklin D.

    1994-01-01

    A preliminary top level study was completed to define power system concepts applicable to Mars surface applications. This effort included definition of power system requirements and selection of power systems with the potential for high commonality. These power systems included dynamic isotope, Proton Exchange Membrane (PEM) regenerative fuel cell, sodium sulfur battery, photovoltaic, and reactor concepts. Design influencing factors were identified. Characterization studies were then done for each concept to determine system performance, size/volume, and mass. Operations studies were done to determine emplacement/deployment maintenance/servicing, and startup/shutdown requirements. Technology development roadmaps were written for each candidate power system (included in Volume 2). Example power system architectures were defined and compared on a mass basis. The dynamic isotope power system and nuclear reactor power system architectures had significantly lower total masses than the photovoltaic system architectures. Integrated development and deployment time phasing plans were completed for an example DIPS and reactor architecture option to determine the development strategies required to meet the mission scenario requirements.

  19. Risks attached to container- and bunker-storage of nuclear waste

    International Nuclear Information System (INIS)

    Jager, D. de

    1987-12-01

    The results are presented of a literature study into the risks attached to the two dry-storage options selected by the Dutch Central Organization For Radioactive Waste (COVRA): the container- and the bunker-storage for irradiated nuclear-fuel elements and nuclear waste. Since the COVRA does not make it clear how these concepts should have to be realized, the experiences abroad with dry interim-storage are considered. In particular the Castor-container-storage and the bunker storage proposed in the committee MINSK (Possibilities of Interim-storage in the Netherlands of Irradiated nuclear-fuel elements and Nuclear waste) are studied further in depth. The committee MINSK has performed a study into the technical realizability of various interim-storage facilities, among which a storage in bunkers. (author). 75 refs.; 14 figs.; 16 tabs

  20. Idaho National Laboratory - Nuclear Research Center

    International Nuclear Information System (INIS)

    Zaidi, M.K.

    2005-01-01

    Full text: The Idaho National Laboratory is committed to the providing international nuclear leadership for the 21st Century, developing and demonstrating compiling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multiprogram national laboratories. INL runs three major programs - Nuclear, Security and Science. nuclear programs covers the Advanced test reactor, Six Generation technology concepts selected for R and D, Targeting tumors - Boron Neutron capture therapy. Homeland security - Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science - INL facility established for Geocentrifuge Research, Idaho Laboratory, a Utah company achieved major milestone in hydrogen research and INL uses extremophile bacteria to ease bleaching's environmental cost. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (Inset). The institute will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer Inset is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'

  1. Nuclear safety based on nuclear knowledge - A Romanian approach

    International Nuclear Information System (INIS)

    Valeca, S.C.; Popescu, D.

    2007-01-01

    Full text: The recognized 'father' of the nuclear field, the scientist A. Einstein inherited us with a CONTRADICTION. On one hand he was the supporter of researches in the nuclear field, but on the other hand, when he saw the first devastating results of the atomic explosions he suddenly became a fervent opponent. In such conditions, the nuclear field made its first step in the conscience of humanity. Unfortunately it was a left first step. For this reason and also because of the nuclear incidents passed over the history of the field and due to yet unclear strategies regarding the final disposal of radioactive waste, a part of public opinion 'embraced' the concept 'NIMBY - Not In My Back Yard'. At present and for the future we have to fight against this concept in order to transform it in 'PIMY - Please In My Yard'. As a consequence, alongside numerous activities well-known by the specialists in the field, regulated and authorized by the regulatory body in the nuclear field, associated programmes for the CONTINUOUS qualification and education of human resources are needed. The Concept of Nuclear Security covers all the activities resulted from the nuclear fuel cycle. Taking into consideration the international experience in this field in our country's case, these activities were estimated for periods of approximately 70 years, as following: 10 years: the characterization and selection of the site, the design, construction and the commission of a nuclear power plant; 40 years: the operation, maintenance and modernization of a nuclear power plant; 20 years: the preservation for the decommissioning and the decommissioning of the nuclear power plant. In all these stages until present Romania based a lot on the indigene component regarding the activities of research and development, design, construction - assembling, exploitation and maintenance (both for NPP Unit 1 and Unit 2, where this component was approximately of 50%). In such conditions, it was needed the

  2. Summary of trial design of improved marine nuclear reactors

    International Nuclear Information System (INIS)

    1984-01-01

    In order to carry out the research and development of improved marine nuclear reactors, the Japan Nuclear Ship Research and Development Agency decided the project for the purpose in accordance with the procedure of research and development shown by the Nuclear Ship Research and Development Committee of Atomic Energy Commission in December, 1979, and along the basic plan regarding the development of nuclear ships of the Agency decided in February, 1981. As the first step, the Agency has been advancing the research on the design evaluation comprising the trial design and conceptual design to establish the concept of the marine reactor plant with excellent economical efficiency and reliability, which will be developed as the practical plant for future nuclear ships. The trial design started as a three-year project from 1983 is related to a 100 MWt marine reactor, and it is to obtain the concept of improved marine reactors which can be realized after adequate development period based on the pressurized water reactors of separate type, one-body type and semi-one-body type. In this summary, the works carried out in fiscal year 1983 are reported, that is, the design and calculation of the reactor core and the equipment of primary cooling system, and the selection of the required items of research and development. (Kako, I.)

  3. Selected works of basic research on the physics and technology of accelerator driven clean nuclear power system

    International Nuclear Information System (INIS)

    Zhao Zhixiang

    2002-01-01

    38 theses are presented in this selected works of basic research on the physics and technology of accelerator driven clean nuclear power system. It includes reactor physics and experiment, accelerators physics and technology, nuclear physics, material research and partitioning. 13 abstracts, which has been presented on magazines home and abroad, are collected in the appendix

  4. Heat resistant materials and their feasibility issues for a space nuclear transportation system

    International Nuclear Information System (INIS)

    Olsen, C.S.

    1991-01-01

    A number of nuclear propulsion concepts based on solid-core nuclear propulsion are being evaluated for a nuclear propulsion transportation system to support the Space Exploration Initiative (SEI) involving the reestablishment of a manned lunar base and the subsequent exploration of Mars. These systems will require high-temperature materials to meet the operating conditions with appropriate reliability and safety built into these systems through the selection and testing of appropriate materials. The application of materials for nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems and the feasibility issues identified for their use will be discussed. Some mechanical property measurements have been obtained, and compatibility tests were conducted to help identify feasibility issues. 3 refs., 1 fig., 4 tabs

  5. Protection against malevolent use of vehicles at Nuclear Power Plants. Vehicle barrier system selection guidance

    International Nuclear Information System (INIS)

    Nebuda, D.T.

    1994-08-01

    This manual provides a simplified procedure for selecting land vehicle barriers that will stop the design basis vehicle threat adopted by the U.S. Nuclear Regulatory Commission. Proper selection and construction of vehicle barriers should prevent intrusion of the design basis vehicle. In addition, vital safety related equipment should survive a design basis vehicle bomb attack when vehicle barriers are properly selected, sited, and constructed. This manual addresses passive vehicle barriers, active vehicle barriers, and site design features that can be used to reduce vehicle impact velocity

  6. Empirical evidence of the effectiveness of concept mapping as a learning intervention for nuclear medicine technology students in a distance learning radiation protection and biology course.

    Science.gov (United States)

    Passmore, Gregory G; Owen, Mary Anne; Prabakaran, Krishnan

    2011-12-01

    Metacognitive learning strategies are based on instructional learning theory, which promotes deep, meaningful learning. Educators in a baccalaureate-level nuclear medicine technology program demonstrated that students enrolled in an online, distance learning section of an introductory radiation protection and radiobiology course performed better when traditional instruction was supplemented with nontraditional metacognitive learning strategies. The metacognitive learning strategy that was used is best known as concept mapping. The concept map, in addition to the standard homework problem assignment and opportunity for question-answer sessions, became the template for misconception identification and remediation interactions between the instructor and the student. The control group relied on traditional homework problems and question-answer sessions alone. Because students in both the "treatment" groups (i.e., students who used concept mapping) and the control group were distance learning students, all personal communications were conducted via e-mail or telephone. The final examination of the course was used to facilitate a quantitative comparison of the performance of students who used concept mapping and the performance of students who did not use concept mapping. The results demonstrated a significantly higher median final examination score for the concept mapping group than for the non-concept mapping group (z = -2.0381, P = 0.0415), with an appropriately large effect size (2.65). Concept mapping is a cognitive learning intervention that effectively enables meaningful learning and is suitable for use in the independent learner-oriented distance learning environments used by some nuclear medicine technology programs.

  7. The concept of underground nuclear heat and power plants (UNHPP) of upgraded safety, developed on the basis of ship-building technologies

    International Nuclear Information System (INIS)

    Pashin, V.M.; Petrov, Eh.L.; Shalik, G.P.; Khazov, B.S.; Malyshev, S.P.

    1996-01-01

    A concept of underground nuclear heat and power plants (UNHPP) of upgraded safety on the basis of ship-building technologies is considered, in which the priority is set to population security and environmental protection. Ways of realization of ziro radiation risk for the population residing in a close vicinity of UNHPP are substantiated. basic principles of the concept are formulated which envisage the use of ship propulsion reactor facilities that have been multiply tested in operation. The sources of economic competitiveness of UNHPPs, as compared with the existing NPPs, are shown

  8. Summary of space nuclear reactor power systems, 1983--1992

    Energy Technology Data Exchange (ETDEWEB)

    Buden, D.

    1993-08-11

    This report summarizes major developments in the last ten years which have greatly expanded the space nuclear reactor power systems technology base. In the SP-100 program, after a competition between liquid-metal, gas-cooled, thermionic, and heat pipe reactors integrated with various combinations of thermoelectric thermionic, Brayton, Rankine, and Stirling energy conversion systems, three concepts:were selected for further evaluation. In 1985, the high-temperature (1,350 K), lithium-cooled reactor with thermoelectric conversion was selected for full scale development. Since then, significant progress has been achieved including the demonstration of a 7-y-life uranium nitride fuel pin. Progress on the lithium-cooled reactor with thermoelectrics has progressed from a concept, through a generic flight system design, to the design, development, and testing of specific components. Meanwhile, the USSR in 1987--88 orbited a new generation of nuclear power systems beyond the, thermoelectric plants on the RORSAT satellites. The US has continued to advance its own thermionic fuel element development, concentrating on a multicell fuel element configuration. Experimental work has demonstrated a single cell operating time of about 1 1/2-y. Technology advances have also been made in the Stirling engine; an advanced engine that operates at 1,050 K is ready for testing. Additional concepts have been studied and experiments have been performed on a variety of systems to meet changing needs; such as powers of tens-to-hundreds of megawatts and highly survivable systems of tens-of-kilowatts power.

  9. Summary of space nuclear reactor power systems, 1983--1992

    International Nuclear Information System (INIS)

    Buden, D.

    1993-01-01

    This report summarizes major developments in the last ten years which have greatly expanded the space nuclear reactor power systems technology base. In the SP-100 program, after a competition between liquid-metal, gas-cooled, thermionic, and heat pipe reactors integrated with various combinations of thermoelectric thermionic, Brayton, Rankine, and Stirling energy conversion systems, three concepts:were selected for further evaluation. In 1985, the high-temperature (1,350 K), lithium-cooled reactor with thermoelectric conversion was selected for full scale development. Since then, significant progress has been achieved including the demonstration of a 7-y-life uranium nitride fuel pin. Progress on the lithium-cooled reactor with thermoelectrics has progressed from a concept, through a generic flight system design, to the design, development, and testing of specific components. Meanwhile, the USSR in 1987--88 orbited a new generation of nuclear power systems beyond the, thermoelectric plants on the RORSAT satellites. The US has continued to advance its own thermionic fuel element development, concentrating on a multicell fuel element configuration. Experimental work has demonstrated a single cell operating time of about 1 1/2-y. Technology advances have also been made in the Stirling engine; an advanced engine that operates at 1,050 K is ready for testing. Additional concepts have been studied and experiments have been performed on a variety of systems to meet changing needs; such as powers of tens-to-hundreds of megawatts and highly survivable systems of tens-of-kilowatts power

  10. An independent safety assessment of Department of Energy nuclear reactor facilities: Training of operating personnel and personnel selection

    International Nuclear Information System (INIS)

    Drain, J.F.

    1981-02-01

    This study has been prepared for the Department of Energy's Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee. Its purpose is to provide the Committee with background information on, and assessment of, the selection, training, and qualification of nuclear reactor operating personnel at DOE-owned facilities

  11. Proposals for the Future Development of the Russian Automated Federal Information System for Nuclear Material Control and Accounting: The Universal Reporting Concept

    International Nuclear Information System (INIS)

    Martyanov, Alexander; Pitel, Victor; Kasumova, Leila; Babcock, Rose A.; Heinberg, Cynthia L.

    2004-01-01

    Development of the automated Russian Federation Federal Information System for Nuclear Material Control and Accounting (FIS) started in 1996. From the beginning, the creation of the FIS was based on the concept of obtaining data from the material balance areas of the organizations, which would enable the system to collect detailed information on nuclear material. In December 2000, the organization-level summarized reporting method was mandated by the Russian Federation and subsequently implemented for all organizations. Analysis of long-term FIS objectives, reporting by all the MBAs in Russia, showed that the present summarized reporting approach decreed by regulations posed a fair number of problems. We need alternative methods that allow the FIS to obtain more detailed information on nuclear material but which accurately reflect the technical and economic resources available to Russian organizations. One possible solution is the universal reporting method. In August 2003, the proposals of the FIS working group to transition to the universal reporting method were approved at the fourth meeting of the Joint Coordinating Committee for Implementation of the Russian Federation and U.S. Government-to-Government Agreement on Cooperation in the Area of Nuclear Material Physical Protection, Control and Accounting (JCC). One of the important elements of universal reporting is that organizations handling nuclear material will establish 'reporting areas' in cooperation with MinAtom of Russia. A reporting area may consist of one MBA, several MBAs, or even an entire organization. This paper will discuss the universal reporting concept and its major objectives and methods for the FIS.

  12. Knowledge gaps in economic analyses of advanced reactor concepts

    International Nuclear Information System (INIS)

    Moore, M.; Pencer, J.; Leung, L.K.H.; Sadhankar, R.

    2014-01-01

    The development of next generation nuclear systems is predicated on improvement in sustainability, safety, proliferation resistance and economics. The economic assessment of the reactor concept is required as early as in the concept development stage. The Generation IV International Forum (GIF) has developed a methodology for economic assessment of the Generation IV (GEN-IV) nuclear energy systems. The GIF economics methodology was used for the assessment of one of the reactor concepts for the Super-Critical Water-cooled Reactors (SCWR), namely the European pressure-vessel type concept referred to as the High Performance Light Water Reactor (HPLWR). The economic analysis involved studying the sensitivity of two main economic indicators, namely, the Levelized Unit Electricity Cost (LUEC) and the Total Capital Investment Cost (TCIC). The knowledge gaps in estimating the capital costs and fuel costs, as well as the uncertainties in other cost parameters affecting the economic assessment of the nuclear energy system in the concept development stage are presented. (author)

  13. Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

    International Nuclear Information System (INIS)

    Ramli, A.T.; Basri, N.A.; Abu Hanifah, N.Z.H.

    2014-01-01

    Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

  14. Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Ramli, A. T.; Basri, N. A.; Abu Hanifah, N. Z.H., [Department of Physics, Faculty of Science Universiti Teknologi Malaysia Johor (Malaysia)

    2014-10-15

    Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

  15. Selection and Training of Personnel for the New Nuclear Medicine and Radiation Therapy Centre in Bariloche

    International Nuclear Information System (INIS)

    Lopez, M.P.

    2016-01-01

    Full text: A basic strategy for the development of a new organization is the selection of personnel, especially if it is an institute that offers a technological and professional innovation. This work aims to define specific profiles for the Centre for Nuclear Medicine and Radiation Therapy, Bariloche, and to design a plan for selecting and training professionals. (author

  16. Understanding and managing corrosion in nuclear power plants

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Jarrell, D.B.; Sinha, U.P.; Shah, V.N.

    1991-03-01

    The main theme of this paper is a concept: understanding and managing corrosion in nuclear power plants. The concept is not new--in various forms the concept has been applied throughout the development and maturing of nuclear technology. However, the concept has frequently not been well conceived and applied. Too often, understanding corrosion has been based on reaction rather than on anticipation. Regulatory and utility industry initiatives are creating a climate and framework for more effective application of the concept. This paper characterizes the framework and provides some illustrations of how the concept is being applied, drawing from work conducted under the Nuclear Plant Aging Research (NPAR) Program, sponsored by the Nuclear Regulatory Commission's (NRCs) Office of Research. Nuclear plants are becoming an increasingly important factor in the national electrical grid. Initiatives are currently underway to extend the operating licenses beyond the current 40-year period and to evaluate advanced reactor designs the feature higher safety factors. Corrosion has not caused a major nuclear accident, but numerous corrosion mechanisms, have degraded nuclear systems and components. New corrosion phenomena continue to appear, and occasionally corrosion phenomena cause reactor shutdowns. Effective application of understanding and managing corrosion is important to safe and economic operation of the nuclear plants and also to public perception of a soundly operated technology. 53 refs., 11 figs., 5 tabs

  17. Research on evacuation planning as nuclear emergency preparedness

    International Nuclear Information System (INIS)

    Yamamoto, Kazuya

    2007-10-01

    The International Atomic Energy Agency (IAEA) has introduced new concepts of precautionary action zone (PAZ) and urgent protective action planning zone (UPZ) in 'Preparedness and Response for a Nuclear or Radiological Emergency' (GS-R-2 (2002)), in order to reduce substantially the risk of severe deterministic health effects. Open literature based research was made to reveal problems on evacuation planning and the preparedness for nuclear emergency arising from introduction of PAZ into Japan that has applied the emergency planning zone (EPZ) concept currently. In regard to application of PAZ, it should be noted that the requirements for preparedness and response for a nuclear or radiological emergency are not only dimensional but also timely. The principal issue is implementation of evacuation of precautionary decided area within several hours. The logic of evacuation planning for a nuclear emergency and the methods of advance public education and information in the U.S. is effective for even prompt evacuation to the outside of the EPZ. As concerns evacuation planning for a nuclear emergency in Japan, several important issues to be considered were found, that is, selection of public reception centers which are outside area of the EPZ, an unique reception center assigned to each emergency response planning area, public education and information of practical details about the evacuation plan in advance, and necessity of the evacuation time estimates. To establish a practical evacuation planning guide for nuclear emergencies, further researches on application of traffic simulation technology to evacuation time estimates and on knowledge of actual evacuation experience in natural disasters and chemical plant accidents are required. (author)

  18. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2003-01-01

    This chapter discuss on nuclear power and its advantages. The concept of nucleus fission, fusion, electric generation are discussed in this chapter. Nuclear power has big potential to become alternative energy to substitute current conventional energy from coal, oil and gas

  19. Exotic power and propulsion concepts

    International Nuclear Information System (INIS)

    Forward, R.L.

    1990-01-01

    The status of some exotic physical phenomena and unconventional spacecraft concepts that might produce breakthroughs in power and propulsion in the 21st Century are reviewed. The subjects covered include: electric, nuclear fission, nuclear fusion, antimatter, high energy density materials, metallic hydrogen, laser thermal, solar thermal, solar sail, magnetic sail, and tether propulsion

  20. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

    International Nuclear Information System (INIS)

    1979-12-01

    Volume 6 of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power-generating capability and one without. This volume also provides estimates of the time required for development of large-scale commercial reactor systems to reach the construction permit application stage and for fuel-cycle facilities to reach the operating license application stage, which is a measure of the relative technical status of alternative nuclear systems

  1. Selection and Analysis of Social Studies Concepts for Inclusion in Tests of Concept Attainment.

    Science.gov (United States)

    Tabachnick, B. Robert; And Others

    Major social studies concepts taught to fourth graders in Madison, Wisconsin, were identified by examining the school district course of study and social studies textbooks and by consulting central office supervisors and teachers. The concepts identified in this manner fell into three major categories: Geographic Region, Man and Society, and Map…

  2. Nuclear measurements

    International Nuclear Information System (INIS)

    Schenkel, R.

    2005-01-01

    Nuclear measurements play a fundamental role in the development of nuclear technology and the assurance of its peaceful use. They are also required in many non-power nuclear applications such as in nuclear medicine, agriculture, environmental protection, etc. This presentation will show examples of most recent advances in measurement methodology or technology in the areas described below. The Generation IV International Forum has selected six innovative reactor systems as candidates for a next generation of sustainable, economic and safe nuclear energy systems. The choice of the best options relies heavily on the availability of accurate nuclear data that can only be obtained, in an international effort, using highly specialised facilities. Significant efforts are being directed towards the partitioning and transmutation of highly active nuclear waste. Different concepts involving fast reactors or accelerator-driven systems are being studied in view of their transmutation capabilities. State of the art equipment has been developed to assess basic properties of nuclear fuel at very high burn-up; some fine examples of this work will be shown. Physical and chemical methods play a crucial role in the detection and identification of radioisotopes used in various stages of the nuclear fuel cycle. Radiation measurement techniques are used, for example, to monitor the quantities of uranium, plutonium and other actinide elements in fuel enrichment and reprocessing facilities. Another field of application of physical and chemical methods is the characterisation of nuclear material seized from illicit trafficking. Seized material has to be analysed in order to obtain clues on its origin and intended use and to prevent diversion of nuclear material from the same source in the future. A recent highlight in basic physics relates to nuclear fission and transmutation with high intensity lasers. Ultra-fast high intensity lasers can produce high energy (tens of MeV) photons through

  3. Screening methodology for site selection of a nuclear waste repository in shale formations in Germany

    International Nuclear Information System (INIS)

    Hoth, P.; Krull, P.; Wirth, H.

    2004-01-01

    The radioactive waste disposal policy in the Federal Republic of Germany is based on the principle that all types of radioactive waste must be disposed of in deep geological formations. Because of the favourable properties of rock salt and the existence of thick rock salt formations in Germany, so far most of the research in the field of radioactive waste disposal sites was focused on the study of the use of rock salt. In addition, German research organisations have also conducted generic research and development projects in alternative geological formations (Wanner and Brauer, 2001), but a comprehensive evaluation of their utilisation has been only done for parts of the crystalline rocks in Germany. Research projects on argillaceous rocks started relatively late, so that German experience is mainly connected to German research work with the corresponding European Underground Research Laboratories and the exploration of the former Konrad iron mine as a potential repository site for radioactive waste with negligible heat generation. The German Federal Government has signed in 2001 an agreement with national utility companies to end electricity generation by nuclear power. This decision affected the entire German radioactive waste isolation strategy and especially the repository projects. The utility companies agreed upon standstill of exploration at the Gorleben site and the Federal Ministry for the Environment tries to establish a new comprehensive procedure for the selection of a repository site, built upon well-founded criteria incorporating public participation. Step 3 of the planning includes the examination of further sites in Germany and the comparison with existing sites and concepts. Under these circumstances, argillaceous rock (clay and shale) formations are now a special area of interest in Germany and the development of a screening methodology was required for the evaluation of shales as host and barrier rocks for nuclear waste repositories. (author)

  4. Conception and activity directions of journal ''Nuclear and radiation safety''

    International Nuclear Information System (INIS)

    Olena, M.; Volodymyr, S.

    2000-01-01

    In connection with the State Scientific and Technical Centre onr Nuclear and Radiation Safety (SSTC NRA) and Odessa State Polytechnic University the journal 'Nuclear and Radiation Safety' was established in 1998. In Ukraine many people are interested in nuclear energy problems. The accident in Chernobyl NPP unit 4 touches all Ukrainians and brings about strong and regular attention to nuclear and radiation safety of nuclear installations and nuclear technology, on the other side more than 50 per cent of electric power is produced in 5 NPPs and as following national power supply depends on stability of NPPs work. Main goals of the journal are: Support to Nuclear Regulatory Administration (NRA) of MEPNS of Ukraine, creation of information space for effective exchange of results of scientific, scientific and technical, scientific and analytical work in the field of Nuclear and Radiation Safety, assistance in integrated development of research for Nuclear and Radiation Safety by publication in a single issue of scientific articles, involvement of state scientific potential in resolving actual problems, participation in international collaboration in the framework of agreements, programs and plans. (orig.)

  5. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Furtek, A.

    2008-01-01

    Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

  6. New concepts of nuclear reactors and fuel cycles: performing agile technometric studies to understand the promises and the current reality

    Energy Technology Data Exchange (ETDEWEB)

    Reis Junior, Jose S.B.; Barroso, Antonio C.O., E-mail: jsreis@ipen.br, E-mail: barroso@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The progress of previous projects pointed out the need to face some problems of software for detecting emerging research and development trends from databases of scientific publication. Given the lack of efficient computing applications dedicated to this purpose that we consider to be an artifact of great usefulness to better planning R and D programs in institutions, which are obliged to manage and develop, with limited resources and within the realm of complex and multidisciplinary technology fields as is the case of the Brazilian nuclear sector. We performed a review of the currently available software in such a way that we could clearly delineate the opportunity to develop new tools. As a result, we developed a software called Cite snake, which was especially designed to help the detection and study of emerging trends from the analysis of networks of various types extracted from the scientific databases. Using this powerful and stable computational tool, we performed preliminary analyzes of emerging research and development trends in a few thematic fields. The case that concerns this paper is the one devoted to the eld of Generation IV Nuclear Power Generation Systems. We analyzed the productivity of authors, co-authorship networks, co-citation networks, development structure and emerging sub-areas of research. The idea was to nd what reactors and fuel cycles have evolved more over the past ten years, in such a way to compare the what from the most promising concepts selected from the Generation Four Initiative have better evolved to fulfill some of their promises. (author)

  7. New concepts of nuclear reactors and fuel cycles: performing agile technometric studies to understand the promises and the current reality

    International Nuclear Information System (INIS)

    Reis Junior, Jose S.B.; Barroso, Antonio C.O.

    2013-01-01

    The progress of previous projects pointed out the need to face some problems of software for detecting emerging research and development trends from databases of scientific publication. Given the lack of efficient computing applications dedicated to this purpose that we consider to be an artifact of great usefulness to better planning R and D programs in institutions, which are obliged to manage and develop, with limited resources and within the realm of complex and multidisciplinary technology fields as is the case of the Brazilian nuclear sector. We performed a review of the currently available software in such a way that we could clearly delineate the opportunity to develop new tools. As a result, we developed a software called Cite snake, which was especially designed to help the detection and study of emerging trends from the analysis of networks of various types extracted from the scientific databases. Using this powerful and stable computational tool, we performed preliminary analyzes of emerging research and development trends in a few thematic fields. The case that concerns this paper is the one devoted to the eld of Generation IV Nuclear Power Generation Systems. We analyzed the productivity of authors, co-authorship networks, co-citation networks, development structure and emerging sub-areas of research. The idea was to nd what reactors and fuel cycles have evolved more over the past ten years, in such a way to compare the what from the most promising concepts selected from the Generation Four Initiative have better evolved to fulfill some of their promises. (author)

  8. Generic repository concept for RBMK-1500 spent nuclear fuel disposal in crystalline rocks in Lithuania

    International Nuclear Information System (INIS)

    Poskas, P.; Brazauskaite, A.; Narkunas, E.; Smaizys, A.; Sirvydas, A.

    2006-01-01

    During 2002-2005 investigations on possibilities to dispose of spent nuclear fuel (SNF) in Lithuania were performed with support of Swedish experts. Disposal concept for RBMK-1500 SNF in crystalline rocks in Lithuania is based on Swedish KBS-3 concept with SNF emplacement into the copper canister with cast iron insert. The bentonite and its mixture with crushed rock are also foreseen as buffer and backfill material. In this paper modelling results on thermal, criticality and other important disposal characteristics for RBMK-1500 SNF fuel emplaced in copper canisters are presented. Based on thermal calculations, the distances between the canisters and between the tunnels were justified. Criticality calculations for the canister with fresh fuel with 2.8 % 235 U enrichment demonstrated that effective neutron multiplication factor k eff values are less than allowable value of 0.95. Dose calculations have shown that total equivalent dose rate from the canister with 50 years stored RBMK-1500 SNF is rather high and is defined mainly by the γ radiation. (author)

  9. Site selection for new nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur, E-mail: paul.rizzo@rizzoassoc.com, E-mail: melissa.dubinsky@rizzoassoc.com, E-mail: onur.tastan@rizzoassoc.com [RIZZO Associates Inc., Pittsburgh, PA (United States); Miano, Sandra C., E-mail: scm27@psu.edu [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), RJ (Brazil); Pennsylvania State University, Department of Mechanical and Nuclear Engineering, State College, PA (United States)

    2015-07-01

    The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

  10. Site selection for new nuclear power plants

    International Nuclear Information System (INIS)

    Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur; Miano, Sandra C.

    2015-01-01

    The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

  11. Performance Evaluation of the Concept of Hybrid Heat Pipe as Passive In-core Cooling Systems for Advanced Nuclear Power Plant

    International Nuclear Information System (INIS)

    Jeong, Yeong Shin; Kim, Kyung Mo; Kim, In Guk; Bang, In Cheol

    2015-01-01

    As an arising issue for inherent safety of nuclear power plant, the concept of hybrid heat pipe as passive in-core cooling systems was introduced. Hybrid heat pipe has unique features that it is inserted in core directly to remove decay heat from nuclear fuel without any changes of structures of existing facilities of nuclear power plant, substituting conventional control rod. Hybrid heat pipe consists of metal cladding, working fluid, wick structure, and neutron absorber. Same with working principle of the heat pipe, heat is transported by phase change of working fluid inside metal cask. Figure 1 shows the systematic design of the hybrid heat pipe cooling system. In this study, the concept of a hybrid heat pipe was introduced as a Passive IN-core Cooling Systems (PINCs) and demonstrated for internal design features of heat pipe containing neutron absorber. Using a commercial CFD code, single hybrid heat pipe model was analyzed to evaluate thermal performance in designated operating condition. Also, 1-dimensional reactor transient analysis was done by calculating temperature change of the coolant inside reactor pressure vessel using MATLAB. As a passive decay heat removal device, hybrid heat pipe was suggested with a concept of combination of heat pipe and control rod. Hybrid heat pipe has distinct feature that it can be a unique solution to cool the reactor when depressurization process is impossible so that refueling water cannot be injected into RPV by conventional ECCS. It contains neutron absorber material inside heat pipe, so it can stop the reactor and at the same time, remove decay heat in core. For evaluating the concept of hybrid heat pipe, its thermal performance was analyzed using CFD and one-dimensional transient analysis. From single hybrid heat pipe simulation, the hybrid heat pipe can transport heat from the core inside to outside about 18.20 kW, and total thermal resistance of hybrid heat pipe is 0.015 .deg. C/W. Due to unique features of long heat

  12. Safeguards systems concepts for nuclear material transportation. Final report

    International Nuclear Information System (INIS)

    Baldonado, O.C.; Kevany, M.; Rodney, D.; Pitts, D.; Mazur, M.

    1977-09-01

    The report describes the development of system concepts for the safeguarding of special strategic nuclear materials (SNM) against malevolent adversary action during the interfacility transport of the SNM. The methodology used includes techniques for defining, classifying, and analyzing adversary action sequences; defining safeguards system components; assessing the vulnerability of various safeguards systems and their component parts to the potential adversary action sequences, and conceptualizing system design requirements. The method of analysis is based primarily on a comparison of adversary actions with safeguards measures, to estimate vulnerability. Because of the paucity of the data available for assessing vulnerability, the Delphi approach was used to generate data: values were estimated in a structured exercise by a panel of experts in the safeguards and terrorist fields. It is concluded that the probability of successful attack against a truck/escort convoy manned by well-trained, well-armed personnel is low enough to discourage all but the strongest adversaries. Secrecy of operations and careful screening of personnel are very important. No reliance should be placed on current capabilities of local law enforcement agencies. The recommendation of the study is the use of road transport in the near future and air transport at a later time when the number of shipments reaches a level to justify it, and when present safety problems are resolved

  13. Concepts involved in a proposed application of uncertainty analysis to the performance assessment of high-level nuclear waste isolation systems

    International Nuclear Information System (INIS)

    Maerker, R.E.

    1986-03-01

    This report introduces the concepts of a previously developed methodology which could readily be extended to the field of performance assessment for high-level nuclear waste isolation systems. The methodology incorporates sensitivities previously obtained with the GRESS code into an uncertainty analysis, from which propagated uncertainties in calculated responses may be derived from basic data uncertainties. Following a definition of terms, examples are provided illustrating commonly used conventions for describing the concepts of covariance and sensitivity. Examples of solutions to problems previously encountered in related fields involving uncertainty analysis and use of a generalized linear least-squares adjustment procedure are also presented. 5 refs., 14 tabs

  14. Principles and criteria for creation of a concept for national radwaste repository

    International Nuclear Information System (INIS)

    Milanov, M.; Strezov, A.; Kojuharov, D.

    1993-01-01

    General principles and criteria based on the international experience and requirements as well as on specific Bulgarian conditions are used in the creation of the Concept for Radwaste Repository Construction as a first stage of the Bulgarian nuclear programme. The Concept contains about 70 projects of common or more specific character. The Bulgarian territory is categorized and several prospective areas are selected as a final result of the analysis performed. A model for development of a National System for Radwaste Management is considered. The formation of a working group appointed by governmental authorities as a solution of the existing highly complex situation connected with the treatment and storage of radwaste in the country is proposed. 1 fig., 14 refs. (author)

  15. Selective nuclear export of specific classes of mRNA from mammalian nuclei is promoted by GANP

    Science.gov (United States)

    Wickramasinghe, Vihandha O.; Andrews, Robert; Ellis, Peter; Langford, Cordelia; Gurdon, John B.; Stewart, Murray; Venkitaraman, Ashok R.; Laskey, Ronald A.

    2014-01-01

    The nuclear phase of the gene expression pathway culminates in the export of mature messenger RNAs (mRNAs) to the cytoplasm through nuclear pore complexes. GANP (germinal- centre associated nuclear protein) promotes the transfer of mRNAs bound to the transport factor NXF1 to nuclear pore complexes. Here, we demonstrate that GANP, subunit of the TRanscription-EXport-2 (TREX-2) mRNA export complex, promotes selective nuclear export of a specific subset of mRNAs whose transport depends on NXF1. Genome-wide gene expression profiling showed that half of the transcripts whose nuclear export was impaired following NXF1 depletion also showed reduced export when GANP was depleted. GANP-dependent transcripts were highly expressed, yet short-lived, and were highly enriched in those encoding central components of the gene expression machinery such as RNA synthesis and processing factors. After injection into Xenopus oocyte nuclei, representative GANP-dependent transcripts showed faster nuclear export kinetics than representative transcripts that were not influenced by GANP depletion. We propose that GANP promotes the nuclear export of specific classes of mRNAs that may facilitate rapid changes in gene expression. PMID:24510098

  16. Department of Nuclear Energy

    International Nuclear Information System (INIS)

    2002-01-01

    Full text: The activities of Department was engaged in the selected topics in nuclear fission reactor science and engineering. Present and future industry competitiveness, economic prosperity and living standards within the world are strongly dependent on maintaining the availability of energy at reasonable prices and with security of supply. Also, protection of man and the environment from the harmful effects of all uses of energy is an important element of the quality of life especially in Europe. It is unrealistic to assume that the technology for renewable (hydro, wind, solar and biomass) available within a 20-30 year perspective could provide the production capacity to replace present use of nuclear power and at the same time substantially reduce the use of fossil fuels, especially when considering that energy demand in industrialized countries can be expected to continue to increase even within a framework of overall energy conservation and continued improvement of efficiency in energy usage. In the area of nuclear fission, we continue support to maintain and develop the competence needed to ensure the safety of existing and future reactors and other nuclear installations. In addition support is given to explore the potential for improving present fission technology from a sustainable development point of view. The focus on advanced modelling of improved reactor and fuel cycle concepts, including supporting experimental research, with a view to improving the utilisation of the inherent energy content of uranium and other nuclear fuels, whilst at the same time reducing the amount of long-lived radioactive waste produced. A common scientific understanding of the frequently used concept of ''reasonable assurance of safety'' for the long-term, post-closure phase of repositories for spent fuel and high-level waste developed in order to ensure reasonably equivalent legal interpretations in environmental impact assessment and licensing procedures. Also, research is

  17. Comparison of Oxidation Characteristics of Selected Nuclear Graphite Grades

    International Nuclear Information System (INIS)

    Chi, Se Hwan; Kim, Gen Chan

    2010-02-01

    The oxidation behavior of some selected nuclear graphite grades (i.e., IG-110, IG-430, NBG-18, NBG-25) were compared in view of their filler coke type and the physical property of the grades. Oxidation rates were determined at six temperatures between 600 ∼ 960 .deg. C in air by using a three-zone vertical tube furnace at a 10 L/min air flow rate. The specimens were a cylinder with a 25.4 mm diameter and a 25.4 mm length. Results showed that, even though the four examined nuclear graphite grades showed a highly temperature-sensitive oxidation behavior through out the test temperature range of 600 ∼ 950 .deg. C, the differences between the grades were not significant. The oxidation rates determined for a 5∼10 % weight loss at the six temperatures were nearly the same except for 702 and 808 .deg. C, where the pitch coke graphites showed an apparent decrease in their oxidation rate, more so than the petroleum coke graphites. These effects of the coke type reduced or nearly disappeared with an increasing temperature. The average activation energy determined for 608 ∼ 808 .deg. C was 161.5 ± 7.3 kJ/mol, showing that the dominant oxidation reaction occurred by a chemical control

  18. Visualizing the nuclear science and technology knowledge domain

    Energy Technology Data Exchange (ETDEWEB)

    Melo, Bruno Mattos Souza de Souza; Honaiser, Eduardo H.R. [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)]. E-mails: brunomelo@ieee.org; ehonaiser@yahoo.com.br

    2007-07-01

    In this paper, a knowledge domain visualization approach is applied to the nuclear science and technology fields. A so-called concept density map based on the abstracts of the papers presented at the ICONE 14 is constructed. The concept map provides an overview of the nuclear science and technology fields by visualizing the associations between their main concepts. To analyze recent developments the concept map is compared with a concept map based on abstracts of earlier ICONE meetings. The analysis presented in the paper provides insight into the structure of the nuclear science and technology fields and into the most significant developments carried out during the last few years. (author)

  19. 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.

  20. Selected review of regulatory standards and licensing issues for nuclear power plants

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Thomas, F.A.

    1982-11-01

    This report presents a compilation and description of current foreign regulatory standards and licensing issues in the areas of interest associated with Siting, Structural Engineering, Metallurgy and Materials, and Mechanical Engineering. In addition, summary comparisons of the requirements of both the US and foreign nuclear power plant regulatory standards are provided. The selected foreign countries surveyed include Canada, France, Japan, Sweden, United Kingdom of Great Britain and Northern Ireland, and the Federal Republic of Germany