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Sample records for related featuresin nuclear

  1. Nuclear energy related research

    International Nuclear Information System (INIS)

    Salminen, Pertti

    1989-03-01

    This annual Research Programme Plan covers the publicly funded nuclear energy related research planned to be carried out at the Technical Research Centre of Finland (VTT) in 1989. The research will be financed by the Ministry of Trade and Industry, the Finnish Centre for Radiation and Nuclear Safety, the Nordic Council of Ministers and VTT itself

  2. Nuclear energy related research

    International Nuclear Information System (INIS)

    Salminen, P.; Mattila, L.

    1990-08-01

    The annual Research Programme Plan describes the publicly funded nuclear energy related research to be carried out at the Technical Research Centre of Finland (VTT) in 1990. The research is financed primarily by the Ministry of Trade and Industry (KTM), the Finnish Centre for Radiation and Nuclear Safety (STUK) and VTT itself. Utilities and industry also contribute to some projects

  3. Nuclear energy related research

    International Nuclear Information System (INIS)

    Mattila, L.; Vanttola, T.

    1991-10-01

    The annual Research Programme Plan describes the publicly funded nuclear energy related research to be carried out mainly at the Technical Research Centre of Finland (VTT) in 1991. The research is financed primarily by the Ministry of Trade and Industry (KTM), the Finnish Centre for Radiation and Nuclear Safety (STUK) and VTT itself. Other research institutes, utilities and industry also contribute to many projects

  4. Nuclear energy related research

    International Nuclear Information System (INIS)

    Rintamaa, R.

    1992-05-01

    The annual Research Programme Plan describes publicly funded nuclear energy related research to be carried out mainly at the Technical Research Centre of Finland (VTT) in 1992. The research is financed primarily by the Ministry of Trade and Industry (KTM), the Finnish Centre for Radiation and Nuclear Safety (STUK) and VTT itself. Other research institutes, utilities and industry also contribute to many projects

  5. Nuclear energy related research

    International Nuclear Information System (INIS)

    Salminen, P.

    1988-02-01

    This annual Research Programme Plan covers the publicly funded nuclear energy related research planned to be carried out at the Technical Research Centre of Finland (VTT) in 1988. The research will be financed by the Ministry of Trade and Industry, the Finnish Centre for Radiation and Nuclear Safety, the Nordic Council of Ministers and VTT itself

  6. Nuclear public relations campaign

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    A two-day hearing to investigate DOE's participation in a $30 million nuclear public relations program at a time when the country is asked to decrease spending and in conjunction with similar efforts by the nuclear industry focused on the issue of whether ratepayers or shareholders should finance the effort. Shelby Brewer, Assistant Secretary for Nuclear Energy, defended the expenditures as a response to public demand for information and the need to correct misinformation. The testimony of 14 other witnesses includes the views of citizen and professional groups, utilities, and government agencies. Their testimony is followed by additional material submitted for the record. (DCK)

  7. Nuclear energy related research

    International Nuclear Information System (INIS)

    Toerroenen, K.; Kilpi, K.

    1985-01-01

    This research programme plan for 1985 covers the nuclear energy related research planned to be carried out at the Technical Research Centre of Finland (VTT) and funded by the Ministry of Trade and Industry in Finland, the Nordic Council of Ministers and VTT

  8. Nuclear energy related research

    International Nuclear Information System (INIS)

    Salminen, Pertti

    1987-02-01

    This annual Research Programme Plan covers the nuclear related research planned to be carried out at the Technical Research Centre of Finland (VTT) in 1987 and funded by the Ministry of Trade and Industry in Finland, the Nordic Council of Ministers and VTT itself

  9. Nuclear data and related services

    International Nuclear Information System (INIS)

    Tuli, J.K.

    1985-01-01

    National Nuclear Data Center (NNDC) maintains a number of data bases containing bibliographic information and evaluated as well as experimental nuclear properties. An evaluated computer file maintained by the NNDC, called the Evaluated Nuclear Structure Data File (ENSDF), contains nuclear structure information for all known nuclides. The ENSDF is the source for the journal Nuclear Data Sheets which is produced and edited by NNDC. The Evaluated Nuclear Data File (ENDF), on the other hand is designed for storage and retrieval of such evaluated nuclear data as are used in neutronic, photonic, and decay heat calculations in a large variety of applications. The NNDC maintains three bibliographic files: NSR - for nuclear structure and decay data related references, CINDA - a bibliographic file for neutron induced reactions, and CPBIB - for charged particle reactions. Selected retrievals from evaluated data and bibliographic files are possible on-line or on request from NNDC

  10. Relative costs to nuclear plants: international experience

    International Nuclear Information System (INIS)

    Souza, Jair Albo Marques de

    1992-03-01

    This work approaches the relative costs to nuclear plants in the Brazil. It also presents the calculation methods and its hypothesis to determinate the costs, and the nacional experience in costs of investment, operating and maintenance of the nuclear plants

  11. Neutron spectroscopy, nuclear structure, related topics. Abstracts

    International Nuclear Information System (INIS)

    Sukhovoj, A.M.

    1996-01-01

    Neutron spectroscopy, nuclear structure and related topics are considered. P, T-breaking, neutron beta decay, neutron radiative capture and neutron polarizability are discussed. Reaction with fast neutrons, methodical aspect low-energy fission are considered too

  12. Virtual reality. Fundamentals and nuclear related applications

    International Nuclear Information System (INIS)

    Ishii, Hirotake

    2010-01-01

    Since the first virtual reality (VR) system was developed by Dr. Ivan Sutherland in the 1960s, various research and development have been conducted to apply VR to many fields. One promising applications is a nuclear-related one. VR is useful for control room design support, operation training, maintenance training, decommissioning planning support, nuclear education, work image sharing, telecollaboration, and even providing an experimental test-bed. In this lecture note, fundamental knowledge of VR is presented first, and various VR applications to nuclear fields are stated along with their advantages. Then appropriate cases for introducing VR are summarized and future prospects are given. (author)

  13. Nuclear energy: strategy of public relations

    Energy Technology Data Exchange (ETDEWEB)

    Timell, S [Swedish Power Association, Stockholm, Sweden

    1981-02-21

    A referendum was held in Sweden on 23rd March 1980, stimulated by the Three Mile Island accident in USA, to determine the future nuclear power development policy. The electricity supply background is that in 1980, 65% of power was hydro, 25% nuclear and 10% coal and oil. In terms of total power consumption, the country is heavily dependent on oil, which represents about 75%. The intensive public relations activity previous to the referendum is described, and this involved fact accumulation and assimilation, dissemination through various media, including brochures, displays, films and leaflets. In the political arena three lines developed: (1) (Conservatives); continue nuclear power, building at least 12 reactors, (2) (Social democrats and liberals); similar to (1), but more cautious, with emphasis on energy conservation, (3) (Centre parties and communists); no more nuclear power, and prevention of uranium extraction in Sweden. The voting was (1) 18.9%, (2) 39.1%, (3) 38.7%, (No dec of the most topical is concerned with the inventory of risks due to each industrial energy sector. This session was in two parts, the first devoted to problems specific to each source of energy including nuclear, the second to commo The extension to longer distances may be made with caution and to the satisfaction of the regulatory authority.

  14. Nuclear energy: strategy of public relations

    International Nuclear Information System (INIS)

    Timell, S.

    1981-01-01

    A referendum was held in Sweden on 23rd March 1980, stimulated by the Three Mile Island accident in USA, to determine the future nuclear power development policy. The electricity supply background is that in 1980, 65% of power was hydro, 25% nuclear and 10% coal and oil. In terms of total power consumption, the country is heavily dependent on oil, which represents about 75%. The intensive public relations activity previous to the referendum is described, and this involved fact accumulation and assimilation, dissemination through various media, including brochures, displays, films and leaflets. In the political arena three lines developed: (1) (Conservatives); continue nuclear power, building at least 12 reactors, (2) (Social democrats and liberals); similar to (1), but more cautious, with emphasis on energy conservation, (3) (Centre parties and communists); no more nuclear power, and prevention of uranium extraction in Sweden. The voting was (1) 18.9%, (2) 39.1%, (3) 38.7%, (No decision) 3.3%. (G.C.)

  15. Safety related terms for advanced nuclear plants

    International Nuclear Information System (INIS)

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

  16. Safety related terms for advanced nuclear plants

    International Nuclear Information System (INIS)

    1991-09-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

  17. 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)

  18. Nuclear waste transmutation and related innovative technologies

    International Nuclear Information System (INIS)

    2002-01-01

    The main topics of the summer school meeting were 1. Motivation and programs for waste transmutation: The scientific perspective roadmaps; 2. The physics and scenarios of transmutation: The physics of transmutation and adapted reactor types. Impact on the fuel cycle and possible scenarios; 3. Accelerator driven systems and components: High intensity accelerators. Spallation targets and experiments. The sub critical core safety and simulation physics experiments; 4. Technologies and materials: Specific issues related to transmutation: Dedicated fuels for transmutation. Fuel processing - the role of pyrochemistry. Materials of irradiation. Lead/lead alloys. 5. Nuclear data: The N-TOF facility. Intermediate energy data and experiments. (orig./GL)

  19. IAEA receives Iraq's nuclear-related declaration

    International Nuclear Information System (INIS)

    2002-01-01

    Full text: The Director General of the International Atomic Energy Agency, Mohamed ElBaradei, announced that the IAEA received this evening, Sunday, 8 December 2002, at its Headquarters in Vienna, an approximately 2400 page declaration on Iraq's nuclear programme. The declaration consists of about 2100 pages in English and 300 pages in Arabic. The declaration was submitted by the Government of Iraq in response to paragraph 3 of Security Council resolution 1441 (8 November 2002), which requires Iraq to provide to UNMOVIC, the IAEA and to the Security Council, not later than 30 days of the date of that resolution, with 'currently accurate, full, and complete declaration of all aspects of its programmes to develop chemical, biological, and nuclear weapons, ballistic missiles, and other delivery systems... as well as all other chemical, biological, and nuclear programmes, including any which it claims are for purposes not related to weapon production or material'. 'The IAEA will immediately begin to assess this important new document,' said Mr. ElBaradei, 'including the painstaking and systematic cross-checking of the information provided by Iraq against information which the IAEA already has, information that it expects to receive from other Member States, as contemplated in resolution 1441, and results of past and present Agency verification activities.' Complete assessment of the declaration will be time consuming, particularly in light of the need to translate the 300 pages of Arabic text into English. However, the IAEA expects to be able to provide a preliminary analysis of the document to the Security Council within the next ten days, with a fuller assessment to be provided when it reports to the Council at the end of January. (IAEA)

  20. Aging of nuclear safety related concrete structures

    International Nuclear Information System (INIS)

    Cerny, R.; Vydra, V.; Toman, J.; Vodak, F.

    1994-01-01

    An analysis of aging processes in nuclear-safety-related concrete structures (NSRCS) is presented. The major environmental stressor and aging factors affecting the performance of NSRCS are summarized, as are drying and plastic shrinkage, expansion of water during the freeze-thaw cycle, water passing through cracks dissolving or leaching the soluble calcium hydroxide, attack of acid rain and ground water, chemical reactions between particular aggregates and the alkaline solution within cement paste, reaction of calcium hydroxide in cement paste hydration products with atmospheric carbon dioxide, and physical radiation effects of neutrons and gamma radiation. The current methods for aging management in NSRCS are analyzed and evaluated. A new treatment is presented for the monitoring, evaluation and prediction of aging processes, consisting in a combination of theoretical methods, laboratory experiments, in-situ measurements and numerical simulations. 24 refs

  1. Safety related events at nuclear installations in 1995

    DEFF Research Database (Denmark)

    Korsbech, Uffe C C

    1996-01-01

    Nuclear safety related events of significance at least corresponding to level 2 of the International Nuclear Event Scale are described. In 1995 only two events occured at nuclear power plants, and four events occured at plants using ionizing radiation for processing or research.......Nuclear safety related events of significance at least corresponding to level 2 of the International Nuclear Event Scale are described. In 1995 only two events occured at nuclear power plants, and four events occured at plants using ionizing radiation for processing or research....

  2. Relativity damps OPEP in nuclear matter

    International Nuclear Information System (INIS)

    Banerjee, M.K.

    1998-06-01

    Using a relativistic Dirac-Brueckner analysis the OPEP contribution to the ground state energy of nuclear matter is studied. In the study the pion is derivative-coupled. The author finds that the role of the tensor force in the saturation mechanism is substantially reduced compared to its dominant role in a usual nonrelativistic treatment. He shows that the damping of derivative-coupled OPEP is actually due to the decrease of M * /M with increasing density. He points out that if derivative-coupled OPEP is the preferred form of nuclear effective lagrangian nonrelativistic treatment of nuclear matter is in trouble. Lacking the notion of M * it cannot replicate the damping. He suggests an examination of the feasibility of using pseudoscalar coupled πN interaction before reaching a final conclusion about nonrelativistic treatment of nuclear matter

  3. Improvements in or relating to nuclear reactors

    International Nuclear Information System (INIS)

    Timofeev, A.V.; Batjukov, V.I.; Fadeev, A.I.; Shapkin, A.F.; Shikhiyan, T.G.; Ordynsky, G.V.; Drachev, V.P.; Pogodin, E.N.

    1980-01-01

    A refuelling installation for nuclear reactor complexes is described for recharging the reactor vessels of such complexes with new fuel assemblies and for removing spent fuel assemblies from the reactor vessel. (U.K.)

  4. Nuclear power and related safety issues

    International Nuclear Information System (INIS)

    Valdezco, Eulinia M.

    2009-01-01

    There are a cluster of trends that reinforce the importance of nuclear power on the world scene. Energy is the essential underpinning for economic and societal progress and, as the developing world advances, the demand for energy is growing significantly. At the same time, the carbon-intensive sources of energy on which the world has traditionally relied - in particular, coal, oil, and natural gas - pose grave threats because the growing concentrations of carbon dioxide in the atmosphere will bring about climate and ocean acidification. At the same time, rising and volatile fossil fuel prices, coupled with concerns about the security of supplies of oil and gas, enhance interest in sources of energy that do not pose the same costs and risks. As an important part of the world's response to these threats, many countries are embarking on either new or expanded nuclear power programs, more commonly referred to as a nuclear renaissance. The construction of nuclear power plants is under consideration in over thirty countries that do not currently use nuclear power. For new entrants that may have experience in constructing and operating large-scale industrial and infrastructure projects, they may not be fully familiar with the unique requirements of nuclear power and may not be fully recognize the major commitments and understandings that they must assume. Additionally, an understanding of the full range of obligations may have diminished in those countries with only one or a few reactors and where nuclear construction has not been undertaken for a long time. It is therefore in the interest of all to ensure that every country with a nuclear power program has the resources, expertise, authority and capacity to assure safety in a complete and effective manner and is committed to doing so. This presentation will outline some of the more important national infrastructure considerations including nuclear safety issues for launching a nuclear power program. An update on the

  5. Estimation of nuclear power-related expenditures in fiscal 1982

    International Nuclear Information System (INIS)

    1981-01-01

    In fiscal 1982 (April to March, 1983), the research and development on nuclear power should be promoted actively and extensively by taking the appropriate measures. In view of the importance, the budgetary expenditures are to be estimated duly for the purpose, considering also the stringent financial situation. The budgetary expenditures for nuclear power estimated for the fiscal year 1982 are about 292,800 Million in total and the obligation act limit is about 139,900 Million. The following matters are described: nuclear power-related measures for securing nuclear power safety, promotion of nuclear power generation, establishment of the nuclear fuel cycle, development of power reactors, research on nuclear fusion, strengthening of the foundation in nuclear power research, development and utilization, promotion of international cooperation, etc.; estimated budgetary expenditures; tables of budgetary demands in various categories. (J.P.N.)

  6. Nuclear and nuclear related analytical methods applied in environmental research

    International Nuclear Information System (INIS)

    Popescu, Ion V.; Gheboianu, Anca; Bancuta, Iulian; Cimpoca, G. V; Stihi, Claudia; Radulescu, Cristiana; Oros Calin; Frontasyeva, Marina; Petre, Marian; Dulama, Ioana; Vlaicu, G.

    2010-01-01

    Nuclear Analytical Methods can be used for research activities on environmental studies like water quality assessment, pesticide residues, global climatic change (transboundary), pollution and remediation. Heavy metal pollution is a problem associated with areas of intensive industrial activity. In this work the moss bio monitoring technique was employed to study the atmospheric deposition in Dambovita County Romania. Also, there were used complementary nuclear and atomic analytical methods: Neutron Activation Analysis (NAA), Atomic Absorption Spectrometry (AAS) and Inductively Coupled Plasma Atomic Emission Spectrometry (ICP-AES). These high sensitivity analysis methods were used to determine the chemical composition of some samples of mosses placed in different areas with different pollution industrial sources. The concentrations of Cr, Fe, Mn, Ni and Zn were determined. The concentration of Fe from the same samples was determined using all these methods and we obtained a very good agreement, in statistical limits, which demonstrate the capability of these analytical methods to be applied on a large spectrum of environmental samples with the same results. (authors)

  7. United States - Japanese nuclear relations: implications for the pacific region

    International Nuclear Information System (INIS)

    Suttmeier, R.P.

    1980-01-01

    The initiation of a new approach to non-proliferation policy by the United States in 1977 was the most upsetting development in the history of US-Japanese nuclear relations. The policy has seemingly altered Japanese views of its own nuclear future very little, yet it has altered the tone of the nuclear relationship with the United States. Recent Japanese nuclear power developments, both technical and administrative, are outlined and the prospects for the future of the United States-Japanese nuclear relationship and for Pacific regional cooperation assessed. Issues of importance in the relationship include reprocessing - enrichment, plutonium management, spent fuel and waste management and uranium supplies

  8. Press problem related to nuclear energy news reporting

    International Nuclear Information System (INIS)

    Arai, Mitsuo

    2008-01-01

    Since the event of Niigataken Chuetsu-oki Earthquake in 2007 and the subsequent press reports on damage of nuclear power station after it, a stance of media is being questioned. In order to clear this problem, basic organizational structure of the press related to nuclear energy news was analyzed. Local news department, social news department, science news department and economical news department involve in nuclear energy news the accordance with their own situations and concerns. This structure makes problem of nuclear energy news reporting complicated. Changing this system is required but very difficult. It is concluded that the press problem around nuclear energy news is strange. (author)

  9. Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

    International Nuclear Information System (INIS)

    Li Tianshu

    2013-01-01

    Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

  10. Malaysian public perception towards nuclear power energy-related issues

    Science.gov (United States)

    Misnon, Fauzan Amin; Hu, Yeoh Siong; Rahman, Irman Abd.; Yasir, Muhamad Samudi

    2017-01-01

    Malaysia had considered nuclear energy as an option for future electricity generation during the 9th Malaysia Development Plan. Since 2009, Malaysia had implemented a number of important preparatory steps towards this goal, including the establishment of Nuclear Power Corporation of Malaysia (MNPC) as first Nuclear Energy Programme Implementing Organization (NEPIO) in Malaysia. In light of the establishment of MNPC, the National Nuclear Policy was formulated in 2010 and a new comprehensive nuclear law to replace the existing Atomic Energy Licensing Act (Act 304) is currently in the pipeline. Internationally, public acceptance is generally used to gauge the acceptance of nuclear energy by the public whenever a government decides to engage in nuclear energy. A public survey was conducted in between 14 March 2016 to 10 May 2016 focusing on the Malaysian public acceptance and perception towards the implementation of nuclear energy in Malaysia. The methodology of this research was aim on finding an overview of the general knowledge, public-relation recommendation, perception and acceptance of Malaysian towards the nuclear power development program. The combination of information gathered from this study can be interpreted as an indication of the complexity surrounding the development of nuclear energy and its relationship with the unique background of Malaysian demography. This paper will focus mainly on energy-related section in the survey in comparison with nuclear energy.

  11. Improvements in or relating to nuclear shields

    International Nuclear Information System (INIS)

    Hawkins, R.J.; Riley, K.; Powell, C.

    1981-01-01

    A nuclear radiation shield comprises two pieces of steel held together edge to edge by a weld, the depth of which is less than the thickness of either of the edges. As the radiaion shielding effect of the weld will be less than the steel, an insert is bolted or welded over the weld. (U.K.)

  12. Improvements in or relating to nuclear reactors

    International Nuclear Information System (INIS)

    Savin, N.I.; Khramov, D.A.; Filippov, V.J.; Bugrov, V.V.

    1979-01-01

    A nuclear reactor is described, comprising a core accommodating a plurality of fuel assemblies and a refuelling device for replacing spent fuel assemblies. The design of the fuel assembly and of the refuelling device, and the method of carrying out the refuelling operation, are specified. (U.K.)

  13. On the nuclear crisis in public relations and corporate strategies

    International Nuclear Information System (INIS)

    Fan Fei

    2012-01-01

    Perilous and crisis-prone, which caused by economic globalization and information technology, are the characteristics of this era. In the face of crisis, some enterprises make the 'crises' as a 'chance' ride, while some businesses are facing bankruptcy. Crisis public relations in the modern enterprise management is an important issue, but the nuclear industry, which had involved less. By learning from other industries' good theories and experience. Combined with characteristics of the nuclear industry itself, proposed nuclear power companies public relations crisis should follow the basic principles and specific methods of operation, the nuclear industry for the promotion of healthy, rapid and safe development plays an important role. (author)

  14. Augmented reality. Fundamentals and nuclear related applications

    International Nuclear Information System (INIS)

    Ishii, Hirotake

    2010-01-01

    In recent years, Augmented Reality (AR) has attracted considerable interest from both academia and industry. Virtual Reality enables users to interact only with virtual objects in a virtual environment, but AR enables users to interact with both virtual objects and real objects in the real world. This feature supports application of AR to various fields such as education, driving, entertainment, and navigation. Especially, by application of AR to support workers in nuclear power plants, it is expected that working time and human error can be decreased. However, many problems remain unsolved to apply AR to real fields. In this lecture note, fundamental knowledge of AR is presented first including the overview of elemental technologies to realize AR. Then various AR applications to nuclear fields are described. Finally, future prospects are given. (author)

  15. Nuclear spectroscopy with direct relations II. Proceedings

    International Nuclear Information System (INIS)

    Throw, F. E.

    1964-01-01

    The Symposium on Nuclear Spectroscopy with Direct Reactions, sponsored and organized by Argonne National Laboratory under the auspices of the U. S. Atomic Energy Commission, was held on 9-11 March 1964 at the Center for Continuing Education, University of Chicago. The present volume contains the invited papers along with abstracts or summaries of the few short papers selected for their special relevance to the topics of the invited lecturers . Edited versions of the discussions are also included

  16. Nuclear relations with administrations of industry services

    International Nuclear Information System (INIS)

    Bernardez Garcia, A.

    2011-01-01

    The object of the article is to try to answer to the following question that can arise to the holder of a nuclear power station: What Administration of Industry must I myself direct to be able to support my complementary facilities of Industrial Security inside the in force legality?. The raised discussion arise between if the competent administration for the legal steps, is the Central Administration across his delegates and sub delegates of government, or is of the Territorial Services of Industry of Autonomous communities. (Author)

  17. Nuclear medicine and related radionuclide applications in developing countries

    International Nuclear Information System (INIS)

    1986-01-01

    The Symposium presentations were divided into sessions devoted to the following topics: Radioimmunoassay and related techniques (4 papers and 4 poster presentations); Radionuclide applications in the diagnosis of parasitic diseases (7 papers and 2 posters); Instrumentation (6 papers and 4 posters); Clinical nuclear medicine: liver, bones, thyroid, cardiovascular system, lungs, kidneys, brain (23 papers and 15 posters); Organization of nuclear medicine services in the developing countries (9 papers and 5 posters); Training in nuclear medicine (4 papers) and the panel discussion. Future of Nuclear Medicine in the developing countries. A separate abstract was prepared for each of these papers and posters

  18. Promotion of public awareness relating nuclear power in young generation

    International Nuclear Information System (INIS)

    Kobayashi, Yoko

    2011-01-01

    Although nuclear power presents problems of waste, safety and non-proliferation, many people understand that it is an essential energy for addressing the global climate and reducing CO2. However, a vague negative-image to the radiation and nuclear power is deep-rooted among the public. Young generation is not an exception. It is very important to transfer many information from the experienced generation in the industry to young generations. In this paper, the research that applied the information intelligence to nuclear power, which involves of the nuclear fuel cycle, and the communication related activities for the social acceptance and improvement. (author)

  19. A new relation to estimate nuclear radius

    International Nuclear Information System (INIS)

    Singh, M.; Kumar, Pradeep; Singh, Y.; Gupta, K.K.; Varshney, A.K.; Gupta, D.K.

    2013-01-01

    The uncertainty found in Grodzins semi empirical relation may be due to the non - consideration of asymmetry in the relation. In the present work we propose a new relation connecting B(E2; 2 1 + → 0 1 + ) and E2 1 + with asymmetric parameter γ

  20. Phase relations, crystal structures and physical properties of nuclear fuels

    International Nuclear Information System (INIS)

    Tagawa, Hiroaki; Fujino, Takeo; Tateno, Jun

    1975-07-01

    Phase relations, crystal structures and physical properties of the compounds for nuclear fuels are presented, including melting point, thermal expansion, diffusion and magnetic and electric properties. Emphasis is on oxides, carbides and nitrides of thorium, uranium and plutonium. (auth.)

  1. The relations between de-alerting nuclear force and nuclear strategy

    International Nuclear Information System (INIS)

    Li Zhimin

    2001-01-01

    De-alerting nuclear force is a hot-point issue in recent years. The relations between de-alerting and strategy (including nuclear force, target doctrine and use principle et al.), stability, advanced conventional force and NMD of the United States are analyzed, the impact of de-alerting on Chinese nuclear force were discussed and the proposal of de-alerting by stages is presented

  2. Nuclear halo and its related reactions

    International Nuclear Information System (INIS)

    Zhang Huanqiao

    2005-01-01

    In order to search proton halo, the reaction cross sections of 27,28 P, 29 S and the corresponding isotones on Si target were measured at intermediate energies. The measured reaction cross sections of the N=12 and 13 isotones show an abrupt increase at Z=15. The experimental results for the isotones with Z=14 as well as 28 P can be well described by the modified Glauber theory of the optical limit approach. The enhancement of the reaction cross sections for 28 P could be explained in the modified Glauber theory with an enlarged core. Theoretical analysis with the modified Glauber theory of the optical limit and few-body approaches underpredicted the experimental data of 27 P. Our theoretical analysis shows that an enlarged core together with proton halo is probably the mechanism responsible for the enhancement of the cross sections for the reaction of 27 P+ 28 Si. In addition, we find from the experimental results that 29 S may have a moderate proton halo structure. Except the nuclei near or at drop-lines, halo may appear in the excited states of stable nuclei. By means of the asymptotic normalization coefficients (ANC's) extracted from transfer reactions of 11 B(d, p) 12 B, 12 C(d, p) 13 C, and H( 6 He, n) 6 Li, we have verified that the second ( Jπ = 2 - ) and third (Jπ = 1 - ) excited states in 12 B and the first (Jπ =1/2 + ) excited state in 13 C are the neutron halo states, while the second excited state (3.56 MeV, Jπ = 0 + ) in 6 Li is a proton-neutron halo state. We have proposed a procedure to extract the probability for valence particle being out of the binding potential from the measured nuclear asymptotic normalization coefficients. With this procedure, available data regarding the nuclear halo candidates are systematically analyzed and a number of halo nuclei are confirmed. Based on these results we have got a much relaxed condition for nuclear halo occurrence. Furthermore, we have presented the scaling laws for the dimensionless quantity 2 >/R 2 of

  3. Study of relational nuclear databases and online services

    International Nuclear Information System (INIS)

    Fan Tieshuan; Guo Zhiyu; Liu Wenlong; Ye Weiguo; Feng Yuqing; Song Xiangxiang; Huang Gang; Hong Yingjue; Liu Tinjin; Chen Jinxiang; Tang Guoyou; Shi Zhaoming; Liu Chi; Chen Jiaer; Huang Xiaolong

    2004-01-01

    A relational nuclear database management and web-based services software system has been developed. Its objective is to allow users to access numerical and graphical representation of nuclear data and to easily reconstruct nuclear data in original standardized formats from the relational databases. It presents 9 relational nuclear libraries: 5 ENDF format neutron reaction databases (BROND), CENDL, ENDF, JEF and JENDL), the ENSDF database, the EXFOR database, the IAEA Photonuclear Data Library and the charged particle reaction data from the FENDL database. The computer programs providing support for database management and data retrievals are based on the Linux implementation of PHP and the MySQL software, and are platform-independent. The first version of this software was officially released in September 2001

  4. Predominance and Role of Myanmar Women in Nuclear Related Fields

    International Nuclear Information System (INIS)

    Nyein, T.N.; Tharn Diang, A.

    2015-01-01

    This poster reflects the current and future endeavor of Myanmar women in nuclear science and technology related fields. Though Myanmar has not yet planned for nuclear power program, but strongly interested in nuclear energy due to rising awareness of future energy demand. The DAE is central in conducting career development, (E&T) as well as (R&D) in nuclear application fields, cooperating with the international societies and local institutions. According to survey, the status of women power in administration, rule and regulation sector is 62%, that in research, 34%, that in radiation application and protection, 57% and that in education and training, 46%. The current trend indicates that female are perceptibly wider participants in DAE. Qualified personnel and sufficient human resource are of essence in nuclear engineering and science. Thus, so as not to face the shortage of personnel, we aim to promote the interest of young generation ,to make competent and efficient manpower based on current and future national nuclear programmes since the parliament agreed on decision for acceleration of human resource development in nuclear field in order to urge government on June 23, 2014. Moreover, activities should be undertaken by the government and associated departments to persuade the interest of secondary and high school level student, to enhance academic programme for nuclear engineering and other sciences in private and government technical schools and training centre, to develop infrastructure according to near future nuclear programs, to enlighten people the benefits of nuclear science and technology and applications, and to raise public awareness of zero carbon emitting energy resource. These potential efforts should be extended, upgraded and encouraged not only by government, stakeholders and also by the help of nuclear network of other international organizations, since larger numbers of WiN Myanmar are required to access practically and globally integrated

  5. Safety-related occurrences at the Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Reponen, H.; Viitasaari, O.

    1985-04-01

    This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Report for this period, Operation of Finnish Nuclear Power Plants (STUK-B-YTO 7), which is supplemented by this report intended for experts. (author)

  6. Safety-related occurrences at the Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Viitasaari, O.; Rantavaara, A.

    1984-03-01

    This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Report for this period, Operation of Finnish Nuclear Power Plants (STL-B-RTO-83/7), which is supplemented by this report intended principally for experts. (author)

  7. Safety-related incidents at the Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, P.

    1985-01-01

    This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Reports, Operation of Finnish Nuclear Power Plants, which are supplemented by this report intended for experts. (author)

  8. University students' understanding level about words related to nuclear power

    International Nuclear Information System (INIS)

    Oiso, Shinichi; Watabe, Motoki

    2012-01-01

    The authors conducted a survey of university students' understanding level about words related to nuclear power before and after Fukushima Daiichi Power Plant accident, and analyzed the difference between before and after the accident. The results show that university students' understanding level improved after the accident, especially in the case of reported words by mass media. Understanding level of some nuclear power security words which were not reported so much by mass media also improved. That may be caused by rising of people's concern about nuclear power generation after the accident, and there is a possibility that the accident motivated people to access such words via internet, journals, etc. (author)

  9. Safety-related incidents at the Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, P.

    1986-03-01

    This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Reports, Operation of Finnish Nuclear Power Plants, which are supplemented by this report intended for experts. (author)

  10. Analytical solution of dispersion relations for the nuclear optical model

    Energy Technology Data Exchange (ETDEWEB)

    VanderKam, J.M. [Center for Communications Research, Thanet Road, Princeton, NJ 08540 (United States); Weisel, G.J. [Triangle Universities Nuclear Laboratory, and Duke University, Box 90308, Durham, NC 27708-0308 (United States); Penn State Altoona, 3000 Ivyside Park, Altoona, PA 16601-3760 (United States); Tornow, W. [Triangle Universities Nuclear Laboratory, and Duke University, Box 90308, Durham, NC 27708-0308 (United States)

    2000-12-01

    Analytical solutions of dispersion integral relations, linking the real and imaginary parts of the nuclear optical model, have been derived. These are displayed for some widely used forms of the volume- and surface-absorptive nuclear potentials. When the analytical solutions are incorporated into the optical-model search code GENOA, replacing a numerical integration, the code runs three and a half to seven times faster, greatly aiding the analysis of direct-reaction, elastic scattering data. (author)

  11. Constitutive relations for nuclear reactor core materials

    International Nuclear Information System (INIS)

    Zaverl, F. Jr.; Lee, D.

    1978-01-01

    A strain rate dependent constitutive equation is proposed which is capable of describing inelastic deformation behavior of anisotropic metals, such as Zircaloys, under complex loading conditions. The salient features of the constitutive equations are that they describe history dependent inelastic deformation behaviour of anisotropic metals under three-dimensional stress states in the presence of fast neutron flux. It is shown that the general form of the constitutive relations is consistent with experimental observations made under both unirradiated and irradiated conditions. The utility of the model is demonstrated by examining the analytical results obtained for a segment of tubing undergoing different loading histories in a reactor. (Auth.)

  12. Relations among several nuclear and electronic density functional reactivity indexes

    Science.gov (United States)

    Torrent-Sucarrat, Miquel; Luis, Josep M.; Duran, Miquel; Toro-Labbé, Alejandro; Solà, Miquel

    2003-11-01

    An expansion of the energy functional in terms of the total number of electrons and the normal coordinates within the canonical ensemble is presented. A comparison of this expansion with the expansion of the energy in terms of the total number of electrons and the external potential leads to new relations among common density functional reactivity descriptors. The formulas obtained provide explicit links between important quantities related to the chemical reactivity of a system. In particular, the relation between the nuclear and the electronic Fukui functions is recovered. The connection between the derivatives of the electronic energy and the nuclear repulsion energy with respect to the external potential offers a proof for the "Quantum Chemical le Chatelier Principle." Finally, the nuclear linear response function is defined and the relation of this function with the electronic linear response function is given.

  13. Relative evaluation on decommissioning accident scenarios of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jei-Kwon; Hyun, Dong-Jun; Kim, Geun-Ho; Kim, Tae-Hyoung; Jo, Kyung-Hwa; Seo, Jae-Seok; Jeong, Seong-Young; Lee, Jung-Jun

    2012-01-01

    Highlights: ► This paper suggests relative importance on accident scenarios during decommissioning of nuclear facilities. ► The importance of scenarios can be performed by using AHP and Sugeno fuzzy method. ► The AHP and Sugeno fuzzy method guarantee reliability of the importance evaluation. -- Abstract: This paper suggests the evaluation method of relative importance on accident scenarios during decommissioning of nuclear facilities. The evaluation method consists of AHP method and Sugeno fuzzy integral method. This method will guarantee the reliability of relative importance evaluation for decommissioning accident scenarios.

  14. Peer Relations of Adolescents from Nuclear and Separated Families.

    Science.gov (United States)

    Noack, Peter; Krettek, Christine; Walper, Sabine

    2001-01-01

    Examined peer relations of young people from nuclear families, step families, and single-parent families. Findings suggest peer relations were affected by parental separation only to a minor extent as compared to, e.g. gender- or age-specific effects. A central aspect of friendship quality, however, namely admiration by friends, clearly suffered…

  15. Changing relations between civil and military nuclear technology

    International Nuclear Information System (INIS)

    Walker, W.B.

    1999-01-01

    Nuclear energy has inhabited two distinct environments since its inception - the environments of nuclear deterrence and of electricity supply. The relationships between the technologies and institutions inhabiting these environments have been both intimate and troublesome. As both nuclear weapons and nuclear power rely upon the fission energy of uranium and plutonium, and as both generate harmful by-products, they are bound to have technologies, materials and liabilities in common. However, nuclear deterrence belongs in the realm of high politics, whilst electricity production is part of the commercial world rooted in civil society. Establishing a political, industrial and regulatory framework that allows nuclear activities to develop safely and acceptably in both domains has been a difficult and contentious task. In this paper I wish to make some observations about the relations between military and civil nuclear technology at the end of this century, and about their likely character in years ahead. My main contention is that developments in the military sector and in international security will remain influential, but that their consequences will be of a different kind than in the past. (orig.)

  16. ISINN-2. Neutron spectroscopy, nuclear structure and related topics

    International Nuclear Information System (INIS)

    1994-01-01

    The proceedings contain the materials presented at the Second International Seminar on Neutron-Nucleus Interactions (ISINN-2) dealing with the problems of neutron spectroscopy, nuclear structure and related topics. The Seminar took place in Dubna on April 26-28, 1994. Over 120 scientists from Belgium, Bulgaria, Czech Republic, Germany, Holland, Italy, Japan, Latvia, Mexico, Poland, Slovakia, Slovenia, Ukraine, US and about 10 Russian research institutes took part in the Seminar. The main problems discussed are the following: P-odd and P-even angular correlation and T-reversal invariance in neutron reactions, nuclear structure investigations by neutron capture, the mechanism of neutron reactions, nuclear fission processes, as well as neutron data for nuclear astrophysics

  17. United Kingdom: Procurement Related Nuclear Experience (Operating Experience)

    International Nuclear Information System (INIS)

    2016-01-01

    Procurement of nuclear facilities in the United Kingdom is subject to nuclear site licence conditions issued by the Government through the Office for Nuclear Regulation (ONR). Each nuclear facility in the United Kingdom must have a nuclear site licence and must comply with the 36 general conditions that are set out in the Licence Condition Handbook (October 2014). In addition, the ONR has published a technical assessment guide for the procurement of nuclear safety related items or services; a guide on intelligent customers and a guide on records management also apply to the procurement phase, and ONR interventions look across all three of these documents. Procurement governance arrangements need to be developed (including a policy, manual, procedures and template documents) and approved within the utility company. The ONR monitors the arrangements via interventions and deems the arrangements to be ‘adequate’. Some procurement contracts become lifetime records for nuclear safety related systems and need to be retained while the plant is in place. A formal record retention schedule needs to be created and managed by the procurement organization. The utility company may elect to set hold points during the various procurement stages and, importantly, obtain approval for the contract and its content from all technical stakeholders (with particular emphasis on the engineering, project management and design authority quality functions before contract award). For contracts with high nuclear safety significance, the ONR may enforce additional hold points before and/or after contract award. There is a general requirement that the utility puts in place adequate arrangements to ensure that suitably qualified and experienced personnel are employed to implement adequate management arrangements and to act as an intelligent customer. This includes being able to demonstrate that any contractor or supplier is suitable, capable and experienced, and has the necessary processes and

  18. Build of virtual instrument laboratory related to nuclear species specialized

    International Nuclear Information System (INIS)

    Shan Jian; Zhao Guizhi; Zhao Xiuliang; Tang Lingzhi

    2009-01-01

    As rapid development of specialized related to nuclear science,the requirement of laboratory construct is analyzed in this article at first, One total conceive, One scheme deploy soft and hardware,three concrete characteristics targets and five different phases of put in practice of virtual instrument laboratory of specialized related to nuclear science are suggest in the paper,the concrete hardware structure and the headway of build of virtual instrument laboratory are described,and the first step effect is introduced.Lastly,the forward target and the further deliberateness that the virtual instrument laboratory construct are set forth in the thesis. (authors)

  19. Energy-range relations for hadrons in nuclear matter

    Science.gov (United States)

    Strugalski, Z.

    1985-01-01

    Range-energy relations for hadrons in nuclear matter exist similarly to the range-energy relations for charged particles in materials. When hadrons of GeV kinetic energies collide with atomic nuclei massive enough, events occur in which incident hadron is stopped completely inside the target nucleus without causing particle production - without pion production in particular. The stoppings are always accompanied by intensive emission of nucleons with kinetic energy from about 20 up to about 400 MeV. It was shown experimentally that the mean number of the emitted nucleons is a measure of the mean path in nuclear matter in nucleons on which the incident hadrons are stopped.

  20. IAEA activity related to safety of nuclear desalination

    International Nuclear Information System (INIS)

    Gasparini, M.

    2000-01-01

    The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. The current safety approach, based on the achievement of the fundamental safety functions and defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

  1. Developments related to the National Nuclear Safety Authority of Romania

    International Nuclear Information System (INIS)

    Baciu, Florin

    1998-01-01

    The contribution presents the status of the National Commission for Nuclear Activity Control (CNCAN) as indicated by the provisions of a Romanian Government Decision of May 1998. As specified in the art.3 the main tasks of the Commission are the following: to issue authorization and exercise permits of activities in nuclear field; to supervise the applications of the provisions stipulated by the law concerning development in safety conditions of nuclear activities; to develop instructions as well as nuclear safety regulations to ensure the quality assurance and functioning in safety conditions of the nuclear facilities and plants, the protection against nuclear radiation of the professionally exposed personnel, of the population, of the environment and of the material goods, the physical protection, the records, preservation and transport of radioactive material and of fissionable materials as well as the management of radioactive waste; organizes expert and is responsible for the state control concerning the integrated application of the law provisions in the field of quality constructions in which nuclear installations of national interest are located, during all the phases and for all the components of the quality system in this field; issues specialty and information documentation specific to its own activity, provides the information of the public through official publication, official statements to the press and other specific form of information; carries out any other tasks provided by law in the field of regulations and control of nuclear activity. Author presents also the CNCAN staff number evolution, the new structure, the staff distribution at headquarters, local agencies and national radiation monitoring network. Finally, the author discusses the legal provisions related to management manual procedures

  2. Nuclear data for radiation damage assessment and related safety aspects

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1989-12-01

    The IAEA Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Related Safety Aspects was held at the IAEA Headquarters in Vienna, 19-22 September 1989. This report contains the conclusions and recommendations of this meeting. The papers which the participants prepared for and presented at the meeting will be published as an IAEA Technical Document. (author)

  3. Extrapolations of nuclear binding energies from new linear mass relations

    DEFF Research Database (Denmark)

    Hove, D.; Jensen, A. S.; Riisager, K.

    2013-01-01

    We present a method to extrapolate nuclear binding energies from known values for neighboring nuclei. We select four specific mass relations constructed to eliminate smooth variation of the binding energy as function nucleon numbers. The fast odd-even variations are avoided by comparing nuclei...

  4. Simple probabilistic method for relative risk evaluation of nuclear terrorism events

    International Nuclear Information System (INIS)

    Zhang Songbai; Wu Jun

    2006-01-01

    On the basis of the event-tree and probability analysis methods, a probabilistic method of nuclear terrorism risk was built, and the risk of terrorism events was analyzed. With the statistical data for and hypothetical data for relative events, the relative probabilities of the four kinds of nuclear terrorism events were obtained, as well as the relative risks of these four kinds of nuclear terrorism events were calculated by using this probabilistic method. The illustrated case show that the descending sequence of damages from the four kinds of nuclear terrorism events for single event is as following: nuclear explosive and improvised nuclear explosive, nuclear facility attacked, and 'dirty bomb'. Under the hypothetical condition, the descending sequence of possibilities for the four kinds of nuclear terrorism events is as following: 'dirty bomb', nuclear facility attacked, improvised nuclear explosive and nuclear explosive, but the descending sequence of risks is as following: 'dirty bomb', improvised nuclear explosive, nuclear facility attacked, and nuclear explosive . (authors)

  5. Holdup-related issues in safeguarding of nuclear materials

    International Nuclear Information System (INIS)

    Pillay, K.K.S.

    1988-03-01

    Residual inventories of special nuclear materials (SNM) remaining in processing facilities (holdup) are recognized as an insidious problem for both safety and safeguards. This paper identifies some of the issues that are of concern to the safeguards community at-large that are related to holdup of SNM in large-scale process equipment. These issues range from basic technologies of SNM production to changing regulatory requirements to meet the needs of safeguarding nuclear materials. Although there are no magic formulas to resolve these issues, there are several initiatives that could be taken in areas of facility design, plant operation, personnel training, SNM monitoring, and regulatory guidelines to minimize the problems of holdup and thereby improve both safety and safeguards at nuclear material processing plants. 8 refs

  6. JAEA's activities relating the Fukushima Nuclear Plant accident

    International Nuclear Information System (INIS)

    Tagawa, Akihiro

    2012-01-01

    JAEA started the activities relating to the Fukushima nuclear plant accident immediately after the Great East Japan Earthquake. The Office of Fukushima Partnership Operations for Environmental Remediation was opened and the JAEA staff was stationed as the base of cooperation with other organizations. It is conducting environmental radiation monitoring, environmental radioactivity analyses, resident public consulting, and demonstration of decontamination technology. Experts of JAEA are providing technical advice and supports to the Nuclear Safety Commission of Japan and the Ministry of Education, Culture and Sports. Furthermore, the water radiolysis leading to hydrogen gas evolution by Cs 137 adsorbed zeolite and the technique for radioactive waste process and its disposal of fuel debris are being studied. JAEA's Nuclear Emergency Assistance and Training Center (NEAT) is acting as a center of these supporting activities of JAEA. (S. Ohno)

  7. Indian Nuclear Society annual conference-1994 on advanced technologies related to nuclear power: proceedings

    International Nuclear Information System (INIS)

    Grover, R.B.

    1994-01-01

    The focal theme of the conference is advanced technologies related to nuclear power. Over the past three decades civilian nuclear power plants around the world have accumulated about 6000 reactor years of experience and have performed quite well. Overall safety record has been satisfactory. However, nuclear community is trying to compete with its own record by trying to enhance the safety characteristics of the best operating plant. A safety culture has been established in the nuclear establishments, which is providing impetus to advances in all aspects of nuclear technology all over the world. India has ongoing programmes for the development of advanced reactors and related advanced technologies. Evolution of pressurised heavy water reactors in India, developments made in the design of advanced heavy water reactor and the fast reactor programme, are some of the topics covered in addition to highlighting worldwide developments for the next generation of light water reactors. India is one of the few countries in the world where expertise about complete fuel cycle is available. Developments in the back end of the fuel cycle, use of thorium and plutonium and other related issues are also discussed. Technology control regimes being advocated and adopted by developed nations make it imperative for us to indigenise every equipment and component that goes into a power plant. In view of this, some aspects of manufacturing technologies, inspection techniques and maintenance problems are also covered. Relevant papers are processed separately for INIS. (M.K.V.)

  8. Report on estimated nuclear energy related cost for fiscal 1991

    International Nuclear Information System (INIS)

    1991-01-01

    The report first describes major actions planned to be taken in Japan in fiscal 1991 in the field of nuclear energy utilization. Major activities to be made for comprehensive strengthening of safety assurance measures are described, focusing on improvement of nuclear energy related safety regulations, promotion of research for safety assurance, improvement and strengthening of disaster prevention measures, environmental radioactivity surveys, control of exposure of workers engaged in radioactivity related jobs, etc. The report then describes actions required for the establishment of a nuclear fuel cycle, focusing on the procurement of uranium resources, establishment of a uranium enrichment process, reprocessing of spent fuel, application of recovered uranium, etc. Other activities are required for the development of new type reactors, effective application of plutonium, development of basic techniques, international contributions, cooperation with the public. Then, the report summarizes estimated costs required for the activities to be performed by the Japan Atomic Energy Research Institute, Power Reactor and Nuclear Fuel Development Corporation, National Institute of Radiological Sciences, Institute of Physical and Chemical Research. (N.K.)

  9. Brazilian nuclear politics in the context of contemporary international relations

    International Nuclear Information System (INIS)

    Carpes, Mariana Montez

    2006-09-01

    The present dissertation analyses the retaking of the debate over Brazilian nuclear Program's recovery by Luis Inacio Lula da Silva government, based on the defense of the utilization of an already acquired technology of its own to enrich uranium. In spite of the intrinsic duality on this subject and having in mind the pacific ends concerning the utilization of such technology by Brazil, the hypothesis sustained in this work is that the Program's defense is considered a strategy of sovereign international insertion with relative autonomy and an instrument of national valorization against other powers. In order to verify the hypothesis outlined above, we will analyse the actual government, comparing it to, two other moments in Brazilian History in which the nuclear issue also acquired preponderance on the national agenda, namely, Geisel and Sarney governments. Although these three moments differ in relation to their internal political regime, our goal is to identify their similarities. (author)

  10. The role of the National INIS Center in presenting Macedonian nuclear and nuclear related sciences

    International Nuclear Information System (INIS)

    Sejmenova-Gichevska, Marija

    2007-01-01

    The Republic of Macedonia is 95th Member State of INIS and its participation in this cooperative decentralized system started in 1996 when the Macedonian INIS Center was established to be operated by the National and University Library 'Kliment Ohridski' in Skopje. The main objective of this study is to give an overview of the Macedonian nuclear and nuclear related scientific thought presented in the INIS Database. A statistical analysis of the Macedonian INIS Center's contribution to the INIS Database for the period of its constitution to 2006, by quantifying and reviewing the language, publication type and INIS subject categories of the submitted records is presented. (author)

  11. Concerning major items in government ordinance requiring modification of part of enforcement regulation for law relating to control of nuclear material, nuclear fuel and nuclear reactor

    International Nuclear Information System (INIS)

    1989-01-01

    The report describes major items planned to be incorporated into the enforcement regulations for laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The modifications have become necessary for the nation to conclude a nuclear material protection treaty with other countries. The modification include the definitions of 'special nuclear fuel substances' and 'special nuclear fuel substances' and 'special nuclear fuel substances subject to protection'. The modifications require that protective measures be taken when handling and transporting special nuclear fuel substances subject to protection. Transport of special nuclear fuel substances requires approval from the Prime Minister or Transport Minister. Transport of special nuclear fuel substances subject to protection should be conducted after notifying the prefectural Public Safety Commission. Transport of special nuclear fuel substances subject to protection requires the conclusion of arrangements among responsible persons and approval of them from the Prime Minister. (N.K.)

  12. Nuclear and related techniques in animal production and health

    International Nuclear Information System (INIS)

    1986-01-01

    The international symposium was attended by about 130 participants from 45 countries and included 83 scientific presentations of which 42 were posters. This volume covers four principal and interrelated topics: adaptation of animals to the environment, and animal reproduction, health and nutrition. Within each topic, consideration is given to those nuclear and related techniques currently employed in investigative research and their usefulness in studying animal production systems. Progress towards new areas of application and new techniques is also covered, particularly the development and practicability of immunoassay and related biotechnological methods for the diagnosis of livestock diseases. A separate abstract was prepared for each of the papers in this volume

  13. Nuclear medium effects in the evaluation of Callan Gross relation

    International Nuclear Information System (INIS)

    Zaidi, F.; Haider, H.; Athar, M. Sajjad; Singh, S.K.

    2015-01-01

    JLab has recently measured F 1 (x) and F 2 (x) structure functions separately as well as studied the difference F 2 (x) - 2 xF 1 (x) (Callan-Gross relation) using electron-nucleus deep inelastic scattering (DIS) in the energy region of 2-6 GeV of the electron beam. Theoretically, it is important to understand nuclear medium effects for a fundamental process eN → eX (N is the nucleon and X is jet of hadrons) taking place with a nucleon bound inside the nucleus. Generally, nuclear medium effects in the DIS region are understood due to shadowing and antishadowing effects, mesonic cloud contributions, Fermi motion and binding energy etc. In the present paper we have studied nuclear medium effects in microscopic model using relativistic nucleon spectral function to describe nucleon momentum distribution. The Fermi motion, binding energy effect and nucleon-nucleon correlations are taken into account using spectral functions. The spectral functions that describe energy and momentum distribution of nucleon is obtained by using the Lehmann's representation for the relativistic nucleon propagator and nuclear many body theory is used to calculate it for an interacting Fermi sea in nuclear matter. A local density approximation is then applied to translate these results to a finite nucleus. We have taken into account pion and rho mesons cloud contributions which are found to have important contribution in the intermediate region of Bjorken variable x. Furthermore, shadowing and antishadowing effects are also taken into account using phenomenological model of Kulagin and Petti. Numerical evaluation have been performed both at the leading order (LO) and next-to-leading order (NLO)

  14. Exploiting Semantic Search Methodologies to Analyse Fast Nuclear Reactor Nuclear Related Information

    International Nuclear Information System (INIS)

    Costantini, L.

    2016-01-01

    Full text: This paper describes an experiment to evaluate the outcomes of using the semantic search engine together with the entity extraction approach and the visualisation tools in large set of nuclear data related to fast nuclear reactors (FNR) documents originated from INIS database and the IAEA web publication. The INIS database has been used because is the larger collection of nuclear related data and a sub-set of it can be utilised to verify the efficiency and the effectiveness of this approach. In a nutshell, the goal of the study was to: 1) find and monitor documents dealing with FNR; 2) building knowledge base (KB) according to the FNR nuclear components and populate the KB with relevant documents; 3) communicate the conclusion of the analysis by utilising visualisation tools. The semantic search engine used in the case study has the capability to perform what is called evidential reasoning: accruing, weighing and evaluating the evidence to determinate a mathematical score for each article that measures its relevance to the subject of interest. This approach provides a means to differentiate between articles that closely meet the search criteria versus those less relevant articles. Tovek software platform was chosen for this case study. (author

  15. ISINN-3. Neutron spectroscopy, nuclear structure, related topics

    International Nuclear Information System (INIS)

    1995-01-01

    The proceedings contain the materials presented at the Third International Seminar on Neutron-Nucleus Interactions (ISINN-3) dealing with the problems of neutron spectroscopy, nuclear structure and related topics. The Seminar took place in Dubna on April 26-28, 1995. Over 100 scientists from Belgium, Bulgaria, Czech Republic, Germany, Japan, Latvia, Mexico, Poland, Slovakia, Ukraine, USA and from more than 10 Russian research institutes took part in the Seminar. The Seminar is dedicated to the memory of the founder of the Neutron Physics Laboratory of JINR, the famous soviet scientist Professor Fedor L. Shapiro, whose 80th anniversary is being observed. The main problems discussed are the following: fundamental interactions and symmetries in neutron-induced reactions, fundamental properties of the neutron, properties of excited nuclei after neutron capture and some other ones. Special emphasis is laid upon γ decay and neutron induced nuclear fission as well as upon the methodical aspects of new experiments

  16. Application of nuclear track detectors for radon related measurments

    International Nuclear Information System (INIS)

    Abu-Jarad, F.A.

    1988-01-01

    The application of nuclear track detectors for radon related measurements is discussed. The ''Can Technique'', used for measuring radon emanation from building materials, walls and soil; the ''Working Level Monitor'', used for measuring short period working levels of radon daughters in houses; and ''Passive Radon Dosimeters'', used to measure radon levels in houses for long term (few months) periods are described. Application of nuclear track detectors for measuring the radon daughters plate-out on the surface of mixing fan blades and walls are discussed. The uranium content of some wall papers was found to be 6 ppm. The variation of radon progeny concentration in the same room was measured and supported by another study through Gas Chromatograph measurements. The independence of radon concentration on room level in high-rise buildings was established. The effect of sub-floor radon emanation on radon concentration in houses is dependent on whether there is sub-floor ventilation or not. (author)

  17. Public relations in the State Office for Nuclear Safety

    International Nuclear Information System (INIS)

    Prochazkova, Radka

    2000-01-01

    The State Office for Nuclear Safety (SONS) is a government agency. The Office is headed by a chairperson who is appointed by the Czech Government. The Office has got its own budget and reports directly to the Czech Government. SONS was established in 1993 and continued activities of the former Czechoslovak Commission for Atomic Energy. SONS main activity is the central administration and supervision of the peaceful utilization of nuclear power and ionizing radiation and in the field of radiation protection. SONS is regulated mainly by the Atomic Act. A separate department of Public Relations was established last year in SONS especially due to the enactment of the statutory obligation of government agencies to render information. Basic P.R. communication means in the field of external communication include: Information Center; Internet; Press Releases; Publications - publishing regularly or for topical events; Seminars; Meetings; Press conferences; Editorial articles; Answering questions

  18. 78 FR 25488 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Science.gov (United States)

    2013-05-01

    ... Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for... regulatory guide (DG), DG-1235, ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants... entitled ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants'' is temporarily...

  19. Large fire scenarios in relation to sabotage of nuclear installations

    International Nuclear Information System (INIS)

    Contri, P.; Guerpinar, A.; ); Schneider, U.

    2005-01-01

    The analyses of sabotage scenarios carried out in recent years identified two major damaging mechanisms associated with such scenarios, namely: the mechanical interaction of solid bodies or pressure waves with the installations and the fire-related effects from burning substances. While the former effect may be addressed by available analytical tools developed for accidental scenarios, the latter deserves a new, specific engineering effort. In fact, all nuclear facilities are designed in relation to accidental fires; even so, they need to be assessed in relation to sabotage induced fire scenarios due to the special characteristics of such scenarios, not addressed by the current engineering practice for the design of nuclear installations. Conventional fire hazard analysis is based on the hypothesis of the presence of combustible materials in the buildings and limited number of contemporaneous sources of fire. In addition, conventional fire safety assessment relies upon the presence of mitigation measures and fire related operational procedures. In a sabotage event the validity of all these assumptions need to be checked and if the assumptions cannot be supported, then the analysis should be revised and other alternatives of protection should be developed. Also the implementation of emergency planning should be reviewed to take account of this concern. This paper collects state-of-the-art experience from some Countries, which represents the background information for the development of new IAEA documents in this field. The paper reviews how the current design practice for nuclear installations can cope with large fire scenarios caused by malevolent actions and provides recommendations to designers and operators on how to address these issues in a reasonable framework. (authors)

  20. Proceedings of VII International Symposium on Nuclear and Related Techniques. XIII Workshop on Nuclear Physics. WONP-NURT 2011

    International Nuclear Information System (INIS)

    2011-02-01

    This year the XIII Workshop on Nuclear Physics (WONP) and the VII Symposium on Nuclear and Related Techniques (NURT) are organized jointly, by Instituto Superior de Tecnologias y Ciencias Aplicadas and Centro de Aplicaciones Tecnologicas y Desarrollo Nuclear. Both events gather scientists from several countries with top research work on nuclear physics and its applications. WONP has been carried out since 1994 promoting an ever-exchanging exchange between professionals of various nuclear and applied physics fields, those related to environmental and health care. NURT is one of the key Cuban scientific meetings since 1997 dealing with the peaceful applications of nuclear techniques in several domains of the society. WONP and NURT provide an unique opportunity for the national and international scientific community to meet outstanding researchers and discuss current trends in several areas of theoretical, experimental and applied nuclear physics and related topics. The papers submitted to this event are presented in this CD-ROM

  1. Proceedings of VI International Symposium on Nuclear and Related Techniques. XII Workshop on Nuclear Physics. WONP-NURT 2009

    International Nuclear Information System (INIS)

    2009-02-01

    This year the XII Workshop on Nuclear Physics (WONP) and the VI Symposium on Nuclear and Related Techniques (NURT) are organized jointly, by Instituto Superior de Tecnologias y Ciencias Aplicadas and Centro de Aplicaciones Tecnologicas y Desarrollo Nuclear. Both events gather scientists from several countries with top research work on nuclear physics and its applications. WONP has been carried out since 1994 promoting an ever-exchanging exchange between professionals of various nuclear and applied physics fields, those related to environmental and health care. NURT is one of the key Cuban scientific meetings since 1997 dealing with the peaceful applications of nuclear techniques in several domains of the society. WONP and NURT provide an unique opportunity for the national and international scientific community to meet outstanding researchers and discuss current trends in several areas of theoretical, experimental and applied nuclear physics and related topics. The papers submitted to this event are presented in this CD-ROM

  2. To what extent can the nuclear public relations be effective?

    Energy Technology Data Exchange (ETDEWEB)

    Ohnishi, Teruaki [CRC Research Institute, Tokyo (Japan)

    1996-06-01

    The effect of public relations (PRs) on the public`s attitude to nuclear energy was assessed using a model developed under the assumption that the extent of attitude change of the public by the PRs activity is essentially the same as that by the nuclear information released by the newsmedia. The attitude change of the public was quantitatively estimated by setting variables explicitly manifesting the activities such as the circulation of exclusive publicity and the area of advertising messages in the newspaper as parameters. The public`s attitude became clear to have a nonlinear dependence on the amount of activity, the extent of its change being varied considerably with demographic classes. Under a given financial condition, the offer of PRs information to the people, as many as possible in a target region, in spite of its little force of appeal, was found to be more effective for the amelioration of public attitude than the repeated offer of the information to a limited member of the public. It also became clear that there exists the most effective media mix for the activity depending on the extent of target region and on the target class of demography, therefore, it is quite significant to determine beforehand the proper conditions for the activity to be executed, such a situation indicating the need for the introduction of nuclear PRs management. (Author).

  3. To what extent can the nuclear public relations be effective?

    International Nuclear Information System (INIS)

    Ohnishi, Teruaki

    1996-01-01

    The effect of public relations (PRs) on the public's attitude to nuclear energy was assessed using a model developed under the assumption that the extent of attitude change of the public by the PRs activity is essentially the same as that by the nuclear information released by the newsmedia. The attitude change of the public was quantitatively estimated by setting variables explicitly manifesting the activities such as the circulation of exclusive publicity and the area of advertising messages in the newspaper as parameters. The public's attitude became clear to have a nonlinear dependence on the amount of activity, the extent of its change being varied considerably with demographic classes. Under a given financial condition, the offer of PRs information to the people, as many as possible in a target region, in spite of its little force of appeal, was found to be more effective for the amelioration of public attitude than the repeated offer of the information to a limited member of the public. It also became clear that there exists the most effective media mix for the activity depending on the extent of target region and on the target class of demography, therefore, it is quite significant to determine beforehand the proper conditions for the activity to be executed, such a situation indicating the need for the introduction of nuclear PRs management. (Author)

  4. Radiation-related impacts for nuclear plant physical modifications

    International Nuclear Information System (INIS)

    Sciacca, F.; Knudson, R.; Simion, G.; Baca, G.; Behling, H.; Behling, K.; Britz, W.; Cohen, S.

    1989-10-01

    The radiation fields in nuclear power plants present significant obstacles to accomplishing repairs and modifications to many systems and components in these plants. The NRC's generic cost estimating methodology attempts to account for radiation-related impacts by assigning values to the radiation labor productivity factor. This radiation labor productivity factor is then used as a multiplier on the greenfield or new nuclear plant construction labor to adjust for the actual operating plant conditions. The value assigned to the productivity factor is based on the work-site radiation levels. The relationship among ALARA practices, work-place radiation levels, and radiation-related cost impacts previously had not been adequately characterized or verified. The assumptions made concerning the use and application of radiation-reduction measures such as system decontamination and/or the use of temporary shielding can significantly impact estimates of both labor requirements and radiation exposure associated with a particular activity. Overall guidance was needed for analysts as to typical ALARA practices at nuclear power plants and the effects of these practices in reducing work-site dose rates and overall labor requirements. This effort was undertaken to better characterize the physical modification cost and radiological exposure impacts related to the radiation environment of the work place. More specifically, this work sought to define and clarify the quantitative relationships between or among: radiation levels and ALARA practices, such as the use of temporary shielding, decontamination efforts, or the use of robots and remote tools; radiation levels and labor productivity factors; radiation levels, in-field labor hours, and worker radiation exposure; radiation levels and health physics services costs; and radiation levels, labor hours, and anti-contamination clothing and equipment. 48 refs., 4 figs., 4 tabs

  5. Optimal improvement of graphs related to nuclear safeguards problems

    International Nuclear Information System (INIS)

    Jacobsen, S.E.

    1977-08-01

    This report develops the methodology for optimally improving graphs related to nuclear safeguards issues. In particular, given a fixed number of dollars, the report provides a method for optimally allocating such dollars over the arcs of a weighted graph (the weights vary as a function of dollars spent on arcs) so as to improve the system effectiveness measure which is the shortest of all shortest paths to several targets. Arc weights can be either clock times or detection probabilities and the algorithm does not explicitly consider all paths to the targets

  6. Statistical evaluation of design-error related nuclear reactor accidents

    International Nuclear Information System (INIS)

    Ott, K.O.; Marchaterre, J.F.

    1981-01-01

    In this paper, general methodology for the statistical evaluation of design-error related accidents is proposed that can be applied to a variety of systems that evolves during the development of large-scale technologies. The evaluation aims at an estimate of the combined ''residual'' frequency of yet unknown types of accidents ''lurking'' in a certain technological system. A special categorization in incidents and accidents is introduced to define the events that should be jointly analyzed. The resulting formalism is applied to the development of U.S. nuclear power reactor technology, considering serious accidents (category 2 events) that involved, in the accident progression, a particular design inadequacy. 9 refs

  7. Safety-related decision making at a nuclear power plant

    International Nuclear Information System (INIS)

    Vaurio, J.K.

    1998-01-01

    The decision making environment of an operating nuclear power plant is presented. The organizations involved, their roles and interactions as well as the main influencing factors and decision criteria are described. The focus is on safety-related decisions, and the framework is based on the situation at Loviisa power station. The role of probabilistic safety assessment (PSA) is illustrated with decisions concerning plant modifications, optimization, acceptance of temporary configurations and extended repair times. Suggestions are made for rational and flexible risk-based control of allowed times to operate the plant with some components out of service. (orig.)

  8. OECD Nuclear Energy Agency Activities Related to Fast Reactor Development

    International Nuclear Information System (INIS)

    Dujardin, Thierry; Gulliford, Jim

    2013-01-01

    • Despite impact of Fukushima, there remains a high level of interest in continued development of advanced nuclear systems and fuel cycles: – better use of natural resources; – minimisation of waste and reduction of constraints on deep geological repositories. • Ambitious R&D programmes on-going at national level in many countries, also through international projects: – expected to lead to development of advanced reactors and fuel cycle facilities. • OECD/NEA will continue to support member countries in field of fast reactor development and related advanced fuel cycles: – forum for exchange of information; – collaborative activities

  9. Progress on study of nuclear data theory and related fields at the Theory Group of CNDC

    Energy Technology Data Exchange (ETDEWEB)

    Zhigang, Ge [China Nuclear Data Center, CIAE (China)

    1996-06-01

    The Theory Group of CNDC (China Nuclear Data Center) has made a lot of progress in nuclear reaction theory and its application as well as many other related fields in 1995. The recent progress in nuclear reaction theory study and its applications, the recent progress in the nuclear data calculation and related code development are introduced. The production rate of radioactive nuclear beam induced by 70 MeV protons on {sup 72}Ge target were calculated. The calculated results are presented.

  10. Some political issues related to future special nuclear materials production

    International Nuclear Information System (INIS)

    Peaslee, A.T. Jr.

    1981-08-01

    The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors

  11. Safety related terms for advanced nuclear plants; Terminos relacionados con la seguridad para centrales nucleares avanzadas

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety.

  12. Problems relating to international transport of nuclear fuels

    International Nuclear Information System (INIS)

    Timm, U.E.

    1985-01-01

    Owing to the tremendous geographic distances between uranium deposits of interest, to the various degrees of sophistication of nuclear industry in industrialized countries and to the close international cooperation in the field of nuclear energy, safe international transports, physical protection and transport handling play an important role. It is suggested to better coordinate the activities of nuclear power plant operators, the nuclear industry and specialized transport companies with respect to all national and international issues of nuclear fuel transports. (DG) [de

  13. 78 FR 67206 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Science.gov (United States)

    2013-11-08

    ... Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Revision to regulatory guide; issuance..., ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants.'' This RG is being revised to provide... Operators Installed Inside the Containment of Nuclear Power Plants,'' dated January 1974. ADDRESSES: Please...

  14. Resource Letter MP-1: The Manhattan Project and related nuclear research

    Science.gov (United States)

    Reed, B. Cameron

    2005-09-01

    This Resource Letter provides a guide to literature on the Manhattan Project and related nuclear research. Books and journal articles are cited for the following topics: general works, technical works, biographical and autobiographical works, the German nuclear program, and technical papers of historical interest. A list of videos and websites dealing with the Manhattan Project, nuclear weapons, and nuclear issues is also given.

  15. Provisions relating to Nuclear Energy. II - International Conventions

    International Nuclear Information System (INIS)

    This book published by the Portuguese Junta de Energia Nuclear (Nuclear Energy Commission) reproduces in Portuguese and in the original language (English or French), texts of a series of international conventions in the nuclear field and the Statutes of international nuclear organisations and undertakings. The following are among the texts included: the Statutes of the IAEA, NEA, Eurochemic; the Euratom Treaty; the Tlatelolco Treaty; the co-operation agreement between Portugal and the United States on the peaceful uses of nuclear energy. (NEA) [fr

  16. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

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

  17. Dismantling of nuclear facilities and related problems - Conference proceedings

    International Nuclear Information System (INIS)

    Tournebize, Frederic; Bordet, Didier; Charlety, Philippe; Gore, Thierry; Estrade, Jerome; Lemaire, Hermine; Ginet, Annick; Fabrier, Lionel; Evrard, Lydie; Furois, Timothee; Butez, Marc; Dutzer, Michel; Faure, Vincent; Billarand, Yann; Menuet, Lise; Lahaye, Thierry; Pin, Alain; Mougnard, Philippe; Charavy, Sylvain; Poncet, Philippe; Moggia, Fabrice; Dochy, Arnaud; Benjamin, Patrick; Poncet, Pierre-Emmanuel; Beneteau, Yannick; Richard, Jean-Baptiste; Pellenz, Gilles; Ollivier Dehaye, Catherine; Gerard, Stephane; Denissen, Luc; Davain, Henri; Duveau, Florent; Guyot, Jean-Luc; Ardellier, Luc

    2012-11-01

    The oldest French nuclear facilities, built for some of them in the 1950's for research or power generation purposes, have reached more or less the end of their life. More than 30 facilities have entered the shutdown or dismantling phase, among which 8 reactors of the very first generations of Electricite de France (EdF) reactors. The aim of this two-days conference is to take stock of the present day status and perspectives of the dismantling activity, to approach the question of the management of the wastes produced, and to share experience about large scale operations already carried out. This document gathers the available presentations given during this conference: 1 - the 'Passage' project (F. Tournebize); 2 - CEA-Grenoble: from Louis Neel to key enabling technologies (D. Bordet); 3 - Dismantling actions in France (L. Evrard); 4 - Securing control of long-term charges funding (T. Furois); 5 - Waste disposal projects and their contribution to the management of dismantling wastes (M. Butez); 6 - Specificities linked with dismantling activities (Y. Billarand); 7 - Dismantling safety: the ASN's point of view (L. Evrad); 8 - Labor Ministry viewpoint about the dismantling related questions (T. Lahaye); 9 - Consideration of organizational and human factors in dismantling operations: a new deal in the operators-service providers relation (L. Menuet); 10 - Diploma and training experience (A. Pin); 11 - Glove-boxes dismantling at La Hague plant - status and experience feedback (P. Mougnard); 12 - Dismantling of Siloe reactor (CEA-Grenoble): application of the ALARA approach (P. Charlety); 13 - BR3 - a complex dismantling: the neutron shield tank (NST) in remote operation and indirect vision (L. Denissen); 14 - Cleansing and dismantling of the Phebus PF containment (S. Charavy); 15 - Integration of dismantling at the design and exploitation stages of nuclear facilities (P. Poncet); 16 - Consideration during the design and exploitation stages of dispositions aiming at

  18. IAEA activities in nuclear medicine and related medical applications of nuclear techniques

    International Nuclear Information System (INIS)

    Dudley, R.A.

    1986-01-01

    One of the objectives of the International Atomic Energy Agency, as specified in its Statute, is to ''enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.'' Its programmes in human health include both the exploitation and measurement of radiation fields (radiotherapy and dosimetry) and the use of radionuclides in an investigative or tracer role (the primary subject of this Symposium). The Agency carries out its programmes by means of several mechanisms. The technical co-operation programme, responding to requests for support from governments of Member States, is the dominant mechanism. Through it, experts may be made available to introduce new skills to a laboratory; essential equipment may be provided; and training may be organized in various forms. A second mechanism is the research contract programme, providing financial support to individual laboratories for particular research projects. A third mechanism is information exchange: scientific meetings, publications and the nuclear abstracts service of the International Nuclear Information System (INIS). In the field covered by this Symposium, the technical content of the projects supported by the Agency using these mechanisms may be classed in several categories. One domain that penetrates all others is instrumentation: selection, quality control and maintenance to prevent or correct breakdowns. Another category of activity, requiring the least sophisticated technology, is radioimmunoassay and related procedures. A third category involves the use of radionuclides in vivo, notably the classic applications of nuclear medicine in diagnosing the health status of individual patients, but including also investigation of the nature and aetiology of disease. A fourth category of project includes the study of the biological role of trace elements, especially by neutron activation analysis

  19. Assessment of Used Nuclear Fuel Inventory Relative to Disposition Options

    International Nuclear Information System (INIS)

    Wagner, John C.; Peterson, Joshua L.; Mueller, Don; Gehin, Jess C.; Worrall, Andrew; Taiwo, Temitope; Nutt, Mark; Williamson, Mark A.; Todosow, Mike; Wigeland, Roald; Halsey, William; Omberg, Ronald; Swift, Peter; Carter, Joe

    2013-01-01

    This paper presents a technical assessment of the current inventory [∼70,150 metric tons of heavy metal (MTHM) as of 2011] of U.S.-discharged used nuclear fuel (UNF) to support decisions regarding fuel cycle strategies and research, development and demonstration (RD and D) needs. The assessment considered discharged UNF from commercial nuclear electricity generation and defense and research programs and determined that the current UNF inventory can be divided into the following three categories: 1. Disposal - excess material that is not needed for other purposes; 2. Research - material needed for RD and D purposes to support waste management (e.g., UNF storage, transportation, and disposal) and development of alternative fuel cycles (e.g., separations and advanced fuels/reactors); and 3. Recycle/Recovery - material with inherent and/or strategic value. A set of key assumptions and attributes relative to the disposition options was used to categorize the current UNF inventory. Based on consideration of RD and D needs, time frames and material needs for deployment of alternative fuel cycles, characteristics of the current UNF inventory, and possible uses to support national security interests, it was determined that the vast majority of the category, without the need for retrieval for reuse or research purposes. Access to the material in the Research and Recycle/Recovery categories should be retained to support RD and D needs and national security interests. This assessment does not assume any decision about future fuel cycle options or preclude any potential options, including those with potential recycling of commercial UNF, since the ∼2,000 MTHM that is generated annually could provide the feedstock needed for deployment of alternative fuel cycles.

  20. Review of concrete biodeterioration in relation to nuclear waste.

    Science.gov (United States)

    Turick, Charles E; Berry, Christopher J

    2016-01-01

    Storage of radioactive waste in concrete structures is a means of containing wastes and related radionuclides generated from nuclear operations in many countries. Previous efforts related to microbial impacts on concrete structures that are used to contain radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete structures used to store or dispose of radioactive waste. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources such as components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The microbial contribution to degradation of the concrete structures containing radioactive waste is a constant possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Parameters to focus on for modeling activities and possible options for mitigation that would minimize concrete biodegradation are discussed and include key conditions that drive microbial activity on concrete surfaces. Copyright © 2015. Published by Elsevier Ltd.

  1. Survey on Issues related to National Nuclear Promotion Policy

    International Nuclear Information System (INIS)

    Woo, Byungchool; Lee, Youngjoon; Lee, Youngcheol; Jeong, I. K.; Kim, Hyunjun; Kim, Youngsoo; Yun, Sungwon; Moon, Keehwan; Chung, Whansam

    2013-06-01

    Ο Major issues surrounding nuclear are including suspicions about nuclear safety, spent-fuel management, acquiring the advanced R and D capabilities and making the nuclear a creative industry Ο Solid measures for securing safety should be formulated and implemented for reducing public anxiety of nuclear use Ο The long-term R and D performance system from a scientific perspective should be established for expanding Research and Development for safer use of nuclear Ο The spent-fuel management policy should be determined through publicizing process Ο Establishing small and medium enterprises-oriented supply system of reactors and SMRs and Encouraging the radiation fusion technology industrialization for promoting creative industry utilizing nuclear

  2. Review of Soviet studies related to peaceful underground nuclear explosions

    International Nuclear Information System (INIS)

    Lin, W.

    1978-01-01

    Theoretical and empirical studies of contained and crater-forming underground nuclear explosions by USSR investigators are reviewed and summarized. Published data on U.S., USSR, and French cavity-forming nuclear explosions are compared with those predicted by the formula. Empirical studies on U.S. and USSR cratering explosions, both high explosions, both high explosive and nuclear are summarized. The parameters governing an excavation explosion are reviewed

  3. The nuclear present. A guide to recent books on nuclear war, weapons, the peace movement, and related issues, with a chronology of nuclear events, 1789-1991

    International Nuclear Information System (INIS)

    Burns, G.

    1992-01-01

    The Nuclear Present brings the interested reader up-to-date on significant English-language books about nuclear weapons and related topics, identifying primarily important works of nuclear non-fiction that have come out since 1984. Each reference has a paragraph of comment about its subject and value. General organizational areas include the following: Reference Works; Nuclear weapons and Nuclear war (14 sub-headings including overviews, development, effects, tests, arms race, prospectives, legal considerations etc.); Strategy; proliferation; Stratigic Defense; Arms control and disarmament; ethical, pholosophical and religous perspectives; new paths to peace; periodic guide; the Chernobyl Disaster. An extensive Nuclear Chronology (1789-1991) written by the author allows a fairly detailed sense of the historical record of nuclear weapons, including testing, manufacture, use and movements for arms control and disarmament

  4. Nuclear energy in relation to the elimination of social conflict

    International Nuclear Information System (INIS)

    Klose, A.

    1980-01-01

    It is pointed out that, in Austria, employers and labour have both been in favour of nuclear energy and that nuclear energy problems have been the main causes of political disagreement. The importance of maintaining employment and stable currency is noted and the question is raised whether technical progress can endanger political stability. Reference is made to the 1979 European nuclear energy conference and the need for finding solutions which do not endanger the political system is emphasised. The importance of a decision on the Zwentendorf nuclear power station is stated. (G.M.E.)

  5. Third party liability cover for nuclear damage and related problems

    International Nuclear Information System (INIS)

    Carbone, Ferdinando; Gambardella, Elio.

    1974-06-01

    This paper analyses the financial security and cover for third party liability for nuclear damage as provided for by Act No. 1860 of 31 December 1962 on the peaceful uses of nuclear energy. The relevant Sections of the Act are quoted and explained, as are the nuclear operator's obligation to furnish financial security for his liability. Different possible types of security and cover are described, also with reference to other national legislation. Finally, the author mentions the Paris Convention which provides the basis for Italian nuclear third party liability legislation. (NEA) [fr

  6. Nuclear Security Management for Research Reactors and Related Facilities

    International Nuclear Information System (INIS)

    2016-03-01

    This publication provides a single source guidance to assist those responsible for the implementation of nuclear security measures at research reactors and associated facilities in developing and maintaining an effective and comprehensive programme covering all aspects of nuclear security on the site. It is based on national experience and practices as well as on publications in the field of nuclear management and security. The scope includes security operations, security processes, and security forces and their relationship with the State’s nuclear security regime. The guidance is provided for consideration by States, competent authorities and operators

  7. Model of influence of nuclear education on public relations to nuclear power

    International Nuclear Information System (INIS)

    Elagin, Yu.P.

    1996-01-01

    Method for evaluating the effect of the pupils nuclear education, as part of activities for improving the attitude of the population to nuclear power engineering is proposed. Results of calculations, made with constants values, obtained from Japan, are discussed. It is shown that the attitude to nuclear energy, formed at school, plays an essential role in formation of the future public opinion

  8. Public relations campaign for shipping spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bushee, Tom [Northern States Power Company, Minneapolis, MN (United States)

    1989-07-01

    An example of positive outcome of proper attitude of the media and public on the occasion of shipping of nuclear fuel is described. Nothing new was invented in the way of public relations issue management. But a combination of a number of proven techniques were put together and the public relations plan that was highly successful. early planning was of great help. Public officials were well informd by means of ANS organized seminars. ANS had experts from Sandia Labs (a major government research facility), General Electric (the cask supplier), the railroad we planned to use and Northern States Power Company on the program to describe what was going to happen and why it was safe. These sessions are believed to head off a major portion of the local opposition. A cooperation was established with the states of Wisconsin and Minnesota in providing shipment-specific training for emergency response personnel along the route. Safety, obviously, was the number one concern expressed by public officials. Knowing that would be the case, it was decided to provide some optional extras to go with the shipments. There was a consultant yo do a safety analysis of all the possible rail routes between the plant and storage facility. Though none was required by law, a shipment-specific emergency response plan which was prepared. Another important effort which was maintained from the beginning was sharing information among the participants. In dealing with the news media, an attemp was made to stick to a single source of information as much as possible. When dealing with the news media, one should refuse to apologize for modern technology. One should attack, at every opportunity, the idea that a ''risk-free'' society is worth the price of returning to the Dark Ages. The contributions of nuclear technology are numerous and far-reaching. Its negative impacts on health and safety have been minor compared with most other major industrial technologies. Certainly there is risk in stepping out

  9. Public relations campaign for shipping spent nuclear fuel

    International Nuclear Information System (INIS)

    Bushee, Tom

    1989-01-01

    An example of positive outcome of proper attitude of the media and public on the occasion of shipping of nuclear fuel is described. Nothing new was invented in the way of public relations issue management. But a combination of a number of proven techniques were put together and the public relations plan that was highly successful. early planning was of great help. Public officials were well informd by means of ANS organized seminars. ANS had experts from Sandia Labs (a major government research facility), General Electric (the cask supplier), the railroad we planned to use and Northern States Power Company on the program to describe what was going to happen and why it was safe. These sessions are believed to head off a major portion of the local opposition. A cooperation was established with the states of Wisconsin and Minnesota in providing shipment-specific training for emergency response personnel along the route. Safety, obviously, was the number one concern expressed by public officials. Knowing that would be the case, it was decided to provide some optional extras to go with the shipments. There was a consultant yo do a safety analysis of all the possible rail routes between the plant and storage facility. Though none was required by law, a shipment-specific emergency response plan which was prepared. Another important effort which was maintained from the beginning was sharing information among the participants. In dealing with the news media, an attemp was made to stick to a single source of information as much as possible. When dealing with the news media, one should refuse to apologize for modern technology. One should attack, at every opportunity, the idea that a r isk-freesociety is worth the price of returning to the Dark Ages. The contributions of nuclear technology are numerous and far-reaching. Its negative impacts on health and safety have been minor compared with most other major industrial technologies. Certainly there is risk in stepping out of

  10. Proceedings of XIV Workshop on Nuclear Physics. VIII International Symposium on Nuclear and Related Techniques. WONP-NURT 2013

    International Nuclear Information System (INIS)

    2013-02-01

    This year 2013, the XIV Workshop on Nuclear Physics and VIII International Symposium on Nuclear and Related Techniques, WONP-NURT 2013 organized by the Center of Technological Applications and Nuclear Development from 5 to 8 February at the National Museum of Fine Arts. NURT is one of the key Cuban scientific meetings since 1997 dealing with the peaceful applications of nuclear techniques in several domains of the society. WONP and NURT provide an unique opportunity for the national and international scientific community to meet outstanding researchers and discuss current trends in several areas of theoretical, experimental and applied nuclear physics and related topics. The papers submitted to this event are presented in this CD-ROM

  11. Proceedings of XV Workshop on Nuclear Physics. IX International Symposium on Nuclear and Related Techniques. WONP-NURT 2015

    International Nuclear Information System (INIS)

    2015-02-01

    This year 2015, the XV Workshop on Nuclear Physics and IX International Symposium on Nuclear and Related Techniques, WONP-NURT 2015 organized by the Center of Technological Applications and Nuclear Development from 9 to 13 February at the National Museum of Fine Arts. NURT is one of the key Cuban scientific meetings since 1997 dealing with the peaceful applications of nuclear techniques in several domains of the society. WONP and NURT provide an unique opportunity for the national and international scientific community to meet outstanding researchers and discuss current trends in several areas of theoretical, experimental and applied nuclear physics and related topics. The papers submitted to this event are presented in this CD-ROM.

  12. Legal approaches to transboundary pollution - relating to nuclear activities

    International Nuclear Information System (INIS)

    Hintsteiner, G.

    2000-05-01

    This work examines the legal approaches to pollution in a transboundary context. Particular consideration is given to transboundary pollution that is related to the use of nuclear energy for peaceful purposes. Since I have chosen to approach the very topic not so much in the hope of finding a single and unequivocal answer but rather by building a circumstantial case, the present work naturally relies to a great extent on decisions of international courts and tribunals, as well as on principles and rules stemming from international law in general. The international norm that basically guides the topic is the prohibition of transboundary pollution, or, expressed as a positive duty, i.e. the obligation to prevent transboundary harm, which has found expression in Principle 21 of the Stockholm Declaration on the Human Environment. The very obligation is relevant from the perspective of prevention of environmental harm, as well as reparation when harm has actually occurred. One of the primary issues of this work accordingly relates to the obligation's preventive function, thus its extent, meaning and scope are examined, and in particular its approach to transboundary risk-creation. In the overall context of transboundary pollution the principle of the sovereign equality of states and other basic rules that directly emanate from it are of continuos importance. This work is further strongly impacted by notions of equity together with the establishment of a balancing of interests test which application merits special consideration in cases where a conflict between two states cannot be solved by mere reliance on their sovereign rights. Rules relating to the prevention of environmental harm, now increasingly guided by the Precautionary Principle, are also relevant under the law of state responsibility for wrongful acts and in the context of defining obligations erga omnes. (author)

  13. Nuclear power and related issues: the US outlook

    International Nuclear Information System (INIS)

    Burstein, S.

    1989-01-01

    The author notes there are now 108 nuclear units licensed to operate in the US and another 18 under construction or completed but not licensed; nuclear power provided 19.5% of US total electrical energy as of May 1988. One of the most disturbing items is the increase in operating and maintenance costs of US nuclear plants which, in some cases, exceed costs of coal-fired plants. US leadership in nuclear power has lost much momentum due primarily to institutional rather than technological problems. There are some indications, however, that the anti-nuclear fever of the past is receding, namely: (1) President Reagan recently endorsing the need for nuclear power by signing legislation extending Price-Anderson nuclear insurance protection; (2) a more favorable regulatory climate; (3) some progress on the nuclear waste problem; (4) more supportive public acceptance; (5) decommissioning activities; (6) increased attention of plant aging and 40-yr. license requirement; (7) radon concerns, ironically, because of conservation practices; and (8) substantial progress in advanced reactor technology

  14. Nuclear energy and public relation in the Czech Republic and its neighbours

    International Nuclear Information System (INIS)

    John, A.

    2004-01-01

    The paper presents issues of the nuclear power industry in relations to opinions and feelings of the general public on the obtaining electricity from nuclear power sources. The presentation introduces these matters in a historical context and specifically it focuses on the situation around the CEZ's nuclear power plants. In addition, it shows tools that have been used for the promotion of safe and reliable operations of both NPPs. As a separate part, it introduces the World Association of Nuclear Operators and its contribution to improvement of NPPs' safety. In conclusion, call appeal for active approach to propagation of nuclear power industry is formulated for all nuclear associated stakeholders. (author)

  15. Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport

    International Nuclear Information System (INIS)

    2007-11-01

    This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

  16. Relativity evaluation of reliability on operation in nuclear power plant

    International Nuclear Information System (INIS)

    Inata, Takashi

    1987-01-01

    The report presents a quantitative method for evaluating the reliability of operations conducted in nuclear power plants. The quantitative reliability evaluation method is based on the 'detailed block diagram analysis (De-BDA)'. All units of a series of operations are separately displayed for each block and combined sequentially. Then, calculation is performed to evaluate the reliability. Basically, De-BDA calculation is made for pairs of operation labels, which are connected in parallel or in series at different subordination levels. The applicability of the De-BDA method is demonstrated by carrying out calculation for three model cases: operations in the event of malfunction of the control valve in the main water supply system for PWR, switching from an electrically-operated water supply pump to a turbin-operated water supply pump, and isolation and water removal operation for a low-pressure condensate pump. It is shown that the relative importance of each unit of a series of operations can be evaluated, making it possible to extract those units of greater importance, and that the priority among the factors which affect the reliability of operations can be determined. Results of the De-BDA calculation can serve to find important points to be considered in developing an operation manual, conducting education and training, and improving facilities. (Nogami, K.)

  17. Investigation of potential fire-related damage to safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Wanless, J.

    1985-11-01

    Based on a review of vendor information, fire damage reports, equipment qualification and hydrogen burn test results, and material properties, thirty-three types of equipment found in nuclear power plants were ranked in terms of their potential sensitivity to fire environments. The ranking considered both the functional requirements and damage proneness of each component. A further review of the seven top-ranked components was performed, considering the relative prevalence and potential safety significance of each. From this, relays and hand switches dominate as first choices for fire damage testing with logic equipment, power supplies, transmitters, and motor control centers as future candidates

  18. DOE Manpower Assessment Brief. No. 37: Nuclear-related employment declines in 1995

    International Nuclear Information System (INIS)

    1996-05-01

    The 1993-1995 period represents a time of significant transition for workers engages in nuclear-related activities. Total nuclear-related employment fell markedly from about 300,000 workers in 1993 to 265, 000 in 1995, a 12% decline. This is the lowest level since the 1970s. In 1995, a third of all nuclear-related employment was in the reactor operation and maintenance segment. 6 figs, 1 table

  19. USNRC licensing process as related to nuclear criticality safety

    International Nuclear Information System (INIS)

    Ketzlach, N.

    1987-01-01

    The U.S. Code of Federal Regulations establishes procedures and criteria for the issuance of licenses to receive title to, own, acquire, deliver, receive, possess, use, and initially transfer special nuclear material; and establishes and provides for the terms and conditions upon which the Nuclear Regulatory Commission (NRC) will issue such licenses. Section 70.22 of the regulations, ''Contents of Applications'', requires that applications for licenses contain proposed procedures to avoid accidental conditions of criticality. These procedures are elements of a nuclear criticality safety program for operations with fissionable materials at fuels and materials facilities (i.e., fuel cycle facilities other than nuclear reactors) in which there exists a potential for criticality accidents. To assist the applicant in providing specific information needed for a nuclear criticality safety program in a license application, the NRC has issued regulatory guides. The NRC requirements for nuclear criticality safety include organizational, administrative, and technical requirements. For purely technical matters on nuclear criticality safety these guides endorse national standards. Others provide guidance on the standard format and content of license applications, guidance on evaluating radiological consequences of criticality accidents, or guidance for dealing with other radiation safety issues. (author)

  20. Costs related to radioactive residues from nuclear power

    International Nuclear Information System (INIS)

    1988-06-01

    The nuclear power enterprises are responsible for proper actions for safe handling and final storage of spent nuclear fuel and radioactive waste from Swedish nuclear power facilities. The most important actions are to plan, build and operate necessary plants and systems. The nuclear power enterprises have designated Swedish Nuclear Fuel and Waste Management Co., (SKB), to perform these tasks. In this report calculations concerning costs to carry out these tasks are presented. The calculations are based upon a plan prepared by SKB. The plan is described in the report. As final storage of the long lived and highly radioactive waste is planned to take place in the 21st century continuing research and development may indicate new methods which may affect system design as well as costs in a simplifying way. Plants and systems already operational are: Transport systems for radioactive waste products; A central temporary storage for spent nuclear fuel, 'CLAB'; A final storage for radioactive waste from operating nuclear facilities, 'SFR 1'. (L.F.)

  1. The future of nuclear energy in relation with climate change

    International Nuclear Information System (INIS)

    Dautray, R.

    2001-01-01

    especially of the potentially most dangerous and difficult to treat, that is plutonium (and its daughters), leads thus necessarily to a 'plutonium (and its daughters) plan'. Nuclear safety is a major preoccupation. The French electronuclear stock is a recognized success and when it will be necessary to replace the latter, it will be possible to use the European Pressurized Reactor French-German project; the latter includes protections against very unlikely events and its implementation would be a factor of substantial progress for nuclear safety. Radioprotection, as well as its scientific bases, epidemiology and radiobiology, have funding that is not at the level of the funding devoted to the technical and industrial realizations. As for proliferation, it can be noticed that the countries that have recently at their disposal nuclear weapons have done it independently of their eventual electronuclear stock and furthermore each of the latter used a different scientific and technical process. As for the eventual relations between reprocessing and proliferation, the problem should be solved if the total produced plutonium could be denatured in the reactors of the electronuclear stock. It must be noticed that the major potential danger would rather be the dispersion of radio-toxic products about which the department of ONU in charge of all of these questions is aware of increasing contraband from eastern Europe since some years. (author)

  2. A statement on safety and related topics respecting nuclear power

    International Nuclear Information System (INIS)

    1982-01-01

    It is stated that nuclear power is remarkably safe and certainly safer than power from coal or oil. Waste presents no genuine problem in terms of storage, disposal or quantity while the ecological environmental impact is less than that of virtually all possible alternatives. Use of nuclear power can make the UK independent of external politically unreliable sources of energy. There are ethical arguments for choosing it in preference to coal or oil and it is broadly irrelevant to the question of nuclear proliferation. (U.K.)

  3. International legislation relative to nuclear pollution of the oceans

    International Nuclear Information System (INIS)

    Birot, Chantal.

    1973-01-01

    The part played by various competent international bodies in the establishment of international rules concerning the nuclear pollution of oceans is analysed. As it stands this legislation distinguishes clearly between pollution caused by peaceful and military uses of nuclear energy. In studying the former type of pollution the problems of radioactive wastes, sea transport of radioactive substances, ships propelled by nuclear energy and isotopic generators in a marine environment are considered in turn. From the military viewpoint the legislation seems more complicated and the problems are of two kinds: that of nuclear armaments in a marine environment and the consequent risks, and that of fall-out from experimental atmospheric explosions carried out in peace time but for military purposes [fr

  4. Human resource issues related to an expanding nuclear power programme

    International Nuclear Information System (INIS)

    2006-05-01

    The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that the IAEA develop guidelines on human resource management (including staffing) and training/education programmes for new nuclear power plant (NPP) designs. This recommendation was made in recognition that these future NPPs may have significantly different needs in this area compared to operating plants, and if so, NPP operating organizations should integrate these needs into their planning for future NPP projects. This report is primarily intended for use by NPP operating organizations that already have units in operation and that are considering adding to their fleet. Therefore, the addition of both new and current designs are addressed in this report. However, it should also be of value to those organizations that are considering the initial implementation of nuclear power, as well as decision makers in government, and in other nuclear industry organizations

  5. Aspects related to the decommissioning of the nuclear power plants

    International Nuclear Information System (INIS)

    Goicea, Andrei; Andrei, Veronica

    2003-01-01

    All power plants, either coal, gas or nuclear, at the end of their life needs to be decommissioned and demolished and thus, to made the site available for other uses. The first generation nuclear power plants were designed for a life of about 30 years and some of them proved capable of continuing well beyond this term. Newer plants have been designed for a 40 to 60 years operating life. To date, other 90 commercial power reactors have been retired from operation. For nuclear power plants and nuclear facilities in general the decommissioning process consists of some or all of the following activities: the safe management of nuclear materials held in the facility, cleaning-up of radioactivity (decontamination), plant dismantling, progressive demolition of the plant and site remediation. Following the decommissioning, the regulatory controls covering facility end, partially or totally, and the safe site is released for appropriate alternative use. Cernavoda NPP is a young plant and it can benefit from the continuously developing experience of the decommissioning process at the international level. The current experience allows the most metallic parts of a nuclear power to be decontaminated and recycled and makes available proven techniques and equipment to dismantle nuclear facilities safely. As experience is gained, decommissioning costs for nuclear power plants, including disposal of associated wastes, are reducing and thus, contribute in a smaller fraction to the total cost of electricity generation. The new specific Romanian regulations establish a funding system for decommissioning and provisions for long-term radioactive waste management. In the near future a decommissioning plan will be made available for Cernavoda NPP. Since the plant has only 7 years operation, that plan can be improved in order to benefit from international experience that is growing. (authors)

  6. Survey of threat studies related to the nuclear power industry

    International Nuclear Information System (INIS)

    Wagner, N.R.

    1977-08-01

    A considerable effort has been directed toward the determination of threat characteristics, resulting in a voluminous collection of documents. This report summarizes several of the major studies in order to make the information more accessible. This summary includes only studies involving attacks on nuclear material, plus those incidents which because of their objectives, resources, or motivations may lend insight into potential threat against nuclear facilities or material

  7. Development Trends in Nuclear Technology and Related Safety Aspects

    International Nuclear Information System (INIS)

    Kuczera, B.; Juhn, P.E.; Fukuda, K.

    2002-01-01

    The IAEA Safety Standards Series include, in a hierarchical manner, the categories of Safety Fundamentals, Safety Requirements and Safety Guides, which define the elements necessary to ensure the safety of nuclear installations. In the same way as nuclear technology and scientific knowledge advance continuously, also safety requirements may change with these advances. Therefore, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) one important aspect among others refers to user requirements on the safety of innovative nuclear installations, which may come into operation within the next fifty years. In this respect, the major objectives of the INPRO sub-task 'User Requirements and Nuclear Energy Development Criteria in the Area of Safety' have been: a. to overview existing national and international requirements in the safety area, b. to define high level user requirements in the area of safety of innovative nuclear technologies, c. to compile and to analyze existing innovative reactor and fuel cycle technology enhancement concepts and approaches intended to achieve a high degree of safety, and d. to identify the general areas of safety R and D needs for the establishment of these technologies. During the discussions it became evident that the application of the defence in depth strategy will continue to be the overriding approach for achieving the general safety objective in nuclear power plants and fuel cycle facilities, where the emphasis will be shifted from mitigation of accident consequences more towards prevention of accidents. In this context, four high level user requirements have been formulated for the safety of innovative nuclear reactors and fuel cycles. On this basis safety strategies for innovative reactor designs are highlighted in each of the five levels of defence in depth and specific requirements are discussed for the individual components of the fuel cycle. (authors)

  8. Issues related to EM management of DOE spent nuclear fuel

    International Nuclear Information System (INIS)

    Abbott, D.G.; Abashian, M.S.; Chakraborti, S.; Roberson, K.; Meloin, J.M.

    1993-07-01

    This document is a summary of the important issues involved in managing spent nuclear fuel (SNF) owned by the Department of Energy (DOE). Issues related to civilian SNF activities are not discussed. DOE-owned SNF is stored primarily at the Hanford Site, Idaho National Engineering Laboratory (INEL), Savannah River Site (SRS), Oak Ridge National Laboratory (ORNL), and West Valley Demonstration Project. Smaller quantities of SNF are stored at Brookhaven National Laboratory, Sandia National Laboratories, and Los Alamos National Laboratory (LANL). There is a wide variety of fuel types, including both low and high enrichment fuels from weapons production, DOE reactors, research and development programs, naval programs, and universities. Most fuel is stored in pools associated with reactor or reprocessing facilities. Smaller quantities are in dry storage. Physical conditions of the fuel range from excellent to poor or severely damaged. An issue is defined as an important question that must be answered or decision that must be made on a topic or subject relevant to achieving the complimentary objectives of (a) storing SNF in compliance with applicable regulations and orders until it can be disposed, and (b) safely disposing of DOE's SNF. The purpose of this document is to define the issues; no recommendations are made on resolutions. As DOE's national SNF management program is implemented, a system of issues identification, documentation, tracking, and resolution will be implemented. This document is an initial effort at issues identification. The first section of this document is an overview of issues that are common to several or all DOE facilities that manage SNF. The common issues are organized according to specific aspects of spent fuel management. This is followed by discussions of management issues that apply specifically to individual DOE facilities. The last section provides literature references

  9. Review Of Concrete Biodeterioration In Relation To Buried Nuclear Waste

    International Nuclear Information System (INIS)

    Turick, C.

    2012-01-01

    Long-term storage of low level radioactive material in below ground concrete disposal units (DUs) (Saltstone Disposal Facility) is a means of depositing wastes generated from nuclear operations of the U.S. Department of Energy. Based on the currently modeled degradation mechanisms, possible microbial induced effects on the structural integrity of buried low level wastes must be addressed. Previous international efforts related to microbial impacts on concrete structures that house low level radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the recent research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete vaults housing stored wastes and the wastes themselves. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources like components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The results of this review suggest that microbial activity in Saltstone, (grouted low level radioactive waste) is unlikely due to very high pH and osmotic pressure. Biodegradation of the concrete vaults housing the radioactive waste however, is a possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Results from this review point to parameters to focus on for modeling activities and also, possible options for mitigation that would minimize concrete biodegradation. In addition, key chemical components that drive microbial

  10. Review of Concrete Biodeterioration in Relation to Buried Nuclear Waste

    Energy Technology Data Exchange (ETDEWEB)

    Turick, C; Berry, C.

    2012-10-15

    Long-term storage of low level radioactive material in below ground concrete disposal units (DUs) (Saltstone Disposal Facility) is a means of depositing wastes generated from nuclear operations of the U.S. Department of Energy. Based on the currently modeled degradation mechanisms, possible microbial induced effects on the structural integrity of buried low level wastes must be addressed. Previous international efforts related to microbial impacts on concrete structures that house low level radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the recent research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete vaults housing stored wastes and the wastes themselves. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources like components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The results of this review suggest that microbial activity in Saltstone, (grouted low level radioactive waste) is unlikely due to very high pH and osmotic pressure. Biodegradation of the concrete vaults housing the radioactive waste however, is a possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Results from this review point to parameters to focus on for modeling activities and also, possible options for mitigation that would minimize concrete biodegradation. In addition, key chemical components that drive microbial

  11. Radiation damage studies related to nuclear waste forms

    International Nuclear Information System (INIS)

    Gray, W.J.; Wald, J.W.; Turcotte, R.P.

    1981-12-01

    Much of the previously reported work on alpha radiation effects on crystalline phases of importance to nuclear waste forms has been derived from radiation effects studies of composite waste forms. In the present work, two single-phase crystalline materials, Gd 2 Ti 2 O 7 (pyrochlore) and CaZrTi 2 O 7 (zirconolite), of relative importance to current waste forms were studied independently by doping with 244 Cm at the 3 wt % level. Changes in the crystalline structure measured by x-ray diffraction as a function of dose show that damage ingrowth follows an expected exponential relationship of the form ΔV/V 0 = A[1-exp(-BD)]. In both cases, the materials became x-ray amorphous before the estimated saturation value was reached. The predicted magnitudes of the unit cell volume changes at saturation are 5.4% and 3.5%, respectively, for Gd 2 Ti 2 O 7 and CaZrTi 2 O 7 . The later material exhibited anisotropic behavior in which the expansion of the monoclinic cell in the c 0 direction was over five times that of the a 0 direction. The effects of transmutations on the properties of high-level waste solids have not been studied until now because of the long half-lives of the important fission products. This problem was circumvented in the present study by preparing materials containing natural cesium and then irradiating them with neutrons to produce 134 Cs, which has only a 2y half-life. The properties monitored at about one year intervals following irradiation have been density, leach rate and microstructure. A small amount of x-ray diffraction work has also been done. Small changes in density and leach rate have been observed for some of the materials, but they were not large enough to be of any consequence for the final disposal of high level wastes

  12. Nuclear-related training and education offered by nonacademic organizations (preliminary)

    International Nuclear Information System (INIS)

    Howard, L.

    1981-11-01

    The results of a survey of nuclear-related training and education provided by nonacademic training organizations are presented in this report. The survey instrument was distributed by the Institute of Nuclear Power Operations to 136 training organizations. The scope of the survey was not intended to be comprehensive, but rather to include the primary sources of nonacademic nuclear-related training and education offered to utility personnel. The survey universe was compiled from training organizations listed in the 1981 Nuclear News Buyer's Guide. Forty-three percent of the survey population (59 organizations) responded to the questionnaire of which 31 percent (42) reported they offered nuclear-related training programs and 12 percent (17) reported they did not offer any nuclear-related training

  13. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers

    International Nuclear Information System (INIS)

    1993-04-01

    The Director General has received a Note Verbale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Verbale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Note Verbale is annexed hereto [fr

  14. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers

    International Nuclear Information System (INIS)

    1993-04-01

    The Director General has received a Note Ver bale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Ver bale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Ver bale, the text of the Note Ver bale is annexed hereto

  15. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers

    International Nuclear Information System (INIS)

    1993-04-01

    The Director General has received a Note Verbale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Verbale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Note Verbale is annexed hereto [es

  16. Japan's compensation system for nuclear damage - As related to the TEPCO Fukushima Daiichi nuclear accidents

    International Nuclear Information System (INIS)

    Nomura, Toyohiro; Matsuura, Shigekazu; Takahashi, Yasufumi; Takenaka, Chihiro; Hokugo, Taro; Kamada, Toshihiko; Kamai, Hiroyuki

    2012-01-01

    Following the TEPCO Fukushima Daiichi nuclear power plant accident, extraordinary efforts were undertaken in Japan to implement a compensation scheme for the proper and efficient indemnification of the affected victims. This publication provides English translations of key Japanese legislative and administrative texts and other implementing guidance, as well as several commentaries by Japanese experts in the field of third party nuclear liability. The OECD Nuclear Energy Agency (NEA) has prepared this publication in co-operation with the government of Japan to share Japan's recent experience in implementing its nuclear liability and compensation regime. The material presented in the publication should provide valuable insights for those wishing to better understand the regime applied to compensate the victims of the accident and for those working on potential improvements in national regimes and the international framework for third party nuclear liability

  17. Analysis on Domestic Law and Management Trend Related to Small-Quantity Nuclear Material

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Beom; Lee, Kyong Woo; Shim, Hye Won; Min, Gyung Sik [National Nuclear Management and Control Agency, Daejeon (Korea, Republic of)

    2005-07-01

    International Atomic Energy Agency (IAEA) has requested Korea to establish and manage the law ruling all nuclear materials through the INFCIRC/153. Now, it has been 30 years since Korea made the agreement, INFCIRC/153, with IAEA. Korea has tried their best to accomplish the international standard in nuclear control field and it is a fact that Korea finally produced some results in the nuclear control field. Related to nuclear material control, Korea is above the common level appropriately ranked 6th in the world in terms of nuclear power. Before 2000, Korea was making the foundation secure in the nuclear control. IAEA did not urge to establish the law supervising the small-quantity nuclear material and depleted uranium (DU). In a turnaround from early IAEA moderate line to Korea, the situation was changed. Since IAEA brought up the agenda to 2000 Joint Review Meeting between Korea-IAEA, IAEA has asked Korea to establish the control system for smallquantity nuclear material and DU. In 2003, the Korean government set up a project establishing the control system about all nuclear material including small-quantity nuclear material and DU. National Nuclear Management and Control Agency (NNCA), delegating the business relating to international controlling materials from government, developed some modules in nuclear material control system and operated it. The system includes a controlling system for small-quantity nuclear material. NNCA on behalf of government has collected the information and Korea Ministry of Science and Technology (MOST) has reported the information to the IAEA. This paper introduces you the background of controlling the small-quantity nuclear material and the system of controlling nuclear material in Korea. And it will suggest the improvement of the management method in the system for small-quantity nuclear material.

  18. Analysis on Domestic Law and Management Trend Related to Small-Quantity Nuclear Material

    International Nuclear Information System (INIS)

    Park, Jae Beom; Lee, Kyong Woo; Shim, Hye Won; Min, Gyung Sik

    2005-01-01

    International Atomic Energy Agency (IAEA) has requested Korea to establish and manage the law ruling all nuclear materials through the INFCIRC/153. Now, it has been 30 years since Korea made the agreement, INFCIRC/153, with IAEA. Korea has tried their best to accomplish the international standard in nuclear control field and it is a fact that Korea finally produced some results in the nuclear control field. Related to nuclear material control, Korea is above the common level appropriately ranked 6th in the world in terms of nuclear power. Before 2000, Korea was making the foundation secure in the nuclear control. IAEA did not urge to establish the law supervising the small-quantity nuclear material and depleted uranium (DU). In a turnaround from early IAEA moderate line to Korea, the situation was changed. Since IAEA brought up the agenda to 2000 Joint Review Meeting between Korea-IAEA, IAEA has asked Korea to establish the control system for smallquantity nuclear material and DU. In 2003, the Korean government set up a project establishing the control system about all nuclear material including small-quantity nuclear material and DU. National Nuclear Management and Control Agency (NNCA), delegating the business relating to international controlling materials from government, developed some modules in nuclear material control system and operated it. The system includes a controlling system for small-quantity nuclear material. NNCA on behalf of government has collected the information and Korea Ministry of Science and Technology (MOST) has reported the information to the IAEA. This paper introduces you the background of controlling the small-quantity nuclear material and the system of controlling nuclear material in Korea. And it will suggest the improvement of the management method in the system for small-quantity nuclear material

  19. Accidents and failures related to nuclear fuel facilities and nuclear power stations in fiscal 1982

    International Nuclear Information System (INIS)

    1983-01-01

    In the chemical preparation room of the reprocessing plant in the Tokai Establishment, Power Reactor and Nuclear Fuel Development Corp., the nasal contamination of small amount (3.6 pCi at maximum) was detected on two workers in June, 1982, but abnormality was not observed in the Lung-monitor of the workers themselves. There was not the effect to the surrounding environment. The failures reported by electric power companies to the Agency of Natural Resources and Energy in accordance with the laws related to atomic energy were 26 cases. The main causes were 5 cases due to improper design management, 2 cases due to improper manufacture management, 4 cases due to improper construction management, 11 cases due to improper maintenance management and 4 other cases. Among those 26 cases, 17 cases occurred in operation, and 9 cases occurred or were detected during shutdown such as regular inspection. Among the 17 cases, 7 cases were the automatic stop by reactor protection system, and 10 cases were the finding by regular in-operation inspection. Among the 9 cases, 5 cases were the breaking of steam generator tubes, 2 cases the breaking of bumper plates at feed heater entrance, and 2 cases other troubles. Moreover, there were 41 minor troubles. (Kako, I.)

  20. Relative radiation hazards of coal based and nuclear power plants

    International Nuclear Information System (INIS)

    Mishra, U.C.

    1983-04-01

    Coal, like most materials found in nature, contains trace quantities of naturally occurring radionuclides. However, low concentrations may become important if large quantities of coal are burnt in thermal power plants. Therefore a study was performed to determine the radioactivity in coal, in fly-ash and slag and assess the importance of radioactive emissions from thermal power plants. The results were compared to the radiological impact of nuclear power stations. Based on these data, theoretical estimates for the population living within 80km from power stations indicate that the collective dose commitments of coal-fired plants are one order of magnitude higher than those for BWR-type nuclear plants. Measurements taken in the vicinity of coal-fired plants were comparable to those for nuclear plants, i.e. within the range of variation of natural background radiation in India

  1. Nuclear energy related capabilities at Sandia National Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Pickering, Susan Y. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-02-01

    Sandia National Laboratories' technology solutions are depended on to solve national and global threats to peace and freedom. Through science and technology, people, infrastructure, and partnerships, part of Sandia's mission is to meet the national needs in the areas of energy, climate and infrastructure security. Within this mission to ensure clean, abundant, and affordable energy and water is the Nuclear Energy and Fuel Cycle Programs. The Nuclear Energy and Fuel Cycle Programs have a broad range of capabilities, with both physical facilities and intellectual expertise. These resources are brought to bear upon the key scientific and engineering challenges facing the nation and can be made available to address the research needs of others. Sandia can support the safe, secure, reliable, and sustainable use of nuclear power worldwide by incorporating state-of-the-art technologies in safety, security, nonproliferation, transportation, modeling, repository science, and system demonstrations.

  2. The influence of nuclear risk sense to atomic industry's public relation

    International Nuclear Information System (INIS)

    Biryukova, P.; Kazakevich, Yu.

    2001-01-01

    The goal of this report is estimation of the influence of sensing of nuclear risk to atomic industry's public relation. In this report the reasons of the negative relation to nuclear energetic owing to inadequate sensing of the risk dealing with this fields have been represented. (authors)

  3. Proceedings of firsts workshop on Nuclear and related techniques in health

    International Nuclear Information System (INIS)

    1997-01-01

    The book presents papers submitted to the first Workshop on Nuclear and related techniques in health that was holder at the first International Symposium on Nuclear and Related Techniques in Agriculture, held in Havana, Cuba, on October 28 th and 30 th, 1997

  4. Characteristic relation for the mass and energy distribution of the nuclear fission products

    International Nuclear Information System (INIS)

    Alexandru, G.

    1977-01-01

    The dispersion relation for nuclear fission is written in the two part fragmentation approach which allows to obtain the characteristic relation for the mass and energy distribution of the nuclear fission products. One explains the resonance approximation in the mass distribution of the fission products taking into account the high order resonances too. (author)

  5. On accounting difficulties: Risks related to nuclear power

    International Nuclear Information System (INIS)

    Plot, Emmanuelle; Vidal, Olivier

    2014-01-01

    An extreme risk has a very slight probability but potentially heavy consequences. Despite the existence of three accountancy methods for dealing with them (provisions, contingent liabilities and insurance), the transposition of such risks into financial statements is based on a sequential analysis of both the probability of the risk happening and the ability to estimate the effects. This method keeps us from taking into account risks with a highly uncertain probability of occurrence, such as accidents at nuclear power plants - independently of the 'amount' at stake. As management reports from firms concerned by nuclear risks show, the diffusion of qualitative information does not offset this gap in bookkeeping

  6. On accounting difficulties: risks related to nuclear power

    International Nuclear Information System (INIS)

    Plot, E.; Vidal, O.

    2014-01-01

    An extreme risk has a very slight probability but potentially heavy consequences. Despite the existence of 3 accountancy methods for dealing with them (provisions, contingent liabilities and insurance), the transposition of such risks into financial statements is based on a sequential analysis of both the probability of the risk happening and the ability to estimate the effects. This method keeps us from taking into account risks with a highly uncertain probability of occurrence, such as accidents at nuclear power plants - independently of the 'amount' at stake. As management reports from firms concerned by nuclear risks show, the diffusion of qualitative information does not offset this gap in bookkeeping. (authors)

  7. Nuclear-related training and education offered by academic institutions (less than baccalaureate degree) (preliminary)

    International Nuclear Information System (INIS)

    Howard, L.

    1981-11-01

    This study presents the results of a survey of academic institutions offering nuclear-related training and education at the less than baccalaureate degree level. The scope of the survey includes only those programs which have a nuclear power industry application, and excludes all programs which are affiliated with nuclear medicine. The survey instrument was distributed by the Institute of Nuclear Power Operations to 262 academic institutions. The survey universe was compiled from a number of publications that listed nuclear-related academic programs. Since the initial mailing in May 1981, ten of the institutions have been determined to no longer exist and eight other listings have been identified as duplications, thus reducing the universe to 244 institutions. Fifty-five percent of the survey population (134 institutions) responded to the questionnaire, of which 45 percent (109) were out of the survey scope and 10 percent (25) indicated they offered less than baccalaureate degree, nuclear-related programs

  8. Solid state nuclear magnetic resonance: investigating the spins of nuclear related materials

    International Nuclear Information System (INIS)

    Charpentier, Th.

    2007-10-01

    The author reviews his successive research works: his research thesis work on the Multiple Quantum Magic Angle Spinning (MQMAS) which is a quadric-polar nucleus multi-quanta correlation spectroscopy method, the modelling of NMR spectra of disordered materials, the application to materials of interest for the nuclear industry (notably the glasses used for nuclear waste containment). He presents the various research projects in which he is involved: storing glasses, nuclear magnetic resonance in paramagnetism, solid hydrogen storing matrices, methodological and instrument developments in high magnetic field and high resolution solid NMR, long range distance measurement by solid state Tritium NMR (observing the structure and dynamics of biological complex systems at work)

  9. Compilation of benchmark results for fusion related Nuclear Data

    International Nuclear Information System (INIS)

    Maekawa, Fujio; Wada, Masayuki; Oyama, Yukio; Ichihara, Chihiro; Makita, Yo; Takahashi, Akito

    1998-11-01

    This report compiles results of benchmark tests for validation of evaluated nuclear data to be used in nuclear designs of fusion reactors. Parts of results were obtained under activities of the Fusion Neutronics Integral Test Working Group organized by the members of both Japan Nuclear Data Committee and the Reactor Physics Committee. The following three benchmark experiments were employed used for the tests: (i) the leakage neutron spectrum measurement experiments from slab assemblies at the D-T neutron source at FNS/JAERI, (ii) in-situ neutron and gamma-ray measurement experiments (so-called clean benchmark experiments) also at FNS, and (iii) the pulsed sphere experiments for leakage neutron and gamma-ray spectra at the D-T neutron source facility of Osaka University, OKTAVIAN. Evaluated nuclear data tested were JENDL-3.2, JENDL Fusion File, FENDL/E-1.0 and newly selected data for FENDL/E-2.0. Comparisons of benchmark calculations with the experiments for twenty-one elements, i.e., Li, Be, C, N, O, F, Al, Si, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zr, Nb, Mo, W and Pb, are summarized. (author). 65 refs

  10. Relations between scientists and government: the case of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Katz, J E

    1982-05-01

    This article discusses the role and influence of the scientific communities in less-developed countries (LDC) on national high-technology policy by examining the particular case of nuclear energy. This area has been largely overlooked by other literature on LDC's scientific development. Based on an examination of scientific involvement in nuclear energy policy in selected countries, it becomes clear that the influence of scientists can range from making cardinal decisions about programs to simply legitimating or implementing decisions made by political or bureaucratic leaders. Within governmental structures, there are opportunities for scientists to incrementally shape technology policies, despite the fact that the magnitude of this influence is circumscribed by domestic considerations, not only of physical resources, but also intangibles such as national prestige and security. While a scientist can on rare occasion seize opportunities to dramatically restructure a nation's scientific or nuclear program, the overwhelming majority of scientists never exercise any such power. But even in day-to-day operations of government scientists can exert subtle influence, not only on nuclear energy programs, but also in an indirect way on the fabric of a nation's culture. Despite this significant impact, in any direct contest between the scientist and the politician, the scientist inevitably loses. In conclusion, scientists seem much more aware of their limitations rather than their potential to influence national technology policy, and tend to act in accord with priorities and goals as defined by their nation-state. 18 references.

  11. Electronics Related to Nuclear Medicine Imaging Devices. Chapter 7

    Energy Technology Data Exchange (ETDEWEB)

    Ott, R. J. [Joint Department of Physics, Royal Marsden Hospital and Institute of Cancer Research, Surrey (United Kingdom); Stephenson, R. [Rutherford Appleton Laboratory, Oxfordshire (United Kingdom)

    2014-12-15

    Nuclear medicine imaging is generally based on the detection of X rays and γ rays emitted by radionuclides injected into a patient. In the previous chapter, the methods used to detect these photons were described, based most commonly on a scintillation counter although there are imaging devices that use either gas filled ionization detectors or semiconductors. Whatever device is used, nuclear medicine images are produced from a very limited number of photons, due mainly to the level of radioactivity that can be safely injected into a patient. Hence, nuclear medicine images are usually made from many orders of magnitude fewer photons than X ray computed tomography (CT) images, for example. However, as the information produced is essentially functional in nature compared to the anatomical detail of CT, the apparently poorer image quality is overcome by the nature of the information produced. The low levels of photons detected in nuclear medicine means that photon counting can be performed. Here each photon is detected and analysed individually, which is especially valuable, for example, in enabling scattered photons to be rejected. This is in contrast to X ray imaging where images are produced by integrating the flux entering the detectors. Photon counting, however, places a heavy burden on the electronics used for nuclear medicine imaging in terms of electronic noise and stability. This chapter will discuss how the signals produced in the primary photon detection process can be converted into pulses providing spatial, energy and timing information, and how this information is used to produce both qualitative and quantitative images.

  12. Perturbation Expansion in Dynamical Nuclear Field Theory and Its Relation with Boson Expansion Theory : Nuclear Physics

    OpenAIRE

    Teruo, KISHIMOTO; Tetsuo, KAMMURI; Institute of Physics, University of Tsukuba; Department of Physics, Osaka University

    1990-01-01

    With the Dynamical Nuclear Field Theory (DNFT) in the Tamm-Dancoff representation we examine higher order corrections in the vibrational mode of a spherical nuclear system. Due to the effects of bubble diagrams, the perturbation expansion in terms of the unrenormalized coupling strength and boson energy fails at full self-consistency. On the other hand, it becomes applicable in the form of linked-cluster expansion when we use thses constants renormalized by the effect of bubble diagrams, in t...

  13. Safeguards considerations related to the decontamination and decommissioning of former nuclear weapons facilities

    International Nuclear Information System (INIS)

    Crawford, D.

    1995-01-01

    In response to the post-Cold War environment and the changes in the U. S. Department of Energy defense mission, many former nuclear operations are being permanently shut down. These operations include facilities where nuclear materials production, processing, and weapons manufacturing have occurred in support of the nation's defense industry. Since defense-related operations have ceased, many of the classification and sensitive information concerns do not exist. However, nuclear materials found at these sites are of interest to the DOE from environmental, safety and health, and materials management perspectives. Since these facilities played a role in defense activities, the nuclear materials found at these facilities are considered special nuclear materials, primarily highly enriched uranium and/or plutonium. Consequently, these materials pose significant diversion, theft, and sabotage threats, and significant nuclear security issues exist that must be addressed. This paper focuses on the nuclear materials protection issues associated with facility decommissioning and decontamination, primarily safeguards

  14. Concerning the application of the nuclear and related techniques

    International Nuclear Information System (INIS)

    Desdin Garcia, Luis Felipe

    1997-01-01

    The present work intends to describe briefly, some of the nuclear and connected techniques of greater application in the conditions of developing countries, which are employed in the Center of Studies Applied to the Nuclear Development, and that can be of interest for the Latin-American countries. Within those techniques we have: radiobiology, that consists of the employment of ionizing radiations to induce mutations oriented to the improvement of the cultivations. It mentions the atmospheric contamination generated by the industry of the exposition to metals and toxic waste, and of mortiferous parasites that adapt quickly to the unhealthy environmental conditions. It also enumerates some advantages of the utilization of instruments based on radioisotopic fountains. (S. Grainger) [es

  15. JENDL special purpose data files and related nuclear data

    International Nuclear Information System (INIS)

    Iijima, Shungo

    1989-01-01

    The objectives of JENDL Special Purpose Data Files under development are the applications of nuclear data to the evaluation of the fuel cycle, nuclear activation, and radiation damage. The files in plan consist of 9 types of data, viz., the actinide cross sections, the decay data, the activation cross sections, the (α,n) cross sections, the photo-reaction cross sections, the dosimetry cross sections, the gas production cross sections, the primary knock-on atom spectra and KERMA factors, and the data for standard. The status of the compilation and the evaluation of these data are briefly reviewed. In particular, the features of the data required for the evaluation of the activation cross sections, (α,n) cross sections, photo-reaction cross sections, and PKA data are discussed in some detail. The need for the realistic definition of the scope of the work is emphasized. (author)

  16. Legal questions relating to nuclear installations close to national frontiers

    International Nuclear Information System (INIS)

    Zieger, G.

    1983-01-01

    Main emphasis is placed on the criteria to decide whether the construction and operation of a nulcear power plant close to a national frontier is permissible or not. The author discusses the relevant provisions of the international law and those of the Treaty of Rome pertaining to the settlement of conflicts between neighbour states. According to the opinion of the author, nuclear installations close to borders are incompatible with international law only if they do not comply with accepted safety standards. The international agreements do not prohibit the construction of nuclear installations close to frontiers. It would be desirable, however, the author says, to conclude international treaties providing for mutual consultation and information, thus offering a platform for discussing controversial national interests; this idea already being put into practice in customary international law. (WB) [de

  17. Fuel handling, reprocessing, and waste and related nuclear data aspects

    International Nuclear Information System (INIS)

    Kuesters, H.; Lalovic, M.; Wiese, H.W.

    1979-06-01

    The essential processes in the out-of-pile nuclear fuel cycle are described, i.e. mining and milling of uranium ores, enrichment, fuel fabrication, storage, transportation, reprocessing of irradiated fuel, waste treatment and waste disposal. The aspects of radiation (mainly gammas and neutrons) and of heat production, as well as special safety considerations are outlined with respect to their potential operational impacts and long-term hazards. In this context the importance of nuclear data for the out-of-pile fuel cycle is discussed. Special weight is given to the LWR fuel cycle including recycling; the differences of LMFBR high burn-up fuel with large PuO 2 content are described. The HTR fuel cycle is discussed briefly as well as some alternative fuel cycle concepts. (orig.) [de

  18. Some studies related to decommissioning of nuclear reactors

    International Nuclear Information System (INIS)

    Bergman, C.; Menon, S.

    1990-02-01

    Decommissioning of large nuclear reactors has not yet taken place in the Nordic countries. Small nuclear installations, however, have been dismantled. This NKA-programme has dealt with some interesting and important factors which have to be analysed before a large scale decommissioning programme starts. Prior to decommissioning, knowledge is required regarding the nuclide inventory in various parts of the reactor. Measurements were performed in regions close to the reactor tank and the biological shield. These experimental data are used to verify theoretical calculations. All radioactive waste generated during decommissioning will have to be tansported to a repository. Studies show that in all the Nordic countries there are adequate transport systems with which decommissioning waste can be transported. Another requirement for orderly decommissioning planning is that sufficient information about the plant and its operation history must be available. It appears that if properly handled and sorted, all such information can be extracted from existing documentation. (authors)

  19. Difficulties are multiplying - topical legal issues relating to nuclear waste disposal

    International Nuclear Information System (INIS)

    Strassburg, W.

    1985-01-01

    The report points out topical legal issues relating to nuclear waste disposal, yet leaves no doubt that the technical-scientific concept for nuclear waste disposal incorporated into the nuclear energy law in 1976 was a success. Nonetheless it is desirable that there should be persistent efforts especially on the part of parliament when issuing legislation or statutory orders to reach greater clearness and thus predictability in areas where technology has been proven by many years of practice. (orig./HSCH) [de

  20. Relation between Romanian NGOs Acting in Nuclear Field and Other Stakeholders

    International Nuclear Information System (INIS)

    Andrei, V.; Pantazi, D.; Radulescu, G.; Bucur, C.; Stanciu, L.; Apostol Minodora, M.

    2015-01-01

    In Romania, three main NGOs act in promoting peaceful use of nuclear energy. The organization with the longest road is the Romanian Association for Nuclear Energy (AREN), created by individual persons acting in nuclear field in 1990. In 2001, a number of Romanian and foreign legal entities having core competence or unfolding nuclear energy related industrial and research activities created the Romanian Industrial Forum (Romatom). Both AREN and Romatom are active parts of European nuclear world: AREN is European Nuclear Society member and Romatom is Foratom member. The 3rd NGO is Women in Nuclear Romania (WiNRo) which registered in 2011. However, the women acting in nuclear field have become earlier active independent voices particularly in public communication on nuclear field matters. The debut was in 1993 when the women group acting in AREN became members of WiN Global, the organization that they trust would become a real opportunity to share their professional competences and improve their communication knowledge and skills in the light of the mission they decided to embrace, namely, that of clear, transparent and trustful communication with stakeholders, particularly the general public on peaceful use of nuclear energy. Today, WiN Ro is also part of WiN Europe where common European desiderates aim to establish and achieve. Today, Romanian NGOs act to continue the trustful relations they have built with a large portfolio of stakeholders adapting their endeavors for answering to various stakeholders needs for transparency and effective communication on nuclear matters at national level. At international level, the Romanian NGOs aim to register benefic experience for their organizational works and opportunities for promotion of the national good approaches, from relations with stakeholders acting in the international arena of nuclear world. Relevant aspects on how the Romanian NGOs have approached relations with stakeholders will be presented. (author)

  1. Resource Letter MP-2: The Manhattan project and related nuclear research

    Science.gov (United States)

    Reed, B. Cameron

    2011-02-01

    This Resource Letter is a supplement to my earlier Resource Letter MP-1 and provides further sources on the Manhattan Project and related nuclear research. Books and journal articles are cited for the following topics: General works, technical works, biographical and autobiographical works, foreign wartime programs and allied intelligence, technical papers of historical interest, and postwar policy and technical developments. I also give a list of videos and websites dealing with the Manhattan Project, nuclear weapons, and nuclear issues.

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  3. IAEA specialists' meeting on the fusion evaluated nuclear data library related to the ITER activity

    International Nuclear Information System (INIS)

    Goulo, V.; Lorenz, A.

    1988-01-01

    This is the summary report of an IAEA Specialists' Meeting on the Fusion Evaluated Nuclear Data Library Related to the ITER Activity, convened by the IAEA Nuclear Data Section in Vienna from 16 to 18 November 1987. The objective of the meeting was to formulate a detailed programme and time schedule for the development of the Fusion Evaluated Nuclear Data Library (FENDL) to meet the future needs of the ITER activity

  4. IAEA, EU Senior Officials Review Nuclear-Related Cooperation, Chart Way Ahead

    International Nuclear Information System (INIS)

    Amano, Y.

    2014-01-01

    International Atomic Energy Agency (IAEA) and European Union officials met this week for the second annual Senior Officials Meeting to review and further strengthen their nuclear-related cooperation. In the past year, the two institutions have improved collaboration in nuclear safety, security, safeguards and peaceful use of nuclear energy through implementing a number of initiatives. In 2013, new contracts for projects have been signed amounting to approximately 24 million euros. These included an EU Council decision to support IAEA nuclear security and verification activities worth of 8.05 million euros. Furthermore, a Memorandum of Understanding establishing a framework for cooperation to help improve nuclear safety was signed, as well as the Practical Arrangement on technical nuclear security issues. The EU and the IAEA have also worked to explore and identify new areas for cooperation such as using nuclear applications for socio-economic development. The meeting addressed enhanced cooperation in the areas of nuclear safety, nuclear security, nuclear applications, nuclear energy and safeguards. Participants agreed on the following steps, including holding a Senior Officials Meeting planned in early 2015 in the premises of the European Commission in Luxembourg

  5. Medical lessons learned from chernobyl relative to nuclear detonations and failed nuclear reactors.

    Science.gov (United States)

    Dallas, Cham E

    2012-12-01

    The Chernobyl disaster in 1986 involved the largest airborne release of radioactivity in history, more than 100 times as much radioactivity as the Hiroshima and Nagasaki atomic bombs together. The resulting emergency response, administrative blunders, and subsequent patient outcomes from this large-scale radiological disaster provide a wealth of information and valuable lessons for those who may find themselves having to deal with the staggering consequences of nuclear war. Research findings, administrative strategies (successful and otherwise), and resulting clinical procedures from the Chernobyl experience are reviewed to determine a current utility in addressing the appropriate protocols for a medical response to nuclear war. As various myths are still widely associated with radiation exposure, attention is given to the realities of a mass casualty medical response as it would occur with a nuclear detonation.

  6. Analytical relations between nuclear symmetry energy and single-nucleon potentials in isospin asymmetric nuclear matter

    International Nuclear Information System (INIS)

    Xu Chang; Li Baoan; Chen Liewen; Ko, Che Ming

    2011-01-01

    Using the Hugenholtz-Van Hove theorem, we derive general expressions for the quadratic and quartic symmetry energies in terms of the isoscalar and isovector parts of single-nucleon potentials in isospin asymmetric nuclear matter. These expressions are useful for gaining deeper insights into the microscopic origins of the uncertainties in our knowledge on nuclear symmetry energies especially at supra-saturation densities. As examples, the formalism is applied to two model single-nucleon potentials that are widely used in transport model simulations of heavy-ion reactions.

  7. Oil shale research related to proposed nuclear projects

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, H C; Sohns, H W; Dinneen, G U [Laramie Petroleum Research Center, Bureau of Mines, Department of the Interior, Laramie, WY (United States)

    1970-05-15

    The Bureau of Mines is conducting research to develop data pertinent to in situ retorting of oil shale fractured by a nuclear explosion or other means. Maximum utilization of the Green River oil shale found in Colorado, Utah, and Wyoming, at depths ranging from outcrops to several thousand feet, requires development of several methods of processing. Early research was devoted to developing processes for application to oil shale occurring at depths suitable for mining. In present research, the emphasis is on in situ retorting and recovery processes that would be more satisfactory for oil shales occurring at greater depths. Development of an in situ process depends upon finding or establishing sufficient permeability in the oil shale beds for the passage of fluids which serve as a heat carrier in bringing the oil shale to retorting temperature. Use of a nuclear explosive seems to offer the best chance for successfully fracturing the thicker and more deeply buried portions of the deposit to give the required permeability. Processing the very large quantity of broken and fractured oil shale that would be produced presents many problems which require new background data for their solution. This paper describes research the Bureau of Mines is conducting to develop pertinent data. Primarily this research involves laboratory determination of properties of oil shale, pilot scale investigation of retorting characteristics of ungraded broken shale, and underground combustion of shale fractured by pressure and chemical explosives. Application of the research results should aid in designing the oil recovery phase and provide an estimate of the quantity of oil that may be obtained in a nuclear experiment in oil shale. (author)

  8. Oil shale research related to proposed nuclear projects

    International Nuclear Information System (INIS)

    Carpenter, H.C.; Sohns, H.W.; Dinneen, G.U.

    1970-01-01

    The Bureau of Mines is conducting research to develop data pertinent to in situ retorting of oil shale fractured by a nuclear explosion or other means. Maximum utilization of the Green River oil shale found in Colorado, Utah, and Wyoming, at depths ranging from outcrops to several thousand feet, requires development of several methods of processing. Early research was devoted to developing processes for application to oil shale occurring at depths suitable for mining. In present research, the emphasis is on in situ retorting and recovery processes that would be more satisfactory for oil shales occurring at greater depths. Development of an in situ process depends upon finding or establishing sufficient permeability in the oil shale beds for the passage of fluids which serve as a heat carrier in bringing the oil shale to retorting temperature. Use of a nuclear explosive seems to offer the best chance for successfully fracturing the thicker and more deeply buried portions of the deposit to give the required permeability. Processing the very large quantity of broken and fractured oil shale that would be produced presents many problems which require new background data for their solution. This paper describes research the Bureau of Mines is conducting to develop pertinent data. Primarily this research involves laboratory determination of properties of oil shale, pilot scale investigation of retorting characteristics of ungraded broken shale, and underground combustion of shale fractured by pressure and chemical explosives. Application of the research results should aid in designing the oil recovery phase and provide an estimate of the quantity of oil that may be obtained in a nuclear experiment in oil shale. (author)

  9. Morality and Nuclear Energy : Perceptions of Risks and Benefits, Personal Norms, and Willingness to Take Action Related to Nuclear Energy

    NARCIS (Netherlands)

    de Groot, Judith I. M.; Steg, Linda

    We examined factors underlying people's willingness to take action in favor of or against nuclear energy from a moral perspective. We conducted a questionnaire study among a sample of the Dutch population (N = 123). As expected, perceptions of risks and benefits were related to personal norms (PN),

  10. Numerical simulation design of nuclear safety related expansion muffler

    International Nuclear Information System (INIS)

    Huang Bingchen; Shen Wei; Yang Tieming; Luo Jianping; Jing Feng

    2014-01-01

    According to the working conditions and technical requirements for pipe discharge muffler in passive nuclear power plant, the numerical simulation was used in analyzing sound transmission loss and fluid pressure loss of multi-section expansion muffler by finite element analysis (FEA) software ANSYS. The effect of different muffler structural parameters on sound transmission loss, passing frequency and pressure loss was also analyzed. Based on the analysis results, a reasonable combination of the muffler structural parameters was determined, and a pipe discharge muffler with good performance was obtained. (authors)

  11. Cost related to nuclear power plants: the international experience

    International Nuclear Information System (INIS)

    1995-03-01

    This report about the international costs of nuclear electricity generations is divided in two distinct parts: the first one shows the competitiveness of the main sources of electricity generation for base load operation according to studies carried on by OECD and UNIPEDE since 1983; the second one discusses the most recent OECD study about the different types of power plants to be constructed in its number states, based on the experience of each country and the technology evolution of the different fuels used. (F.E.). 4 refs, 2 figs, 27 tab

  12. Regulatory trends and practices related to nuclear reactor decommissioning

    International Nuclear Information System (INIS)

    Cantor, R.A.

    1984-01-01

    In the next several decades, the electric utility industry will be faced with the retirement of 50,000 megawatts (mW) of nuclear capacity. Responsibility for the financial and technical burdens this activity entails has been delegated to the utilities operating the reactors. However, the operators will have to perform the tasks of reactor decommissioning within the regulatory environment dictated by federal, state and local regulations. The purpose of this paper is to highlight some of the current and likely trends in regulations and regulatory practices that will significantly affect the costs, technical alternatives and financing schemes encountered by the electric utilities and their customers

  13. Nuclear and related techniques in the control of communicable diseases

    International Nuclear Information System (INIS)

    1991-07-01

    The IAEA has a programme component entitled ''Nuclear Techniques in Communicable Diseases'', the aims of which are to encourage research in the development of new methods of controlling communicable diseases and to transfer the technology to institutes in endemic regions. Implementation of the programme component includes information exchange through publications, symposiums and seminars. The two most recent seminars were held in Bombay in November 1988 and Belo Horizonte in November 1989, and a selection of the papers presented have been published in this Technical Document. Refs, figs and tabs

  14. NESSY, a relational PC database for nuclear structure and decay data

    International Nuclear Information System (INIS)

    Boboshin, I.N.; Varlamov, V.V.; Trukhanov, S.K.

    1994-11-01

    The universal relational database NESSY (New ENSDF Search SYstem) based on the international ENSDF system (Evaluated Nuclear Structure Data File) is described. NESSY, which was developed for IBM compatible PC, provides high efficiency processing of ENSDF information for searches and retrievals of nuclear physics data. The principle of the database development and examples of applications are presented. (author)

  15. Note n. SD3-DEM-01 regulations procedures relative to the based nuclear installations dismantling

    International Nuclear Information System (INIS)

    2003-02-01

    This note aims to define the regulations procedures relative to the safety of based nuclear installations dismantling defined by the decree of the 11 december 1963 modified. The first part describes the two main phases of a based nuclear installation life, the operating and the dismantling phase. The second part is devoted to the procedures. (A.L.B.)

  16. Underwater inspection and maintenance programs within nuclear and non-nuclear related operating systems

    International Nuclear Information System (INIS)

    Vallance, C.; Goulet, B.; Black, S.

    2008-01-01

    The increasing age of the nuclear and non-nuclear power generating facilities requires extended inspection, repair and maintenance (IRM) activities to prolong the operation of these facilities past their original design life. Commercial divers are often utilized to perform critical work at nuclear power plants, fuel reprocessing plants, waste storage facilities, and research institutions. These various tasks include inspection, welding, mechanical modifications and repairs, coating applications, and work associated with plant decommissioning. Programs may take place in areas such as the reactor vessel, equipment pool, spent fuel pool, and suppression chamber using manned intervention and remotely operated vehicles. Some of these tasks can also be conducted using remotely operated vehicles (ROV's). Although specialist robots are not uncommon to the nuclear industry, the use of free-swimming vehicle's and remote systems for the inspection of underwater assets has increased due to improvements of the supporting technologies and information requirements needed to extend the life of these facilities. This paper will provide an overview of the procedures and equipment necessary to perform unique work tasks using manned and unmanned techniques. (author)

  17. Coordination chemistry of technetium as related to nuclear medicine

    International Nuclear Information System (INIS)

    Srivastava, S.C.; Richards, P.

    1982-01-01

    Significant advances have been made in the area of technetium coordination chemistry during the last five years. The main driving force behind this recent surge of interest in the field has been due to the practical application of technetium-99m in the rapidly growing speciality of nuclear medicine. Technetium-99 is one of the products of nuclear fission reactions, but it was the development of the molybdenum-99-technetium-99m generator about two decades ago that provided the basis for the development of radiopharmaceuticals routinely used in modern diagnostic applications. The chemistry of this element has proven to be quite rich owing to its multiple oxidation states and variable geometry. This can be attributed to its position in the middle of the periodic table. Diagnostic radiopharmaceuticals comprise predominantly III, IV and V oxidation states of Tc and involve a variety of coordination complexes. Even though the chemistry of Tc has been slow to evolve, recent synthetic advances have provided a more scientific basis for the study of a number of compounds with diverse coordination geometries and structures. Ligands with oxygen, nitrogen and sulfur donor atoms have been utilized to elucidate various aspects of the coordination chemistry of Tc. Single crystal X-ray structural analysis has been extensively used to characterize Tc complexes and thus construct a firm foundation for the study of synthetic and mechanistic aspects of the chemistry of this element. (author)

  18. The approach of nuclear related issues by the press

    International Nuclear Information System (INIS)

    Manetti, Cristiane Teixeira; Tanimoto, Katia Suemi; Hiromoto, Goro

    2009-01-01

    Nuclear energy has always been a polemic issue, and it is usually more intensely associated, by the general public, to the risks than to the benefits from its use; in this sense, the mass media have clearly had its share of responsibility for public opinion formation. This paper presents a report on the coverage of the nuclear issue in the press, identifying the amount of negative and positive views on the subject, as well as the people involved in the process. The analysis comprises the period from February 2007 to February 2008, right after the edition of the 4th IPCC Report. From that sample, 172 texts published in widely known newspapers and magazines, most of them from Sao Paulo State, were identified. The analyzed speeches were classified according to five information sources: specialists, users, authorities, protagonists and entrepreneurs. It was noted the predominance of positive articles, mainly due to the weight of the favorable speeches by authorities, cited as the most frequent in this paper. (author)

  19. Nuclear spin dynamics in soap solutions and related systems

    International Nuclear Information System (INIS)

    Bloom, M.

    1973-01-01

    Soap molecules consist of a hydrophilic head and a hydrophobic lipid tail. For example, potassium laureate, the soap molecule on which the most complete study of nuclear spin dynamics has been made has the chemical formula KCOO(CH 2 ) 10 CH 3 . High concentration (greater than or approximately equal to 20% soap molecules by weight) soap solutions in water form ordered, liquid crystal structures in which the polar heads are arranged on regular surfaces which define a lattice having long range order. The soap molecules diffuse very rapidly parallel to the surfaces and undergo rapid conformational changes. Studies of T 1 , Tsub(1p) and Tsub(D) have indicated a wide spectrum of correlation times associated with these changes. Because of the orientational order of the soap molecules, the dipolar interactions between nuclear spins on a single molecule are not averaged to zero by the molecular motions. Thus, it is possible to use NMR techniques normally applied to solids (i.e. transfer of Zeeman into dipolar order, etc.) to study their static and dynamical properties. These systems are unusual in that they are basically one-dimensional systems in which the effective, time-averaged, dipolar coupling constants become progressively stronger for protons closer to the polar heads ot the molecules. A review will be presented of the experimental and theoretical NMR work performed on such systems to date. (author)

  20. The approach of nuclear related issues by the press

    Energy Technology Data Exchange (ETDEWEB)

    Manetti, Cristiane Teixeira; Tanimoto, Katia Suemi; Hiromoto, Goro [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: cristianemanetti@hotmail.com, e-mail: katia_tanimoto@hotmail.com, e-mail: hiromoto@ipen.br

    2009-07-01

    Nuclear energy has always been a polemic issue, and it is usually more intensely associated, by the general public, to the risks than to the benefits from its use; in this sense, the mass media have clearly had its share of responsibility for public opinion formation. This paper presents a report on the coverage of the nuclear issue in the press, identifying the amount of negative and positive views on the subject, as well as the people involved in the process. The analysis comprises the period from February 2007 to February 2008, right after the edition of the 4th IPCC Report. From that sample, 172 texts published in widely known newspapers and magazines, most of them from Sao Paulo State, were identified. The analyzed speeches were classified according to five information sources: specialists, users, authorities, protagonists and entrepreneurs. It was noted the predominance of positive articles, mainly due to the weight of the favorable speeches by authorities, cited as the most frequent in this paper. (author)

  1. Safety related requirements on future nuclear power plants

    International Nuclear Information System (INIS)

    Niehaus, F.

    1991-01-01

    Nuclear power has the potential to significantly contribute to the future energy supply. However, this requires continuous improvements in nuclear safety. Technological advancements and implementation of safety culture will achieve a safety level for future reactors of the present generation of a probability of core-melt of less than 10 -5 per year, and less than 10 -6 per year for large releases of radioactive materials. There are older reactors which do not comply with present safety thinking. The paper reviews findings of a recent design review of WWER 440/230 plants. Advanced evolutionary designs might be capable of reducing the probability of significant off-site releases to less than 10 -7 per year. For such reactors there are inherent limitations to increase safety further due to the human element, complexity of design and capability of the containment function. Therefore, revolutionary designs are being explored with the aim of eliminating the potential for off-site releases. In this context it seems to be advisable to explore concepts where the ultimate safety barrier is the fuel itself. (orig.) [de

  2. Nuclear-related budget for fiscal 1982 increased by 7.1 %

    International Nuclear Information System (INIS)

    1982-01-01

    In the budget draft for fiscal 1982, highest priority is given to the cost of energy countermeasures, and 563,200 million yen is earmarked, which is 13.2 % increase as compared with the budget for 1981. Emphasis is placed on the stable supply of oil and the development of the alternative sources of energy. The main pillar of the measures for alternative energy sources is nuclear power development. 290,448 million yen is allocated to the nuclearrelated budget, which is 7.1 % increase as compared with that for 1981. Besides, in order to develop overseas uranium resources and to promote nuclear fuel cycle industries and the domestic production of nuclear power equipments, the fiscal loans and investments of 159,000 million yen are available. The budget draft for the nuclear power development in the Science and Technology Agency is 243,038 million yen, which amounts to 83.7 % of the nuclear-related budget mentioned above. The budget for the STA is roughly classified into the expansion and reinforcement of nuclear safety measures, the establishment of nuclear fuel cycle, the development of advenced power reactors, the R and D on nuclear fusion and HTGRs, the R and D on nuclear ships, the smooth siting of nuclear facilities, etc. (Kako, I.)

  3. Present situation and problems of nuclear-security-related legislation in Japan

    International Nuclear Information System (INIS)

    Irie, Kazutomo

    2013-01-01

    This paper shows surveys of current Japanese regulations relevant to nuclear security, including regulations for nuclear damage compensation. It also shows the regulatory issues still left unresolved, particularly the question of whether existing laws are broad enough, or whether new legislation will be needed. The largest unresolved issue is how to establish a system of physical protection of nuclear materials for broader nuclear security purposes within a system that was originally introduced only to control nuclear proliferation. Such a system will necessitate a radical revision of the relevant law. Moreover, the current regulations have left unresolved the physical protection of radioactive materials used in research, medical, and non-nuclear-power-related industrial operations. Japanese legislation has already authorized an integrated Nuclear Regulatory Commission. Its mandate should include introduction of a physical protection system for currently unregulated radioactive materials. This will also necessitate a radical revision of the relevant law. Comprehensive consideration should also be given to transportation of nuclear materials away from the site of nuclear material processing businesses. Current regulation also leaves this issue unresolved. There is a possibility that consistent protective measures may not be possible across transportation modes even under the recent legislation that authorized reorganization of nuclear regulatory authorities. (author)

  4. Estimation of the fiscal year 1985 expenditures in nuclear energy relation

    International Nuclear Information System (INIS)

    1985-01-01

    In Japan, the electric power by nuclear energy accounts for about 20 % of the total power at present. Then, radiation is utilized extensively in such fields as industries, agriculture and medicine. The expenditures (budgets) estimated for the fiscal year 1985 are about 343.8 billion yen plus contract authorization limitation about 146.7 billion yen. In connection with the expenditures estimation (of which a breakdown is given in tables), the research and development plans for nuclear energy relation for fiscal year 1985 are presented: strengthening in nuclear energy safety, promotion of nuclear power generation, establishment of the nuclear fuel cycle, development of advanced power reactors, research on nuclear fusion, promotion of radiation utilizations, strengthening in the research and development infrastructure, promotion of international cooperation, etc. (Mori, K.)

  5. Nuclear-related training and education offered by academic institutions (less-than-baccalaureate degree)

    International Nuclear Information System (INIS)

    Howard, L.

    1982-01-01

    Current projections indicate that in addition to the 10,100 technician positions and 6100 existing operator positions in the nuclear power industry, another 9100 technicians and 9700 operators will be required over the next decade. With 56 nuclear plants currently in operation and an additional 35 plants under construction, it is essential that trained technical personnel be available for employment in the nuclear utilities. Because of the growing demand for technicians in the nuclear utility industry, this report has been prepared to identify the nuclear-related, less-than-baccalaureate, technical educational programs provided by academic institutions and to ascertain both the current number of students and the maximum number that could be trained, given present staff and facilities. The data serve as a gauge for the proportion of technician training required by the nuclear industry that can be provided by academic institutions

  6. Global nuclear renaissance - today's issues, challenges and differences relative to the first wave of nuclear plant projects

    International Nuclear Information System (INIS)

    Gardner, William N.

    2010-01-01

    The development and negotiation of an Engineering, Procurement and Construction (EPC) contract is a multi-disciplined and time consuming process. Relative to the first wave on new nuclear build projects of the 1950's - 1970's, today's EPC contracts are more complex for a variety of reasons including more demanding regulatory and environmental requirements, global supply chain versus localization issues and different world wide economic considerations. This paper discusses the impacts of some of these challenges on developing an EPC contract in today's Nuclear Renaissance. (authors)

  7. Commercial grade item (CGI) dedication of generators for nuclear safety related applications

    International Nuclear Information System (INIS)

    Das, R.K.; Hajos, L.G.

    1993-01-01

    The number of nuclear safety related equipment suppliers and the availability of spare and replacement parts designed specifically for nuclear safety related application are shrinking rapidly. These have made it necessary for utilities to apply commercial grade spare and replacement parts in nuclear safety related applications after implementing proper acceptance and dedication process to verify that such items conform with the requirements of their use in nuclear safety related application. The general guidelines for the commercial grade item (CGI) acceptance and dedication are provided in US Nuclear Regulatory Commission (NRC) Generic Letters and Electric Power Research Institute (EPRI) Report NP-5652, Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications. This paper presents an application of these generic guidelines for procurement, acceptance, and dedication of a commercial grade generator for use as a standby generator at Salem Generating Station Units 1 and 2. The paper identifies the critical characteristics of the generator which once verified, will provide reasonable assurance that the generator will perform its intended safety function. The paper also delineates the method of verification of the critical characteristics through tests and provide acceptance criteria for the test results. The methodology presented in this paper may be used as specific guidelines for reliable and cost effective procurement and dedication of commercial grade generators for use as standby generators at nuclear power plants

  8. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  9. Review of the total system related to operation of nuclear-powered ship

    International Nuclear Information System (INIS)

    Takamasa, Tomoji; Miyashita, Kunio

    2000-01-01

    It is essential to establish a marine reactor having excellent safety and reliability, which is capable of competing economically with conventional ships, and which can be accepted by international society, in order to be prepared for practical application of future nuclear-powered ships. For this purpose, it is important not only to demonstrate a marine reactor using a model or test device to simulate actual operation, but also to establish the environmental requirements for operation of a nuclear-powered ship, such as safety standards that are operationally and internationally common for ships, and to establish a repair base for nuclear-powered ships. Systems research for the practical application of nuclear-powered ships was conducted for five years, fiscal years 1992 through 1996, by a group in the Japan Atomic Energy Research Institute (JAERI), under the project title 'Review of the total system related to operation of nuclear-powered ships.' The project sought to summarize requirements for the practical application of nuclear-powered ships from the standpoint of the need side, e.g., what nuclear-powered ships will be requested, and what functions will be provided under the expected future social environment; to show a complete system concept for the operation of nuclear-powered ships; and to clarify the situations creating demand for nuclear-powered ships, as well as the system and environmental conditions to be established for operation of practical nuclear-powered ships. Study considerations included the size of the operation system for a nuclear-powered ship, a scenario for introducing a nuclear-powered container ship, and economic evolution from the effects on the whole shipping system, based on container ships, of introducing a nuclear-powered ship. The results of these considerations were made the framework for constructing an entire system and evaluating its economy. The treatment and disposal of radioactive waste from a nuclear-powered ship, and the

  10. OECD/NEA Ongoing activities related to the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Cornet, S.M.; McCarthy, K.; Chauvin, N.

    2013-01-01

    As part of its role in encouraging international collaboration, the OECD Nuclear Energy Agency is coordinating a series of projects related to the Nuclear Fuel Cycle. The Nuclear Science Committee (NSC) Working Party on Scientific Issues of the Nuclear Fuel Cycle (WPFC) comprises five different expert groups covering all aspects of the fuel cycle from front to back-end. Activities related to fuels, materials, physics, separation chemistry, and fuel cycles scenarios are being undertaken. By publishing state-of-the-art reports and organizing workshops, the groups are able to disseminate recent research advancements to the international community. Current activities mainly focus on advanced nuclear systems, and experts are working on analyzing results and establishing challenges associated to the adoption of new materials and fuels. By comparing different codes, the Expert Group on Advanced Fuel Cycle Scenarios is aiming at gaining further understanding of the scientific issues and specific national needs associated with the implementation of advanced fuel cycles. At the back end of the fuel cycle, separation technologies (aqueous and pyrochemical processing) are being assessed. Current and future activities comprise studies on minor actinides separation and post Fukushima studies. Regular workshops are also organized to discuss recent developments on Partitioning and Transmutation. In addition, the Nuclear Development Committee (NDC) focuses on the analysis of the economics of nuclear power across the fuel cycle in the context of changes of electricity markets, social acceptance and technological advances and assesses the availability of the nuclear fuel and infrastructure required for the deployment of existing and future nuclear power. The Expert Group on the Economics of the Back End of the Nuclear Fuel Cycle (EBENFC), in particular, is looking at assessing economic and financial issues related to the long term management of spent nuclear fuel. (authors)

  11. Identification of High Confidence Nuclear Forensics Signatures. Results of a Coordinated Research Project and Related Research

    International Nuclear Information System (INIS)

    2017-08-01

    The results of a Coordinated Research Project and related research on the identification of high confidence nuclear forensic isotopic, chemical and physical data characteristics, or signatures, provides information on signatures that can help identify the origin and history of nuclear and other radioactive material encountered out of regulatory control. This research report compiles findings from investigations of materials obtained from throughout the nuclear fuel cycle to include radioactive sources. The report further provides recent results used to identify, analyse in the laboratory, predict and interpret these signatures relative to the requirements of a nuclear forensics examination. The report describes some of the controls on the incorporation and persistence of these signatures in these materials as well as their potential use in a national system of identification to include a national nuclear forensics library.

  12. Final argument relating to the Canadian nuclear power program

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1978-05-01

    This report is the second brief, and one of a number of documents, submitted by Atomic Energy of Canada Limited (AECL) to the Ontario Royal Commission on Electric Power Planning. It is intended to update the original brief (AECL--5800) with respect to those matters that emerged during the course of the hearings and which had not been fully anticipated in that brief, as well as to summarize the AECL position on the various issues. To enable it to qualify as a ''final argument'' it contains only evidence or material that has been presented to the Royal Commission and is provided with marginal notations identifying the source of each section. It is AECL's position that the Canadian nuclear power program provides a safe, proven and efficient means of making a needed contribution to electricity supply, while strengthening the economy through the deployment of indigenous technology and resources. (author)

  13. Elevated temperature weldment behavior as related to nuclear design criteria

    International Nuclear Information System (INIS)

    King, R.T.; Canonico, D.A.; Brinkman, C.R.

    1975-01-01

    Factors affecting the physical and mechanical properties of weldments are reviewed. Data are presented that show wide variability in the properties of weld metal and heat-affected zones both within a given weldment and from weldment to weldment. The weld metal or heat-affected zone may be stronger or weaker, and more or less ductile than the base metal joined. This implies that current design rules, which are presumed to have well-known safety factors based on the properties of base metals, may have other actual safety factors in welded construction, due to the differences between weld metal and base metal properties. Suggestions for obtaining further data that can subsequently be used to improve confidence in design rules or to change design rules for nuclear application are presented

  14. Manual on quality assurance for computer software related to the safety of nuclear power plants

    International Nuclear Information System (INIS)

    1988-01-01

    The objective of the Manual is to provide guidance in the assurance of quality of specification, design, maintenance and use of computer software related to items and activities important to safety (hereinafter referred to as safety related) in nuclear power plants. This guidance is consistent with, and supplements, the requirements and recommendations of Quality Assurance for Safety in Nuclear Power Plants: A Code of Practice, 50-C-QA, and related Safety Guides on quality assurance for nuclear power plants. Annex A identifies the IAEA documents referenced in the Manual. The Manual is intended to be of use to all those who, in any way, are involved with software for safety related applications for nuclear power plants, including auditors who may be called upon to audit management systems and product software. Figs

  15. Morality and nuclear energy: perceptions of risks and benefits, personal norms, and willingness to take action related to nuclear energy.

    Science.gov (United States)

    De Groot, Judith I M; Steg, Linda

    2010-09-01

    We examined factors underlying people's willingness to take action in favor of or against nuclear energy from a moral perspective. We conducted a questionnaire study among a sample of the Dutch population (N = 123). As expected, perceptions of risks and benefits were related to personal norms (PN), that is, feelings of moral obligation toward taking action in favor of or against nuclear energy. In turn, PN predicted willingness to take action. Furthermore, PN mediated the relationships between perceptions of risk and benefits and willingness to take action. In line with our hypothesis, beliefs about the risks and benefits of nuclear energy were less powerful in explaining PN for supporters compared to PN of opponents. Also, beliefs on risks and benefits and PN explained significantly more variance in willingness to take action of opponents than of supporters. Our results suggest that a moral framework is useful to explain willingness to take action in favor of and against nuclear energy, and that people are more likely to protest in favor of or against nuclear energy when PN are strong. © 2010 Society for Risk Analysis.

  16. Public relations activities of the Service Hall for Kashiwazaki-Kariwa Nuclear Power Station

    International Nuclear Information System (INIS)

    Kono, T.

    1998-01-01

    This article includes information of the Service Hall for Kashiwazaki-Kariwa Nuclear Power Station. About 30% of the total electricity production in Japan is due to 16 power stations and 52 reactors. The service hall is a kind of atomic power pavilion for public relations. In Japan, each nuclear power station has such a pavilion, which acts a a center of public relations activities for the atomic power. (S. Grainger)

  17. Research study on public relations and public participation in the nuclear energy field

    International Nuclear Information System (INIS)

    Gunji, Ikuko; Tabata, Rimiko; Otoshi, Sachio; Kuwagaki, Reiko; Ishibashi, Yoichiro

    2006-01-01

    The purpose of this research is to clarify the effect of public relations activities in the nuclear energy field and public participation toward the improvement of the risk literacy of nuclear energy. According to the survey results of the actual public relations activities taken by nuclear energy industry, the opportunity for interactive communications between the public and the industry is insufficient. Consequently, we propose building up more opportunities for participation and collaboration of citizens and industries in order to improve interactive communications reflecting public opinions and points of view. (author)

  18. Public opinion on age-related degradation in nuclear power plants

    International Nuclear Information System (INIS)

    Matsuda, Toshihiro

    2005-01-01

    The first objective of this study is to shed light on the public opinion on age-related degradation at nuclear power plants, namely, on how the general public recognizes or views age-related degradation, which is a safety-related issue and one of the factors contributing to accidents and failures which occur at nuclear power plants. The second objective is to look into the impacts of the accident at Mihama Unit 3, which was caused by a failure to check on the piping wall thickness, on the public opinion on age-related degradation. The first survey was conducted in August 2003, followed by the second survey in October 2004, two months after the accident. The surveys found that the age-related degradation is being perceived by people as one of the risk factors that affect the safety of nuclear power plants. The characteristics of the citizens' perceptions toward age-related degradation in the form of piping cracks are that: (a) many respondents feel uneasy but a relatively few people consider that nuclear operators are technologically capable of coping with this problem; (b) many people believe that radioactivity may be released; and (c) numerous respondents consider that signs of cracks must be thoroughly detected through inspections, while on the other hand, a large percentage of the respondents attribute the accident to improper inspections/maintenance. Based on these results, the government and nuclear operators are expected to give most illuminating explanation on the current situation of and remedial measures against age-related degradation at nuclear power plants. As for the effects of the Mihama-3 accident on the public opinion on age-related degradation, it was revealed that the accident has not so significantly affected the general view for the safety of nuclear power plants, but has newly or strongly aroused people's consciousness of two of the risk factors - improper inspections/maintenance and the age-related degradation of piping. (author)

  19. Design related aspects in advanced nuclear fission plants

    International Nuclear Information System (INIS)

    Hoffelner, Wolfgang

    2011-01-01

    Important issues to be considered for design of future reactors are: extrapolation of stress rupture data, creep-fatigue, negligible creep, damage monitoring. The paper highlights some new developments taking examples from a martensitic steel (mod 9% Cr), oxide dispersion strengthened (ODS) steels and nickel-base superalloys. Traditional approaches to extrapolation of (thermal) stress rupture data like Larson-Miller Parameter or Monkman-Grant rule seem to be valid concepts also for advanced reactors. However, a significant influence of cyclic softening on creep rates and stress rupture data can be expected as shown for grade 91. This is particularly true for creep-fatigue interactions. Based on cyclic stress-strain behaviour it is also possible to get very good life-time predictions under creep-fatigue with a strain range separation (inelastic fatigue and creep ranges) technique which could replace the currently used linear life fraction rule. Results from in-beam irradiation creep reveal no significant influence of dispersoid size. It can be assumed that irradiation creep is a matrix property. Finally it is shown that micro-sample testing of exposed material could be used as an advanced method for damage assessment in future nuclear power plants.

  20. Effectiveness of cleanup criteria relative to an accidental nuclear release

    International Nuclear Information System (INIS)

    Chen, S.Y.; Yuan, Y.C.

    1988-01-01

    In the event of an accidental nuclear release, the associated long-term radiological risks would result primarily from ground contamination pathways. Cleanup of the contaminated ground surfaces is a necessary step toward reducing the radiological risk to the general population. Ideally, the radiological risk decreases as the level of cleanup effort increases; however, as the cleanup criterion (i.e., the required contaminant concentration after cleanup) becomes more stringent, the cleanup effort may become prohibitively costly. This study examines several factors that are important in determining the effectiveness of the cleanup criteria for selected radionuclides: (a) annual individual dose commitment (mrem/yr), (b) total population environmental dose commitment (person-rem), and (c) total area (km 2 ) requiring cleanup following an accident. To effectively protect the general population, the benefits of cleanup should be weighed against the potentially large increase in cleanup area (and the associated costs) as the cleanup criterion becomes more stringent. The effectiveness of cleanup will vary, depending largely on site-specific parameters such as population density and agricultural productivity as well as on the amount and type of radionuclide released. Determination of an optimum cleanup criterion should account for all factors, including a comprehensive cost/benefit analysis

  1. Management of age-related degradation for nuclear power plants

    International Nuclear Information System (INIS)

    Gregor, Frank E.

    2004-01-01

    Life extension for nuclear power plants has been studied in the USA for the last six years, largely supported by EPRI, DOE and the USNRC. Though there are diverse opinions for the strategies and priorities of life extension and aging management, one common conclusion has been formulated regarding the need of current maintenance programs having to focus on aging and degradation management. Such program, called 'Maintenance Effectiveness Evaluation and Enhancement' or M3E for short, has been developed to assist plant operators to upgrade and enhance existing programs by integrating aging/degradation management activities for important or critical equipment and components. The key elements of the M3E program consist of the definition and selection of the critical components or commodities to be included in the scope, the survey/inventory of the current programs and their respective action steps, frequencies, corrective measures and extent of coverage, the component/commodity degradation mechanism, sites and severity, safety functions and service environments and lastly, the correlation of degradation/aging with the individual maintenance activities. The degree of correlation provides a measure of effectiveness and the opportunity to identify/specify needed enhancements, abandonment or generation of new maintenance activities. Implementation of the activities can then be prioritized at the option of the plant staff. (author)

  2. 25 CFR 170.900 - What is the purpose of the provisions relating to transportation of hazardous and nuclear waste?

    Science.gov (United States)

    2010-04-01

    ... transportation of hazardous and nuclear waste? 170.900 Section 170.900 Indians BUREAU OF INDIAN AFFAIRS... and Nuclear Waste Transportation § 170.900 What is the purpose of the provisions relating to transportation of hazardous and nuclear waste? Sections 170.900 through 170.907 on transportation of nuclear and...

  3. Impacts of age-related failures on nuclear systems

    International Nuclear Information System (INIS)

    Meale, B.M.; Satterwhite, D.G.; Krantz, E.A.; MacDonald, P.E.

    1986-01-01

    Aging-related failure data from nine light water reactor safety, support, and power conversion systems have been extracted from an operational data base. Systems and components within the systems that are most affected by aging are identified. In addition, information on aging-related root causes of component failures has been extracted for service water and Class 1E electrical power distribution systems. Engineering insights are presented, and preliminary quantification of the importance of aging-related root causes for a service water system is provided

  4. 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.)

  5. A study on the establishment of nuclear cooperative relations and future direction between Korea and Egypt

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-10-01

    This study was carried out in order to review the cooperation with Egypt and establish and activate the cooperative relations with Egypt. Recent policy trends in the use and development of nuclear energy in Egypt, were investigated including introduction of nuclear power plant, and cooperative relations between two nations were also established under the implementation of the project. It was agreed through exchanges of visits of nuclear cooperation delegation; 1) exchange of visits of cooperation delegation, 2) invitation of egypt experts to policy seminar 3) cooperation between relevant nuclear related organizations of two countries, 4) future cooperation fields and directions between two countries. It is recommended that cooperation with Egypt be implemented systematically through the long term based on national basic cooperation directions and integrated strategies.

  6. A study on the establishment of nuclear cooperative relations and future direction between Korea and Egypt

    International Nuclear Information System (INIS)

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

    2000-10-01

    This study was carried out in order to review the cooperation with Egypt and establish and activate the cooperative relations with Egypt. Recent policy trends in the use and development of nuclear energy in Egypt, were investigated including introduction of nuclear power plant, and cooperative relations between two nations were also established under the implementation of the project. It was agreed through exchanges of visits of nuclear cooperation delegation; 1) exchange of visits of cooperation delegation, 2) invitation of egypt experts to policy seminar 3) cooperation between relevant nuclear related organizations of two countries, 4) future cooperation fields and directions between two countries. It is recommended that cooperation with Egypt be implemented systematically through the long term based on national basic cooperation directions and integrated strategies

  7. Experience on environmental qualification of safety-related components for Darlington Nuclear Generating Station

    International Nuclear Information System (INIS)

    Yu, A.S.; Kukreti, B.M.

    1987-01-01

    The proliferation of Nuclear Power Plant safety concerns has lead to increasing attention over the Environmental Qualification (EQ) of Nuclear Power Plant Safety-Related Components to provide the assurance that the safety related equipment will meet their intended functions during normal operation and postulated accident conditions. The environmental qualification of these components is also a Licensing requirement for Darlington Nuclear Generating Station. This paper provides an overview of EQ and the experience of a pilot project, in the qualification of the Main Moderator System safety-related functions for the Darlington Nuclear Generating Station currently under construction. It addresses the various phases of qualification from the identification of the EQ Safety-Related Components List, definition of location specific service conditions (normal, adbnormal and accident), safety-related functions, Environmental Qualification Assessments and finally, an EQ system summary report for the Main Moderator System. The results of the pilot project are discussed and the methodology reviewed. The paper concludes that the EQ Program developed for Darlington Nuclear Generating Station, as applied to the qualification of the Main Moderator System, contained all the elements necessary in the qualification of safety-related equipment. The approach taken in the qualification of the Moderator safety-related equipment proves to provide a sound framework for the qualification of other safety-related components in the station

  8. UPDATED MASS SCALING RELATIONS FOR NUCLEAR STAR CLUSTERS AND A COMPARISON TO SUPERMASSIVE BLACK HOLES

    International Nuclear Information System (INIS)

    Scott, Nicholas; Graham, Alister W.

    2013-01-01

    We investigate whether or not nuclear star clusters and supermassive black holes (SMBHs) follow a common set of mass scaling relations with their host galaxy's properties, and hence can be considered to form a single class of central massive object (CMO). We have compiled a large sample of galaxies with measured nuclear star cluster masses and host galaxy properties from the literature and fit log-linear scaling relations. We find that nuclear star cluster mass, M NC , correlates most tightly with the host galaxy's velocity dispersion: log M NC = (2.11 ± 0.31)log (σ/54) + (6.63 ± 0.09), but has a slope dramatically shallower than the relation defined by SMBHs. We find that the nuclear star cluster mass relations involving host galaxy (and spheroid) luminosity and stellar and dynamical mass, intercept with but are in general shallower than the corresponding black hole scaling relations. In particular, M NC ∝M 0.55±0.15 Gal,dyn ; the nuclear cluster mass is not a constant fraction of its host galaxy or spheroid mass. We conclude that nuclear stellar clusters and SMBHs do not form a single family of CMOs.

  9. Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods

    Science.gov (United States)

    Mariani, Robert Dominick

    2014-09-09

    Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350.degree. C. to 750.degree. C., and a second additive having a solubility in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350.degree. C. to 750.degree. C. and a solubility of the second additive in the first additive over the temperature range extending from 350.degree. C. to 750.degree. C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

  10. Efficient algorithms for flow simulation related to nuclear reactor safety

    International Nuclear Information System (INIS)

    Gornak, Tatiana

    2013-01-01

    Safety analysis is of ultimate importance for operating Nuclear Power Plants (NPP). The overall modeling and simulation of physical and chemical processes occuring in the course of an accident is an interdisciplinary problem and has origins in fluid dynamics, numerical analysis, reactor technology and computer programming. The aim of the study is therefore to create the foundations of a multi-dimensional non-isothermal fluid model for a NPP containment and software tool based on it. The numerical simulations allow to analyze and predict the behavior of NPP systems under different working and accident conditions, and to develop proper action plans for minimizing the risks of accidents, and/or minimizing the consequences of possible accidents. A very large number of scenarios have to be simulated, and at the same time acceptable accuracy for the critical parameters, such as radioactive pollution, temperature, etc., have to be achieved. The existing software tools are either too slow, or not accurate enough. This thesis deals with developing customized algorithm and software tools for simulation of isothermal and non-isothermal flows in a containment pool of NPP. Requirements to such a software are formulated, and proper algorithms are presented. The goal of the work is to achieve a balance between accuracy and speed of calculation, and to develop customized algorithm for this special case. Different discretization and solution approaches are studied and those which correspond best to the formulated goal are selected, adjusted, and when possible, analysed. Fast directional splitting algorithm for Navier-Stokes equations in complicated geometries, in presence of solid and porous obstacles, is in the core of the algorithm. Developing suitable pre-processor and customized domain decomposition algorithms are essential part of the overall algorithm amd software. Results from numerical simulations in test geometries and in real geometries are presented and discussed.

  11. The Nuclear Shell Model and its Relation with Other Nuclear Models

    Energy Technology Data Exchange (ETDEWEB)

    Elliott, J. P. [University of Sussex, Brighton (United Kingdom)

    1963-01-15

    The starting point of all versions of the shell model is the physical idea that the interaction between a given nucleon and all the others resembles that between a nucleon and a fixed field. From this starting point one might attempt to construct a field which is self-consistent but this approach is not followed in most shell-model calculations because of the complications that arise. The more usual approach has been to use the idea of an average field to provide a complete set of sin gle-particle wave functions. Then, if the parameters of the field (e.g. its size) are correctly chosen, we would expect to reach a good approximation to the nuclear-wave function by taking that configuration of single-particle wave functions which has lowest energy in this field. The wave functions could clearly be improved by allowing the mixing of excited configurations but this is rarely done because of the resulting complexity of the problem. Even in the lowest configuration there are in general many independent wave functions for a many-particle system which would all be degenerate in the average field. To find the nuclear energy levels and wave functions we must therefore build up the energy matrix in this degenerate set, using the inter-nucleon two-body forces, and then diagonalize this matrix. If the detailed form of the nuclear forces was known we might regard such calculations as the first step towards an exact calculation in which higher configurations were included but every indication is that the convergence would be extremely slow. It is more usual to treat an energy calculation in the lowest configuration unashamedly as a model calculation and to attempt to deduce, by comparisons with experimental data in the many-particle nuclei, the nature of the effective nuclear forces required in that configuration. If the model is realistic then we should not expect these effective forces to change very much in going from one nucleus to its neighbour and since there are many more

  12. Role of the nuclear envelope in the pathogenesis of age-related bone loss and osteoporosis

    Science.gov (United States)

    Vidal, Christopher; Bermeo, Sandra; Fatkin, Diane; Duque, Gustavo

    2012-01-01

    The nuclear envelope is the most important border in the eukaryotic cell. The role of the nuclear envelope in cell differentiation and function is determined by a constant interaction between the elements of the nuclear envelope and the transcriptional regulators involved in signal transcription pathways. Among those components of the nuclear envelope, there is a growing evidence that changes in the expression of A-type lamins, which are essential components of the nuclear lamina, are associated with age-related changes in bone affecting the capacity of differentiation of mesenchymal stem cells into osteoblasts, favoring adipogenesis and affecting the function and survival of the osteocytes. Overall, as A-type lamins are considered as the 'guardians of the soma', these proteins are also essential for the integrity and quality of the bone and pivotal for the longevity of the musculoskeletal system. PMID:23951459

  13. Status of the Romanian nuclear power program and the strategy related to the public information

    International Nuclear Information System (INIS)

    Stiopol, Mihaela; Chirica, Teodor

    1999-01-01

    The year 1997 represented for the Romanian nuclear power sector the year of the performances and capabilities proved Cernavoda NPP s unit operation, after one year of successful operation. Good performances of this unit could represent a positive impact on further development of nuclear power in Romania, considering first the completion of Unit 2 and for National Heavy Water Reactor Program. On the other hand, 'The years of 1997 and 1998 marked for the Romanian Electricity Authority a new and completely different perception of the Romanian power sector'. Recently, the first step of the restructuring of power sector has been accomplished. The Romanian Government approved the creation of the National Power Grid Company and the moving-out of the nuclear activities. The present Nuclear Power Group from RENEL was transformed in a separate entity, the National 'Nuclear Ellectrica' Company, including three subsidiaries, no legal persons, one for nuclear power production CNE-PROD (Cernavoda Unit 1), one for nuclear power development CNE-INVEST (Cernavoda Unit 2 to 5) and one for nuclear fuel fabrication FCN (Pitesti Nuclear Fuel Plant). The other Units from Nuclear Power Group, such as the Heavy Water Plant - ROMAG, Center of Technology and Engineering for Nuclear Projects - CTON and the Institute for Nuclear Research-Pitesti - ICN have been transformed in a state owned company for nuclear activities. To better understand the aspects related to the nuclear power in Romania and the necessity of the continuation and development of a public information strategy based on the new look of the nuclear power sector, please, allow me to present you a few things with regard the Romanian nuclear program. The main targets of Public Information Program Strategy considered when assessing the strategy related to the public information were: education and built-up of a credibility on the construction of a nuclear power plant in general, and of the Cernavoda NPP, in particular; and once

  14. Safety-Related Contractor Activities at Nuclear Power Plants. New Challenges for Regulatory Oversight

    Energy Technology Data Exchange (ETDEWEB)

    Chockie, Alan [Chockie Group International, Inc., Seattle, WA (United States)

    2005-09-15

    The use of contractors has been an integral and important part of the design, construction, operation, and maintenance of nuclear power plants. To ensure the safe and efficient completion of contracted tasks, each nuclear plant licensee has developed and refined formal contract management processes to meet their specific needs and plant requirements. Although these contract management processes have proven to be effective tools for the procurement of support and components tailored to the needs of nuclear power plants, contractor-related incidents and accidents have revealed some serious weaknesses with the implementation of these processes. Identifying and addressing implementation problems are becoming more complicated due to organizational and personnel changes affecting the nuclear power industry. The ability of regulators and licensees to effectively monitor and manage the safety-related performance of contractors will likely be affected by forthcoming organization and personnel changes due to: the aging of the workforce; the decline of the nuclear industry; and the deregulation of nuclear power. The objective of this report is to provide a review of current and potential future challenges facing safety-related contractor activities at nuclear power plants. The purpose is to assist SKI in establishing a strategy for the proactive oversight of contractor safety-related activities at Swedish nuclear power plants and facilities. The nature and role of contractors at nuclear plants is briefly reviewed in the first section of the report. The second section describes the essential elements of the contract management process. Although organizations have had decades of experience with the a contract management process, there remain a number of common implantation weaknesses that have lead to serious contractor-related incidents and accidents. These implementation weaknesses are summarized in the third section. The fourth section of the report highlights the

  15. Safety-Related Contractor Activities at Nuclear Power Plants. New Challenges for Regulatory Oversight

    International Nuclear Information System (INIS)

    Chockie, Alan

    2005-09-01

    The use of contractors has been an integral and important part of the design, construction, operation, and maintenance of nuclear power plants. To ensure the safe and efficient completion of contracted tasks, each nuclear plant licensee has developed and refined formal contract management processes to meet their specific needs and plant requirements. Although these contract management processes have proven to be effective tools for the procurement of support and components tailored to the needs of nuclear power plants, contractor-related incidents and accidents have revealed some serious weaknesses with the implementation of these processes. Identifying and addressing implementation problems are becoming more complicated due to organizational and personnel changes affecting the nuclear power industry. The ability of regulators and licensees to effectively monitor and manage the safety-related performance of contractors will likely be affected by forthcoming organization and personnel changes due to: the aging of the workforce; the decline of the nuclear industry; and the deregulation of nuclear power. The objective of this report is to provide a review of current and potential future challenges facing safety-related contractor activities at nuclear power plants. The purpose is to assist SKI in establishing a strategy for the proactive oversight of contractor safety-related activities at Swedish nuclear power plants and facilities. The nature and role of contractors at nuclear plants is briefly reviewed in the first section of the report. The second section describes the essential elements of the contract management process. Although organizations have had decades of experience with the a contract management process, there remain a number of common implantation weaknesses that have lead to serious contractor-related incidents and accidents. These implementation weaknesses are summarized in the third section. The fourth section of the report highlights the

  16. Significance of Alkali-Silica reaction in nuclear safety-related concrete structures

    International Nuclear Information System (INIS)

    Le Pape, Y.; Field, K.G.; Mattus, C.H.; Naus, D.J.; Busby, J.T.; Saouma, V.; Ma, Z.J.; Cabage, J.V.; Guimaraes, M.

    2015-01-01

    Nuclear Power Plant license renewal up to 60 years and possible life extension beyond has established a renewed focus on long-term aging of nuclear generating stations materials, and particularly, on concrete. Large irreplaceable sections of most nuclear generating stations include concrete components. The Expanded Materials Degradation Analysis, jointly performed by the Department of Energy, the U.S. Nuclear Regulatory Commission, the Academia and the Power Generation Industry, identified the need to develop a consistent knowledge base of alkali-silica reaction (ASR) within concrete as an urgent priority (Graves et al., 2014). ASR results in an expansion of Concrete produced by the reaction between alkali (generally from cement), reactive aggregate (like amorphous silica) and water absorption. ASR causes expansion, cracking and loss of mechanical properties. Considering that US commercial reactors in operation enter the age when ASR distress can be potentially observed and that numerous non-nuclear infrastructures (transportation, energy production) in a majority of the States have already experienced ASR-related concrete degradation, the susceptibility and significance of ASR for nuclear concrete structures must be addressed. This paper outlines an on-going research program including the investigation of the possibility of ASR in nuclear power plants, and the assessment of the residual shear bearing capacity of ASR-subjected nuclear structures. (authors)

  17. Global development of advanced nuclear power plants, and related IAEA activities

    International Nuclear Information System (INIS)

    2006-09-01

    Renewed interest in the potential of nuclear energy to contribute to a sustainable worldwide energy mix is underlining the IAEA's statutory role in fostering the peaceful uses of nuclear energy, in particular the need for effective exchanges of information and collaborative research and technology development among Member States on advanced nuclear power technologies deployable in the near term as well as in the longer term. For applications in the medium to longer term, with rising expectations for the role of nuclear energy in the future, technological innovation has become a strong focus of nuclear power technology developments by many Member States. To meet Member States' needs, the IAEA conducts activities to foster information exchange and collaborative research and development in the area of advanced nuclear reactor technologies. These activities include coordination of collaborative research, organization of international information exchange, and analyses of globally available technical data and results, with a focus on reducing nuclear power plant capital costs and construction periods while further improving performance, safety and proliferation resistance. In other activities, evolutionary and innovative advances are catalyzed for all reactor lines such as advanced water cooled reactors, high temperature gas cooled reactors, liquid metal cooled reactors and accelerator driven systems, including small and medium sized reactors. In addition, there are activities related to other applications of nuclear energy such as seawater desalination, hydrogen production, and other process heat applications. This brochure summarizes the worldwide status and the activities related to advanced nuclear power technology development and related IAEA activities. It includes a list of the collaborative research and development projects conducted by the IAEA, as well as of the status reports and other publications produced

  18. Evironmental assessment factors relating to reprocessing of spent nuclear fuel

    International Nuclear Information System (INIS)

    1978-05-01

    This document is in two parts. Part I presents the criteria and evaluation factors, based primarily on US experience, which may be used to carry out an environmental assessment of spent fuel reprocessing. The concept of As Low as is Reasonably Achievable (ALARA) is introduced in limiting radiation exposure. The factors influencing both occupational and general public radiation exposure are reviewed. Part II provides information on occupational and general public radiation exposure in relation to reprocessing taken from various sources including UNSCEAR and GESMO. Some information is provided in relation to potential accidents at reprocessing or MOX fuel refabrication plants. The magnitude of the services, energy, land use and non-radiological effluents for the reference design of reprocessing plant are also presented

  19. A survey of nuclear-related agreements and possibilities for nuclear cooperation in South Asia: Cooperative Monitoring Center Occasional Paper/15

    Energy Technology Data Exchange (ETDEWEB)

    RAJEN,GAURAV

    2000-04-01

    Several existing nuclear-related agreements already require India and Pakistan, as members, to share information. The agreements are bilateral, regional, and international. Greater nuclear transparency between India and Pakistan could be promoted by first understanding the information flows required by existing agreements. This understanding is an essential step for developing projects that can incrementally advance the sensitivity of the information being shared. This paper provides a survey of existing nuclear-related agreements involving India and Pakistan, and suggests future confidence-building projects using the frameworks provided by these agreements. The Bilateral Agreement on the Prohibition of Attack against Nuclear Reactors and Nuclear Facilities is discussed as a basis for creating further agreements on restricting the use and deployment of nuclear weapons. The author suggests options for enhancing the value of the list of nuclear facilities exchanged annually as a part of this agreement. The International Atomic Energy Agency's regional cooperation agreement among countries in the Asia-Pacific region is an opportunity for greater subregional nuclear cooperation in South Asia. Linking the regional agreement with South Asian environmental cooperation and marine pollution protection efforts could provide a framework for projects involving Indian and Pakistani coastal nuclear facilities. Programs of the Food and Agriculture Organization of the United Nations that use nuclear techniques to increase food and crop production and optimize water management in arid areas also provide similar opportunities for nuclear cooperation. Other frameworks for nuclear cooperation originate from international conventions related to nuclear safety, transportation of nuclear wastes, worker protection against ionizing radiation, and the nondeployment of nuclear weapons in certain areas. The information shared by existing frameworks includes: laws and regulations

  20. A survey of nuclear-related agreements and possibilities for nuclear cooperation in South Asia: Cooperative Monitoring Center Occasional Paper/Draft

    International Nuclear Information System (INIS)

    Rajen, Gaurav

    2000-01-01

    Several existing nuclear-related agreements already require India and Pakistan, as members, to share information. The agreements are bilateral, regional, and international. Greater nuclear transparency between India and Pakistan could be promoted by first understanding the information flows required by existing agreements. This understanding is an essential step for developing projects that can incrementally advance the sensitivity of the information being shared. This paper provides a survey of existing nuclear-related agreements involving India and Pakistan, and suggests future confidence-building projects using the frameworks provided by these agreements. The Bilateral Agreement on the Prohibition of Attack against Nuclear Reactors and Nuclear Facilities is discussed as a basis for creating further agreements on restricting the use and deployment of nuclear weapons. The author suggests options for enhancing the value of the list of nuclear facilities exchanged annually as a part of this agreement. The International Atomic Energy Agency's regional cooperation agreement among countries in the Asia-Pacific region is an opportunity for greater subregional nuclear cooperation in South Asia. Linking the regional agreement with South Asian environmental cooperation and marine pollution protection efforts could provide a framework for projects involving Indian and Pakistani coastal nuclear facilities. Programs of the Food and Agriculture Organization of the United Nations that use nuclear techniques to increase food and crop production and optimize water management in arid areas also provide similar opportunities for nuclear cooperation. Other frameworks for nuclear cooperation originate from international conventions related to nuclear safety, transportation of nuclear wastes, worker protection against ionizing radiation, and the nondeployment of nuclear weapons in certain areas. The information shared by existing frameworks includes: laws and regulations (including

  1. An approach to safety problems relating to ageing of nuclear power plant components

    International Nuclear Information System (INIS)

    Conte, M.; Deletre, G.; Henry, J.Y.; Le Meur, M.

    1989-10-01

    The safety of nuclear power plants, in France, is discussed. The attention is focused on the ageing phenomena, as a potential cause of the degradation of the systems functional capabilities. The allowance for ageing in design and its importance on safety, are analyzed. The understanding of phenomena relating to ageing and the components surveillance, are considered. As the effective ageing on the components of nuclear power plants is not fully understood, technical improvements and more accurate analysis are required

  2. American National Standard: guidelines for evaluating site-related geotechnical parameters at nuclear power sites

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    This standard presents guidelines for evaluating site-related geotechnical parameters for nuclear power sites. Aspects considered include geology, ground water, foundation engineering, and earthwork engineering. These guidelines identify the basic geotechnical parameters to be considered in site evaluation, and in the design, construction, and performance of foundations and earthwork aspects for nuclear power plants. Also included are tabulations of typical field and laboratory investigative methods useful in identifying geotechnical parameters. Those areas where interrelationships with other standards may exist are indicated

  3. Public relations campaign in siting of nuclear power plants in Nigeria

    International Nuclear Information System (INIS)

    Angulu, H.A.

    2008-01-01

    Having understood the issues at stake and the need for public support, there is need to create public relations campaign to raise awareness of citing nuclear power plants and stimulate the much needed public support for the introduction of nuclear power into the energy mix. This calls for ally with the Federal Ministry of Information and Communications charged with development of necessary communication strategies for publicizing, educating and informing the people on policies, actions and programmes of Government

  4. A selection of problems related to safe working conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Brunner, K.H.

    1984-01-01

    Two representative examples were chosen to demonstrate that the problems related to safe working conditions can be solved with work being prepared extensively and in detail taking into consideration radiation protection and conventional job safety measures and with qualified staff. Most of the job safety problems in nuclear power plants are pretty much the same as in conventional plants. Despite successful implementation of employment and radiation protection in nuclear power plants, improvements in detail are possible and make sense. (orig.) [de

  5. Education and public relations in nuclear power toward the next generation in Korea

    International Nuclear Information System (INIS)

    I, Han-Joo; Seo, Doo-Han.

    1989-01-01

    The report outlines the education in nuclear engineering in colleges and universities in Korea, experiments and training in nuclear reactor operation, research project for education in peaceful utilization of nuclear power, and public relations activities and special plans intended for the new generation in the nation. Programs covering the education of students in nuclear engineering in colleges and universities in Korea, and public relations toward some selected groups and brackets have been conducted successfully, producing good results. On the other hand, some improvements in educational activities, including the revision of textbooks, are required in such a field of education of pupils in primary, middle and high schools. Specially-designed introductory courses and advanced courses in the peaceful utilization of nuclear power should be established to ensure that students in scientific or technological fields other than nuclear engineering will gain deeper understanding of the issue. For this, the preparation of textbooks are currently under way. It is hoped that public relations activities will be expanded on a more continuous and consistent basis, instead of the current intermittent basis, by making good use of the mass media to distribute information among the general public. (Nogami. K.)

  6. Education and public relations in nuclear power toward the next generation in Korea

    Energy Technology Data Exchange (ETDEWEB)

    I, Han-Joo; Seo, Doo-Han.

    1989-02-01

    The report outlines the education in nuclear engineering in colleges and universities in Korea, experiments and training in nuclear reactor operation, research project for education in peaceful utilization of nuclear power, and public relations activities and special plans intended for the new generation in the nation. Programs covering the education of students in nuclear engineering in colleges and universities in Korea, and public relations toward some selected groups and brackets have been conducted successfully, producing good results. On the other hand, some improvements in educational activities, including the revision of textbooks, are required in such a field of education of pupils in primary, middle and high schools. Specially-designed introductory courses and advanced courses in the peaceful utilization of nuclear power should be established to ensure that students in scientific or technological fields other than nuclear engineering will gain deeper understanding of the issue. For this, the preparation of textbooks are currently under way. It is hoped that public relations activities will be expanded on a more continuous and consistent basis, instead of the current intermittent basis, by making good use of the mass media to distribute information among the general public. (Nogami. K.).

  7. Fusion-related work at the Nuclear Energy Agency Data Bank

    International Nuclear Information System (INIS)

    Henriksson, H.; Mompean, F.J.; Kodeli, I.

    2007-01-01

    The OECD Nuclear Energy Agency (NEA) Data Bank is part of an international network of data centres in charge of the compilation and dissemination of basic nuclear reaction data. Through its activities in the reaction data field, the NEA participates in the preparation of data for the modelling of future nuclear facility concepts and the development of reactor installations. A working party at the NEA on international nuclear data evaluation cooperation (WPEC) is established to promote the exchange of nuclear data evaluations, measurements, nuclear model calculations and validation. WPEC provides a framework for co-operative activities, such as the high priority request list for experimental data of special interest for certain applications, such as IFMIF or ITER. The NEA Data Bank administrates the collection and validation as well as the distribution of the Joint Evaluated Fusion and Fission (JEFF) library, where the activities in the European Fusion and Activation File projects (EFF and EAF respectively) play an important role for new data evaluations. The topics cover verification of activation and transport data, calculation methods and validation via integral experiments. The EFF project brings together all available expertise in Europe related to the nuclear data requirements of existing and future fusion devices, and the project contributed greatly to the internationally recognised nuclear data library JEFF-3.1, released in May 2005. The NEA also provides tools for the EFF project, such as computer codes for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments collected in the Shielding Integral Benchmark Archive Database (SINBAD) database. SINBAD is an internationally established set of radiation shielding and dosimetry data containing over 80 experiments relevant for reactor and accelerator shielding. About 30 of these experiments are dedicated to fusion blanket neutronics. Materials

  8. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Alvarez, A.; Correa, E.; Navarro, N.; Sancho, C.; Angeles, A.

    2000-01-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  9. Management of severely damaged nuclear fuel and related waste

    International Nuclear Information System (INIS)

    1991-01-01

    This report is concerned primarily with severe fuel damage accidents in large electric power producing reactors such as those in the TMI and Chernobyl plants. It does include, as appropriate, knowledge gained from accidents in other power, research and military reactors. It is believed that the conclusions and recommendations apply to a large extent to severe fuel damage accidents in all types of reactors. The period considered in this publication begins after the initial crisis of an accident has been brought under control. (This initial crisis could be from one day to several weeks after the event, depending on the specific conditions). Accordingly, it is assumed that the plant is shut down, the reactor is under control and decay heat removal is in progress in a stable manner so that attention must be given to cleanup. This report addresses the principles involved in planning, engineering, construction, operation and other activities to characterize, clean up and dispose of the fuel and related waste. The end of the period under consideration is when the fuel and abnormal wastes are packaged either for interim storage or final disposal and activities are started either to restore the plant to service or to establish a safe state from which decommissioning planning can start. 36 refs, 3 figs, 4 tabs.

  10. Legal framework related to access to information and public participation on nuclear activity

    International Nuclear Information System (INIS)

    Arias, M. C.; Bernaldez, A.L.; Ghiggeri, M.; Tula, C.

    2011-01-01

    The right of access to information by citizens about activities related to scientific and technological development of nuclear energy for peaceful uses, has evolved over time. Governments began to perceive the necessity and the benefits of informing the community, who manifested certain prejudices about nuclear activity as a consequence of the propelling of nuclear bombs in Nagasaki and Hiroshima. With the advent of environmental law and the influence of its principles, the idea of transparency of information in the nuclear field was imposed, and also the importance of both the inhabitants of countries with nuclear developments and neighbouring countries who may be affected by the bordering effects of ionizing radiation, could have access to information and to participate actively. The access to information and citizen participation has been institutionalized and reflected in international regulations through international conventions subscribed by our country and nationally through the National Constitution, the Provincials Constitutions, the City of Buenos Aires Constitution, Laws No. 25.675, 25.831 and PEN Decree No. 1172/03, among others. The present work aims to make an overview of the legal framework related to access to information on nuclear activity. (authors) [es

  11. Harmonization of health related environmental measurements using nuclear and isotopic techniques. Proceedings of an international symposium

    International Nuclear Information System (INIS)

    1997-01-01

    One of the particular strengths of nuclear methods is in analytical quality assurance, including the validation of analytical methods and the development of new analytical reference materials. These methodologies are therefore helping to harmonize the data produced not only by nuclear techniques themselves, but also by other non-nuclear methods of analysis. The aim of this symposium was to provide an international forum for discussion of these topics. Its programme covered a wide variety of applications of nuclear (and related) analytical techniques (mainly neutron activation analysis, energy dispersive X ray fluorescence, particle induced X ray emission and inductively coupled plasma-mass spectrometry) as used in the study of air particulates, solid waste products, sediments, food, water, human tissues, biomonitors and other kinds of environmental samples

  12. Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

    International Nuclear Information System (INIS)

    Ichikawa, M.

    1994-01-01

    The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs

  13. Triton-3He relative and differential flows and the high density behavior of nuclear symmetry

    International Nuclear Information System (INIS)

    Yong, Gaochan; Li, Baoan; Chen, Liewen

    2010-01-01

    Using a transport model coupled with a phase-space coalescence after-burner we study the triton- 3 He relative and differential transverse flows in semi-central 132 Sn + 124 Sn reactions at a beam energy of 400 MeV/nucleon. We find that the triton- 3 He pairs carry interesting information about the density dependence of the nuclear symmetry energy. The t- 3 He relative flow can be used as a particularly powerful probe of the high-density behavior of the nuclear symmetry energy. (author)

  14. Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

    Energy Technology Data Exchange (ETDEWEB)

    Ichikawa, M [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    1994-12-31

    The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs.

  15. The application of nuclear and nuclear-related techniques for environmental pollution studies in Vietnam

    International Nuclear Information System (INIS)

    Nguyen Mong Sinh

    1992-01-01

    The applicability of neutron activation analysis, X-ray fluorescence and other related techniques to environmental samples from Viet Nam has been investigated. Results show that multielemental analysis of environmental samples and the determination of heavy metal pollution in the environment is best performed by a combination of techniques. Preliminary results of studying the environmental pollution associated with solid wastes are reported. 4 refs, 5 figs, 17 tabs

  16. Sector activities related to spent nuclear fuel in the spanish nuclear power plants; Actuaciones sectoriales en relaci@n con el combustible nuclear gastado en las centrales nucleares espa@olas.

    Energy Technology Data Exchange (ETDEWEB)

    Francia, L.

    2016-07-01

    Royal Decree 102/2014 of February 21 defines spent nuclear fuel as the irradiated nuclear fuel in the reactor core that is permanently removed from it. Spent nuclear fuel can be considered either as a usable resource that can be reprocessed, or else as a radioactive waste destined for final disposal. Likewise, spent nuclear fuel management refers to all the activities related to handling, temporary storage, reprocessing and final storage. The article presents all the plans and actions taken by the nuclear power plants, which can be divided into the following two categories: Actions taken by the plants themselves to not only maintain the fuel in stable, safe conditions, but also to characterize and process it for the subsequent management routes established by the current General Radioactive Waste Plan. Activities undertaken under the UNESA umbrella to help implement the above mentioned management routes.

  17. Inspection of Nuclear Power Plant Structures - Overview of Methods and Related Applications

    International Nuclear Information System (INIS)

    Naus, Dan J.

    2009-01-01

    The objectives of this limited study were to provide an overview of the methods that are available for inspection of nuclear power plant reinforced concrete and metallic structures, and to provide an assessment of the status of methods that address inspection of thick, heavily-reinforced concrete and inaccessible areas of the containment metallic pressure boundary. In meeting these objectives a general description of nuclear power plant safety-related structures was provided as well as identification of potential degradation factors, testing and inspection requirements, and operating experience; methods for inspection of nuclear power plant reinforced concrete structures and containment metallic pressure boundaries were identified and described; and applications of nondestructive evaluation methods specifically related to inspection of thick-section reinforced concrete structures and inaccessible portions of containment metallic pressure boundaries were summarized. Recommendations are provided on utilization of test article(s) to further advance nondestructive evaluation methods related to thick-section, heavily-reinforced concrete and inaccessible portions of the metallic pressure boundary representative of nuclear power plant containments. Conduct of a workshop to provide an update on applications and needed developments for nondestructive evaluation of nuclear power plant structures would also be of benefit.

  18. Inspection of Nuclear Power Plant Structures - Overview of Methods and Related Applications

    Energy Technology Data Exchange (ETDEWEB)

    Naus, Dan J [ORNL

    2009-05-01

    The objectives of this limited study were to provide an overview of the methods that are available for inspection of nuclear power plant reinforced concrete and metallic structures, and to provide an assessment of the status of methods that address inspection of thick, heavily-reinforced concrete and inaccessible areas of the containment metallic pressure boundary. In meeting these objectives a general description of nuclear power plant safety-related structures was provided as well as identification of potential degradation factors, testing and inspection requirements, and operating experience; methods for inspection of nuclear power plant reinforced concrete structures and containment metallic pressure boundaries were identified and described; and applications of nondestructive evaluation methods specifically related to inspection of thick-section reinforced concrete structures and inaccessible portions of containment metallic pressure boundaries were summarized. Recommendations are provided on utilization of test article(s) to further advance nondestructive evaluation methods related to thick-section, heavily-reinforced concrete and inaccessible portions of the metallic pressure boundary representative of nuclear power plant containments. Conduct of a workshop to provide an update on applications and needed developments for nondestructive evaluation of nuclear power plant structures would also be of benefit.

  19. Sweden: The Swedish nuclear archive regulations and projects related to corporate memory. Annex I-2

    International Nuclear Information System (INIS)

    2008-01-01

    The Swedish radiation protection authority regulations on Filing at Nuclear Plants, SSI FS 1997:1, apply to filing of documentation that has been drawn up or received in connection with practices at nuclear plants. The regulations set out: -The minimum level of documentation; - Archiving requirements; -Availability periods; - Choice of data carrier; - Timely transfer to new media; - Requirements regarding safe keeping of documents. The regulations require that, if the nuclear activity ceases, the archives must be transferred to the Swedish national archives. Examples of the availability periods required for records and environmental specimens are as follows: (a) Operations related measurements - 25 years; (b) Emergency response plan - 50 years; (c) Report of an unusual event - 50 years; (d) Documents relating to final disposal - long term; (e) Environmental specimens - 10 years; (f) Records of measurements on specimens - long term

  20. Proceedings of Fifth International Symposium on Nuclear and Related Techniques NURT 2006

    International Nuclear Information System (INIS)

    2006-04-01

    The Cd-Rom presents papers submitted to the Fifth International Symposium on Nuclear and Related Techniques NURT 2006 held in Havana, Cuba, on April, 2006. The NURT Symposia are one of the key Cuban scientific meetings dealing with the peaceful applications of nuclear techniques in all domains of the society. They are arranged with a two-year frequency and provide a unique opportunity for the international scientific community to meet outstanding researches and to discuss current trends and task in several areas of applied, nuclear related topics. The first editions of the NURT were organized under the auspices of the International Atomic Energy Agency in 1997, 1999, 200, 2003 and hosted delegates and invited scientific from more than 40 countries from all over the world. The join several workshops, each one devoted to an specific field research

  1. Developing and using artificial intelligence related to nuclear energy in Romania

    International Nuclear Information System (INIS)

    Ion, R.

    1995-01-01

    The artificial intelligence (AI) (including Expert Systems (ES), its most important branch) could have a certain place in the future developing of nuclear energy with impact on decision aids techniques and support systems, especially for nuclear safety and radiation protection area. First steps -some based on the Canadian experience - were already done in Romania, in developing AI techniques related to nuclear energy. Newcomers are recommended to start with modest and isolate problems in order to build up the necessary hand-on experience. The moment of the large scale AI implementation in the nuclear energy field will be decided by the balance between conventional computing and Ai computing and also between the advantages and disadvantages of AI. In this frame, the opportunity for research developing and using AI in the nuclear energy field is inherent and must be sustained by the research, design and plant operation authorities and also by the high education universities which are recommended to focus their interest towards the AI field for the next specialists in nuclear energy. (Author) 2 Figs., 2 Tabs., 7 Refs

  2. A method to forecast quantitative variables relating to nuclear public acceptance

    International Nuclear Information System (INIS)

    Ohnishi, T.

    1992-01-01

    A methodology is proposed for forecasting the future trend of quantitative variables profoundly related to the public acceptance (PA) of nuclear energy. The social environment influencing PA is first modeled by breaking it down into a finite number of fundamental elements and then the interactive formulae between the quantitative variables, which are attributed to and characterize each element, are determined by using the actual values of the variables in the past. Inputting the estimated values of exogenous variables into these formulae, the forecast values of endogenous variables can finally be obtained. Using this method, the problem of nuclear PA in Japan is treated as, for example, where the context is considered to comprise a public sector and the general social environment and socio-psychology. The public sector is broken down into three elements of the general public, the inhabitants living around nuclear facilities and the activists of anti-nuclear movements, whereas the social environment and socio-psychological factors are broken down into several elements, such as news media and psychological factors. Twenty-seven endogenous and seven exogenous variables are introduced to quantify these elements. After quantitatively formulating the interactive features between them and extrapolating the exogenous variables into the future estimates are made of the growth or attenuation of the endogenous variables, such as the pro- and anti-nuclear fractions in public opinion polls and the frequency of occurrence of anti-nuclear movements. (author)

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

    Science.gov (United States)

    Bobrowski, Krzysztof; Skotnicki, Konrad; Szreder, Tomasz

    2016-10-01

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

  4. Awareness of the general public relations strategy for nuclear power generation in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chano-Ok

    1989-02-01

    Ten years has passed since the first nuclear power plant was established in Korea. During the period, the total nuclear power generation capacity has increased to 5,716,000 kW, and additional two 950,000 kW plants currently under construction will start operating in 1988 and 1989, respectively. As of the end of 1987, nuclear power generation accounted for 53.1 % of the total power generated in the nation. The average utilization rate of the plants increased continuously from 46.3 % ten years ago up to 79.7 % in 1987. Public opinion polls were conducted in August and October of 1986, the year when the Chernobyl accident took place. The first survey covered 2,000 residents in urban and rural areas while the second one covered a total 1,000 nuclear-related engineers, scientists, administrative officials, businessmen, journalists and writers. The surveys have shown that 74.4 % of the general public agree on the construction of more nuclear power plants. The corresponding figure was 75 % for engineers and 50 % for journalists and writers. However, 73 % of the respondents who are for their construction did not want such a plant to be constructed near their residences. Concerning the safety of these plants, 79.5 % of the experts gave a positive reply while the corresponding figure was only 48.3 % for the general public. It is concluded that more active public relations activities are required in the future. (Nogami, K.).

  5. Awareness of the general public relations strategy for nuclear power generation in Korea

    International Nuclear Information System (INIS)

    Kim, Chano-Ok

    1989-01-01

    Ten years has passed since the first nuclear power plant was established in Korea. During the period, the total nuclear power generation capacity has increased to 5,716,000 kW, and additional two 950,000 kW plants currently under construction will start operating in 1988 and 1989, respectively. As of the end of 1987, nuclear power generation accounted for 53.1 % of the total power generated in the nation. The average utilization rate of the plants increased continuously from 46.3 % ten years ago up to 79.7 % in 1987. Public opinion polls were conducted in August and October of 1986, the year when the Chernobyl accident took place. The first survey covered 2,000 residents in urban and rural areas while the second one covered a total 1,000 nuclear-related engineers, scientists, administrative officials, businessmen, journalists and writers. The surveys have shown that 74.4 % of the general public agree on the construction of more nuclear power plants. The corresponding figure was 75 % for engineers and 50 % for journalists and writers. However, 73 % of the respondents who are for their construction did not want such a plant to be constructed near their residences. Concerning the safety of these plants, 79.5 % of the experts gave a positive reply while the corresponding figure was only 48.3 % for the general public. It is concluded that more active public relations activities are required in the future. (Nogami, K.)

  6. Fire and the related effects of nuclear explosions. 1982 Asilomar Conference

    International Nuclear Information System (INIS)

    Martin, S.B.; Alger, R.S.

    1982-11-01

    This report summarizes the proceedings of a Federal Emergency Management Agency-sponsored Conference on fire and the related effects of nuclear explosions (with passing attention to earthquakes and other nonnuclear mishaps). This conference, the fifth of an annual series (formally called Blast/Fire Interaction Conferences), was held during the week of April 25, 1982, again at Asilomar, California

  7. Historical evolution of nuclear energy systems development and related activities in JAERI. Fission, fusion, accelerator utilization

    Energy Technology Data Exchange (ETDEWEB)

    Tone, Tatsuzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    Overview of the historical evolution of nuclear energy systems development and related activities in JAERI is given in the report. This report reviews the research and development for light water reactor, fast breeder reactor, high temperature gas reactor, fusion reactor and utilization of accelerator-based neutron source. (author)

  8. Aspects of the future Physics teachers imaginary related to problem solving and Nuclear

    Directory of Open Access Journals (Sweden)

    Thirza Pavan Sorpreso

    2008-09-01

    Full Text Available In this paper we try to put in evidence some aspects of the future Physics teachers imaginary when they are is related to work with problem solving and with Nuclear Physics inclusion in High School. We show that this imaginary is evidenced and suffers displacements from specific conditions of production.

  9. Fire and the related effects of nuclear explosions. 1982 Asilomar Conference

    Energy Technology Data Exchange (ETDEWEB)

    Martin, S.B.; Alger, R.S. (eds.)

    1982-11-01

    This report summarizes the proceedings of a Federal Emergency Management Agency-sponsored Conference on fire and the related effects of nuclear explosions (with passing attention to earthquakes and other nonnuclear mishaps). This conference, the fifth of an annual series (formally called Blast/Fire Interaction Conferences), was held during the week of April 25, 1982, again at Asilomar, California.

  10. Hungarian national report on activities related to operator support systems for nuclear power plants

    International Nuclear Information System (INIS)

    Adorjan, F.; Lux, I.; Vegh, J.; Vegh, E.

    1996-01-01

    Computerized operator support systems and related activities in Hungary are summarized. Systems developed in the past, presently developed and used as well as being in a planning phase are briefly described. Activity of the Hungarian participants in the framework of the co-ordinated project on operator support systems for nuclear power plant is summarized. (author). 55 refs

  11. Public relations and public understanding in the nuclear industry in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Roos, E.; Michel, A. [Belgonucleaire, Brussels (Belgium)

    1995-12-31

    Before talking about public understanding and public relations in the nuclear industry in Europe, a word about the mosaic structure of the European energy policy and public is required because a similar structure will be found in the European public understanding policy. Afterwards, we explain what communications tools are available and how the different European countries apply them.

  12. Estimation of unknown nuclear masses by means of the generalized mass relations. Pt. 3

    International Nuclear Information System (INIS)

    Popa, S.M.

    1980-01-01

    A survey of the estimations of the unknown nuclear masses by means of the generalized mass relations is presented. One discusses the new hypotheses supplementing the original general Garvey-Kelson scheme, reviewing the generalized mass relations and formulae, according to the present status of this new formalism. A critical discussions is given of the reliability of these new Garvey-Kelson type extrapolation procedures. (author)

  13. An approach to quantitative assessment of relative proliferation risks from nuclear fuel cycles

    International Nuclear Information System (INIS)

    Silvennoinen, P.; Vira, J.

    1981-01-01

    Feasibility of quantitative assessments of the risk of nuclear weapons proliferation is discussed in this paper. The proliferation risk is defined as a combined utility of the different fuel cycle processes or materials for the proscribed acquisition of a nuclear weapon. Based on a set of selected weighted criteria, the process utilities are calculated employing utility functions or fuzzy expectation values. The methods are compared to each other. The scheme appears feasible in relative comparisons while certain leeway must still be retained for political judgement. (author)

  14. Earthquakes and associated topics in relation to nuclear power plant siting

    International Nuclear Information System (INIS)

    1991-01-01

    This Safety Guide was prepared as part of the Agency's programme for establishing Codes and Safety Guides relating to nuclear power plants. The main purpose of the text is to provide guidance on the determination of the design basis ground motions for a nuclear power plant at a chosen site and on the determination of the potential for surface faulting at that site. Additionally, the Guide discusses other permanent displacement phenomena (liquefaction, slope instability, subsidence and collapse) and introduces the topic of seismically induced flooding. Volcanic activity is not dealt with except in connection with tsunamis. 55 refs

  15. Relation of management, supervision, and personnel practices to nuclear power plant safety

    International Nuclear Information System (INIS)

    Layton, W.L.; Turnage, J.J.

    1980-01-01

    The knowledge base of industrial/organization psychology suggests three major areas of research with important implications for nuclear power plant safety. These areas are: Management and Supervision: Personnel Selection, Training and Placement; and Organizational Climate. Evidence drawn from several Three Mile Island investigations confirms that organizational structure of plants and supervisory practices, the selection and training of personnel, and organizational climate are important factors. Difficulties in decision making and coordination of personnel are pinpointed. Deficiencies in training are highlighted and the climate of working atmosphere is discussed. These matters are related to nuclear power plant safety. Future research directions are presented

  16. Project of law relative to the sanitary consequences of French nuclear weapons tests

    International Nuclear Information System (INIS)

    2009-05-01

    In order to make easy the indemnifications and to include the persons having participate to nuclear weapons tests (Sahara and French Polynesia) and populations leaving in the concerned areas, the project of law relative to the repair of sanitary consequences of nuclear weapons tests proposes to create a right to integral repair of prejudices for the persons suffering of a radioinduced disease coming from these tests. The American example and the British example are given for comparison. The modalities of financing are detailed as well as the social economic and administrative impacts. (N.C.)

  17. 'Low-activation' fusion materials development and related nuclear data needs

    International Nuclear Information System (INIS)

    Cierjacks, S.

    1990-01-01

    So-called ''low-activation'' materials are presently considered as an important means of improving the safety characteristics of future DT fusion reactors. Essential benefits are expected in various problem areas ranging from operation considerations to aspects of decommissioning and waste disposal. Present programs on ''low-activation'' materials development depend strongly on reliable activity calculations for a wide range of technologically important materials. The related nuclear data requirements and important needs for more and improved nuclear data are discussed. (author). 32 refs, 4 figs, 4 tabs

  18. Reaction of the residents to nuclear related policies: in a risk perception perspective

    International Nuclear Information System (INIS)

    Cho, S. K.

    2001-01-01

    In general, most of the nuclear related policies are discussed at governmental level. Siting nuclear related facilities policies is the state as this. The government, as the single decision-maker, tends to decide all procedures from policy drafting, decision making to implementation. That is to say, the government has been opting for DAD(Decide-Announce-Defend) measure. This resulted in many forms of discord because the government overlooked the importance of sufficient communication with resident or the public. However, the precondition for promoting nuclear related policies is public acceptance. Meanwhile, the public including resident fully understand the necessity of nuclear facilities but do not agree with the idea of having them in their residential area. Therefore, the research focuses on identifying the affecting factors toward reaction of the resident derived from previous studies. It also aims to lay the foundation for devising effective communication strategies between the government and the public. The result of case study, it was found that these factors-trust, participation and compensative-have interacted to affect resident's reaction. Ultimately, the government must recognize the residents as decision-maker so as to gain the PA(Public Acceptance). It also necessary to create better decision making processes by substantial participation, reasonable compensation and trust are essential first steps toward improving the situation

  19. The safety related aspects of pressure components in nuclear power plants

    International Nuclear Information System (INIS)

    Lindackers, K.H.

    1979-01-01

    Over the last two years the safety philosophy for nuclear power plants in the Federal Republic of Germany has changed considerably, as everyone working in the field perceives. The original and appropriate philosophy of risk minimalisation through graduated safety barriers has been more and more replaced by the utopian goal of total prevention of any damage. The reasons for this development are discussed briefly especially regarding pressure components. The very numerous pressure components of a nuclear power station are not all of equal importance with respect to safety. Although considerable efforts have been made, it has not been possible, to date, to achieve an agreement between operators, manufacturers, licensing authorities, independent experts, and other specialists about the safety related classification of the manifold pressure bearing parts in nuclear power stations. The background of this extremely regrettable situation is explained. In the last part of the paper the author suggests a simple and clear safety philosophy for pressure components in nuclear power stations. This philosophy is orientated both on Safety Regulations of the Radiation Protection Decree ('Strahlenschutzverordnung') of the 13th October 1976 and on the Safety Criteria for Nuclear Power Stations from 21st October 1977. Only a simple, clear framework can make a contribution to the further improvement of the already exceptional safety of nuclear facilities and to the removal of obstacles in the licensing procedure which, taken as a whole, tie up skilled personnel to a senseless degree, involve considerable financial expenditure, and have no relevance for the safety of nuclear power plants. (orig.) [de

  20. Relation between source term and emergency planning for nuclear power plants

    International Nuclear Information System (INIS)

    Shi Zhongqi; Yang Ling

    1992-01-01

    Some background information of the severe accidents and source terms related to the nuclear power plant emergency planning are presented. The new source term information in NUREG-0956 and NUREG-1150, and possible changes in emergency planning requirements in U.S.A. are briefly provided. It is suggested that a principle is used in selecting source terms for establishing the emergency planning policy and a method is used in determining the Emergency Planning Zone (EPZ) size in China. Based on the research results of (1) EPZ size of PWR nuclear power plants being built in China, and (2) impact of reactor size and selected source terms on the EPZ size, it is concluded that the suggested principle and the method are suitable and feasible for PWR nuclear power plants in China

  1. Economics of nuclear and thermal power plants in the transition to market relations

    International Nuclear Information System (INIS)

    Chernilin, Yu.F.

    1993-01-01

    In the economic conditions taking shape, the provision of electricity for the national economy of Russia, including in the short term (up to the years 2010-2015), depends in many ways on a weighted choice of strategy for the use of alternative means of electricity generation from the standpoint of fuel resources and electrical technology. When considering problems that need to be reassessed, the role of all alternative energy sources, including nuclear power, in the energy system of Russia must be determined, i.e., a strategy must be worked out for the development of the power industry. Information and data are presented on the present state of the electrical power industry in Russia including fossil and nuclear. Issues and policies associated with the transition to a market-driven economy as related to the nuclear power industry is examined. Specifically, a open-quotes Conception of a Power Policy for Russiaclose quotes is discussed

  2. Double beta decays and related subjects for particle and nuclear physics

    International Nuclear Information System (INIS)

    Ejiri, Hiroyasu

    1991-01-01

    Present status and some perspectives in 1990's are briefly given on double beta decays and related subjects. Subjects discussed are as follows I) Double beta decays without neutrinos, which require lepton number non-conservations and finite neutrino mass. II) Double beta decays followed by two neutrinos. III) Double weak processes with strangeness change ΔS = 2, leading to the H particle with 6 quarks of ss uu dd. IV) Charge non-conservation and electron decays. These are very rare nuclear processes studied by Ultra RAre-process NUclear Spectroscopy (URANUS). It is shown that URANUS is an important detector frontier of non-accelerator nuclear physics in 1990's. (orig.)

  3. The use of genetic algorithms with niching methods in nuclear reactor related problems

    International Nuclear Information System (INIS)

    Sacco, Wagner Figueiredo

    2000-03-01

    Genetic Algorithms (GAs) are biologically motivated adaptive systems which have been used, with good results, in function optimization. However, traditional GAs rapidly push an artificial population toward convergence. That is, all individuals in the population soon become nearly identical. Niching Methods allow genetic algorithms to maintain a population of diverse individuals. GAs that incorporate these methods are capable of locating multiple, optimal solutions within a single population. The purpose of this study is to test existing niching techniques and two methods introduced herein, bearing in mind their eventual application in nuclear reactor related problems, specially the nuclear reactor core reload one, which has multiple solutions. Tests are performed using widely known test functions and their results show that the new methods are quite promising, specially in real world problems like the nuclear reactor core reload. (author)

  4. Study on upgrade on nuclear control related open source information website

    International Nuclear Information System (INIS)

    Kim, H. T.; Park, S. S.; Park, W. S.; Choi, Y. M.

    2002-01-01

    The open source information relevant to the nuclear control is regularly collected, analyzed, and published to the three web sites by the Technology Center for Nuclear Control (TCNC) of the Korea Atomic Energy Research Institute (KAERI). These web sites are world-wide, KAERI-wide, and TCNC-wide, respectively. We are to upgrade the KAERI-wide website to the access-controlled world-wide web site with some additional functionality. In this research, the current status of the three nuclear control related open source information websites managed by the TCNC was introduced and methods for upgrading the KAERI-wide open source information website and associated information security technology were reviewed

  5. DOE/LLNL verification symposium on technologies for monitoring nuclear tests related to weapons proliferation

    International Nuclear Information System (INIS)

    Nakanishi, K.K.

    1993-01-01

    The rapidly changing world situation has raised concerns regarding the proliferation of nuclear weapons and the ability to monitor a possible clandestine nuclear testing program. To address these issues, Lawrence Livermore National Laboratory's (LLNL) Treaty Verification Program sponsored a symposium funded by the US Department of Energy's (DOE) Office of Arms Control, Division of Systems and Technology. The DOE/LLNL Symposium on Technologies for Monitoring Nuclear Tests Related to Weapons Proliferation was held at the DOE's Nevada Operations Office in Las Vegas, May 6--7,1992. This volume is a collection of several papers presented at the symposium. Several experts in monitoring technology presented invited talks assessing the status of monitoring technology with emphasis on the deficient areas requiring more attention in the future. In addition, several speakers discussed proliferation monitoring technologies being developed by the DOE's weapons laboratories

  6. Use of nuclear and nuclear-related analytical techniques in studies of trace and minor elements in air pollution

    International Nuclear Information System (INIS)

    Smodis, Borut; Stropnik, Boris

    1994-01-01

    Among nuclear and nuclear-related analytical techniques, neutron activation and X-ray fluorescence analysis are particularly useful for environmental studies owing to their non-destructive character and multi-element capability. In this work, procedures for k o -standardized instrumental neutron activation analysis (INAA) and energy-dispersive X-ray fluorescence (EDXRF) spectrometry for trace and minor elements in air pollution studies were investigated. The methods applied were validated by the analysis of suitable reference materials. Using INAA, 20 experimentally obtained elemental values out of 21 certified and all 29 experimentally obtained values compared with 'consensus' values (for the elements where no certified numbers are available) in two SRMs were statistically indistinguishable. Also, the contents of 28 elements in candidate NIST SRM 1573a Tomato Leaves are reported. The EDXRF results were statistically indistinguishable from certified values for eight out of nine elements in NIST SRM 3087. The detection limit for this method is around at 0.1 μg cm -2 per element, so in BCR CRM No. 128, which is intended for ambient air pollution data, only Fe and Zn out of 14 elements reported in the certificate were detected with acceptable precision (i.e., 10%) owing to the very low air particulate matter loading, lying in the region of only 250 μg cm -2 . (Author)

  7. Review of the IAEA Nuclear Fuel Cycle Materials Section activities related to WWER fuel

    International Nuclear Information System (INIS)

    Killeen, J.

    2003-01-01

    The IAEA Nuclear Fuel Cycle Programme, designated as Programme B, has the main objective of supporting Member States in policy making, strategic planning, developing technology and addressing issues with respect to safe, reliable, economically efficient, proliferation resistant and environmentally sound nuclear fuel cycle. This paper is concentrated on describing the work within Sub-programme B.2 'Fuel Performance and Technology'. Two Technical Working Groups assist in the preparation of the IAEA programme in the nuclear fuel cycle area - Technical Working Group on Water Reactor Fuel Performance and Technology and Technical Working Group on Nuclear Fuel Cycle Options. The activities of the Unit within the Nuclear Fuel Cycle and Materials Section working on Fuel Performance and Technology are given, based on the sub-programme structure of the Agency programme and budget for 2002-2003. Within the framework of Co-ordinated Research Projects a study of the delayed hydride cracking (DHC) of the zirconium alloys used in pressurised heavy water reactors (PHWR) involving 10 countries has been completed. It achieved very effective transfer of know-how at the laboratory level in three technologically important areas: 1) Controlled hydriding of samples to predetermined levels; 2) Accurate measurement of hydrogen concentrations at the relatively low levels found in pressure tubes and RBMK channel tubes; and 3) In the determination of DHC rates under various conditions of temperature and stress. A new project has been started on the 'Improvement of Models used for Fuel Behaviour Simulation' (FUMEX II) to assist Member States in improving the predictive capabilities of computer codes used in modelling fuel behaviour for extended burnup. The IAEA also collaborates with organisations in the Member States to support activities and meetings on nuclear fuel cycle related topics

  8. Hot cell works and related irradiation tests in fission reactor for development of new materials for nuclear application

    International Nuclear Information System (INIS)

    Shikama, Tatsuo

    1999-01-01

    Present status of research works in Oarai Branch, Institute for Materials Research, Tohoku University, utilizing Japan Materials Testing Reactor and related hot cells will be described.Topics are mainly related with nuclear materials studies, excluding fissile materials, which is mainly aiming for development of materials for advanced nuclear systems such as a nuclear fusion reactor. Conflict between traditional and routined procedures and new demands will be described and future perspective is discussed. (author)

  9. Applied research on air pollution using nuclear-related analytical techniques

    International Nuclear Information System (INIS)

    1994-01-01

    A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which will run from 1992-1996, and will build upon the experience gained by the Agency from the laboratory support that it has been providing for several years to BAPMoN - the Background Air Pollution Monitoring Network programme organized under the auspices of the World Meterological Organization. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XFR, and PIXE for the analysis of toxic and other trace elements in suspended particulate matter (including air filter samples), rainwater and fog-water samples, and in biological indicators of air pollution (e.g. lichens and mosses). The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for practically-oriented research and monitoring studies on air pollution ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural areas). This document reports the discussions held during the first Research Co-ordination Meeting (RCM) for the CRP which took place at the IAEA Headquarters in Vienna. Refs, figs and tabs

  10. Establishing management information system to solve the information management problem of nuclear safety related personnel's qualification management

    International Nuclear Information System (INIS)

    Sun Haipeng; Liu Zhijun; Li Tianshu

    2013-01-01

    With the rapid progress of nuclear energy and nuclear technology utilization, nuclear safety related personnel play an increasingly important role in ensuring nuclear safety. NNSA personnel qualification management information system conducts a multi-faceted, effective, real-time monitoring and information collection for nuclear safety staff practice unit management, knowledge management, license application, appraisal management or supervision, training management or supervision and certified staff management, and also is a milestone for NNSA to build the state department with 'five-feature' (learning-oriented, service-oriented, economical, innovative, clean-type). (authors)

  11. Definitions of engineered safety features and related features for nuclear power plants

    International Nuclear Information System (INIS)

    1986-01-01

    In light water moderated, light water cooled nuclear power plants, definitions are given of engineered safety features which are designed to suppress or prevent dispersion of radioactive materials due to damage etc. of fuel at the times of power plant failures, and of related features which are designed to actuate or operate the engineered safety features. Contents are the following: scope of engineered safety features and of related features; classification of engineered safety features (direct systems and indirect systems) and of related features (auxiliaries, emergency power supply, and protective means). (Mori, K.)

  12. 76 FR 70169 - Draft Supplement 2 to Final Environmental Statement Related to the Operation of Watts Bar Nuclear...

    Science.gov (United States)

    2011-11-10

    ... Environmental Statement Related to the Operation of Watts Bar Nuclear Plant, Unit 2; Tennessee Valley Authority... on NUREG-0498, ``Final Environmental Statement, Supplement 2, Related to the Operation of Watts Bar... the Nuclear Regulatory Commission. Stephen J. Campbell, Chief, Watts Bar Special Projects Branch...

  13. 76 FR 80409 - Draft Supplement 2 to Final Environmental Statement Related to the Operation of Watts Bar Nuclear...

    Science.gov (United States)

    2011-12-23

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

  14. Nuclear and related techniques for improving productivity of indigenous animals in harsh environments

    International Nuclear Information System (INIS)

    1986-01-01

    The seminar provided a forum to review the various ways by which nuclear and related methods can be used to improve animal nutrition, reproduction and disease control under the different ecological conditions prevailing in Africa and the Middle East. The seminar was held concurrently with an FAO/IAEA Advisory Group Meeting. The purpose of this meeting was for invited scientists from various disciplines to evaluate those nuclear and related techniques currently used to quantify such functions as animal adaptation, digestion and utilization of poor quality feedstuffs, reproductive efficiency and resistance to disease and other forms of stress. This volume contains a selection of the papers presented during the seminar as well as the Recommendations of the Advisory Group Meeting. Separate abstracts were prepared for 15 papers of this volume

  15. A study on the establishment of nuclear cooperative relations and future direction between Korea and Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Yang, M H; Kim, H S; Chung, W S; Yun, S W; Ko, H S; Lee, J K

    2000-10-01

    This study was carried out in order to review the cooperation with vietnam and establish and activate the cooperative relations with Vietnam. During the study, current status of use and development of nuclear energy in vietnam, were investigated including nuclear power plant and cooperative relations between two nations were also established. It was agreed through exchanges of visits of cooperation delegation; 1) exchange of visits of cooperation delegation, 2) holding of policy seminar for high level decision makers of Vietnam 3) cooperaton between KAERI/VAEC, 4) joint feasibility study for the construction of KSNP into Vietnam and technical presentation of KSNP. It is recommended that cooperaion with vietnam be implemented systematically through the long term based basic directions and integrated national strategies.

  16. A study on the establishment of nuclear cooperative relations and future direction between Korea and Vietnam

    International Nuclear Information System (INIS)

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

    2000-10-01

    This study was carried out in order to review the cooperation with vietnam and establish and activate the cooperative relations with Vietnam. During the study, current status of use and development of nuclear energy in vietnam, were investigated including nuclear power plant and cooperative relations between two nations were also established. It was agreed through exchanges of visits of cooperation delegation; 1) exchange of visits of cooperation delegation, 2) holding of policy seminar for high level decision makers of Vietnam 3) cooperaton between KAERI/VAEC, 4) joint feasibility study for the construction of KSNP into Vietnam and technical presentation of KSNP. It is recommended that cooperaion with vietnam be implemented systematically through the long term based basic directions and integrated national strategies

  17. Assessment of job-related educational qualifications for nuclear power plant operators

    International Nuclear Information System (INIS)

    Saari, L.M.; Melber, B.D.; White, A.S.

    1985-04-01

    This report identifies job-related educational qualifications for the nuclear power plant licensed operator positions of reactor operator (RO), senior reactor operator (SRO), and shift supervisor (SS). The extent to which college engineering curriculum covers job-related academic knowledge was assessed. The approach used was to have subject matter experts in the field of general and nuclear engineering curriculum systematically compare college engineering program content to specific academic knowledge identified by a job analysis as necessary for licensed operators. In addition, these experts made judgments concerning levels of formal engineering education necessary for application of knowledge on the job, based on job samples from a job analysis of activities under selected normal and emergency operating sequences

  18. Childhood cancer mortality in relation to the St Lucie nuclear power station

    International Nuclear Information System (INIS)

    Boice, John D Jr; Mumma, Michael T; Blot, William J; Heath, Clark W Jr

    2005-01-01

    An unusual county-wide excess of childhood cancers of brain and other nervous tissue in the late 1990s in St Lucie County, Florida, prompted the Florida Department of Health to conduct a case-control study within the county assessing residential chemical exposures. No clear associations were found, but claims were then made that the release of radioactive substances such as strontium 90 from the St Lucie nuclear power station, which began operating in 1976, might have played a role. To test the plausibility of this hypothesis, we extended by 17 years a previous study of county mortality conducted by the National Cancer Institute. Rates of total cancer, leukaemia and cancer of brain and other nervous tissue in children and across all ages in St Lucie County were evaluated with respect to the years before and after the nuclear power station began operation and contrasted with rates in two similar counties in Florida (Polk and Volusia). Over the prolonged period 1950-2000, no unusual patterns of childhood cancer mortality were found for St Lucie County as a whole. In particular, no unusual patterns of childhood cancer mortality were seen in relation to the start-up of the St Lucie nuclear power station in 1976. Further, there were no significant differences in mortality between the study and comparison counties for any cancer in the time period after the power station was in operation. Relative rates for all childhood cancers and for childhood leukaemia were higher before the nuclear facility began operating than after, while rates of brain and other nervous tissue cancer were slightly lower in St Lucie County than in the two comparison counties for both time periods. Although definitive conclusions cannot be drawn from descriptive studies, these data provide no support for the hypothesis that the operation of the St Lucie nuclear power station has adversely affected the cancer mortality experience of county residents

  19. FY97 nuclear-related budgets total 493 billion yen (4.4 billion dollars)

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    On September 13, the Atomic Energy Commission of Japan announced the estimated nuclear-related budget requests for FY1997 (April, 1997 - Mach, 1998), giving the breakdowns for eight ministries and agencies. The total amount requested by the government bodies was 493.3 billion yen, 0.8% increase as compared with FY96. this figure includes the budget requests of the Science and Technology Agency (STA), the Ministry of International Trade and Industry (MITI), the Ministry of Foreign Affairs, the Ministry of Transport, the Ministry of Agriculture, Forestry and Fisheries, the Okinawa Development Agency, and the Ministry of Home Affairs, but excludes the budget request made by the Ministry of Education. The budget requests of STA and MITI are 360 billion yen and 126 billion yen, respectively. On August 29, STA released its estimated FY97 budget request. The nuclear-related 360.4 billion yen is 0.9% more than that in year before. Of this sum, 199.9 billion yen is in the general account, and 160.6 billion yen is in the special account for power source development. The details of the nuclear-related amounts are explained. On August 26, MITI released its estimated budget request for FY97, and of the nuclear-related 125.7 billion yen (0.1% increase from FY96), 200 million yen is in the general account, and 98.9 billion yen and 26.6 billion yen are in the special accounts for power resource development and power source diversification, respectively. (K.I.)

  20. Application of project management methodology in design management of nuclear safety related structure

    International Nuclear Information System (INIS)

    Chen Mao

    2004-01-01

    This paper focuses on the application of project management methodology in the design management of Nuclear Safety Related Structure (NSRS), considering the design management features of its civil construction. Based on the experiences from the management of several projects, the project management triangle is proposed to be used in the management, to well treat the position of design interface in the project management. Some other management methods are also proposed

  1. Continuing the service of safety-related concrete structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.; Mori, Y.; Arndt, E.G.

    1993-01-01

    The Structural Aging (SAG) Program is addressing the aging management of safety-related concrete structures in nuclear power plants (NPPs) for the purpose of providing improved technical bases for their continued service. The program consists of three technical tasks: materials property data base, structural component assessment/repair technologies, and quantitative methodologies for continued service determinations. Recent accomplishments under each of these tasks are summarized

  2. Attutude-action consistency and social policy related to nuclear technology

    International Nuclear Information System (INIS)

    Lindell, M.K.; Perry, R.W.; Greene, M.

    1980-06-01

    This study reports the results of a further analysis of questionnaire data--parts of which have been previously reported by Lindell, Earle, Hebert and Perry (1978)--that are related to the issue of consistency of attitudes and behavior toward nuclear power and nuclear waste management. Three factors are considered that might be expected to have a significant bearing on attitude-action consistency: social support, attitude object importance and past activism. Analysis of the data indicated that pronuclear respondents were more likely to show consistency of attitudes and actions (66%) than were antinuclear respondents (51%) although the difference in proportions is not statistically significant. Further analyses showed a strong positive relation between attitude-action consistency and perceived social support, measured by the degree to which the respondent believed that close friends and work associated agreed with his attitude. This relationship held up even when controls for attitude object importance and past activism were introduced. Attitude object importance--the salience of the issue of energy shortage--had a statistically significant effect only when perceived social support was low. Past activism had no significant relation to attitude-action consistency. These data suggest that the level of active support for or opposition to nuclear technology will be affected by the distribution of favorable and unfavorable attitudes among residents of an area. Situations in which pro- and antinuclear attitudes are concentrated among members of interacting groups, rather than distributed randomly, are more likely to produce high levels of polarization

  3. Dealing with nuclear-related emotions: an investigation of the despair and empowerment process

    International Nuclear Information System (INIS)

    Lilly-Weber, J.M.

    1986-01-01

    The main goal of this study was to determine the short-term and follow-up effectiveness of despair and empowerment workshops. Such workshops are designed to encourage the expression of feelings related to the nuclear threat (as well as other planetary issues), and to generate a greater sense of personal powerfulness. Results were as follows. At pretest, experimental workshop participants reported a significantly lower level of nuclear-related denial, and were found to be significantly more politically active than control participants. When controlling for these pretest differences, no significant differences were found across conditions at post-test or follow-up. In addition, experimental workshop participants were found to report significantly more powerfulness than nonworkshop control participants at post-test, but no significant post-test differences were found between the two workshop conditions. Open ended evaluation questions, asked only of experimental workshop participants, suggested that most participants responded favorably to the despair and empowerment workshops - particularly in reference to being given the opportunity to express their nuclear-related concerns and to feel supported by others. In summary, this study provides some evidence, despite mixed results, of the effectiveness of despair and empowerment workshops

  4. Assessment of inservice conditions of safety-related nuclear plant structures

    International Nuclear Information System (INIS)

    Ashar, H.; Bagchi, G.

    1995-06-01

    The report is a compilation from a number of sources of information related to the condition Of structures and civil engineering features at operating nuclear power plants in the United States. The most significant information came from the hands-on inspection of the six old plants (licensed prior to 1977) performed by the staff of the Civil Engineering and Geosciences Branch (ECGB) in the Division of Engineering of the Office of Nuclear Reactor Regulation. For the containment structures, most of the information related to the degraded conditions came from the licensees as part of the Licensing Event Report System (10 CFR 50.73), or as part of the requirement under limiting condition of operation of the plant-specific Technical Specifications. Most of the information related to the degradation of other Structures and civil engineering features was extracted from the industry survey, the reported incidents, and the plant visits. The report discusses the condition of the structures and civil engineering features at operating nuclear power plants and provides information that would help detect, alleviate, and correct the degraded conditions of the structures and civil engineering features

  5. Relative economic incentives for hydrogen from nuclear, renewable, and fossil energy sources

    International Nuclear Information System (INIS)

    Gorensek, Maximilian B.; Forsberg, Charles W.

    2009-01-01

    The specific hydrogen market determines the value of hydrogen from different sources. Each hydrogen production technology has its own distinct characteristics. For example, steam reforming of natural gas produces only hydrogen. In contrast, nuclear and solar hydrogen production facilities produce hydrogen together with oxygen as a by-product or co-product. For a user who needs both oxygen and hydrogen, the value of hydrogen from nuclear and solar plants is higher than that from a fossil plant because ''free'' oxygen is produced as a by-product. Six factors that impact the relative economics of fossil, nuclear, and solar hydrogen production to the customer are identified: oxygen by-product, avoidance of carbon dioxide emissions, hydrogen transport costs, storage costs, availability of low-cost heat, and institutional factors. These factors imply that different hydrogen production technologies will be competitive in different markets and that the first markets for nuclear and solar hydrogen will be those markets in which they have a unique competitive advantage. These secondary economic factors are described and quantified in terms of dollars per kilogram of hydrogen. (author)

  6. FY1990 Nuclear-related budget demand totals 398 billion yen, up 2.7%

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    Funds needed to promote the development and utilization of nuclear energy in fiscal 1990 in a planned and integrated way total yen398,427 million on a cash basis, up 2.7% over fiscal 1989. The Science and Technology Agency, which has two major nuclear RandD organizations -- the Japan Atomic Energy Research Institute and the Power Reactor and Nuclear Fuel Development Corp. -- within its jurisdiction, has asked for a total of yen297,765 million (up 5.7%), about three-fourths of the total nuclear-related budget demand. The budget demand of the Ministry of International Trade and Industry aggregates yen96.375 million, down 5.1%. The budget demand of the Ministry of Foreign Affairs is yen2,962 million, including subscriptions and contributions to IAEA, and that of the Ministry of Transport, yen42 million, including research and analysis costs for setting safety standards for the transportation of radioactive materials. The budget demand of the Ministry of Agriculture, Forestry and Fisheries is yen167 million, including costs for the prevention and elimination of melon-flies in the Amami Islands, and for the Tsukuba Agriculture and Forestry Research Exchange Center. (N.K.)

  7. Validation of generic cost estimates for construction-related activities at nuclear power plants: Final report

    International Nuclear Information System (INIS)

    Simion, G.; Sciacca, F.; Claiborne, E.; Watlington, B.; Riordan, B.; McLaughlin, M.

    1988-05-01

    This report represents a validation study of the cost methodologies and quantitative factors derived in Labor Productivity Adjustment Factors and Generic Methodology for Estimating the Labor Cost Associated with the Removal of Hardware, Materials, and Structures From Nuclear Power Plants. This cost methodology was developed to support NRC analysts in determining generic estimates of removal, installation, and total labor costs for construction-related activities at nuclear generating stations. In addition to the validation discussion, this report reviews the generic cost analysis methodology employed. It also discusses each of the individual cost factors used in estimating the costs of physical modifications at nuclear power plants. The generic estimating approach presented uses the /open quotes/greenfield/close quotes/ or new plant construction installation costs compiled in the Energy Economic Data Base (EEDB) as a baseline. These baseline costs are then adjusted to account for labor productivity, radiation fields, learning curve effects, and impacts on ancillary systems or components. For comparisons of estimated vs actual labor costs, approximately four dozen actual cost data points (as reported by 14 nuclear utilities) were obtained. Detailed background information was collected on each individual data point to give the best understanding possible so that the labor productivity factors, removal factors, etc., could judiciously be chosen. This study concludes that cost estimates that are typically within 40% of the actual values can be generated by prudently using the methodologies and cost factors investigated herein

  8. Preservation of primary information related to radiological protection and nuclear safety in the Argentine Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    Chahab, Martin

    2008-01-01

    The preservation of primary information related to Radiological Protection and Nuclear Safety in the Argentine Nuclear Regulatory Authority began as a need of and as significant contribution to the future activities of the institution. Since 2005 a high number of experts have retired from the organization and will continue to do so until 2010. Besides, the primary information that experts possess is technical information produced at the beginning of Argentina's regulatory activity in the 50 's. If this information on account of its relevance - could not be preserved properly or be made available to the future generation of scientists and technicians, such an issue could have a negative impact on the efficiency and effectiveness of the institution in the future. The methodology selected for the project comprises several stages. Overall, the first stage consists in identifying primary information and expert's explicit knowledge through interviews and personal consultations. The second stage consists in converting to digital format the documentation that experts have traditionally kept in paper format. The third stage deals with transferring to a new database the already digitalized information from the computers of experts who are about to retire. The final stage is based on managing this information by creating knowledge maps and socio-grams, experts personal Web sites and a database with a mega browser to make information readily accessible. During the early months of the project, 190 pages have on average been converted to digital format on a daily basis, the equivalent of around 8 MB of information. The men/hours employed for this task has been around 40 minutes per day. As time went by, the method turned more efficient and as a result, some 400 pages were converted to digital format on a daily basis, accounting for 16 MB of information. The men/hours employed for this task has been around 60 minutes per day. Up until mid 2008, more than 1,000 documents have been

  9. Resource Letter MP-3: The Manhattan Project and Related Nuclear Research

    Science.gov (United States)

    Reed, B. Cameron

    2016-10-01

    This Resource Letter is a supplement to the earlier Resource Letters MP-1 and MP-2, and provides further sources on the Manhattan Project and related research. Books, review papers, journal articles, videos, and websites are cited for the following topics: general works, technical works, biographical and autobiographical works, foreign wartime nuclear programs and related allied intelligence, the use of the bombs against Hiroshima and Nagasaki, technical papers of historical interest, postwar policy and technical developments, and educational materials. Together, these three Resource Letters describe nearly 400 sources of information on the Manhattan Project.

  10. Comments on future tasks for Romanian research related to nuclear power

    International Nuclear Information System (INIS)

    Dumitrache, I.

    2000-01-01

    Four main research areas are identified: - nuclear safety, - waste management, - fuel cycles and - plant life management. A significant number of tasks are related to each of these areas. Unfortunately, the cost of the needed research is much too high for the current electricity planning of Romania. Up to now, the international co-operation in CANDU field was not very efficient. Canada, India, Korea and Argentina have distinct intentions related to the use of nuclear power potential. Romania is the only European country interested to investigate CANDU reactor problems. Consequently, the author believes that the future Romanian nuclear power research effort must be clearly divided in two main classes: a. CR = 'Concentrated Research' on specific subjects, aimed to a better understanding, and to a complete solving of the associated problems, when possible, and b. CAR = 'Covering Areas Research' to maintain and update the know-how needed in the nuclear power activities. A given research subject may successively pass from one class to another, if needed; however, for a given period of one-to-five years, the class must be stated for each project, from the beginning. No research effort must be planned in the first class, CR, if the needed resources (human, technical and financial) are not ensured. Usually, the power plant leaders and the Institute researchers wish to dedicate their efforts to investigation of the 'hot problems'. Apparently, they are always right. In fact, the allocation of human and financial resources must be based on a very careful evaluation of the 'conditions required for success'. Otherwise, instead of the needed solution, the research will probably offer' a significant number of original methods, successfully applied', 'a more detailed knowledge of phenomena', 'several patents', a few papers 'published or accepted for publication in world over recognized scientific journals' etc. Although valuable, such results are not accepted instead of the needed

  11. Economic aspects of ecological risk due to nuclear and coal-fired electricity production (general comparison, related to the USSR)

    International Nuclear Information System (INIS)

    Novikov, V.; Wahlstroem, B.; Demin, V.; Lebedev, O.; Ignatiyev, V.

    1991-05-01

    The content of this paper is reflected in the chapter headings: (1) Introduction (2) Environmental problems relating to the coal-fired power plants (3) Costs of environmental protection for coal-fired power plants (4) Comparison of economic efficiency of nuclear and coal-fired power plants (5) Cost of environmental protection for normal operation of a nuclear power plant and its fuel facilities (6) Accidental risk from off-reactor nuclear fuel cycle facilities (7) Conclusion. (Quittner)

  12. The immediate need for US universities to promote research related to a nuclear-weapon-free world

    International Nuclear Information System (INIS)

    Ionno, S.

    1999-01-01

    If disarmament is a goal, then the requisite skills must be fostered in academic research. Too many students today view nuclear weapons as a non-issue. It is crucial that those people in positions of influence encourage more young people to explore in-depth the political, scientific, and social changes that a nuclear-weapon-free world will require. The data presented are based on a search of nuclear-weapons-related keywords in the UMI Dissertation Abstracts Database which includes work from over 1000 North American graduate schools and European Universities. The search was focused on US Phd dissertations between 1987 and 1996. There was no PhDs focused on issues such as: zero-level nuclear-weapons-free world; nuclear-weapons-free zones; decreasing nuclear alert status; a nuclear weapons convention; no-first-use or-no use against non-nuclear-weapons-states; START; French nuclear weapons; a possible 'Eurobomb'; peace groups outside the USA, UK, and Germany; nuclear-weapons secrecy; funding disarmament; the role od UN in a nuclear-weapons-free world; an so on

  13. Performance Monitoring for Nuclear Safety Related Instrumentation at PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

    2015-01-01

    The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on performance monitoring for nuclear safety related instrumentation in TRIGA PUSPATI Reactor (RTP) of based on various parameter of reactor safety instrument channel such as log power, linear power, Fuel temperature, coolant temperature will take into consideration. Methodology of performance on estimation and monitoring is to evaluate and analysis of reactor parameters which is important of reactor safety and control. And also to estimate power measurement, differential of log and linear power and fuel temperature during reactor start-up, operation and shutdown .This study also focus on neutron power fluctuation from fission chamber during reactor start-up and operation. This work will present result of performance monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that performance of nuclear safety related instrumentation will improved the reactor control and safety parameter during reactor start-up, operation and shutdown. (author)

  14. Commercial grade item (CGI) dedication of MDR relays for nuclear safety related applications

    Science.gov (United States)

    Das, Ranjit K.; Julka, Anil; Modi, Govind

    1994-08-01

    MDR relays manufactured by Potter & Brumfield (P&B) have been used in various safety related applications in commercial nuclear power plants. These include emergency safety features (ESF) actuation systems, emergency core cooling systems (ECCS) actuation, and reactor protection systems. The MDR relays manufactured prior to May 1990 showed signs of generic failure due to corrosion and outgassing of coil varnish. P&B has made design changes to correct these problems in relays manufactured after May 1990. However, P&B does not manufacture the relays under any 10CFR50 Appendix B quality assurance (QA) program. They manufacture the relays under their commercial QA program and supply these as commercial grade items. This necessitates CGI Dedication of these relays for use in nuclear-safety-related applications. This paper presents a CGI dedication program that has been used to dedicate the MDR relays manufactured after been used to dedicate the MDR relays manufactured after May 1990. The program is in compliance with current Nuclear Regulatory Commission (NRC) and Electric Power Research Institute (EPRI) guidelines and applicable industry standards; it specifies the critical characteristics of the relays, provides the tests and analysis required to verify the critical characteristics, the acceptance criteria for the test results, performs source verification to quality P&B for its control of the critical characteristics, and provides documentation. The program provides reasonable assurance that the new MDR relays will perform their intended safety functions.

  15. Tendency of nuclear-related words usage at the diet discussion in Japan

    International Nuclear Information System (INIS)

    Tsuboi, Hiroshi

    2004-01-01

    'The Diet Minutes Search Engine', which can search whole sentences of the Diet minutes from that of the 1st Diet session held under the Constitution of Japan in May 1947 to the present one, operated by the National Diet Library, is easily accessible through the Internet. By this system, we can investigate the number of the Diet minutes with which a specific term is included. In this paper, the tendency of deliberations on the nuclear related issues in the Diet is analyzed by investigating 12 nuclear related terms in details. For example, the term 'atomic energy' was used 9.769 times of the committees which account for about 12% out of whole totals 83,204 of the committees of the Diet in 57 years, and 299 times of the year 1957 were the maximum. The breakdown of the term 'atomic energy' are: in the Standing Committee on Budget at 1,618 times (16.6%), and then, committees related the science and technology, the Plenary Session, committees related the commerce and industry, and committees related the foreign-affairs were also taken up about 1,000 times, respectively. (author)

  16. Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures

    International Nuclear Information System (INIS)

    Naus, Dan J.

    2010-01-01

    Nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: degradation mechanisms, damage models, and material performance; assessment and remediation (i.e., component selection, in-service inspection, non-destructive examinations, and remedial actions); and estimation of performance at present or some future point in time (i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk). Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

  17. Development of a relational database for nuclear material (NM) accounting in RC and I Group

    International Nuclear Information System (INIS)

    Yadav, M.B.; Ramakumar, K.L.; Venugopal, V.

    2011-01-01

    A relational database for the nuclear material accounting in RC and I Group has been developed with MYSQL for Back-End and JAVA for Front-End development. Back-End has been developed to avoid any data redundancy, to provide random access of the data and to retrieve the required information from database easily. JAVA Applet and Java Swing components of JAVA programming have been used in the Front-End development. Front-End has been developed to provide data security, data integrity, to generate inventory status report at the end of accounting period, and also to have a quick look of some required information on computer screen. The database has been tested for the data of three quarters of the year 2009. It has been implemented from 1st January, 2010 for the accounting of nuclear material in RC and I Group. (author)

  18. Development of a relational database for nuclear material (NM) accounting in RC and I Group

    Energy Technology Data Exchange (ETDEWEB)

    Yadav, M B; Ramakumar, K L; Venugopal, V [Radioanalytical Chemistry Division, Radiochemistry and Isotope Group, Bhabha Atomic Research Centre, Mumbai (India)

    2011-07-01

    A relational database for the nuclear material accounting in RC and I Group has been developed with MYSQL for Back-End and JAVA for Front-End development. Back-End has been developed to avoid any data redundancy, to provide random access of the data and to retrieve the required information from database easily. JAVA Applet and Java Swing components of JAVA programming have been used in the Front-End development. Front-End has been developed to provide data security, data integrity, to generate inventory status report at the end of accounting period, and also to have a quick look of some required information on computer screen. The database has been tested for the data of three quarters of the year 2009. It has been implemented from 1st January, 2010 for the accounting of nuclear material in RC and I Group. (author)

  19. An analysis method of the press information related with the nuclear activity in Argentina

    International Nuclear Information System (INIS)

    Alsina, Griselda.

    1989-01-01

    The articles published by the newspapers during the year 1987 were analyzed and classified according to their contents. An attribute was assigned to each article (positive, negative or neutral) in agreement with its connotation regarding the nuclear activity in Argentina. An ISIS base system was developed using these data. The purpose of this analysis was to evaluate the influence of the press in the public opinion. The relation between the different variables show the importance and approach (environmental, technico-scientifical or political) given by the press to the different subjects. The results show a general lack of knowledge about nuclear activities and a concern among the readers associated with the environmental risks, which calls for the need to develop an information program for the community. The fundamentals of this program should improve the organization in order to make the information reach the external demands, to promote educational programs and to continuously provide information to the press. (S.M.) [es

  20. Towards assuring the continued performance of safety-related concrete structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.; Mori, Y.; Arndt, E.G.

    1993-01-01

    The Structural Aging (SAG) Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. Pertinent concrete structures are described in terms of their importance, design considerations, and materials of construction. Degradation factors which can potentially impact the ability of these structures to meet their functional and performance requirements are identified. A review of the performance history of the concrete components in nuclear power plants is provided. Accomplishments of the SLAG Program are summarized, i.e., development of the structural materials information center, development of a structural aging assessment methodology, evaluation of models for predicting the remaining life of in-service concrete, review of in-service inspection methods, and development of a methodology for reliability-based condition assessment and life prediction of concrete structures. On-going activities are also described

  1. Hungarian national report on activities related to operator support systems for nuclear power plants

    International Nuclear Information System (INIS)

    Adorjan, F.; Lux, I.; Vegh, J.; Vegh, E.

    1993-01-01

    According to the summary report of the Co-ordinated Research Meeting on ''Operator Support Systems in Nuclear Power Plants'', 13-16 October 1992, the national reports shall cover the following topics: General summary of the national activity; description of the results in the framework of the CRP; overview of the OSS related recent national activity. Accordingly, in the first section we give an overview of the operator support systems developed in Hungary. The second section summarizes the data collected in order to comply with the Tasks 4.1.1 and 4.1.2 of the CRP. In the third section we summarize the most recent works pertaining to the development and application of OSS at nuclear power plants

  2. Significant change of predictions related to the future of nuclear power

    International Nuclear Information System (INIS)

    Dumitrache, Ion

    2002-01-01

    During the last two decades of the 20th century, nuclear power contribution increased slowly in the world. This trend was mainly determined by the commissioning of new nuclear power plants, NPP, in the non-developed countries, except for Japan and South Korea. Almost all the forecasts offered the image of the stagnant nuclear power business. Sweden, Germany, Holland and Belgium Governments made clear the intention to stop the production of electricity based on fission. Recently, despite the negative effects on nuclear power of the terrorism events of September 11, 2001, the predictions related to the nuclear power future become much more optimistic. USA, Japan, South Korea and Canada made clear that new NPPs will offer their significant electricity contribution several decades, even after years 2020-2030. Moreover, several old NPP from USA obtained the license for an additional 20 years period of operation. The analysis indicated that most of the existing NPP in USA may increase the level of the maximum global power defined by the initial design. In the European Union the situation is much more complicated. About 35% of the electricity is based now on fission. Several countries, like Sweden and Germany, maintain the position of phasing out the NPPs, as soon as the licensed life-time is over. Finland decided to build a new power plant. France is very favorable to nuclear power, but does not need more energy. In the UK several very old NPP will be shut down, and companies like BNFL and British Energy intend to build new NPP, based on Westinghouse or AECL-Canada advanced reactors. Switzerland and Spain are favorable to the future use of nuclear power. In the eastern part of Europe, almost all the countries intend to base their electricity production on coal, fission, hydro and gas, nuclear contribution being significant. The most impressive increases of nuclear power output are related to Asia; in China, from 2.2 Gwe in 1999, to 18.7 Gwe in 2020, reference case, or 10

  3. Childhood cancer incidence in relation to distance from the former nuclear testing site in Semipalatinsk, Kazakhstan.

    Science.gov (United States)

    Zaridze, D G; Li, N; Men, T; Duffy, S W

    1994-11-15

    Rates of childhood cancer between 1981 and 1990 in the 4 administrative zones of Kazakhstan were studied to assess the relationship, if any, with distance from nuclear testing sites. Risk of various cancers among children aged 14 years or younger were estimated in relation to distance from (1) a site where testing in air was performed before 1963, (2) a site where underground testing took place thereafter, and (3) a reservoir, known as "Atom Lake," created by 4 nuclear explosions in 1965. Risk of acute leukaemia rose significantly with increasing proximity of residence to the testing areas, although the absolute value of the risk gradient was relatively small. The relative risk for those living less than 200 km from the air-testing site was 1.76 compared with those living 400 km or more away from the site. Similar relative risks were observed for the underground site and "Atom Lake." There was also some evidence of increased risk of brain tumours in association with proximity to the test sites. In 2 of the 4 zones studied, there was substantial regional variation in acute leukaemia rates which was not attributable to distance from the test site. The findings may be affected by potential confounders, notably urban/rural status and ethnic factors.

  4. Definitional Hegemony as a Public Relations Strategy: The Rhetoric of the Nuclear Power Industry after Three Mile Island.

    Science.gov (United States)

    Dionisopoulos, George N.; Crable, Richard E.

    1988-01-01

    Examines (1) definitional hegemony as one of several rhetorical options available to issue managers; (2) the post-accident rhetorical context of the Three Mile Island nuclear crisis; and (3) the specific strategies utilized to deal with this crisis. Assesses the nuclear industry's public relations efforts. (MS)

  5. Analysis of data related to the updating of diagnosis reference levels in radiology and nuclear medicine. Assessment 2007-2008

    International Nuclear Information System (INIS)

    2010-01-01

    This report presents the results of the analysis of 'patient' dosimetric data which radiology and nuclear medicine establishments must supply every year to the IRSN (the French Radioprotection and Nuclear Safety Institute) according to a decree related to diagnosis reference levels in radiology and nuclear medicine. The analysed dosimetric data concern assessments performed during 2007 and 2008. For the different concerned practices (radiology, scanography, nuclear medicine), the report proposes a presentation and a discussion of global data, and then a presentation of data either for different types of examination on adults and on children, or for the different parts of the body

  6. Amendment of the atomic energy basic law and other related laws and establishment of the nuclear safety commission

    International Nuclear Information System (INIS)

    Ochi, Kenji

    1978-01-01

    The Atomic Energy Basic Law and related several laws were amended in the recent diet session. The amendment of the laws was requested after the radiation leakage from nuclear-powered ship ''Mutsu''. The reform of administrative system of atomic energy development and utilization are consisted of two important points: one is to establish the Nuclear Safety Commission for strengthening nuclear safety administration, and the other is to give an authority to each ministry or agency to regulate nuclear power reactor from the establishment to operation according to its original mission. (author)

  7. Hexagon's atom. History of the relation between France and the nuclear energy

    International Nuclear Information System (INIS)

    Leridon, A.

    2009-01-01

    As soon as the end of the second World war, France, with the creation of the atomic energy commission (CEA), started a research program for the development of civil applications of nuclear energy, but also for the development of weapons. The come back of C. De Gaulle at the head of the country fostered the research efforts in both domains. Then, the election of G. Pompidou contributed to separate the military and civilian applications and led to the launching of the big French nuclear power program in March 1974. Nuclear contestation has shown a progressive development too, encouraged by the main accidents of Three Mile Island and more recently Tchernobyl. The debate has progressively moved with time from the safety of power plants towards the management of spent fuels. In this book, the author presents some particularities which are characteristic of France: the remnants of some kind of a 'scientism' inherited of the first half of the 20. century, the particular relations between 'scientists' and the republic, the policy of secret, the power of the senior officials corps and technocrats, the French taste for big works, the republican Jacobinism, the liabilities more easily given to State corps than to industrialists, and finally, on the opponents side, the search for the spectacular action to the detriment of efficiency. In this big fight, the know-how of nationalized companies, EdF and CEA, has been undeniable. The political power has very often taken refuge behind their competence but sometimes with a lack of democracy

  8. Defining criteria related to wastes for use in multi-criteria decision tool for nuclear accidents

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo N.G.; Guimaraes, Jean R.D., E-mail: dneves@biof.ufrj.br, E-mail: jeanrdg@biof.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto de Biofisica Carlos Chagas Filho; Rochedo, Elaine R.R.; De Luca, Christiano, E-mail: elainerochedo@gmail.com, E-mail: christiano_luca@hotmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Rochedo, Pedro R.R., E-mail: rochedopedro@gmail.com [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto Alberto Luiz Coimbra de Pos-Graduacao e Pesquisa de Engenharia

    2013-07-01

    The selection of protective measures and strategies for remediation of contaminated areas after a nuclear accident must be based on previously established criteria in order to prevent stress of the population and the unnecessary exposure of workers. After a nuclear accident resulting in environmental contamination, decisions on remediation of areas is complex due to the large numbers of factors involved in decontamination processes. This work is part of a project which aims to develop a multi-criteria tool to support a decision-making process in cases of a radiological or a nuclear accident in Brazil. First, a database of remediation strategies for contaminated areas was created. In this process, the most relevant aspects for the implementation of these strategies were considered, including technical criteria regarding aspects related to the generation of wastes in a reference urban area, which are discussed in this paper. The specific objective of this study is to define criteria for the aspects of radioactive wastes, resulted by the implementation of some urban measures, in order to be incorporated in a multi-criteria decision tool. Main aspects considered were the type, the amount and the type of treatment necessary for each procedure. The decontamination procedures are then classified according to the selected criteria in order to feed the multi-criteria decision tool. This paper describes the steps for the establishment of these criteria and evaluates the potential for future applications in order to improve predictions and to support the decisions to be made. (author)

  9. The contribution of nuclear-related technical cooperation to national development

    International Nuclear Information System (INIS)

    Cook, D.

    1988-01-01

    The present situation of nuclear technical assistance and the IAEA's programs are reviewed. The perspectives of the developing and of the developed countries are discussed. Australia's aid administrators have been showing an increasing preference for administering its nuclear technical assistance through the Regional Cooperation Agreement for Asia and the Pacific (RCA), because of its direct benefits to the countries in the region, its flexibility, its emphasis on training, and its cooperative nature. The RCA also benefits from IAEA management and IAEA and United Nations Development Program funding. Two examples of Australia's successful RCA activities are the 1988 radiation protection training course held in Sydney and one of the many individual projects within the 1980-86 RCA hydrology program - the application of radioisotope tracer techniques to locating the seepage areas in the Pedu dam in Kedah State, Malaysia. Australia's experience has shown that project design, successful training of the right people, adequate infrastructure in both donor and recipient countries, and detailed post-project evaluation are the keys to successful project implementation. The RCA has achieved wide recognition as a successful tool in nuclear-related technology transfer

  10. Defining criteria related to wastes for use in multi-criteria decision tool for nuclear accidents

    International Nuclear Information System (INIS)

    Silva, Diogo N.G.; Guimaraes, Jean R.D.; Rochedo, Elaine R.R.; De Luca, Christiano; Rochedo, Pedro R.R.

    2013-01-01

    The selection of protective measures and strategies for remediation of contaminated areas after a nuclear accident must be based on previously established criteria in order to prevent stress of the population and the unnecessary exposure of workers. After a nuclear accident resulting in environmental contamination, decisions on remediation of areas is complex due to the large numbers of factors involved in decontamination processes. This work is part of a project which aims to develop a multi-criteria tool to support a decision-making process in cases of a radiological or a nuclear accident in Brazil. First, a database of remediation strategies for contaminated areas was created. In this process, the most relevant aspects for the implementation of these strategies were considered, including technical criteria regarding aspects related to the generation of wastes in a reference urban area, which are discussed in this paper. The specific objective of this study is to define criteria for the aspects of radioactive wastes, resulted by the implementation of some urban measures, in order to be incorporated in a multi-criteria decision tool. Main aspects considered were the type, the amount and the type of treatment necessary for each procedure. The decontamination procedures are then classified according to the selected criteria in order to feed the multi-criteria decision tool. This paper describes the steps for the establishment of these criteria and evaluates the potential for future applications in order to improve predictions and to support the decisions to be made. (author)

  11. Development of a Method for Quantifying the Reliability of Nuclear Safety-Related Software

    International Nuclear Information System (INIS)

    Yi Zhang; Golay, Michael W.

    2003-01-01

    The work of our project is intended to help introducing digital technologies into nuclear power into nuclear power plant safety related software applications. In our project we utilize a combination of modern software engineering methods: design process discipline and feedback, formal methods, automated computer aided software engineering tools, automatic code generation, and extensive feasible structure flow path testing to improve software quality. The tactics include ensuring that the software structure is kept simple, permitting routine testing during design development, permitting extensive finished product testing in the input data space of most likely service and using test-based Bayesian updating to estimate the probability that a random software input will encounter an error upon execution. From the results obtained the software reliability can be both improved and its value estimated. Hopefully our success in the project's work can aid the transition of the nuclear enterprise into the modern information world. In our work, we have been using the proprietary sample software, the digital Signal Validation Algorithm (SVA), provided by Westinghouse. Also our work is being done with their collaboration. The SVA software is used for selecting the plant instrumentation signal set which is to be used as the input the digital Plant Protection System (PPS). This is the system that automatically decides whether to trip the reactor. In our work, we are using -001 computer assisted software engineering (CASE) tool of Hamilton Technologies Inc. This tool is capable of stating the syntactic structure of a program reflecting its state requirements, logical functions and data structure

  12. Criteria adopted by the Argentine Nuclear Regulatory Authority for assessing digital systems related to safety

    International Nuclear Information System (INIS)

    Terrado, Carlos A.; Chiossi, Carlos E.; Felizia, Eduardo R.; Roca, Jose L.; Sajaroff, Pedro M.

    2004-01-01

    Following the technological evolution in Instrumentation and Control (I and C) design, analog components are replaced by digital in almost every industry. Due to growing challenges of obsolescence and increasing maintenance costs, licensees of nuclear and radioactive installations are increasingly upgrading or replacing their existing I and C analog systems and components. In existing installations, this involves analog to digital replacements. In new installations design, the use of digital I and C systems is being considered from the very beginning, becoming a good alternative, even in safety applications. Up to now, in Argentina, there is no specific rules for safety-related digital systems, every safety system, analog or digital, must comply with the same generic regulations. The Nuclear Regulatory Authority is now developing criteria to assess digital systems related to safety in nuclear and radioactive installations. In this paper some of those criteria, based on local research and the recognized state of the art, are explained. From a regulatory point of view, the use of digital technology often raises new technical and licensing issues, particularly for safety-related applications. Examples include new failure modes, the potential for common-cause failure of redundant components, electromagnetic interference (EMI), software verification and validation, configuration management and a more exhaustive quality assurance system. The mentioned criteria comprehend the design, operation, maintenance and acquisition of digital systems and components important to safety. The main topics covered are: requirements specifications for digital systems, planning and documentation for digital system development, effectiveness of a digital system, commercial off the shelf (COTS) treatment and considerations involving tools for software development. (author)

  13. Seismic design and performance of nuclear safety related RC structures based on new seismic design principle

    International Nuclear Information System (INIS)

    Murugan, R.; Sivathanu Pillai, C.; Chattopadhyaya, S.; Sundaramurthy, C.

    2011-01-01

    Full text: Seismic design of safety related Reinforced Concrete (RC) structures of Nuclear power plants (NPP) in India as per the present AERB codal procedures tries to ensure predominantly elastic behaviour under OBE so that the features of Nuclear Power Plant (NPP) necessary for continued safe operation are designed to remain functional and prevent accident (collapse) of NPP under SSE for which certain Structures, Systems and Components (SSCs) those are necessary to ensure the capability to shut down the reactor safely, are designed to remain functional. While the seismic design principles of non safety related structures as per Indian code (IS 1893-2002) are ensuring elastic behaviour under DBE and inelastic behaviour under MCE by utilizing ductility and energy dissipation capacity of the structure effectively. The design principle of AERB code is ensuring elastic behaviour under OBE and is not enlightening much inference about the overall structural behaviour under SSE (only ensuring the capability of certain SSCs required for safe shutdown of reactor). Various buildings and structures of Indian Nuclear power plant are classified from the basis of associated safety functions in a descending order in according with their roles in preventions and mitigation of an accident or support functions for prevention. This paper covers a comprehensive seismic analysis and design methodology based on the AERB codal provisions followed for safety related RC structure taking Diesel Generator Building of PFBR as a case study and study and investigates its performance under OBE and SSE by carrying out Non-linear static Pushover analysis. Based on the analysis, observed variations, recommendations are given for getting the desired performance level so as to implement performance based design in the future NPP design

  14. Role of security during safety-related emergencies at nuclear power plants

    International Nuclear Information System (INIS)

    Cardwell, R.G.; Moul, D.A.; McBride, J.A.; Wilson, C.W.

    1984-03-01

    This report provides an analysis of the literature and on-site data gathering relating to the actions of security forces at licensed nuclear power plants during safety-related emergencies. Literature search findings and results of on-site data gathering are furnished and subjected to analysis. Taking into account the analysis provided, appropriate recommendations are presented. Recommendations are keyed as to how improvements can be made in the regulatory approach and licensee planning and procedures as they relate to the subject matter under examination. In addition, certain technological problems and issues are examined within the context of the study. Appendices provide the results of the literature search, an annotated bibliography, the Data Collection Guide used, and additional details regarding certain aspects of the study that are relevant for further explication of the body of the report

  15. Problems in complying with regulations related to low activity materials: Nuclear fuel cycle issues

    International Nuclear Information System (INIS)

    Coates, R.

    1997-01-01

    The range of issues relating to exemption and clearance within the nuclear fuel cycle is reviewed. It is concluded that current regulatory systems and the underpinning technical criteria are potentially inflexible and over-conservative, resulting in an imbalance in the use of society's resources. Proposals are developed for establishing practical requirements which would ensure that resource allocation is commensurate with the magnitude of the risks and in broad proportion to the other risks affecting society. Such an approach would be consistent with the concept of sustainability and could support wider public acceptance of these issues. Within this approach the practical distinction between exemption and clearance is challenged. (author)

  16. Quality factors quantification/assurance for software related to safety in nuclear power plants

    International Nuclear Information System (INIS)

    Nunez McLeod, J.E.; Rivera, S.S.

    1997-01-01

    Quality assurance plan is needed to guarantee the software quality. The use of such a plan involves activities that should take place all along the life cycle, and which can be evaluated using the so called quality factors. This is due to the fact that the quality itself cannot be measured, but some of its manifestations can be used for this purpose. In the present work, a methodology to quantify a set of quality factors is proposed, for software based systems to be used in safety related areas in nuclear power plants. (author) [es

  17. Advancements in the design of safety-related systems and components of the MARS nuclear plant

    International Nuclear Information System (INIS)

    Caira, M.; Caruso, G.; Naviglio, A.; Sorabella, L.; Farello, C.E.

    1992-01-01

    In the paper, the advancements in the design of safety-related systems and components of the MARS nuclear plant, equipped with a 600 MW th PWR, are described. These advancements are due to the special safety features of this plant, which relies completely on inherent and passive safety. In particular, the new steps of the design of the innovative, completely passive, and with an unlimited autonomy Emergency core Cooling System are described, together with the characteristics of the last version of the steam generator, developed in a new design involving disconnecting components, for a fast erection and an easy maintenance. (author)

  18. External main-induced events in relation to nuclear power plant siting

    International Nuclear Information System (INIS)

    1981-01-01

    This safety Guide recomments procedures and provides information for use in implementing that part of the code of safety in Nuclear Power Plant Siting (IAEA Safety Series No. 50-C-S) which concerns man-induced events external to the plant, up to the evaluation of corresponding design basis parameters. Like the code, the Guide forms part of the IAEA's programme, referred to as the NUSS programme, for establishing codes of practice and safety Guides relating to land-based stationary thermal neutron power plants

  19. History of the bubble chamber and related active- and internal-target nuclear tracking detectors

    International Nuclear Information System (INIS)

    Becchetti, F.D.

    2015-01-01

    Donald Glaser, 1960 Nobel laureate in Physics, recently passed away (2013), as have many of his colleagues who were involved with the early development of bubble chambers at the University of Michigan. In this paper I will review those early years and the subsequent wide-spread application of active-target (AT) bubble chambers that dominated high-energy physics (HEP) research for over thirty years. Some of the related, but more modern nuclear tracking detectors being used in HEP, neutrino astrophysics and dark-matter searches also will be discussed

  20. Safety-related instrumentation and control systems for nuclear power plants

    International Nuclear Information System (INIS)

    1984-01-01

    This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety but are not safety systems. The Guide is intended to expand paragraphs 3.1, 3.2 and 3.3 of the Code of Practice on Design for Safety of Nuclear Power Plants (IAEA Safety Series No.50-C-D) in the area of I and C systems important to safety and refers to them as safety-related I and C systems. It also gives guidance and enumerates requirements for multiplexing and the use of the digital computers employed in this area

  1. MAT-DB - A database for nuclear energy related materials data

    International Nuclear Information System (INIS)

    Over, H.H.

    2009-01-01

    The web-enabled materials database (Mat-DB) of JRC-IE has a long-term history in storing materials test data resulting from European and international research projects. The database structure and the user-guidance has bee permanently updated improved and optimized. The database is implemented in the secure ODIN portal: https://odin.jrc.ec.europa.eu of JRC-IE. This architecture guarantees fast access to confidential and public data and documentation which are stored in an inter-related document management database (DoMa). It is a part of JRC's nuclear knowledge management. Mat-DB hosts the whole pool of IAEA surveillance data of reactor pressure vessel materials from different nuclear power plants of the member states. Mat-DB contains also thousands of European GEN IV reactor systems related R and D materials data which are an important basis for the evaluating and extrapolating design data for candidate materials and setting up design rules covering high temperature exposure, irradiation and corrosion. Those data and rules would match also fusion related components. Mat-DB covers thermo-mechanical and thermo-physical properties data of engineering alloys at low, elevated and high temperatures for base materials and joints, including irradiated materials for nuclear fission and fusion applications, thermal barrier coated materials for gas turbines and properties of corroded materials. The corrosion part refers to weight gain/loss data of high temperature exposed engineering alloys and ceramic materials. For each test type the database structure reflects international test standards and recommendations. Mat-DB features an extensive library of evaluation programs for web-enabled assessment of uniaxial creep, fatigue, crack growth and high temperature corrosion properties. Evaluations can be performed after data retrieval or independently of Mat-DB by transferring other materials data in a given format to the programs. The fast evaluation processes help the user to

  2. Modification and backfitting at the Oskarshamn Nuclear Power Plant Unit 2 in safety related systems

    International Nuclear Information System (INIS)

    Karlsson, Leif; Nilsson, Ove; Lidh, B.

    1995-05-01

    This report is intended for use by the Swedish Nuclear Power Inspectorate. It has been published to enable comparison of modification and backfitting implemented at Oskarshamn-2, with those implemented at other plants, both domestic and abroad. The report summarizes the more notable modifications and backfitting carried out on any safety-related equipment, or software, at Barsebaeck, and covers the decade 1984 to 1994. Modifications to hardware, and to some extent to software, are catalogued, but not described in any detail. No general procedures (operational or maintenance) are dealt with. 3 refs

  3. A cost summary applicable to seismic construction and maintenance of nuclear safety related piping

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1995-01-01

    This paper presents a summary of costs applicable to nuclear power plant piping for an earthquake defined as 0.2 SSE-PGA as a function of three eras of initial construction: 1967--1974, 1974--1981 and 1981--1990. Costs have been presented for both new construction and maintenance in operating plants using both the original PSAR-FSAR design criteria and current SRP requirements. It is recommended that the cost information contained in this report be considered in evaluating the cost benefit relationships associated with current and proposed future changes in seismic design procedures applicable to safety-related piping systems

  4. Public-relation and countermeasure in crisis in the area of nuclear and radiation safety

    International Nuclear Information System (INIS)

    Wang Ruiping

    2009-01-01

    We are living in the world filling crises, with information transparency and economy globalization. The public-relation is one of important measures against those crises, whose achievements have been proved in our past practices. The countermeasure is a complementarity with propaganda and crises preparation for crises. It is a new field, needing new ideas and technology to fit developing situations, and new conceptions and countermeasures to set it up. In the article, the author is trying to explain why to apply the measure to answer crises in the nuclear and radiation safety management. (author)

  5. Global partnering related to nuclear materials safeguards and security - A pragmatic approach to international safeguards work

    International Nuclear Information System (INIS)

    Stanford, Dennis

    2007-01-01

    This paper documents issues Nuclear Fuel Services, Inc. has addressed in the performance of international work to safeguards and security work. It begins with a description of the package we put together for a sample proposal for the Global Threat Reduction Initiative, for which we were ranked number one for technical approach and cost, and concludes with a discussion of approaches that we have taken to performing this work, including issues related to performing the work as part of a team. The primary focus is on communication, workforce, equipment, and coordination issues. Finally, the paper documents the rules that we use to assure the work is performed safely and successfully. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    1982-03-01

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

  7. Opinions and social values related to the disposal of nuclear waste in Switzerland

    Energy Technology Data Exchange (ETDEWEB)

    Seidl, Roman; Stefanelli, Annalisa [ETH Zurich (Switzerland). Inst. for Environmental Decisions

    2015-07-01

    Discourse in media and politics about nuclear waste and its disposal in so-called ''Endlager'' (Germany) or ''Tiefenlager'' (geological deep ground repositories; Switzerland) often consider positions and arguments of diverse interest groups. Mostly polarized discussions are in the focus. However, we find a temporally consistent pattern of four opinion clusters in German speaking communities in Switzerland: one cluster in favor of a repository (perceiving mostly benefits) and one cluster with high-risk ratings opposing a repository; a third cluster of moderate opposition is ambivalent regarding risks and benefits, whereas a fourth cluster seems indifferent. Moreover, in qualitative interviews we found high importance of the development of the participatory process. Participants were sensitive to value related issues such as absence of political influence, transparency, comprehensive and independent information. Important to note is the problem that some of these values can be used as pro- or con-argument regarding a repository by different individuals. For instance, all agree that safety is essential - but both conclusions, to be for or against a repository, are possible. A recent study focused on the arguments, underlying people's opinions. The salient arguments that participants report are related to the sense of responsibility for the country to store safely the nuclear waste and to avoid its export. Moreover, people recognize the necessity of a safe solution for the storage in order to preserve future generations from the risks of nuclear waste. These arguments may be relevant for the fact that participants, on average, have a favorable position regarding a deep ground repository in Switzerland.

  8. Opinions and social values related to the disposal of nuclear waste in Switzerland

    International Nuclear Information System (INIS)

    Seidl, Roman; Stefanelli, Annalisa

    2015-01-01

    Discourse in media and politics about nuclear waste and its disposal in so-called ''Endlager'' (Germany) or ''Tiefenlager'' (geological deep ground repositories; Switzerland) often consider positions and arguments of diverse interest groups. Mostly polarized discussions are in the focus. However, we find a temporally consistent pattern of four opinion clusters in German speaking communities in Switzerland: one cluster in favor of a repository (perceiving mostly benefits) and one cluster with high-risk ratings opposing a repository; a third cluster of moderate opposition is ambivalent regarding risks and benefits, whereas a fourth cluster seems indifferent. Moreover, in qualitative interviews we found high importance of the development of the participatory process. Participants were sensitive to value related issues such as absence of political influence, transparency, comprehensive and independent information. Important to note is the problem that some of these values can be used as pro- or con-argument regarding a repository by different individuals. For instance, all agree that safety is essential - but both conclusions, to be for or against a repository, are possible. A recent study focused on the arguments, underlying people's opinions. The salient arguments that participants report are related to the sense of responsibility for the country to store safely the nuclear waste and to avoid its export. Moreover, people recognize the necessity of a safe solution for the storage in order to preserve future generations from the risks of nuclear waste. These arguments may be relevant for the fact that participants, on average, have a favorable position regarding a deep ground repository in Switzerland.

  9. Use of nuclear and related analytical techniques in environmental research as exemplified by selected air pollution studies

    International Nuclear Information System (INIS)

    Smodis, B.; Jacimovic, R.; Jeran, Z.; Stropnik, B.; Svetina, M.

    2000-01-01

    Among nuclear and nuclear related analytical techniques, neutron activation analysis and X-ray fluorescence spectrometry proved to be particularly useful for environmental studies owing to their nondestructive character and multi element capability. This paper emphasizes their importance among other multielement analytical methods by discussing their specific role due to specific physics basis, quite different to other destructive non-nuclear methods, and by summarizing results obtained in several studies related to air pollution research, including analyses of airborne particulate matter, water samples, lichens and mosses. (author)

  10. U.S. regulatory initiatives related to nuclear research and development

    International Nuclear Information System (INIS)

    Carr, K.M.

    1987-01-01

    U.S. Nuclear Regulatory Commission is working to improve its 'early warning system' in order to recognize trends and identify potential safety problems whether the source of the problems relates to a reactor safety system or to a utility management or organizational issue. The Commission has approved the use of performance indicators to provide a more effective means for top NRC management and the Commission to recognize changes in the safety performance of operating reactors. Research also has a leading role in assuring the safety of the evolving nuclear technology. The primary role of NRC's program is to provide a sound technical basis for decisions on the resolution of safety issues for the current generation of plants and safety issues that may arise for future designs. Topical areas essential to resolve the remaining safety issues or uncertainties related to LWR operation are human factors and accident management, life extension and plant aging, studies on containment integrity, severe accident risk analysis and uncertainty resolution, reliability engineering and the analysis of thermal-hydraulic transients. (Nogami, K.)

  11. Low-mass neutron stars: universal relations, the nuclear symmetry energy and gravitational radiation

    Science.gov (United States)

    O. Silva, Hector; Berti, Emanuele; Sotani, Hajime

    2016-03-01

    Compact objects such as neutron stars are ideal astrophysical laboratories to test our understanding of the fundamental interactions in the regime of supranuclear densities, unachievable by terrestrial experiments. Despite recent progress, the description of matter (i.e., the equation of state) at such densities is still debatable. This translates into uncertainties in the bulk properties of neutron stars, masses and radii for instance. Here we will consider low-mass neutron stars. Such stars are expected to carry important information on nuclear matter near the nuclear saturation point. It has recently been shown that the masses and surface redshifts of low-mass neutron stars smoothly depend on simple functions of the central density and of a characteristic parameter η associated with the choice of equation of state. Here we extend these results to slowly-rotating and tidally deformed stars and obtain empirical relations for various quantities, such as the moment of inertia, quadrupole moment and ellipticity, tidal and rotational Love numbers, and rotational apsidal constants. We discuss how these relations might be used to constrain the equation of state by future observations in the electromagnetic and gravitational-wave spectra.

  12. Relation between molecular electronic structure and nuclear spin-induced circular dichroism

    DEFF Research Database (Denmark)

    Štěpánek, Petr; Coriani, Sonia; Sundholm, Dage

    2017-01-01

    with spatially localized, high-resolution information. To survey the factors relating the molecular and electronic structure to the NSCD signal, we theoretically investigate NSCD of twenty structures of the four most common nucleic acid bases (adenine, guanine, thymine, cytosine). The NSCD signal correlates...... with the spatial distribution of the excited states and couplings between them, reflecting changes in molecular structure and conformation. This constitutes a marked difference to the nuclear magnetic resonance (NMR) chemical shift, which only reflects the local molecular structure in the ground electronic state....... The calculated NSCD spectra are rationalized by means of changes in the electronic density and by a sum-over-states approach, which allows to identify the contributions of the individual excited states. Two separate contributions to NSCD are identified and their physical origins and relative magnitudes...

  13. Age-Related Degradation of Nuclear Power Plant Structures and Components

    International Nuclear Information System (INIS)

    Braverman, J.; Chang, T.-Y.; Chokshi, N.; Hofmayer, C.; Morante, R.; Shteyngart, S.

    1999-01-01

    This paper summarizes and highlights the results of the initial phase of a research project on the assessment of aged and degraded structures and components important to the safe operation of nuclear power plants (NPPs). A review of age-related degradation of structures and passive components at NPPs was performed. Instances of age-related degradation have been collected and reviewed. Data were collected from plant generated documents such as Licensing Event Reports, NRC generic communications, NUREGs and industry reports. Applicable cases of degradation occurrences were reviewed and then entered into a computerized database. The results obtained from the review of degradation occurrences are summarized and discussed. Various trending analyses were performed to identify which structures and components are most affected, whether degradation occurrences are worsening, and what was the most common aging mechanisms. The paper also discusses potential aging issues and degradation-susceptible structures and passive components which would have the greatest impact on plant risk

  14. Radioactive waste management: the relation between geological disposal and advanced nuclear technologies

    International Nuclear Information System (INIS)

    Schroder, Jantine

    2013-01-01

    Throughout this paper we aim to scope the most pregnant themes, issues and research questions concerning the relation between geological disposal and advanced nuclear technologies in the broad context of radioactive waste management. Especially from a socio-technical point of view the mutual impacts, divergences and complementarities between both strategies seem to have received limited dedicated examination up until today. Specific attention is paid to the main arguments that seem to underpin both research streams, related to how the issue of radioactive waste is contextualized and which problems and solutions are consequently identified and proposed. Ultimately we aim to encourage scientifically integer communication and constructive dialogue between both fields, to investigate the common possibilities of enhancing radioactive waste management as a whole. (authors)

  15. Nuclear power and world energy needs: Looking ahead. Address at the 'Quatrieme Annuelle Conference Strategique', Institut de Relations Internationales et Strategiques, Paris, 5 May 1999

    International Nuclear Information System (INIS)

    ElBaradei, M.

    1999-01-01

    In his address at the 'Quatrieme Annuelle Conference Strategique' (Institut de Relations Internationales Strategiques, Paris, 5 May 1999), the Director General of the IAEA presented the future role of the nuclear power from Agency's perspective, emphasizing the following aspects: nuclear power and the environment, nuclear safety and public confidence, economic competitiveness, and the importance of nuclear verification and prevention of illicit trafficking

  16. Overview of the age-related degradation of nuclear power plant structures

    International Nuclear Information System (INIS)

    Deng, Daniel

    2004-01-01

    License renewal of nuclear power plants is an issue of increasing interest to the U.S. nuclear industry and the U.S. NRC. This paper presents and evaluates the plausible age-related degradation mechanisms that may affect the concrete and steel containment structures and other Class I structures to continue to perform their safety functions. Preventive and/or mitigative options are outlined for managing degradation mechanisms that could significantly affect plant performance during the license renewal period. The provided technical information and the degradation management options may be used as references for comparison with plant specific conditions to ensure that age-related degradation is controlled during the license renewal term. Plausible degradation mechanisms described and analyzed as they may affect the concrete, reinforcing steel, containment steel shell, prestressed-tendon, steel liner and other structural components typically used in Class I structures. The significance of these age-related degradation mechanisms to the structural components are evaluated, giving consideration to the design basis and quality of construction; typical service conditions; operating and maintenance history; and current test, inspection and refurbishment practices for containment and Class I structures. Degradation mechanisms which cannot be generically dispositioned on the basis of the two-step approach: (1) they will not cause significant degradation, or (2) any potential degradation will be bounded by current test, inspection, analytical evaluation, and/or refurbishment programs are identified. Aging degradation management measures are recommended to address the remaining age-related degradation mechanisms. A three-phase approach for the management of the containment and Class I structures is introduced. Various techniques, testing tools and the acceptable criteria for each step of the evaluation of the structures status are provided. The preventive and mitigative

  17. Assessment and management of aging of nuclear power plant safety-related structures

    International Nuclear Information System (INIS)

    Naus, D.J.; Graves, H.L. III; Ellingwood, B.R.

    2003-01-01

    Background information and data have been developed for improving existing and developing new methods to assist in quantifying the effects of age-related degradation on the performance of nuclear power plant (NPP) safety-related structures. Factors that can lead to age-related degradation of safety-related structures are identified and their manifestations described. Current regulatory testing and inspection requirements are reviewed and a summary of degradation experience presented. Techniques commonly used to inspect NPP concrete structures to assess and quantify age-related degradation are summarized. An approach for conduct of condition assessments of structures in NPPs is presented. Criteria, based primarily on visual indications, are provided for use in classification and assessment of concrete degradation. Materials and techniques for repair of degraded structures are noted and guidance provided on repair options available for various forms of degradation. A probabilistic methodology for condition assessment and reliability-based life prediction has been developed and applied to structures subject to combinations of structural load processes and to structural systems. The methodology has also been used to investigate optimization of in-service inspection and maintenance strategies to maintain failure probability below a specified target value as well as to minimize costs. Fragility assessments involving analytical solutions and finite-element methods have been utilized to predict the effect of aging degradation on structural component performance. (author)

  18. Mitochondrial and Nuclear DNA Damage and Repair in Age-Related Macular Degeneration

    Directory of Open Access Journals (Sweden)

    Janusz Blasiak

    2013-01-01

    Full Text Available Aging and oxidative stress seem to be the most important factors in the pathogenesis of age-related macular degeneration (AMD, a condition affecting many elderly people in the developed world. However, aging is associated with the accumulation of oxidative damage in many biomolecules, including DNA. Furthermore, mitochondria may be especially important in this process because the reactive oxygen species produced in their electron transport chain can damage cellular components. Therefore, the cellular response to DNA damage, expressed mainly through DNA repair, may play an important role in AMD etiology. In several studies the increase in mitochondrial DNA (mtDNA damage and mutations, and the decrease in the efficacy of DNA repair have been correlated with the occurrence and the stage of AMD. It has also been shown that mitochondrial DNA accumulates more DNA lesions than nuclear DNA in AMD. However, the DNA damage response in mitochondria is executed by nucleus-encoded proteins, and thus mutagenesis in nuclear DNA (nDNA may affect the ability to respond to mutagenesis in its mitochondrial counterpart. We reported that lymphocytes from AMD patients displayed a higher amount of total endogenous basal and oxidative DNA damage, exhibited a higher sensitivity to hydrogen peroxide and UV radiation, and repaired the lesions induced by these factors less effectively than did cells from control individuals. We postulate that poor efficacy of DNA repair (i.e., is impaired above average for a particular age when combined with the enhanced sensitivity of retinal pigment epithelium cells to environmental stress factors, contributes to the pathogenesis of AMD. Collectively, these data suggest that the cellular response to both mitochondrial and nuclear DNA damage may play an important role in AMD pathogenesis.

  19. General principles of nuclear safety management related to research reactor decommissioning

    International Nuclear Information System (INIS)

    Banciu, Ortenzia; Vladescu, Gabriela

    2003-01-01

    The paper contents the general principles applicable to the decommissioning of research reactors to ensure a proper nuclear safety management, during both decommissioning activities and post decommissioning period. The main objective of decommissioning is to ensure the protection of workers, population and environment against all radiological and non-radiological hazards that could result after a reactor shutdown and dismantling. In the same time, it is necessary, by some proper provisions, to limit the effect of decommissioning for the future generation, according to the new Romanian, IAEA and EU Norms and Regulations. Assurance of nuclear safety during decommissioning process involves, in the first step, to establish of some safety principles and requirements to be taken into account during whole process. In the same time, it is necessary to perform a series of analyses to ensure that the whole process is conducted in a planned and safe manner. The general principles proposed for a proper management of safety during research reactor decommissioning are as follows: - Set-up of all operations included in a Decommissioning Plan; - Set-up and qualitative evaluation of safety problems, which could appear during normal decommissioning process, both radiological and nonradiological risks for workers and public; - Set-up of accident list related to decommissioning process the events that could appear both due to some abnormal working conditions and to some on-site and off-site events like fires, explosions, flooding, earthquake, etc.); - Development and qualitative/ quantitative evaluation of scenarios for each incidents; - Development (and evaluation) of safety indicator system. The safety indicators are the most important tools used to assess the level of nuclear safety during decommissioning process, to discover the weak points and to establish safety measures. The paper contains also, a safety case evaluation (description of facility according to the decommissioning

  20. Development of a Method for Quantifying the Reliability of Nuclear Safety-Related Software

    Energy Technology Data Exchange (ETDEWEB)

    Yi Zhang; Michael W. Golay

    2003-10-01

    The work of our project is intended to help introducing digital technologies into nuclear power into nuclear power plant safety related software applications. In our project we utilize a combination of modern software engineering methods: design process discipline and feedback, formal methods, automated computer aided software engineering tools, automatic code generation, and extensive feasible structure flow path testing to improve software quality. The tactics include ensuring that the software structure is kept simple, permitting routine testing during design development, permitting extensive finished product testing in the input data space of most likely service and using test-based Bayesian updating to estimate the probability that a random software input will encounter an error upon execution. From the results obtained the software reliability can be both improved and its value estimated. Hopefully our success in the project's work can aid the transition of the nuclear enterprise into the modern information world. In our work, we have been using the proprietary sample software, the digital Signal Validation Algorithm (SVA), provided by Westinghouse. Also our work is being done with their collaboration. The SVA software is used for selecting the plant instrumentation signal set which is to be used as the input the digital Plant Protection System (PPS). This is the system that automatically decides whether to trip the reactor. In our work, we are using -001 computer assisted software engineering (CASE) tool of Hamilton Technologies Inc. This tool is capable of stating the syntactic structure of a program reflecting its state requirements, logical functions and data structure.

  1. Relational nuclear databases upon the MSU INP CDFE Web-site and Nuclear Data Centres Network CDFE activities. P7

    International Nuclear Information System (INIS)

    Boboshin, I.N.; Varlamov, V.V.; Ivanov, E.M.; Ivanov, S.V.; Peskov, N.N.; Stepanov, M.E.; Chesnokov, V.V.

    2001-01-01

    This report contains only the short review of the work carried out by the CDFE concerning the IAEA Nuclear Reaction Data Centres Network activities for the period of time from the IAEA Advisory Group Meeting (15-19 May 2000, Obninsk, Russia) till May 2001 and the description of the main results obtained

  2. Royal order relating to the transfer of nuclear materials and technology to non-nuclear weapon states

    International Nuclear Information System (INIS)

    1989-05-01

    In implementation of the Act of 1981 on conditions for the export of nuclear materials, equipment and technological data, this Order sets down the detailed mechanisms for such transfers. Its object is to ensure that they will be carried out exclusively for peaceful purposes and in conformity with the NPT [fr

  3. Regulatory surveillance of safety related maintenance at nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-08-01

    The operational safety and reliability of a nuclear power plant as well as its availability for electricity generation depend on, among other things, its maintenance programme. Regulatory bodies therefore have considerable interest in maintenance activities. There are several approaches to maintenance, i.e. reliability centered maintenance or risk focused maintenance, aimed at optimizing maintenance by focusing on important components or systems. These approaches may result in significant changes to maintenance activities and therefore have to be considered for regulatory acceptance. In order to review and discuss the status of maintenance regulation in participating countries, the IAEA convened a Technical Committee Meeting on Regulatory Oversight of Maintenance Activities at Nuclear Power Plants in Vienna from 9 to 13 October 1995. The meeting was attended by 16 experts from 11 countries. In addition to the consideration of papers that were presented and which are reproduced here, extensive group and panel discussions took place during the meeting. These covered three main topics: general features and basic characteristics of maintenance regulation, regulatory acceptance of maintenance optimization and use of PSA for maintenance optimization. The discussion are summarized in Section 2. Section 3 discusses the following three additional topics: regulatory involvement in the maintenance programme, modifications to the maintenance programme and personnel related aspects of maintenance. The conclusions are presented in Section 4. Figs, tabs

  4. Nuclear fusion and fission, and related technologies department: 2007 progress report

    International Nuclear Information System (INIS)

    2007-12-01

    ENEA continues to contribute to broadening plasma physics knowledge as well as to developing the relevant technologies in the framework of the EURATOM-ENEA Association for fusion. This report describes the 2007 research activities carried out by the ENEA Fusion Research Group of the Nuclear Fusion and Fission, and Related Technologies Department (FPN). Other ENEA research groups also contributed to the activities. The following fields were addressed: magnetically confined nuclear fusion (physics and technology), superconductivity and inertial fusion. Planning of the 2007 fusion activities took into account the different scenarios determined by the new organisation of the European programme based on the start of ITER construction. The establishment of the ITER International Organisation and the European Domestic Agency (Fusion for Energy) required a new organisational scheme. This has implied not only the implementation of a more project oriented structure but also the need to launch the constitution of a consortium agreement between the Associations in order to cope with the needs for the design and construction of the components of ITER that require specific know-how, e.g., diagnostics and test blanket module

  5. Assessment of modular construction for safety-related structures at advanced nuclear power plants

    International Nuclear Information System (INIS)

    Braverman, J.; Morante, R.; Hofmayer, C.

    1997-03-01

    Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules

  6. Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature

    International Nuclear Information System (INIS)

    Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

    1982-10-01

    The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searched and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included

  7. Cooperative measures to support the Indo-Pak Agreement Reducing Risk from Accidents Relating to Nuclear Weapons.

    Energy Technology Data Exchange (ETDEWEB)

    Mishra, Sitakanta [Centre for Air Power Studies, New Delhi (India); Ahmed, Mansoor [Quaid-i-Azam Univ., Islamabad (Pakistan)

    2014-04-01

    In 2012, India and Pakistan reaffirmed the Agreement on Reducing the Risk from Accidents Relating to Nuclear Weapons. Despite a history of mutual animosity and persistent conflict between the two countries, this agreement derives strength from a few successful nuclear confidence building measures that have stood the test of time. It also rests on the hope that the region would be spared a nuclear holocaust from an accidental nuclear weapon detonation that might be misconstrued as a deliberate use of a weapon by the other side. This study brings together two emerging strategic analysts from South Asia to explore measures to support the Agreement and further develop cooperation around this critical issue. This study briefly dwells upon the strategic landscape of nuclear South Asia with the respective nuclear force management structures, doctrines, and postures of India and Pakistan. It outlines the measures in place for the physical protection and safety of nuclear warheads, nuclear materials, and command and control mechanisms in the two countries, and it goes on to identify the prominent, emerging challenges posed by the introduction of new weapon technologies and modernization of the respective strategic forces. This is followed by an analysis of the agreement itself leading up to a proposed framework for cooperative measures that might enhance the spirit and implementation of the agreement.

  8. Development of safety-related regulatory requirements for nuclear power in developing countries. Key issue paper no. 4

    International Nuclear Information System (INIS)

    Han, K.I.

    2000-01-01

    In implementing a national nuclear power program, balanced regulatory requirements are necessary to ensure nuclear safety and cost competitive nuclear power, and to help gain public acceptance. However, this is difficult due to the technology-intensive nature of the nuclear regulatory requirements, the need to reflect evolving technology and the need for cooperation among multidisciplinary technical groups. This paper suggests approaches to development of balanced nuclear regulatory requirements in developing countries related to nuclear power plant safety, radiation protection and radioactive waste management along with key technical regulatory issues. It does not deal with economic or market regulation of electric utilities using nuclear power. It suggests that national regulatory requirements be developed using IAEA safety recommendations as guidelines and safety requirements of the supplier country as a main reference after careful planning, manpower buildup and thorough study of international and supplier country's regulations. Regulation making is not recommended before experienced manpower has been accumulated. With an option that the supplier country's regulations may be used in the interim, the lack of complete national regulatory requirements should not deter introduction of nuclear power in developing countries. (author)

  9. Volcanoes and associated topics in relation to nuclear power plant siting

    International Nuclear Information System (INIS)

    1997-01-01

    The main purpose of this report is to provide draft guidance on the criteria and methods for the evaluation of a site for a nuclear power plant with respect to the potential effects of volcanic activity which may jeopardize its safety and to elicit feedback from Member States. Different types of phenomena associated with volcanism are discussed in terms of their influence on site acceptability and on derivation of design basis parameters. This report was developed for application to new nuclear power plant sites. It does not address the issue of the re-evaluation of existing nuclear power sites to the potential effects of volcanic activity, although it contains general information and criteria useful for this purpose. The guidelines and procedures discussed in this report can appropriately be used as the basis for the safe siting and design of nuclear power plants in different volcanic environments. In this report, the description of the phenomena associated with volcanism and the collection of required data and information are separated from the criteria for hazard assessment. Thus Section 2 gives the non-specialist a general description of the different types of volcanic phenomena and Section 4 provides indication on the acquisition of the database. Section 3 outlines the general requirements to be fulfilled during site selection and evaluation. Sections 5, 6 and 7 provide guidance to perform the hazard assessment and to derive the design basis parameters. Finally, Section 8 deals with monitoring systems. As general information for the non-specialist, Annex I provides the major divisions of geological time. With the same spirit, and recognizing that a complete consensus has not been reached in the scientific community on the use and meaning of some terms, a glossary of volcanological definitions is given in Annex II, applicable only to the use of this report. Finally, Annex III provides an example of a classification of volcanoes that may be used for capability

  10. Nuclear power plants: recent developments in Brazil relating to the legal aspect of installation - erection - operation

    International Nuclear Information System (INIS)

    Lima Moreira, Y.M. de.

    1981-10-01

    A Federal statutory system governs the setting up and operation of nuclear power plants in Brazil. This paper describes the general regulatory framework for electric utilities and in particular analyses the licensing procedure for nuclear installations. (NEA) [fr

  11. A Study on the Organizational Components Affecting the Communication-Related Events in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lee, Seung Min; Jang, In Seok; Seong, Poong Hyun

    2009-01-01

    It is important to communicate clearly and effectively in order to achieve and improve team performance, also in the view point of safety, in nuclear power plant (NPP). Researchers have studied on lots of accidents and incidents related to communication and analyzed the elements affecting communication fail in the side of sender-receiver communication process so that they have found which process was failed to communicate each other. But we cannot disregard on human cognition, level of understanding, and individual or team characteristic on the communication process, so we need to analyze the elements of communication-related events in the side of human and team components that we will find why operators could not avoid failing their communication. In this paper we enumerate key organizational components, collect events related to communication in NPP and count the total number of components affecting communication fail. Finally we perform the pairwise-comparison using those values and understand major factors affecting communication-related events

  12. Longitudinal effects of disaster-related experiences on mental health among Fukushima nuclear plant workers: The Fukushima NEWS Project Study.

    Science.gov (United States)

    Ikeda, A; Tanigawa, T; Charvat, H; Wada, H; Shigemura, J; Kawachi, I

    2017-08-01

    The Fukushima Nuclear Energy Workers' Support (NEWS) Project Study previously showed that experiences related to the Fukushima nuclear disaster on 11 March 2011 had a great impact on psychological states, including post-traumatic stress response (PTSR) and general psychological distress (GPD), among the Fukushima nuclear plant workers. To determine the causal relationship between disaster-related experiences and levels of psychological states, we conducted a 3-year longitudinal study from 2011 to 2014. PTSR and GPD of the nuclear plant workers were assessed by annual questionnaires conducted from 2011 to 2014. The present study included a total of 1417 workers who provided an assessment at baseline (2011). A total of 4160 observations were used in the present analysis. The relationship between disaster-related experiences and psychological states over time was analysed using mixed-effects logistic regression models. A declining influence of disaster-related experiences on PTSR over time was found. However, the impact on PTSR remained significantly elevated even 3 years after the disaster in several categories of exposure including the experience of life-threatening danger, experiences of discrimination, the witnessing of plant explosion, the death of a colleague and home evacuation. The associations between GPD and disaster-related experiences showed similar effects. The effects of disaster-related experiences on psychological states among the nuclear plant workers reduced over time, but remained significantly high even 3 years after the event.

  13. Approaches relating to decommissioning of nuclear facilities. Peer discussions on regulatory practices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report arises from the fifth series of peer discussions on regulatory practices entitled 'Approaches relating to decommissioning of nuclear facilities'. Senior regulators from 22 Member States participated in three peer group discussions during 1996-1997. This report presents the outcome of these meetings and recommendations of good practices identified by senior regulators, which do not necessarily reflect those of the governments of the nominating Member States, the nominating organizations, nor the IAEA. In many Member States nuclear facilities such as power and research reactors, nuclear fuel cycle facilities and various industrial and medical facilities have reached the end of their useful life or will reach it in the near future. These facilities need to be safely decommissioned without causing any undue radiological, chemical or other risks to workers, the public and the environment. Today, there is a growing consensus that decommissioning needs to be given consideration from the design phase of a new facility and that planning for decommissioning is to be carried out during the entire life of the nuclear facility. In most Member States, there is no comprehensive set of requirements, be it on a legal or technical level, available to plan, assess, approve and carry out decommissioning operations. Since most of the facilities to be decommissioned in the near future are demonstration or prototype facilities, case by case specific and prescriptive requirements will have to be developed. However, such case by case requirements need to be based on existing applicable regulations as well as on generally accepted principles. In order to assist Member States in ensuring safe decommissioning operations, the IAEA has convened the fifth series of peer discussions on 'Approaches relating to decommissioning of nuclear facilities'. The results and findings of these discussions are summarized in this report, concentrating on recommendations and established good

  14. Approaches relating to decommissioning of nuclear facilities. Peer discussions on regulatory practices

    International Nuclear Information System (INIS)

    1998-04-01

    This report arises from the fifth series of peer discussions on regulatory practices entitled 'Approaches relating to decommissioning of nuclear facilities'. Senior regulators from 22 Member States participated in three peer group discussions during 1996-1997. This report presents the outcome of these meetings and recommendations of good practices identified by senior regulators, which do not necessarily reflect those of the governments of the nominating Member States, the nominating organizations, nor the IAEA. In many Member States nuclear facilities such as power and research reactors, nuclear fuel cycle facilities and various industrial and medical facilities have reached the end of their useful life or will reach it in the near future. These facilities need to be safely decommissioned without causing any undue radiological, chemical or other risks to workers, the public and the environment. Today, there is a growing consensus that decommissioning needs to be given consideration from the design phase of a new facility and that planning for decommissioning is to be carried out during the entire life of the nuclear facility. In most Member States, there is no comprehensive set of requirements, be it on a legal or technical level, available to plan, assess, approve and carry out decommissioning operations. Since most of the facilities to be decommissioned in the near future are demonstration or prototype facilities, case by case specific and prescriptive requirements will have to be developed. However, such case by case requirements need to be based on existing applicable regulations as well as on generally accepted principles. In order to assist Member States in ensuring safe decommissioning operations, the IAEA has convened the fifth series of peer discussions on 'Approaches relating to decommissioning of nuclear facilities'. The results and findings of these discussions are summarized in this report, concentrating on recommendations and established good

  15. Third international workshop on compound nuclear reactions and related topics. Book of abstracts

    International Nuclear Information System (INIS)

    2012-09-01

    The conference was divided into the following sections: Fission; Surrogate reactions; Heavy ion reactions; Neutron-induced reactions; Gamma-ray strength functions; Nuclear astrophysics; Superheavy nuclei; Nuclear level density; Various nuclear reactions; Optical model simulations; and Pre-equilibrium. The publication contains 82 abstracts. (P.A.)

  16. A guide to archival collections relating to radioactive fallout from nuclear weapon testing

    International Nuclear Information System (INIS)

    Martin, B.W.

    1992-09-01

    This ninth edition of A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing constitutes History Associates Incorporated's (HAI) final report of its document collection, processing, and declassification efforts for the Nevada Field Office of the Department of Energy. The most significant feature of this edition is the updated HAI collection effort information. We confirmed the accuracy of this information using our screening, processing, and transmittal records. Unlike previous editions, funding limitations prevented us from systematically revising the collection descriptions and point-of-contact information for this final edition. This guide has been prepared by professional historians who have a working knowledge of many of the record collections included in the following pages. In describing materials, they have tried to include enough information so that persons unfamiliar with the complexities of large record systems will be able to determine that nature of the information in, and the quality of, each record collection

  17. Several issues related to regional environmental investigation to inland nuclear power plant

    International Nuclear Information System (INIS)

    Tian Xinshan; Zhang Xiaofeng

    2010-01-01

    Based on the goal of carrying out regional environmental investigation and review of recent environmental investigations toward inland nuclear power plant(NPP) site, and combined with the characteristics between inland and coastal sites, this paper is to make deeply analysis on population distribution, environmental characteristics, feasibility of performing emergency plan, characteristics of received water and external human-induced incident of NPP vicinity, then advance several significant issues related regional environmental investigation to inland sites, and make comparison with the investigation to coastal sites. Meantime, on guarantee of the integrity of collected materials during investigation, this paper also makes several proposals to provide reference for carrying out regional environmental investigation to inland NPP site. (authors)

  18. Loss of function of the retinoid-related nuclear receptor (RORB) gene and epilepsy

    DEFF Research Database (Denmark)

    Rudolf, Gabrielle; Lesca, Gaetan; Mehrjouy, Mana M

    2016-01-01

    nuclear receptor (RORβ), in four affected family members. In addition, two de novo variants (c.218T>C/p.(Leu73Pro); c.1249_1251delACG/p.(Thr417del)) were identified in sporadic patients by trio-based exome sequencing. We also found two de novo deletions in patients with behavioral and cognitive impairment...... in various types of epilepsies in the past few years. In the present study, we performed whole-exome sequencing in a family with GGE consistent with the diagnosis of eyelid myoclonia with absences. We found a nonsense variant (c.196C>T/p.(Arg66*)) in RORB, which encodes the beta retinoid-related orphan...

  19. Size of nuclear sources from measurements of proton-proton correlations at small relative momentum

    International Nuclear Information System (INIS)

    Rebreyend, D.; Kox, S.; Merchez, F.; Noren, B.; Perrin, C.; Khelfaoui, B.; Gondrand, J.C.; Bondorf, J.P.

    1990-01-01

    This contribution will present recent measurements performed on light heavy ion reactions at intermediate energies. Nuclear source sizes were determined by measuring the correlation at small relative momentum, between two protons detected in the EMRIC set-up. This technique allows the determination of the extent of the emitting source by constructing a correlation function for the coincident protons and analyzing it in the framework of a final state interaction model. We found the apparent source size to be large compared to the dimension of the studied system and low sensitivity of the extracted radii as a function of the target mass and detection angle. We will show that simulations may be needed to fully estimate the correlation induced by detectors with small angular acceptance

  20. Investigation of fluid flow in various geometries related to nuclear reactor using PIV system

    International Nuclear Information System (INIS)

    Kansal, A.K.; Maheshwari, N.K.; Singh, R.K.; Vijayan, P.K.; Saha, D.; Singh, R.K.; Joshi, V.M.

    2011-01-01

    Particle Image Velocimetry (PIV) is a non-intrusive technique for simultaneously measuring the velocities at many points in a fluid flow. The PIV system used is comprised of Nd:YAG laser source, CCD (Charged Coupled Device) camera, timing controller (to control the laser and camera) and software used for analyzing the flow velocities. Several case studies related to nuclear reactor were performed with the PIV system. Some of the cases like flow in circular tube, submerged jet, natural convection in a water pool, flow field of moderator inlet diffuser of 500 MWe Pressurised Heavy Water Reactor (PHWR) and fluidic flow control device (FFCD) used in advanced accumulator of Emergency Core Cooling System (ECCS) have been studied using PIV system. Theoretical studies have been performed and comparisons with PIV results are also given in the present studies. (author)

  1. Potential human factors research relating to modern technology in nuclear power plants

    International Nuclear Information System (INIS)

    Ketchel, J.; Fink, R.; Hanes, L.; Williges, R.; Williges, B.

    1994-01-01

    This paper discusses proposed human factors research to address advanced human-machine interface technology in nuclear power plants. It relates to a current EPRI project to identify a prioritized list of specific research issues that could be assessed to improve control room and other user interface areas. The project seeks to bridge the gap between the functional requirements of advanced design initiatives and the human factors research needed to support them. It seeks to identify potential benefits to be expected, as well as potential problems that might be introduced by advanced technology. It provides an organized approach to identifying human factors research needs, information already available, and measures of performance and effectiveness that might be used to assess the value of potential improvements. Those parts of the proposed plan that are subsequently approved by EPRI management and by the utility advisory committee will provide a basis for recommending research priorities

  2. Requirements and analysis of electromagnetic compatibility of safety-related instrumentation and control system in nuclear power plants

    International Nuclear Information System (INIS)

    Liu Sujuan

    2002-01-01

    The state-of-the-art instrumentation and control system and the influence of their application to the electromagnetic compatibility is analyzed. Based on the present situation of nuclear safety in China and relevant experiences from other countries, the author tries to probe into the requirements and test methods about how safety-related instrument and control system to accommodate electromagnetic interference, radio-frequency interference and power surges in the environments of nuclear power plant so as to develop Chinese safety standards

  3. Proceedings of VII International Symposium on Nuclear and Related Techniques. XIII Workshop on Nuclear Physics. WONP-NURT 2011

    International Nuclear Information System (INIS)

    2012-06-01

    This year 2012, the VII International Workshop held Tecnolaser 2012 alongside the Third International Meeting Optics, Life and Heritage organized by the Center of Technological Applications and Nuclear Development from 10 to 13 April at the National Museum of Fine Arts. Tecnolaser has been held since 1997 and has contributed to the exchange between professionals from various countries of the world in the fields of optics and laser applications. The papers submitted to this event are presented in this CD-ROM.

  4. Project for export system construction of nuclear equipment to IAEA; survey on current market status of the nuclear related international organizations and the domestic possible suppliers

    Energy Technology Data Exchange (ETDEWEB)

    Min, T S; Cho, H K; Kim, H J [Korea Atomic Industrial Forum, Seoul (Korea)

    2001-05-01

    Republic of Korea are keeping the dynamic activities in IAEA as the 8th advanced nuclear country over the world but has occupied very low late less than 0.01% in supplying the equipments to IAEA. About 6,000 nuclear equipment suppliers are registered in IAEA Supply Roster over the world but only 3 Suppliers of our country are registered in IAEA Supply Roster. The supply of nuclear industrial products equivalent to about 100 million dollars into IAEA market will endorse not only the international authorization for our technology and products but also give contribution to activate the domestic nuclear industries in order to increase its expert. The explanation for IAEA procurement market to the 53 nuclear companies will be made on May 16, 2001, and the participants for the export of their goods will be selected. And then we will do all possible supports by the government and related organizations for them to register in IAEA Supply Roster. 21 refs. (Author)

  5. The position of IAEA safeguards relative to nuclear material control accountancy by States

    International Nuclear Information System (INIS)

    Rometsch, R.; Hough, G.

    1977-01-01

    IAEA Safeguards, which are always implemented on the basis of agreements which are concluded between one or more Governments and the IAEA, lay down the rights and obligations of the parties; and the more modern types of agreement, in particular those in connection with the Treaty on the Non-Proliferation of Nuclear Weapons, do this in quite some detail. Several articles, for instance, regulate the working relations between the States and the IAEA inspectorate. These are based on two basic obligations - that of the State to establish and maintain a ''System of Accountancy for and Control of Nuclear Material'' and that of the IAEA to ascertain the absence of diversion of nuclear material by verifying the findings of the States' systems, inter alia through independent measurements and observations. Other articles dealing also with the working relations between States and the IAEA rule that the IAEA should take due account of the technical effectiveness of the States' systems and mention among the criteria for determining the inspection effort, the extent of functional dependence of the State's accountancy on that of the facility operator. However, quantitative relationships in this respect are left to be worked out in practice. With the help of consultants and expert advisory groups a rationale has been developed and possible practical arrangements discussed with several States concerned. The rationale for co-ordinating the work of the States' inspectorate with that of the IAEA was to use a factor by which the significant quantity used for calculating verification sampling plans would be adjusted so as to reduce to a certain extent the IAEA's independent verification work in case the States would themselves do extensive verifications in a manner transparent to the IAEA. However, in practice it proved that there are a number of points in the fuel cycle where such adaptations would have little or no effect on the inspection effort necessary to achieve the safeguards

  6. The position of IAEA safeguards relative to nuclear material control accountancy by states

    International Nuclear Information System (INIS)

    Rometsch, R.; Hough, G.

    1977-01-01

    IAEA Safeguards are always implemented on the basis of agreements which are concluded between one or more Governments and the Agency. They lay down the rights and obligations of the parties; the more modern types of agreements, in particular those in connection with the Treaty on the Non-Proliferation of Nuclear Weapons, do that in quite some details. Several articles, for instance, regulate the working relations between the States and the IAEA inspectorate. Those are based on two basic obligations: that of the State to establish and maintain a ''System of Accountancy for and Control of Nuclear Material'' and that of the Agency to ascertain the absence of diversion of nuclear material by verifying the findings of the States' system, inter alia through independent measurements and observations. Other articles dealing also with the working relations States - IAEA rule that the Agency should take due account of the technical effectiveness of the States' system and mention among the criteria for determining the inspection effort, the extent of functional dependence of the State's accountancy from that of the facility operator. However, quantitative relationships in that respect are left to be worked out in practice. With the help of consultants and expert advisory groups a rational has been developed and possible practical arrangements discussed with several States concerned. The rational for coordinating the work of the States' inspectorate with IAEA's inspectorate was to use a factor by which the significant quantity used for calculating verification sampling plans would be adjusted in order to reduce to a certain extent the Agency's independent verification work in case the States would do extensive verifications themselves in a manner transparent to IAEA. However, in practice it proved that there are quite a number of points in the fuel cycle where such adaptations would have little or no effect on the inspection effort necessary to achieve the safeguards objective

  7. Triton-3He relative and differential flows as probes of the nuclear symmetry energy at supra-saturation densities

    International Nuclear Information System (INIS)

    Yong Gaochan; Li Baoan; Chen Liewen; Zhang Xunchao

    2009-01-01

    Using a transport model coupled with a phase-space coalescence afterburner, we study the triton- 3 He (t- 3 He) ratio with both relative and differential transverse flows in semicentral 132 Sn+ 124 Sn reactions at a beam energy of 400 MeV/nucleon. The neutron-proton ratios with relative and differential flows are also discussed as a reference. We find that similar to the neutron-proton pairs, the t- 3 He pairs also carry interesting information regarding the density dependence of the nuclear symmetry energy. Moreover, the nuclear symmetry energy affects more strongly the t- 3 He relative and differential flows than the π - /π + ratio in the same reaction. The t- 3 He relative flow can be used as a particularly powerful probe of the high-density behavior of the nuclear symmetry energy.

  8. Public relations activities of the Karlsruhe Nuclear Research Center - a national research center contributes to opinion forming

    International Nuclear Information System (INIS)

    Koerting, K.

    1988-01-01

    At the Karlsruhe Nuclear Research Center, the Public Relations Department directly reports to the Chief Executive Officer. The head of the Public Relation Department acts as spokesman of the center in the public, which requires him to be fully informed of the work of all units and of the policy goals of the executive board. The key tools used by the Public Relations Department are KfK-Hausmitteilungen, accident information, the scientific journal KfK-Nachrichten, press releases, exhibitions, fairs, guided tours, and nuclear energy information staff. (DG)

  9. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology. Nuclear-related dual-use transfers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The Director General has received notes verbales dated 30 June 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments` Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material and related Technology. In the light of the wish expressed at the end of each note verbale, the text of the notes verbales is annexed hereto. The enclosure to these notes verbales is also reproduced in full in the Annex.

  10. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology. Nuclear-related dual-use transfers

    International Nuclear Information System (INIS)

    1995-10-01

    The Director General has received notes verbales dated 30 June 1995 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology. The purpose of the notes verbales is to provide further information on those Governments' Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material and related Technology. In the light of the wish expressed at the end of each note verbale, the text of the notes verbales is annexed hereto. The enclosure to these notes verbales is also reproduced in full in the Annex

  11. No 2943. Project of law relative to nuclear transparency and safety

    International Nuclear Information System (INIS)

    2006-03-01

    This project of law comprises 5 titles dealing with: 1 - general dispositions: definition and scope of nuclear safety, security, radiation protection, operators liability, facilities in concern; 2 - the high nuclear safety authority: role and duties; 3 - public information in the domain of nuclear safety and radiation protection: information right of the public, local information commissions, high committee for nuclear safety transparency and information; 4 - basic nuclear facilities and transport of radioactive materials: applicable rules, police controls and measures, penal dispositions (investigations, sanctions); 5 - miscellaneous dispositions: changes made with respect to previous legislative texts. (J.S.)

  12. Quantities of transuranic elements in the environment from operations relating to nuclear weapons

    International Nuclear Information System (INIS)

    Facer, G.

    1980-01-01

    Only nuclear explosions near or above the earth's surface or under water have contributed substantial amounts of transuranic materials to the world bioenvironment. The amounts of transuranics placed in the environment through underground test ventings, accidents involving US nuclear weapons, and releases during weapon production operations have been negligible in comparison with those from atmospheric testing of nuclear explosives. On the order of 10 5 Ci of plutonium has been dispersed within our environment from about 400 nuclear explosive tests, including those by the US, Great Britain, and Russia, between 1945 and 1963, plus more recent nuclear explosive tests in the atmosphere by China, India, and France

  13. Review of nuclear air treatment system related License Event Reports for the period 1985 - 1987

    International Nuclear Information System (INIS)

    Jacox, J.W.

    1989-01-01

    This paper will continue the review of HVAC/NATS related LERS presented at past Air Cleaning Conferences by Dr. D. W. Moeller and his associates. The general approach and format are similar. LER abstracts from mid 1985 through 1987 were reviewed and those related to HVAC/NATS classified and analyzed. The categories were jointly developed by Dr. Moeller, Dr. Casper Sun and myself. In appropriate cases both primary and secondary categories fora problem are given. A basic listing by category and brief statistical review are presented. Additionally a number of categories are discussed in some detail. The categories chosen for specific review are intended to highlight particular problem areas. NUREG/CR-2000 License Event Report (LER) Compilation is the basis for the initial review and coding. In essentially all cases where an LER is classified as of interest the complete LER was obtained and reviewed in full. The intent of this paper is to provide a basis for the industry to document and analyze problem areas that require additional attention. It appears that about 15% of all LERS in the subject period are HVAC/NATS related. This figure is generally consistent with those reported at the 17th DOE Nuclear Air Cleaning Conference. It is hoped that such attention will allow additional resources to be allocated to upgrade systems, procedures and training as well as in some cases government regulation

  14. Accurate relative location estimates for the North Korean nuclear tests using empirical slowness corrections

    Science.gov (United States)

    Gibbons, S. J.; Pabian, F.; Näsholm, S. P.; Kværna, T.; Mykkeltveit, S.

    2017-01-01

    Declared North Korean nuclear tests in 2006, 2009, 2013 and 2016 were observed seismically at regional and teleseismic distances. Waveform similarity allows the events to be located relatively with far greater accuracy than the absolute locations can be determined from seismic data alone. There is now significant redundancy in the data given the large number of regional and teleseismic stations that have recorded multiple events, and relative location estimates can be confirmed independently by performing calculations on many mutually exclusive sets of measurements. Using a 1-D global velocity model, the distances between the events estimated using teleseismic P phases are found to be approximately 25 per cent shorter than the distances between events estimated using regional Pn phases. The 2009, 2013 and 2016 events all take place within 1 km of each other and the discrepancy between the regional and teleseismic relative location estimates is no more than about 150 m. The discrepancy is much more significant when estimating the location of the more distant 2006 event relative to the later explosions with regional and teleseismic estimates varying by many hundreds of metres. The relative location of the 2006 event is challenging given the smaller number of observing stations, the lower signal-to-noise ratio and significant waveform dissimilarity at some regional stations. The 2006 event is however highly significant in constraining the absolute locations in the terrain at the Punggye-ri test-site in relation to observed surface infrastructure. For each seismic arrival used to estimate the relative locations, we define a slowness scaling factor which multiplies the gradient of seismic traveltime versus distance, evaluated at the source, relative to the applied 1-D velocity model. A procedure for estimating correction terms which reduce the double-difference time residual vector norms is presented together with a discussion of the associated uncertainty. The modified

  15. Statistical analysis of events related to emergency diesel generators failures in the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Kančev, Duško, E-mail: dusko.kancev@ec.europa.eu [European Commission, DG-JRC, Institute for Energy and Transport, P.O. Box 2, NL-1755 ZG Petten (Netherlands); Duchac, Alexander; Zerger, Benoit [European Commission, DG-JRC, Institute for Energy and Transport, P.O. Box 2, NL-1755 ZG Petten (Netherlands); Maqua, Michael [Gesellschaft für Anlagen-und-Reaktorsicherheit (GRS) mbH, Schwetnergasse 1, 50667 Köln (Germany); Wattrelos, Didier [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), BP 17 - 92262 Fontenay-aux-Roses Cedex (France)

    2014-07-01

    Highlights: • Analysis of operating experience related to emergency diesel generators events at NPPs. • Four abundant operating experience databases screened. • Delineating important insights and conclusions based on the operating experience. - Abstract: This paper is aimed at studying the operating experience related to emergency diesel generators (EDGs) events at nuclear power plants collected from the past 20 years. Events related to EDGs failures and/or unavailability as well as all the supporting equipment are in the focus of the analysis. The selected operating experience was analyzed in detail in order to identify the type of failures, attributes that contributed to the failure, failure modes potential or real, discuss risk relevance, summarize important lessons learned, and provide recommendations. The study in this particular paper is tightly related to the performing of statistical analysis of the operating experience. For the purpose of this study EDG failure is defined as EDG failure to function on demand (i.e. fail to start, fail to run) or during testing, or an unavailability of an EDG, except of unavailability due to regular maintenance. The Gesellschaft für Anlagen und Reaktorsicherheit mbH (GRS) and Institut de Radioprotection et de Sûreté Nucléaire (IRSN) databases as well as the operating experience contained in the IAEA/NEA International Reporting System for Operating Experience and the U.S. Licensee Event Reports were screened. The screening methodology applied for each of the four different databases is presented. Further on, analysis aimed at delineating the causes, root causes, contributing factors and consequences are performed. A statistical analysis was performed related to the chronology of events, types of failures, the operational circumstances of detection of the failure and the affected components/subsystems. The conclusions and results of the statistical analysis are discussed. The main findings concerning the testing

  16. Statistical analysis of events related to emergency diesel generators failures in the nuclear industry

    International Nuclear Information System (INIS)

    Kančev, Duško; Duchac, Alexander; Zerger, Benoit; Maqua, Michael; Wattrelos, Didier

    2014-01-01

    Highlights: • Analysis of operating experience related to emergency diesel generators events at NPPs. • Four abundant operating experience databases screened. • Delineating important insights and conclusions based on the operating experience. - Abstract: This paper is aimed at studying the operating experience related to emergency diesel generators (EDGs) events at nuclear power plants collected from the past 20 years. Events related to EDGs failures and/or unavailability as well as all the supporting equipment are in the focus of the analysis. The selected operating experience was analyzed in detail in order to identify the type of failures, attributes that contributed to the failure, failure modes potential or real, discuss risk relevance, summarize important lessons learned, and provide recommendations. The study in this particular paper is tightly related to the performing of statistical analysis of the operating experience. For the purpose of this study EDG failure is defined as EDG failure to function on demand (i.e. fail to start, fail to run) or during testing, or an unavailability of an EDG, except of unavailability due to regular maintenance. The Gesellschaft für Anlagen und Reaktorsicherheit mbH (GRS) and Institut de Radioprotection et de Sûreté Nucléaire (IRSN) databases as well as the operating experience contained in the IAEA/NEA International Reporting System for Operating Experience and the U.S. Licensee Event Reports were screened. The screening methodology applied for each of the four different databases is presented. Further on, analysis aimed at delineating the causes, root causes, contributing factors and consequences are performed. A statistical analysis was performed related to the chronology of events, types of failures, the operational circumstances of detection of the failure and the affected components/subsystems. The conclusions and results of the statistical analysis are discussed. The main findings concerning the testing

  17. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    International Nuclear Information System (INIS)

    2003-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 28 February 2003 from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Canada, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Kazakhstan, Latvia, Netherlands, Norway, Portugal, Republic of Korea, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Note Verbales is to provide further information on those Governments' Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full

  18. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    International Nuclear Information System (INIS)

    2005-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 25 October 2004 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Canada, Cyprus, Czech Republic, Estonia, Finland, France, Greece, Hungary, Italy, Japan, Malta, Netherlands, Norway, Republic of Korea, South Africa, Spain, Sweden, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Notes Verbales is to provide further information on those Governments' guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full

  19. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-16

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 28 February 2003 from the Resident Representatives to the Agency of Argentina, Austria, Belgium, Bulgaria, Canada, Cyprus, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Kazakhstan, Latvia, Netherlands, Norway, Portugal, Republic of Korea, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland, and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Note Verbales is to provide further information on those Governments' Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full.

  20. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-02-23

    The Director General of the International Atomic Energy Agency has received Notes Verbales dated 25 October 2004 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Canada, Cyprus, Czech Republic, Estonia, Finland, France, Greece, Hungary, Italy, Japan, Malta, Netherlands, Norway, Republic of Korea, South Africa, Spain, Sweden, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology. The purpose of the Notes Verbales is to provide further information on those Governments' guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Notes Verbales is attached. The attachment to these Notes Verbales is also reproduced in full.

  1. Evaluation of environmental data relating to selected nuclear power plant sites: the Three Mile Island Nuclear Station Site

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-08-01

    Environmental monitoring data for the years 1973 and 1974 pertaining to the Three Mile Island Nuclear Station Unit 1, which began operation in early 1974, were analyzed by the most practical qualitative and quantitative methods. Terrestrial biotic resources were considered for this plant. The effects of the operation of Unit 1 on the local terrestrial organisms were found to be undetectable. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data acquired, method of analysis, and results obtained are presented in detail along with recommendations for improving monitoring techniques

  2. Evaluation of environmental data relating to selected nuclear power plant sites. Prairie Island Nuclear Generating Plant site

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-11-01

    Environmental monitoring data for 1973 through 1975 pertaining to the Prairie Island Nuclear Generating Station (which began commercial operation in December 1973) were analyzed by the most practical qualitative and quantitative methods. Evaluations of aquatic and terrestrial biotic data are presented in this report. The data indicate no significant immediate deleterious effects on the biota from plant operation, thus confirming preoperational predictions. Although the station has not operated long enough to reveal long-term deleterious effects, present indications do not lead to a concerned prediction that any are developing. Recommendations are suggested for improving monitoring techniques

  3. Five nuclear loci resolve the polyploid history of switchgrass (Panicum virgatum L. and relatives.

    Directory of Open Access Journals (Sweden)

    Jimmy K Triplett

    Full Text Available Polyploidy poses challenges for phylogenetic reconstruction because of the need to identify and distinguish between homoeologous loci. This can be addressed by use of low copy nuclear markers. Panicum s.s. is a genus of about 100 species in the grass tribe Paniceae, subfamily Panicoideae, and is divided into five sections. Many of the species are known to be polyploids. The most well-known of the Panicum polyploids are switchgrass (Panicum virgatum and common or Proso millet (P. miliaceum. Switchgrass is in section Virgata, along with P. tricholaenoides, P. amarum, and P. amarulum, whereas P. miliaceum is in sect. Panicum. We have generated sequence data from five low copy nuclear loci and two chloroplast loci and have clarified the origin of P. virgatum. We find that all members of sects. Virgata and Urvilleana are the result of diversification after a single allopolyploidy event. The closest diploid relatives of switchgrass are in sect. Rudgeana, native to Central and South America. Within sections Virgata and Urvilleana, P. tricholaenoides is sister to the remaining species. Panicum racemosum and P. urvilleanum form a clade, which may be sister to P. chloroleucum. Panicum amarum, P. amarulum, and the lowland and upland ecotypes of P. virgatum together form a clade, within which relationships are complex. Hexaploid and octoploid plants are likely allopolyploids, with P. amarum and P. amarulum sharing genomes with P. virgatum. Octoploid P. virgatum plants are formed via hybridization between disparate tetraploids. We show that polyploidy precedes diversification in a complex set of polyploids; our data thus suggest that polyploidy could provide the raw material for diversification. In addition, we show two rounds of allopolyploidization in the ancestry of switchgrass, and identify additional species that may be part of its broader gene pool. This may be relevant for development of the crop for biofuels.

  4. Failure modes of safety-related components at fires on nuclear power plants

    International Nuclear Information System (INIS)

    Aaslund, A.

    2000-03-01

    Probabilistic assessment methods can be used to identify specific plant vulnerabilities. Application of such methods can also facilitate selection among system design alternatives available for safety enhancements. The quality of assessment results is however strongly dependent on realistic and accurate input data for modelling of system component behaviour and failure modes during conditions to be assessed. Use of conservative input data may not lead to results providing guidance on safety upgrades. Adequate input data for probabilistic assessments seems to be lacking for at least failure modes of some electrical components when exposed to a fire. This report presents an attempt to improve the situation with respect to such input data. In order to take advantage of information in existing documentation of fire incident occurrences some of the lessons learned from the fire at Browns Ferry Nuclear Power Plant on March 22, 1975 are discussed in this report. Also a summary of results from different fire tests of electrical cables presented in a fire risk analysis report is a part of the references. The failure modes used to describe fire-induced damage are 'open circuit' and 'hot short' which seems to be commonly accepted terms within the branch. Definitions of the terms are included in the report. Effects of the failure modes when occurring in some of the channels of the reactor protection system are discussed with respect to the existing design of the reactor protection system at Ringhals 2 nuclear power unit. Experiences from the Browns Ferry fire and results from fire tests of electrical cables indicate that the dominating failure mode for electrical cables is 'open circuit'. An 'open circuit' failure leads to circuit disjunction and loss of continuity. The circuit can no longer transmit its signal or power. When affecting channels of the reactor protection system an 'open circuit' failure can cause extensive inadvertent actions of safety related equipment

  5. Analysis of data relative to the update of diagnosis reference levels in radiology and nuclear medicine. Situation 2004-2006

    International Nuclear Information System (INIS)

    2008-01-01

    This report presents the results of the analysis of patients dosimetry data the radiology and nuclear medicine institutions have to transmit yearly to I.R.S.N. in application of the 12. february decree disposal relative to the diagnosis reference levels in radiology and nuclear medicine. The analysed dosimetry data concern the evaluations realised between the date of decree publication, the 16. march 2004 and 31. december 2006. The so considered results have to allow to the Nuclear Safety Authority to define the evolution needs of the regulation. Particularly, the analysis of delivered doses in radiology and the activities given in nuclear medicine lead to propositions on the possible update of reference values of some examination types. (N.C.)

  6. Siting provisions of the U.S. Nuclear Waste Policy Act versus related experience in other countries

    International Nuclear Information System (INIS)

    Paige, H.W.; Owens, J.E.

    1985-01-01

    This paper is based on a report prepared by International Energy Associates Limited (IEAL) under contract to the Department of Energy. The report, whose title is the same as that of this paper, was submitted to DOE a little over one year ago. In that report, the relevant provisions of the Nuclear Waste Policy Act of 1982 setting forth the procedures for obtaining the local acceptance of sites for nuclear waste facilities were compared with the corresponding procedures of fifteen foreign countries also trying to locate sites for nuclear waste facilities. In this paper, the major points on which the Nuclear Waste Policy Act is or is not in keeping with lessons learned in other countries are discussed as well as some general and specific observations related to siting acceptance problems and how the Act addresses them

  7. Studies and research concerning BNFP. Nuclear transportation studies related to use of the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    Anderson, R.T.

    1981-11-01

    It will be necessary to transport radioactive material on a routine basis if the Barnwell Nuclear Fuel Plant (BNFP) is to be utilized. This report examines the current and projected status of transport of high-level nuclear material, with particular application directed toward the operation of the BNFP. The current domestic US status is one of comparative inactivity in the movement of utility spent fuel. Pending the successful disposition of fuel cycle options such as either Away-from-Reactor (AFR) storage or reprocessing, spent fuel transport to the BNFP will be dormant through the mid-1980's. If fuel movement is initiated, the primary areas of concern will be the maze of local, state, and federal regulations on routing, the availability of spent fuel casks, and the logistic concerns of fuel loading and unloading capability at the reactor and the BNFP. The report examines the application of overweight truck (OWT) shipments of spent fuel casks patterned on current European practice. Overweight shipments, whether by truck or intermodal movement (rail or barge combined with truck shipment), can have a significant impact on resolving logistics problems. It seems obvious from our studies that OWT casks will be utilized, along with legal weight truck and rail shipment. Water transport was also examined. It appears that this mode will only be used in the event that highway and rail problems are insuperable

  8. Nuclear-electrica experience related to the public information about nuclear energy and its benefits for development of society

    International Nuclear Information System (INIS)

    Vatamanu, Mariana

    2005-01-01

    All target audience is important in building the confidence, but some categories deserve special attention, considering the today priorities of the company: Local public, including local authorities - as far the anti-nuclear NGOs started a strong campaign against Cernavoda 2 and further development of the site. Mass-media representatives, increasing the co-operation with local newspapers, as well as with the national ones. Politicians, considering this year elections, and the re-drafting process of the political strategies of different parties. Improving the internal communication developing INTRANET and EXTRANET channels, and extending social events inside the company. A better social acceptability of nuclear energy may be obtained through a sustained effort to improve the public trust, using tools as diversified as possible; The public information and public participation are the two main components of the communication process, the accent following to be changed from information to participation; Public communication must be professionalized and planned so that each target group be treated in a specific manner; According to our experience, at this moment the target groups are local communities, mass media representatives and decision makers, but we can not neglect the internal communication which is important for local public involvement; Company has enough flexibility to re-define the target audience, considering possible future reallocation of priorities. (author)

  9. Aging of turbine drives for safety-related pumps in nuclear power plants

    International Nuclear Information System (INIS)

    Cox, D.F.

    1995-06-01

    This study was performed to examine the relationship between time-dependent degradation and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety-related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized-water reactor plants and in the Reactor Core Isolation Cooling and High-Pressure Coolant Injection systems for boiling-water reactor plants. This research has been conducted by examination of failure data in the Nuclear Plant Reliability Data System, review of Licensee Event Reports, discussion of problems with operating plant personnel, and personal observation. The reported failure data were reviewed to determine the cause of the event and the method of discovery. Based on the research results, attempts have been made to determine the predictability of failures and possible preventive measures that may be implemented. Findings in a recent study of AFW systems indicate that the turbine drive is the single largest contributor to AFW system degradation. However, examination of the data shows that the turbine itself is a reliable piece of equipment with a good service record. Most of the problems documented are the result of problems with the turbine controls and the mechanical overspeed trip mechanism; these apparently stem from three major causes which are discussed in the text. Recent improvements in maintenance practices and procedures, combined with a stabilization of the design, have led to improved performance resulting in a reliable safety-related component. However, these improvements have not been universally implemented

  10. A PLC generic requirements and specification for safety-related applications in nuclear power plants

    International Nuclear Information System (INIS)

    Han, Jea Bok; Lee, C. K.; Lee, D. Y.

    2001-12-01

    This report presents the requirements and specification to be applied to the generic qualification of programmable Logic Controller(PLC), which is being developed as part of the KNICS project, 'Development of the Digital Reactor Safety Systems' of which purpose is the application to safety-related instrumentation and control systems in nuclear power plants. This report defines the essential and critical characteristics that shall be included as part of a PLC design for safety-related application. The characteristics include performance, reliability, accuracy, the overall response time from an input to the PLC exceeding it trip condition to the resulting outputs, and the specification of processors and memories in digital controller. It also specifies the quality assurance process for software development, dealing with executive software, firmware, application software tools for developing the application software, and human machine interface(HMI). In addition, this report reviews the published standards and guidelines that are required for the PLC development and the quality assurance processes such as environment requirements, seismic withstand requirements, EMI/RFI withstand requirements, and isolation test

  11. Concrete component aging and its significance relative to life extension of nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.

    1986-09-01

    The objectives of this study are to (1) expand upon the work that was initiated in the first two Electric Power Research Institute studies relative to longevity and life extension considerations of safety-related concrete components in light-water reactor (LWR) facilities and (2) provide background that will logically lead to subsequent development of a methodology for assessing and predicting the effects of aging on the performance of concrete-based materials and components. These objectives are consistent with Nuclear Plant Aging Research (NPAR) Program goals: (1) to identify and characterize aging and service wear effects that, if unchecked, could cause degradation of structures, components, and systems and, thereby, impair plant safety; (2) to identify methods of inspection, surveillance, and monitoring or of evaluating residual life of structures, components, and systems that will ensure timely detection of significant aging effects before loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair, and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

  12. Review of international standards related to the design for control rooms on nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, Masashi; Yoshikawa, Hidekazu; Fujita, Yushi

    2005-01-01

    The improvement of Human-Machine Interface (HMI) design for control rooms on nuclear power plants (NPP) has been accomplished world wide, especially after the TMI-2 accident. The design process and guidelines are standardized in IEC60964 and supplemental standards as international standard. However, technological update is required due to the increased use of computerized control and monitoring equipment and systems in control rooms on NPP in recent years. Standards are becoming more important for computerized control rooms because there is more freedom to design than conventional hardware based system. For computerized control rooms, standards for hardware and software of HMI systems should be also considered. Standards and guidelines for computerized control rooms on NPP have been developed recently in each body such as IEC, ISO, and IEEE etc. Therefore, reviewing these standards and guidelines related to control rooms design of NPP can be useful not only for revision of the international standards such as IEC60964, but also for users of the standards and guidelines. In this paper, we reviewed the international standards related to the design for control rooms, in the two aspects of HMI design and hardware and software design, considering the undergoing revision work and their application. (author)

  13. Relational database hybrid model, of high performance and storage capacity for nuclear engineering applications

    International Nuclear Information System (INIS)

    Gomes Neto, Jose

    2008-01-01

    The objective of this work is to present the relational database, named FALCAO. It was created and implemented to support the storage of the monitored variables in the IEA-R1 research reactor, located in the Instituto de Pesquisas Energeticas e Nucleares, IPEN/CNEN-SP. The data logical model and its direct influence in the integrity of the provided information are carefully considered. The concepts and steps of normalization and de normalization including the entities and relations involved in the logical model are presented. It is also presented the effects of the model rules in the acquisition, loading and availability of the final information, under the performance concept since the acquisition process loads and provides lots of information in small intervals of time. The SACD application, through its functionalities, presents the information stored in the FALCAO database in a practical and optimized form. The implementation of the FALCAO database occurred successfully and its existence leads to a considerably favorable situation. It is now essential to the routine of the researchers involved, not only due to the substantial improvement of the process but also to the reliability associated to it. (author)

  14. Brazilian nuclear politics in the context of contemporary international relations; A politica nuclear brasileira no contexto das relacoes internacionais contemporaneas. Dominio tecnologico como estrategia de insercao internacional

    Energy Technology Data Exchange (ETDEWEB)

    Carpes, Mariana Montez

    2006-09-15

    The present dissertation analyses the retaking of the debate over Brazilian nuclear Program's recovery by Luis Inacio Lula da Silva government, based on the defense of the utilization of an already acquired technology of its own to enrich uranium. In spite of the intrinsic duality on this subject and having in mind the pacific ends concerning the utilization of such technology by Brazil, the hypothesis sustained in this work is that the Program's defense is considered a strategy of sovereign international insertion with relative autonomy and an instrument of national valorization against other powers. In order to verify the hypothesis outlined above, we will analyse the actual government, comparing it to, two other moments in Brazilian History in which the nuclear issue also acquired preponderance on the national agenda, namely, Geisel and Sarney governments. Although these three moments differ in relation to their internal political regime, our goal is to identify their similarities. (author)

  15. Brazilian nuclear politics in the context of contemporary international relations; A politica nuclear brasileira no contexto das relacoes internacionais contemporaneas. Dominio tecnologico como estrategia de insercao internacional

    Energy Technology Data Exchange (ETDEWEB)

    Carpes, Mariana Montez

    2006-09-15

    The present dissertation analyses the retaking of the debate over Brazilian nuclear Program's recovery by Luis Inacio Lula da Silva government, based on the defense of the utilization of an already acquired technology of its own to enrich uranium. In spite of the intrinsic duality on this subject and having in mind the pacific ends concerning the utilization of such technology by Brazil, the hypothesis sustained in this work is that the Program's defense is considered a strategy of sovereign international insertion with relative autonomy and an instrument of national valorization against other powers. In order to verify the hypothesis outlined above, we will analyse the actual government, comparing it to, two other moments in Brazilian History in which the nuclear issue also acquired preponderance on the national agenda, namely, Geisel and Sarney governments. Although these three moments differ in relation to their internal political regime, our goal is to identify their similarities. (author)

  16. U.S.-Latin American Nuclear Relations: From Commitment to Defiance

    Science.gov (United States)

    2012-09-01

    domestic legislation to increase the levels of   3   nuclear transparency and accountability by relying extensively on technical and scientific...which some say was influenced by environmental groups), President Bachelet delayed the decision to build a nuclear power until 2010, when Sebastian...currently engaged in nuclear trafficking, the risk is there. According to Alex Sánchez, in 2008, Colombian security forces discovered that the

  17. Relativity, nuclear polarizability, and screening in sub-Coulomb elastic scattering

    International Nuclear Information System (INIS)

    Lynch, W.G.; Tsang, M.B.; Bhang, H.C.; Cramer, J.G.; Puigh, R.J.

    Elastic scattering of p-shell nuclear projectiles from 208 Pb has been examined for deviations from Rutherford scattering. Four effects can be important: atomic screening, vacuum polarization, nuclear polarizability and a relativistic effect of dynamical origin. The presence of atomic screening, nuclear polarizability and the relativistic effect was observed thus constituting the first measurement of this relativistic effect using complex nuclei and the first measurement of this relativistic effect using complex nuclei and the first measurement of nuclear polarizability in an external Coulomb field

  18. Peaceful uses of nuclear energy and IAEA safeguards and related activities

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    This paper reports that deliberations on the peaceful uses of nuclear energy, both within and outside the United Nations, have focused on two divergent points of view. One emphasizes the potential benefits of the peaceful application of this source of energy to a variety of purposes, particularly the generation of electric power. The other stresses the risks engendered by the transfer of nuclear material, equipment and technology that might lend themselves to the manufacture of nuclear weapons. Recipient States have traditionally underlined their need and their inherent right to have unimpaired access to the peaceful applications of nuclear energy, while the supplier States, wishing to avoid contributing to the spread of a nuclear-weapon capability among recipients, have advocated restrictions on international transfers, especially of nuclear know-how and installations. In 1977, 15 supplier States agreed upon criteria for the application of IAEA safeguards to exports and formulated requirements to prevent unauthorized transactions, including restrictions on re-exportation. In February 1980, the Conference on the International Nuclear Fuel Cycle Evaluation (INFCE), initiated by the United States, completed a technical evaluation of data and options that it had undertaken to find less proliferation-prone nuclear fuel cycles. Sixty-six States-both suppliers and recipients of nuclear technology-took part in the evaluation, which did not, however, lead to the hoped-for result

  19. Nuclear power programs and related R and D topics in Korea

    International Nuclear Information System (INIS)

    Kang, C. S.

    2006-01-01

    Full text: Nuclear power generation has assured the stable supply of energy, reduced national trade deficit, lowered electricity bill, and mitigated the air-pollution problem in Korea. As of 2005, Korea has 20 nuclear power plants in operation and 4 under construction. According to the recent 'Long-Term Electricity Supply Scheme', Korea will have 28 nuclear units in operation by 2017, which will consist of 45% of electricity generation. The 3rd 'Comprehensive Promotion Plan of Nuclear Energy' has been completed, which will constitute the national nuclear policy of Korea during the period of 2007 through 2011. According to the Plan, 1,000 MWe-sized OPRIOOO and 1,400 MWe-sized APR1400 will serve for large-scale electricity generation until 2025. Korea will commercialize 330 MWt-sized SMART for multi-use purpose such as seawater desalination, district heating, ship propulsion, and small-scale electricity generation. Korea has joined GIF and INPRO to develop advanced reactor concepts beyond the year of 2025: SFR for fast reactor program and VHTR for hydrogen production. Along with the Plan, the 'Medium and Long Term Nuclear R and D Program (2007-2011)' has been also formulated to support the Plan through systematic R and D work in the areas of: future reactor systems, nuclear safety, nuclear fuel cycles, radiation technology, and innovative nuclear power technology. The total 5-year R and D budget will be a little over 1 billion US dollars

  20. Synergistic behaviour of nuclear radiation, temperature-humidity extremes and LOCA situation on safety and safety-related equipment in Indian nuclear power plants

    International Nuclear Information System (INIS)

    Kulkarni, R.D.; Bora, J.S.; Prakash, Ravi; Agarwal, Vivek; Sundersingh, V.P.

    2002-01-01

    Full text: The general philosophy for the instrumentation in nuclear power plants is based on the use of equipment/instruments which are capable of continuous satisfactory operation over a long period of time with minimum attention. Long term reliability under varying service conditions is of prime importance. The reliability of nuclear power plant depends on the reliability of safety and safety-related electronic instruments/ equipment used for performing the crucial tasks. The electrical and electronic systems/ circuits/ components of the equipment used in reactor safety systems (e.g. reactor protection system, emergency core cooling system, etc.) and reactor safety-related systems (e.g. reactor containment isolation and cooling system, reactor shutdown system, etc.) are responsible for safe and reliable operation of a nuclear power plant. The performance of reactor safety and safety-related equipment/instruments viz. pressure and differential pressure transmitter, amplifier for ion chamber, etc. has been evaluated under synergistic atmosphere including LOCA to find out the critical link in the circuits and subsequent modifications are suggested. The mathematical representation of the generated database has been done to estimate the life span of the instruments and accordingly the guidelines has been prepared for the operational staff to avoid the forced outage of the plant. All the details are included and mathematical models are presented to predict the future performances

  1. Civil nuclear and responsibilities related to radioactive wastes. The 'cumbersome' wastes of the civil nuclear; The Parliament and the management of wastes from the civil nuclear; The Swiss legal framework related to the shutting down of nuclear power stations and to the management of radioactive wastes; Economic theory and management of radioactive wastes: to dare the conflict

    International Nuclear Information System (INIS)

    Rambour, Muriel; Pauvert, Bertrand; Zuber-Roy, Celine; Thireau, Veronique

    2015-01-01

    This publication presents the contributions to a research seminar organised by the European Centre of research on Risk, Collective Accident and Disasters Law (CERDACC) on the following theme: civil nuclear and responsibilities related to radioactive wastes. Three main thematic issues have been addressed: the French legal framework for waste processing, the comparison with the Swiss case, and the controversy about the exposure of societies to waste-induced risks. The first contribution addressed the cumbersome wastes of the civil nuclear industry: characterization and management solutions, the hypothesis of reversibility of the storage of radioactive wastes. The second one comments the commitment of the French Parliament in the management of wastes of the civil nuclear industry: role of Parliamentary Office of assessment of scientific and technological choices (OPECST) to guide law elaboration, assessment by the Parliament of the management of nuclear wastes (history and evolution of legal arrangements). The next contribution describes the Swiss legal framework for the shutting down of nuclear power stations (decision and decommissioning) and for the management of radioactive wastes (removal, financing). The last contribution discusses the risk related to nuclear waste management for citizen and comments how economists address this issue

  2. Computerized reactor protection and safety related systems in nuclear power plants. Proceedings of a specialists' meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Though the majority of existing control and protection systems in nuclear power plants use old analogue technology and design philosophy, the use of computers in safety and safety related systems is becoming a current practice. The Specialists Meeting on ''Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants'' was organized by IAEA (jointly by the Division of Nuclear Power and the Fuel Cycle and the Division of Nuclear Installation Safety), in co-operation with Paks Nuclear Power Plant in Hungary and was held from 27-29 October 1997 in Budapest, Hungary. The meeting focused on computerized safety systems under refurbishment, software reliability issues, licensing experiences and experiences in implemented computerized safety and safety related systems. Within a meeting programme a technical visit to Paks NPP was organized. The objective of the meeting was to provide an international forum for the presentation and discussion on R and D, in-plant experiences in I and C important to safety, backfits and arguments for and reservations against the digital safety systems. The meeting was attended by 70 participants from 16 countries representing NPPs and utility organizations, design/engineering, research and development, and regulatory organizations. In the course of 4 sessions 25 technical presentations were made. The present volume contains the papers presented by national delegates and the conclusions drawn from the final general discussion

  3. Methodology of radionuclides dis incorporation in people related to nuclear and radiological accidents

    International Nuclear Information System (INIS)

    Jimenez F, E. A.

    2014-01-01

    In this paper a classification of the radiological and nuclear accidents is presented, describing which the activities are, where they have occurred, their incidence and the learned lessons in these successes. The radiological accidents in which radioactive materials intervene can occur anywhere, and they are related to no controlled dangerous sources (abandoned, lost, stolen, or found sources), improper use of dangerous industrial and medical sources, exposition and contamination of people in general by an unknown origin, serious over expositions, menaces and willful misconduct, emergencies during transportation of radioactive material. A person can receive a dose of radiation from an external source, because of radioactive material placed on skin or on equipment, or because of ingestion or inhalation of radiological particles. The ingestion or the inhalation of radioactive material can cause an internal dose to the whole body or to a specific organ during a period of time. That is why a description of the processes of incorporation, the stages of incorporation and a description of the biokinetic models are also realized to understand the ingestion, transference and the excretion of the radioactive elements. In order to offer help to a victim of internal contamination, the dosimetric and medical diagnosis is very important. The most important techniques of dosimetric diagnosis are the dosimetry in vivo (cytogenetics and the counting in vivo of the whole body) and the bioassays. These techniques allow obtain data such as the radionuclide, the target organ, the absorbed dose, etc. At the same time, the doctor in charge must be attentive to the patients symptoms and their manifestation time, since they are an indicator, first, the patient suffered an irradiation, and second, of the range esteem of the received radiation dose. These are the parameters that are useful as criterion to decide if a person has to receive some treatment and select the methodologies that

  4. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2005-01-01

    This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

  5. A cohort study of thyroid disease in relation to fallout from nuclear weapons testing

    International Nuclear Information System (INIS)

    Kerber, R.A.; Till, J.E.; Simon, S.L.; Lyon, J.L.; Thomas, D.C.; Preston-Martin, S.; Rallison, M.L.; Lloyd, R.D.; Stevens, W.

    1993-01-01

    OBJECTIVE--To estimate individual radiation doses and current thyroid disease status for a previously identified cohort of 4818 schoolchildren potentially exposed to fallout from detonations of nuclear devices at the Nevada Test Site between 1951 and 1958. DESIGN--Cohort analytic study. SETTING--Communities in southwestern Utah, southeastern Nevada, and southeastern Arizona. PARTICIPANTS--Individuals who were still residing in the three-state area (n = 3122) were reexamined in 1985 and 1986, and information on the subjects' and their mothers' milk and vegetable consumption during the fallout period was obtained by telephone interview (n = 3545). After exclusions to eliminate missing data and confounding factors, 2473 subjects were available for analysis. MAIN OUTCOME MEASURES--Individual radiation doses to the thyroid were estimated by combining consumption data with radionuclide deposition rates provided by the US Department of Energy and a survey of milk producers. Relative risk models adjusted for age, sex, and state were fitted using maximum likelihood to period prevalence data for thyroid carcinomas, neoplasms, and nodules. RESULTS--Doses ranged from 0 mGy to 4600 mGy, and averaged 170 mGy in Utah. There was a statistically significant excess of thyroid neoplasms (benign and malignant; n = 19), with an increase in excess relative risk of 0.7% per milligray. A relative risk for thyroid neoplasms of 3.4 was observed among 169 subjects exposed to doses greater than 400 mGy. Positive but nonsignificant dose-response slopes were found for carcinomas and nodules. CONCLUSIONS--Exposure to Nevada Test Site-generated radioiodines was associated with an excess of thyroid neoplasms. The conclusions are limited by the small number of exposed individuals and the low incidence of thyroid neoplasms

  6. Crop improvement for salinity and drought tolerance using nuclear and related techniques (abstract)

    International Nuclear Information System (INIS)

    Serraj, R.; Lagoda, P.J.

    2005-01-01

    complex interactions among the traits involved in tolerance to both drought and salinity, pyramiding using marker-assisted breeding, induced mutation and other biotechnologies, combined with a multidisciplinary approach and the participation of farmers, is likely to provide the best strategy to accelerate the progress towards the development of adapted tolerant crop germplasm. The joint FAO/IAEA division is investing considerable effort in evaluating opportunities for using nuclear and related technologies to improve tolerance to abiotic stresses such as drought and salinity. The division has a long-standing experience in developing and coordinating collaborative research programs (CRP) on abiotic stresses, involving NARs in developing countries, international IARCs and expert scientists. Similarly, several technical cooperation projects (TCP) were carried out on crop improvement for tolerance to drought and salinity, at national, regional and interregional levels. The Soil and Biotechnology laboratories at Seibersdorf also have the experience and facilities for developing, testing and applying new isotope and nuclear-related techniques for the improvement of crop productivity and stress tolerance. An important project is currently being implemented by the joint FAO/IAEA division for the identification and development of crop germplasm with superior resource use efficiency and nutritional value and adapted to harsh environments. Two CRPs have been recently launched under this project dealing respectively with (i) the identification and pyramiding of mutated genes, and novel approaches for improving crop tolerance to salinity and drought, and (II) the selection for greater agronomic water-use efficiency in wheat and rice using carbon isotope discrimination under drought and saline environments. This paper will review the recent progress made at the joint FAO/IAEA division in deciphering the complexity of drought and salinity problems and developing drought and salt

  7. Advisory group meeting on safeguards related to final disposal of nuclear material in waste and spent fuel

    International Nuclear Information System (INIS)

    1988-07-01

    This paper is primarily concerned with Section 11 of INFCIRC/153 which provides for the possible termination of safeguards based on a determination that the nuclear material in question has been consumed, has been diluted, or has become practicably irrecoverable. Two distinctly different categories of nuclear material have been suggested for possible termination of safeguards based on a determination that the nuclear material has become practicably irrecoverable: One relates to a variety of low concentration waste materials, meaning thereby materials which the State or plant operator considers to be of questionable economic recoverability and the other relates to the spent fuel placed in facilities described as ''permanent repositories'' which are at least claimed to represent ''final disposal'' facilities and are candidates for a possible determination of practicably irrecoverable. 26 refs, tabs

  8. Some issues related to the development of nuclear power plant in Indonesia

    International Nuclear Information System (INIS)

    Panggabean, L.M.

    1987-01-01

    Indonesia being a member of ASEAN belongs to the group of developing country. If Indonesia decides to embark on the establishment of nuclear power plan then the country will have no choice but to discuss the following issues: Safe operation of the plant and management of the nuclear waste. Safe operation of the power plant is important not only from the point of view of hazards to human being, or economic loss, or even death, but equally important it is also from the psychological point of view in that not to loose the society's confidence in the overall nuclear power plant programme in the future. The issue of safe operation involves both a safely designed system as well as skilled personnels to execute a well designed operation procedure. The issue of nuclear safety is getting more and more attention lately for various, some due to a deep concern about the quality of the inherent safety of the nuclear power plant to be built, others may just use their emotion to ask question like ''what its''. The issue of nuclear waste is as fundamental as the plant safety. Common people make very little difference between an atomic bomb and waste from a nuclear power plant. Another issue is one of transfer of technology which needs to be tied up with the overall industrialization process, meaning that embarking on nuclear power programme needs to contribute to local industrial activities, at least for some parts or components which can be manufactured locally. (author)

  9. Factors relating to the selection of sites for nuclear power stations in certain industrial countries

    International Nuclear Information System (INIS)

    1979-08-01

    The subject is discussed under the following headings: framework conditions of energy supply (energy supply in general (economics, planning); supply of nuclear energy (objectives, national nuclear industry, technology, development, public conflict)); environmental planning (legal foundations, planning levels, public site-provision investigations, electrical utilities); general and statutory atomic licensing procedure, criteria. (U.K.)

  10. The Regulation of Major Risks in Relation to Large Nuclear Installations in France

    International Nuclear Information System (INIS)

    Phan Van, L.

    1991-01-01

    Recently, major risk prevention has generated legislative and regulatory texts in French law, particularly regarding nuclear installations. This article reviews the context and analyses the scope of the new regulations. They require the nuclear operator to take preventive measures, namely more stringent obligations from the safety viewpoint to inform the public. These include risk assessments and preparing emergency plans in case if accidents. (NEA)

  11. A study on establishing export system of nuclear related equipments to the IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Song, Ki Dong; Lee, Man Ki; Moon, Ki Hwan; Kim, Seung Soo; Lim, Chae Young; Kim, Hwa Sup; Min, Tae Sik [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-04-01

    In spite of the advanced status in the international nuclear society, exports of domestic nuclear industries to procurement market of the international organizations has been negligible. This study briefly explained the role and the structure of the IAEA. Then, this study surveyed the size of procurement market, major procurement items, and procurement process. This study also gave an export example to the IAEA from Korea Atomic Energy Research Institute for the ease of understanding the procurement process. Based on these surveys and analysis, this study established the goal and strategy for exports of nuclear equipments to the IAEA. Besides, this study surveyed domestic nuclear industries that have potential to export their products to the IAEA. Then, Korea Atomic Energy Research Institute, by a cooperation with Korea Atomic Industrial Forum Inc., held workshop on 'export of nuclear equipments to IAEA' in May 2001 for them. 4 refs., 1 fig., 10 tabs. (Author)

  12. Nuclear Data Resources for Capture gamma-Ray Spectroscopy and Related Topics

    International Nuclear Information System (INIS)

    Pritychenko, B.

    2011-01-01

    Nuclear reaction data play an important role in nuclear reactor, medical, and fundamental science and national security applications. The wealth of information is stored in internally adopted ENDF-6 and EXFOR formats. We present a complete calculation of resonance integrals, Westcott factors, thermal and Maxwellian-averaged cross sections for Z = 1-100 using evaluated nuclear reaction data. The addition of newly-evaluated neutron reaction libraries, and improvements in data processing techniques allows us to calculate nuclear industry and astrophysics parameters, and provide additional insights on all currently available neutron-induced reaction data. Nuclear reaction calculations will be discussed and an overview of the latest reaction data developments will be given.

  13. A study on establishing export system of nuclear related equipments to the IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Song, Ki Dong; Lee, Man Ki; Moon, Ki Hwan; Kim, Seung Soo; Lim, Chae Young; Kim, Hwa Sup; Min, Tae Sik [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-04-01

    In spite of the advanced status in the international nuclear society, exports of domestic nuclear industries to procurement market of the international organizations has been negligible. This study briefly explained the role and the structure of the IAEA. Then, this study surveyed the size of procurement market, major procurement items, and procurement process. This study also gave an export example to the IAEA from Korea Atomic Energy Research Institute for the ease of understanding the procurement process. Based on these surveys and analysis, this study established the goal and strategy for exports of nuclear equipments to the IAEA. Besides, this study surveyed domestic nuclear industries that have potential to export their products to the IAEA. Then, Korea Atomic Energy Research Institute, by a cooperation with Korea Atomic Industrial Forum Inc., held workshop on 'export of nuclear equipments to IAEA' in May 2001 for them. 4 refs., 1 fig., 10 tabs. (Author)

  14. Workshop on environmental assessment. [Regulation of applications of nuclear energy and related ancillary systems

    Energy Technology Data Exchange (ETDEWEB)

    Watson, E.C. (comp.)

    1982-07-01

    Objectives of the workshop were: to review and evaluate the state-of-the-art of environmental impact assessments as applied to the regulation of applications of nuclear energy and related ancillary systems; to identify areas where existing technology allows establishing acceptable methods or standard practices that will meet the requirements of the NRC regulations, standards and guides for both normal operations and off-standard conditions including accident considerations; to illuminate topics where existing models or analytical methods are deficient because of unverified assumptions, a paucity of empirical data, conflicting results reported in the literature or a need for observation of operation systems; to compile, analyze and synthesize a prioritized set of research needs to advance the state-of-the-art to the level which will meet all of the requirements of the Commission's regulations, standards and guides; and to develop bases for maintaining the core of regulatory guidance at the optimum level balancing technical capabilities with practical considerations of cost and value to the regulatory process. The discussion held in small group sessions on aquatic, atmospheric, and terrestrial pathways are presented. The following research needs were identified as common to all three groups: validation of models; characterization of source terms; development of screening techniques; basis for de minimis levels of contamination; and updating of objectives for environmental monitoring programs.

  15. Establishing Food Traceability System Using Nuclear and Related Techniques in Malaysia

    International Nuclear Information System (INIS)

    Zainon Othman; Nazaratul Ashifa Abdullah Salim; Salmah Moosa; Roslanzairi Mostapha

    2015-01-01

    Determination of food traceability is important in quality control and safety of food. The dramatic increase in the volume of global trade and complexity of supply chains has caused a number of issues concerning food authenticity and safety. Commodities that attract premium prices are subject to fraud such as adulteration and counterfeit. This poses serious health risks due to unknown origin of the counterfeit. In addition to safety concern, the capability to certify food origin is becoming significant economic importance. In several countries, the use of geographical indications allows producers to obtain market recognition and often a premium price. In addressing food safety issues in Malaysia, the Food Hygiene Regulations (2009) has provision for traceability but mechanism on how traceability can be achieved is not prescribed. Present mechanism is mainly paper-based system that passes information along with the commodity. However, such system is subject to failure either inadvertently or deliberately (fraud). Thus there is a need to establish a science-based traceability system to support the food safety surveillance program in Malaysia. This paper presents the concept and use of nuclear and related techniques involving isotopic and elemental fingerprinting in determining the geographical origin of various food products and its potential application for traceability of Malaysian agricultural produce. (author)

  16. Analysis of factors related to man-induced hazard for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young

    2003-03-01

    This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out

  17. Analysis of factors related to man-induced hazard for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young [Seoul National Univ. of Technology, Seoul (Korea, Republic of)

    2003-03-15

    This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out.

  18. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers; Comunicaciones Recibidas De Diversos Estados Miembros Relativas A Las Directrices Para La Exportacion De Tecnologia, Equipo Y Materiales Nucleares. Transferencias Nucleares Y Transferencias De Equipo, Materiales V Tecnologia Afin Al Doble Uso En Materia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-04-15

    The Director General has received a Note Verbale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Verbale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Note Verbale is annexed hereto [Spanish] El Director General ha recibido una nota verbal de fecha 5 de marzo de 1993 del Ministerio de Relaciones Exteriores de la RepUblica Eslovaca. El objetivo de la nota verbal es proporcionar informaciOn sobre las Directrices para las transferencias nucleares y las Directrices para la transferencia de equipo, materiales y tecnologia afin al doble uso en materia nuclear, de dicho Gobierno. Atendiendo a los deseos expresados al final de la nota verbal, se adjunta al presente documento el texto de la nota verbal.

  19. Relative conservatisms of combination methods used in response spectrum analyses of nuclear piping systems

    International Nuclear Information System (INIS)

    Gupta, S.; Kustu, O.; Jhaveri, D.P.; Blume, J.A.

    1983-01-01

    The paper presents the conclusions of a comprehensive study that investigated the relative conservatisms represented by various combination techniques. Two approaches were taken for the study, producing mutually consistent results. In the first, 20 representative nuclear piping systems were systematically analyzed using the response spectrum method. The total response was obtained using nine different combination methods. One procedure, using the SRSS method for combining spatial components of response and the 10% method for combining the responses of different modes (which is currently acceptable to the U.S. NRC), was the standard for comparison. Responses computed by the other methods were normalized to this standard method. These response ratios were then used to develop cumulative frequency-distribution curves, which were used to establish the relative conservatism of the methods in a probabilistic sense. In the second approach, 30 single-degree-of-freedom (SDOF) systems that represent different modes of hypothetical piping systems and have natural frequencies varying from 1 Hz to 30 Hz, were analyzed for 276 sets of three-component recorded ground motion. A set of hypothetical systems assuming a variety of modes and frequency ranges was developed. The responses of these systems were computed from the responses of the SDOF systems by combining the spatial response components by algebraic summation and the individual mode responses by the Navy method, or combining both spatial and modal response components using the SRSS method. Probability density functions and cumulative distribution functions were developed for the ratio of the responses obtained by both methods. (orig./HP)

  20. Evaluation of systems interactions in nuclear power plants: Technical findings related to Unresolved Safety Issue A-17

    International Nuclear Information System (INIS)

    Thatcher, D.

    1989-05-01

    This report presents a summary of the activities related to Unresolved Safety Issue (USI)A-17, ''Systems Interactions in Nuclear Power Plants,'' and also includes the NRC staff's conclusions based on those activities. The staff's technical findings provide the framework for the final resolution of this unresolved safety issue. The final resolution will be published later as NUREG-1229. 52 refs., 4 tabs

  1. Operational safety enhancement of Soviet-designed nuclear reactors via development of nuclear power plant simulators and transfer of related technology

    International Nuclear Information System (INIS)

    Kohut, P.; Epel, L.G.; Tutu, N.K.

    1998-01-01

    The US Department of Energy (DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper

  2. Co-ordinated research programme on the use of nuclear and nuclear-related techniques in the study of environmental pollution associated with solid wastes

    International Nuclear Information System (INIS)

    1991-01-01

    A co-ordinated research programme on the use of nuclear and nuclear-related techniques in the study of environmental pollution associated with solid wastes was started by the IAEA in December 1987 and now comprises twenty-three participants from twenty-one countries. Topics of interest in this programme include studies of atmospheric aerosols, coal fly ash, incinerator ash, sewage sludge and a variety of other environmental specimens contaminated with solid wastes. The analytical techniques used include neutron activation analysis, particle-induced X-ray emission and energy-dispersive X-ray fluorescence. This report summarizes the discussions that took place during the second research co-ordination meeting. Working papers presented by the participants are included as annexes and have been indexed separately. Refs, figs and tabs

  3. Co-ordinated research programme on the use of nuclear and nuclear-related techniques in the study of environmental pollution associated with solid wastes

    International Nuclear Information System (INIS)

    1992-01-01

    A co-ordinated research programme on the use of nuclear and nuclear-related techniques in the study of environmental pollution associated with solid wastes was started by the IAEA in December 1987 and now comprises nineteen participants from seventeen countries. Topics of interest in this programme include studies of atmospheric aerosols, coal fly ash, incinerator ash, sewage sludge and a variety of other environmental specimens contaminated with solid wastes. The analytical techniques used include neutron activation analysis, particle-induced X-ray emission and energy-dispersive X-ray fluorescence. This report summarizes the discussions that took place during the third research co-ordination meeting. Working papers presented by the participants are included as annexes and have been indexed separately. Refs, figs and tabs

  4. Canadian--American relations and the nuclear weapons controversy, 1958--1963

    International Nuclear Information System (INIS)

    Ghent, J.M.

    1976-01-01

    This study attempts to explain the nuclear weapons controversy as it developed between 1958 and 1963. The nuclear controversy centered around Canada's acceptance of a nuclear role, within the American alliance system, for the Canadian armed forces. In the period 1958-1959, when the critical weapons decisions were being taken, Canadian political authorities lost control of the policy-making process, permitting the Canadian and American military bureacracies to initiate nuclear plans suited to their common needs and objectives. Prime Minister Diefenbaker's reluctance to arm the systems acquired by transborder bureaucratic coalition is also re-examined. Previous analysts have regarded the government's hesitations over nuclear weapons as the product of Diefenbaker's personal antagonism towards President Kennedy or as a futile attempt to reverse the process of continental integration. The opening of the Kennedy papers reveals the degree to which Diefenbaker was committed to close Canadian-American cooperation and the effort he made to overcome the president's hostility towards him. This study emphasizes the importance of Diefenbaker's sensitivity to public, parliamentary, and cabinet opposition to nuclear arms. The secret U.S. demand for nuclear bases in Labrador and Newfoundland is revealed. Thus the question of nuclear storage in Canada for Canadian forces was complicated by U.S. insistence that Canada simultaneously provide nuclear storage for the strategic forces of the U.S. Finally, the extent of American responsibility for Diefenbaker's demise is re-assessed, and the conclusion is reached that the U.S., through Canadian-American military interaction and the initiative of the ambassador in Ottawa, did in fact help to bring down the government of Canada

  5. Nuclear model codes and related software distributed by the OECD/NEA Data Bank

    International Nuclear Information System (INIS)

    Sartori, E.

    1993-01-01

    Software and data for nuclear energy applications is acquired, tested and distributed by several information centres; in particular, relevant computer codes are distributed internationally by the OECD/NEA Data Bank (France) and by ESTSC and EPIC/RSIC (United States). This activity is coordinated among the centres and is extended outside the OECD area through an arrangement with the IAEA. This article covers more specifically the availability of nuclear model codes and also those codes which further process their results into data sets needed for specific nuclear application projects. (author). 2 figs

  6. Nuclear skill related training and job identification and placement service for migrant and seasonal farm workers

    International Nuclear Information System (INIS)

    1980-01-01

    The success rate of the NSRT Program - based on placement in unsubsidized employment - was 90%. Most of the participants who did not graduate from the NSRT Program were transferred to other less technical programs, such as TAT, REECO, and the EAST/SLAC programs, and obtained skills that made them employable elsewhere. The follow-up process at the Center for Nuclear Studies continues. Officials here can list place of employment, technical rating, and salary of all of the 90 graduates. Several are now full-fledged nuclear reactor operators licensed by the Nuclear Regulatory Commission

  7. The International Science and Technology Center (ISTC) and ISTC projects related to nuclear safety. Information review

    International Nuclear Information System (INIS)

    Tocheny, Lev V.

    2003-01-01

    The ISTC is an intergovernmental organization created ten years ago by Russia, USA, EU and Japan in Moscow. The Center supports numerous science and technology projects in different areas, from biotechnologies 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. The presentation addresses some technical results of the ISTC projects as well as methods and approaches employed by the ISTC to foster close international collaboration and manage projects towards fruitful results. (author)

  8. Aging management of safety-related concrete structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Arndt, E.G.

    1990-01-01

    The Structural Aging Program has the overall objective of providing the US Nuclear Regulatory Commission with an improved basis for evaluating nuclear power plants for continued service. In meeting this objective, a materials property data base is being developed as well as an aging assessment methodology for concrete structures in nuclear power plants. Furthermore, studies are well under way to review and assess inservice inspection techniques for concrete structures and to develop a methodology which can be used for performing current as well as reliability-based future conditions assessments of these structures. 16 refs., 2 tabs

  9. Accelerator driven systems for energy production and waste incineration: Physics, design and related nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Herman, M; Stanculescu, A [International Atomic Energy Agency, Vienna (Austria); Paver, N [University of Trieste and INFN, Trieste (Italy)

    2003-06-15

    This volume contains the notes of lectures given at the workshops 'Hybrid Nuclear Systems for Energy Production, Utilisation of Actinides and Transmutation of Long-lived Radioactive Waste' and 'Nuclear Data for Science and Technology: Accelerator Driven Waste Incineration', held at the Abdus Salam ICTP in September 2001. The subject of the first workshop was focused on the so-called Accelerator Driven Systems, and covered the most important physics and technological aspects of this innovative field. The second workshop was devoted to an exhaustive survey on the acquisition, evaluation, retrieval and validation of the nuclear data relevant to the design of Accelerator Driven Systems.

  10. Some thoughts about the relations between education, training and nuclear employment

    International Nuclear Information System (INIS)

    Turpin, L.

    2009-01-01

    This article tackles the question of education and training in nuclear industry. The different sectors of education are considered: I.F.P. school, universities. The question of students exchange as recommended by the European nuclear education network (E.N.E.N.) and as practised by the National Institute for nuclear science and technology (I.N.S.T.N., higher education institution under the joint supervision of the Ministries in charge of education and industry whom vocation is to disseminate the cea knowledge and know how). (N.C.)

  11. Accelerator driven systems for energy production and waste incineration: Physics, design and related nuclear data

    International Nuclear Information System (INIS)

    Herman, M.; Stanculescu, A.; Paver, N.

    2003-01-01

    This volume contains the notes of lectures given at the workshops 'Hybrid Nuclear Systems for Energy Production, Utilisation of Actinides and Transmutation of Long-lived Radioactive Waste' and 'Nuclear Data for Science and Technology: Accelerator Driven Waste Incineration', held at the Abdus Salam ICTP in September 2001. The subject of the first workshop was focused on the so-called Accelerator Driven Systems, and covered the most important physics and technological aspects of this innovative field. The second workshop was devoted to an exhaustive survey on the acquisition, evaluation, retrieval and validation of the nuclear data relevant to the design of Accelerator Driven Systems

  12. Discussion of some issues in assessing nuclear and radiation environmental impacts and in related assessment

    International Nuclear Information System (INIS)

    Pan Ziqiang

    1998-01-01

    The author discusses some noticeable issues in drafting assessment report of nuclear and radiation environmental impacts and relevant aspects needed to be considered from the point of view of comprehensive environmental assessment. The considerable issue are principles of radioactive waste management, optimization of radiation protection and collective dose, and uncertainty of the assessment. Implementing reporting system on assessment of nuclear and radiation environmental impacts would improve environmental protection for nuclear and radiation facilities. However, trade's, regional , country and global assessment of environmental impacts has to be enhanced. For this purpose, it is necessary to develop methodology of qualitative and quantitative comprehensive assessment

  13. Nuclear skill related training and job identification and placement service for migrant and seasonal farm workers

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    The success rate of the NSRT Program - based on placement in unsubsidized employment - was 90%. Most of the participants who did not graduate from the NSRT Program were transferred to other less technical programs, such as TAT, REECO, and the EAST/SLAC programs, and obtained skills that made them employable elsewhere. The follow-up process at the Center for Nuclear Studies continues. Officials here can list place of employment, technical rating, and salary of all of the 90 graduates. Several are now full-fledged nuclear reactor operators licensed by the Nuclear Regulatory Commission.

  14. Structural Aging Program to evaluate continued performance of safety-related concrete structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

    1994-01-01

    This report discusses the Structural Aging (SAG) Program which is being conducted at the Oak Ridge National Laboratory (ORNL) for the United States Nuclear Regulatory commission (USNRC). The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. The program is organized into three technical tasks: Materials Property Data Base, Structural Component Assessment/Repair Technologies, and Quantitative Methodology for continued Service Determinations. Objectives and a summary of recent accomplishments under each of these tasks are presented

  15. Studies of Degree and Postgraduate related to nuclear energy in the Polytechnic University of Valencia

    International Nuclear Information System (INIS)

    Escriva, A.; Munoz-Cobo, J. L.

    2008-01-01

    The postgraduate education in Nuclear engineering in Spain has always been of high quality generating specialists that have been incorporated as professionals of the different areas of the nuclear energy sector. these areas go from the technological, developing high quality engineering works, to the management, running departments and even companies, going through the research, the same in the research centers as in the university. This education, that has gone through different phases with an important variation of alumnae number depending on the situation of the nuclear sector, is nowadays in a moment of change derived from the European convergence process (Bologna) whose final situation is not still defined. This article includes the description of the studies given in two of the Spanish universities with more tradition in nuclear education, including the graduate and post-graduate studies. (Author)

  16. Synthesis of superheavy elements and application of nuclear physics methods in related fields

    International Nuclear Information System (INIS)

    Flerov, G.

    1985-01-01

    Heavy ion accelerators are used not only for the synthesis of new elements but also for the production of nuclear filters from polymers. The principle is described of the manufacture of such filters, and their chemical processing. By changes in irradiation conditions and in conditions of chemical leaching, nuclear filters may be obtained of various density, shape and size of pores and with a different angular distribution of tracks in the polymer material. The most frequently used polymer is polyethylene terephthalate film. The uses are described of nuclear filters, such as water treatment in the production of semiconductor instruments, in cryogenic instruments, in the purification concentration and sterilization filtration of viruses and vaccines, etc. Other uses of heavy ion beams are suggested, such as the method of nuclear tracks, the manufacture of membranes with a single opening, the manufacture of laser diaphragms, lithography, etc. (E.S.)

  17. Improvements in and relating to drums for storing fuel assemblies of nuclear reactors

    International Nuclear Information System (INIS)

    Artemiev, L.N.; Batjukov, V.I.; Fadeev, A.I.

    1977-01-01

    A specification is given for an improved design of drums used for storing nuclear reactor fuel assemblies. It is claimed that this new design reduces wear, increases reliability and enables the recharging operation to be speeded up. (UK)

  18. Annotated bibliography of safety-related occurrences in nuclear power plans as reported in 1974

    International Nuclear Information System (INIS)

    Scott, R.L.; Gallaher, R.B.

    1975-05-01

    All abnormal occurrences at nuclear power plants reported in 1974 are reviewed and summarized. This bibliography covers the individual reports on each of the 1421 abnormal occurrences reported to the U. S. Nuclear Regulatory Commission, as well as some 455 other documents pertaining to these and other events of note. The review is intended to provide insight as to where additional effort can be expended to improve operations in nuclear power plants. The individual reports, abstracted by the Nuclear Safety Information Center, concern incidents and failures, design or construction deficiencies, and noncompliance citations for license violations. A bibliography is included which contains 100-word abstracts of each incident. For convenience, the bibliography is organized according to type of facility as follows: boiling-water reactors; pressurized-water reactors; non-water-cooled power reactors; and reactors, general. Key-word and permuted-title indexes are provided for each section. (U.S.)

  19. Aspects of PWR nuclear power plant secondary cycle relating to reactor safety

    International Nuclear Information System (INIS)

    Mueller, A.E.F.; Leal, M.R.L.V.; Dominguez, D.

    1981-01-01

    A safety study of the main steam system, condensate and feedwater systems and water treatment system that belong to the secondary cooling circuits of a PWR nuclear power plant is presented. (E.G.) [pt

  20. Relative source comparison of the NPE to underground nuclear explosions at local distances

    Energy Technology Data Exchange (ETDEWEB)

    Smith, A.T. [Lawrence Livermore National Lab., CA (United States)

    1994-12-31

    The Non-Proliferation Experiment (NPE) provides an opportunity to compare broadband characteristics of chemical to nuclear explosions at a group of local stations (4 to 40 km distant). The locations for these stations were established on bedrock to record a small partially decoupled nuclear explosion and two nearby nuclear experiments, all shots within {open_quotes}N{close_quotes} Tunnel on Rainier Mesa, Area 12. These sites were also occupied to record aftershocks from the Little Skull Mountain earthquake and chemical explosions from the USGS Sierra Experiment. To minimize calibration errors during this period, redundant instrumentation were used for each event. THe analysis emphasizes the source characteristics of the different explosions. The 300-lb chemical calibration explosion allows removal of path effects from each explosion. The NPE and nearby experiments produce very similar waveforms. The decoupled nuclear explosion and the 300-lb chemical calibration explosion show higher frequency content consistent with a higher corner frequency for the sources.

  1. Jurisdictional control of administrative acts related to the safety of nuclear plants

    International Nuclear Information System (INIS)

    Fernandez Plasencia, S.

    1983-01-01

    This paper stresses the importance of jurisdictional control over nuclear power plants to ensure their safe operation. It also describes examples of case law concerning such plants in France, the Federal Republic of Germany, Italy and Spain. (NEA) [fr

  2. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [es

  3. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-09

    The document reproduces the text of the Notes Verbales received by the Director General of the IAEA on 20 October 1999 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom, and the United States of America relating to the transfers of nuclear-related dual-use equipment, materials, software and related technology.

  4. Communications received from certain Member States regarding guidelines for transfers of nuclear-related dual-use equipment, materials, software and related technology

    International Nuclear Information System (INIS)

    2000-01-01

    The document reproduces the text of the Notes Verbales received by the Director General of the IAEA on 20 October 1999 from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belgium, Brazil, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, the Netherlands, New Zealand, Norway, Poland, Portugal, Romania, the Slovak Republic, South Africa, Spain, Sweden, Switzerland, Ukraine, the United Kingdom, and the United States of America relating to the transfers of nuclear-related dual-use equipment, materials, software and related technology

  5. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology

  6. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology

    International Nuclear Information System (INIS)

    2006-01-01

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [fr

  7. Storage, handling and movement of fuel and related components at nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    The report describes in general terms the various operations involved in the handling of fresh fuel, irradiated fuel, and core components such as control rods, neutron sources, burnable poisons and removable instruments. It outlines the principal safety problems in these operations and provides the broad safety criteria which must be observed in the design, operation and maintenance of equipment and facilities for handling, transferring, and storing nuclear fuel and core components at nuclear power reactor sites

  8. The UK health and safety executive's policies on information relating to nuclear safety regulation

    International Nuclear Information System (INIS)

    Williams, L.

    1994-01-01

    How a message is transmitted can be as important as what is said. To be effective a message has to be timely, targeted and clear. People do not always remember what was said, by how and when it was said. This paper discusses some of the tools which the Nuclear Safety Division (NSD), the UK's nuclear regulator, has used and emphasizes the need to recognize the importance of a recipient interest in attempting to transmit a message. (author). 4 refs

  9. Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Perkins, W.C.; Durant, W.S.; Dexter, A.H.

    1980-12-01

    The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents

  10. Legal issues, authoritative licenses and tasks in relation with nuclear safety in Hungary

    International Nuclear Information System (INIS)

    Oerdoegh, J.; Voeroess, L.

    1998-01-01

    After a brief historical overview of nuclear authorities in Hungary, the role and functions of the National Atomic Energy Office are presented. It is the primary authority in this country on nuclear safety, with tasks and functions of licensing, inspection and enforcing safety measures. The organizational structure of NAEO and its position as a Governmental body is shown. Other tasks include the promotion of R and D coordination and international cooperation. (R.P.)

  11. The effect of safeguards on the contractual relations of nuclear suppliers

    International Nuclear Information System (INIS)

    MacIsaac, J.F.D.

    1976-01-01

    Canada applies a safeguards system aimed to ensure that nuclear materials and equipment are not diverted from their peaceful uses. These control requirements have a direct influence on the conditions of export contracts concluded by Canadian suppliers of nuclear materials or equipment. In particular if the buyer does not comply with the safeguards clauses, it may not be possible for the Canadian supplier to fulfill the contract. This possibility is covered by the force majeure clauses. (N.E.A.) [fr

  12. Management by regulatory inspection authorities of experience gained from safety related occurrences in nuclear power plants

    International Nuclear Information System (INIS)

    Tore, E.; Nilsson, R.

    1977-01-01

    A short description is given of the system used by the Swedish Nuclear Power Inspectorate to collect information of events occurring in nuclear power plants. The standard forms used by the utilities when reporting the events are described and a motivation given to their lay-out. The evaluation routine is defined and statistics given of events which occurred during the period July 1 1974 to December 31 1976. (author)

  13. Changes in the structure and relations of property in the Great Britain nuclear power

    International Nuclear Information System (INIS)

    Rumyantsev, V.V.

    1990-01-01

    Analysis of nuclear power development in the Great Britain is given. Currently it is reoriented to a wide application of PWR reactors instead of gas cooled ones, their economic indices being incapable of providing sufficient competitiveness on the British market. Reasons and state of affairs in denationalizing nuclear power, economic and financial difficulties connected with the realization of this politico-economic procedure are reported

  14. Radiation effects issues related to US DOE site remediation and nuclear waste storage

    International Nuclear Information System (INIS)

    Weber, W.J.; Ewing, R.C.

    1994-10-01

    Site restoration activities at DOE facilities and the permanent disposal of nuclear waste generated at the same DOE facilities involve working with and within various types and levels of radiation fields. Radionuclide decay and the associated radiation fields lead to physical and chemical changes that can degrade or enhance material properties. This paper reviews the impact of radiation fields on site restoration activities and on the release rate of radionuclides to the biosphere from nuclear waste forms

  15. Nuclear energy and related research in universities; achieving the intellectual and funding framework

    International Nuclear Information System (INIS)

    Goddard, A.J.H.; OLiveira, C.R.E. de

    2000-01-01

    My purpose in this paper is to discuss the research role of universities in the UK, and how this can contribute to nuclear safety competence in industry, to motivating young researchers towards the nuclear industry (and its employment prospects) and to contributing to a wider informed awareness of safety and other issues. I shall not be dealing with undergraduate (first degree) training or with Masters programmes - which will clearly be the main route for industry staff recruitment. (authors)

  16. Information and communication. In the event of abnormal situations relating to nuclear power. Final report

    International Nuclear Information System (INIS)

    Carlsson, S.; Wuensche, G.

    1995-01-01

    As a consequence of the Chernobyl accident the need for better communication and cooperation between the countries of Nordic Europe (Denmark, Finland, Iceland, Norway and Sweden) in case of nuclear accidents became increasingly obvious. An initiative in this direction was taken by the Nordic Liaison Committee for Atomic Energy (NKA), a intergovernmental body responsible for cooperation in the Nuclear field, established by the Nordic Council. Thus, the Nordic Contact Forum became a reality. The Forum was created to serve as an informal network among nuclear experts, information officers and journalists in the Nordic countries. The network has been held together by a committee consisting of one representative from each country, as appointed by the Governments. The Nordic Contact Forum arranged the first of three seminars for representatives of public authorities, the nuclear industry, and journalists in 1988 in Vikersund, Norway. The Forum also has established a network among information officers for the exchange of information of public interest within the nuclear field. As a result of its work and agreement has been reached as to when and how this information is to be disseminated, and lists of contact points have been drawn up. This will make it easier to give the public in each of the Nordic countries better an, above all, better coordinated information. The existence of this network has had positive results. Thus, on several occasions false rumours of nuclear accidents, radioactive clouds, etc, have been neutralized before they have caused unnecessary public concern. (au)

  17. The internationalization of nuclear industry: state and capital in atomic relations

    International Nuclear Information System (INIS)

    Ferreira Junior, Evaristo Santiago

    1986-03-01

    This paper analyzes the causes and scope of the nuclear energy diffusion process in the capitalist world. It also aims at explaining Brazil's role in this process. The study contemplates two main concepts that are, here, considered to be driving and directing vectors: the World Capital and the Capitalist State. According to the expanded reproduction logic, World Capital forms the world nuclear productive subsystem, which commands and directs, in this process, hundreds (or thousands) of productive units, regardless of their geographical location, nationality or capital control. Thru the utilization of available public intervention tools, the Capitalist state has favored the formation of the world nuclear productive subsystem, thus guiding the accumulation process in the interior of this system. Therefore, the conclusion of the Nuclear Cooperation Agreement between Brazil and Germany and the resultant establishment of the Brazilian Nuclear Program (following the authoritarian model of public administration), is well fitted in the general dynamics of subordination/articulation of the Brazilian economy to the world economy and, particularly, to the world nuclear productive subsystem. (author)

  18. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  19. Biomonitoring of air pollution in Jamaica through trace-element analysis of epiphytic plants using nuclear and related analytical techniques

    International Nuclear Information System (INIS)

    Vutchkov, Mitko

    2001-01-01

    The main goal of the Coordinated Research Project (No:9937/R0), entitled 'Biomonitoring of Air Pollution in Jamaica Through Trace-Element Analysis of Epiphytic Plants Using Nuclear and Related Analytical Techniques', is to identify and validate site specific epiphytic plants for biomonitoring the atmospheric pollution in Jamaica using nuclear analytical techniques at the International Centre for Environmental and Nuclear Sciences (ICENS). The specific objectives for the second year of the project were: Development of HOP for sampling epiphytic plants in Jamaica; Sampling design and sample collection; Sample preparation and analysis; Development of an in-house SRM and participation in the NAT-5 inter-laboratory study; Data analysis and interpretation of the results; Development of a work plan of the third year of the project

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

    Energy Technology Data Exchange (ETDEWEB)

    Jur, T.A.; Huhns, M.N.; Keating, D.A.; Orloff, D.I.; Rhodes, C.A.; Stanford, T.G.; Stephens, L.M.; Tatterson, G.B.; Van Brunt, V.

    1978-12-01

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

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

    International Nuclear Information System (INIS)

    Jur, T.A.; Huhns, M.N.; Keating, D.A.; Orloff, D.I.; Rhodes, C.A.; Stanford, T.G.; Stephens, L.M.; Tatterson, G.B.; Van Brunt, V.

    1978-12-01

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

  2. IAEA/NEA incident reporting system (IRS). Reporting guidelines. Feedback from safety related operating experience for nuclear power plants

    International Nuclear Information System (INIS)

    1998-01-01

    The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants. These guidelines have been jointly developed and approved by the NEA/IAEA

  3. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  4. The nuclear receptor Tlx regulates motor, cognitive and anxiety-related behaviours during adolescence and adulthood.

    Science.gov (United States)

    O'Leary, James D; Kozareva, Danka A; Hueston, Cara M; O'Leary, Olivia F; Cryan, John F; Nolan, Yvonne M

    2016-06-01

    The nuclear receptor Tlx is a key regulator of embryonic and adult hippocampal neurogenesis and has been genetically linked to bipolar disorder. Mice lacking Tlx (Nr2e1(-/-)) display deficits in adult hippocampal neurogenesis and behavioural abnormalities. However, whether Tlx regulates behaviour during adolescence or in a sex-dependent manner remains unexplored. Therefore, we investigated the role of Tlx in a series of behavioural tasks in adolescent male and female mice with a spontaneous deletion of Tlx (Nr2e1(-/-) mice). Testing commenced at adolescence (postnatal day 28) and continued until adulthood (postnatal day 67). Adolescent male and female Nr2e1(-/-) mice were hyperactive in an open field, an effect that persisted in adulthood. Male but not female Nr2e1(-/-) mice exhibited reduced thigmotaxis during adolescence and adulthood. Impairments in rotarod motor performance developed in male and female Nr2e1(-/-) mice at the onset of adulthood. Spontaneous alternation in the Y-maze, a hippocampus-dependent task, was impaired in adolescent but not adult male and female Nr2e1(-/-) mice. Contextual fear conditioning was impaired in adolescent male Nr2e1(-/-) mice only, but both male and female adolescent Nr2e1(-/-) mice showed impaired cued fear conditioning, a hippocampal-amygdala dependent cognitive process. These deficits persisted into adulthood in males but not females. In conclusion, deletion of Tlx impairs motor, cognitive and anxiety-related behaviours during adolescence and adulthood in male and female mice with most effects occurring during adolescence rather than adulthood, independent of housing conditions. This suggests that Tlx has functions beyond regulation of adult hippocampal neurogenesis, and may be an important target in understanding neurobiological disorders. Copyright © 2016 Elsevier B.V. All rights reserved.

  5. Relations between radiobiological hypoxia and nuclear magnetic resonance-imaged blood microcirculation in experimental tumors

    International Nuclear Information System (INIS)

    Koike, Sachiko; Ando, Koichi; Ikehira, Hiroo.

    1993-01-01

    Characteristics of hypoxic cells subjected to radiation were investigated and compared with those of microcirculation for two murine fibrosarcomas growing in C3H mice. Small NFSa tumors, growing in air-breathing mice, developed a radioresistant tail on the survival curve. The tail was indistinguishably parallel to a survival curve for an artificially hypoxic tumor. As the NFSa tumors increased in size, the hypoxic tail moved upward with no change of Do, resulting in increase of hypoxic fraction from 3.9% to 40%. The R1137 tumors had no radioresistant tail nor hypoxic fraction regardless of tumor size. However, large-sized R1137 tumors developed a significant number of radioresistant, hypoxic cells with an intermediate Do, and were effectively sensitized by administrating misonidazole before irradiation. Thus, the NFSa tumors were fractionally hypoxic, and the large R1137 tumors had intermediate hypoxia. Measurement of tumor microcirculation by gadolinium-enhanced nuclear magnetic resonance indicated that both blood flow and blood volume decreased significantly when the NFSa tumor grew large. Similar reduction in these microcirculation parameters was also observed for the R1137 tumor. The small-sized NFSa tumor had relatively larger blood volume and faster blood flow than the small-sized R1137 tumor. When large-sized tumors were compared to each other, the NFSa again had better blood flow than the R1137. However, the blood volume in the large-sized tumors was significantly (p<0.05) smaller for the NFSa tumor than for the R1137 tumor. It was concluded that blood flow could not be a single determinant for tumor hypoxia, and the difference between fractional hypoxia and intermediate hypoxia would be reflected in the ratio of blood flow to blood volume. (author)

  6. External man-induced events in relation to nuclear power plant design

    International Nuclear Information System (INIS)

    1982-01-01

    This Guide deals with the basic design requirements for nuclear power plants, and presents a general design approach for protection against the effects of man-induced events. Section 2 discusses the general design approach. Section 3 outlines the development of the basic information necessary for an evaluation of the adequacy of a design against the effects of aircraft crashes, fires, explosions, and the release of toxic gases or corrosive substances. Section 4 outlines the design logic for protection against external man-induced events. It indicates possible methods of ensuring overall plant safety, including protection against possible secondary effects. Included for each event are: a methodology for calculating the design input parameters from the data generated in the siting study, system protection considerations from the effects of this man-induced event, and criteria for judging the adequacy of the protection provided. Specific design guidance related to acts of sabotage is not provided in this Guide. It should be recognized, however, that for certain situations such acts can be important to safety and could constitute the controlling postulated initiating event for design. The list of events covered is not necessarily complete. However, important events on which enough work has already been done in various Member States to enable their effects to be converted into generally accepted design parameters are included. In addition, other man-induced events such as dam ruptures, ship collisions, construction accidents and the like are identified but no general guidelines for design can be specified for these at present. These events need to be considered on an ad hoc basis, in order to arrive at design input parameters for them

  7. Overview of Cea studies on hydrogen production and related prospects for nuclear power

    International Nuclear Information System (INIS)

    Agator, J.M.; Guigon, A.

    2001-01-01

    The anticipated growth of the world energy demand and the increasing concern about the emission of greenhouse gases, with the objectives of limitation fixed by the Kyoto protocol, provide the impetus for the development of hydrogenous fuels, and especially that of hydrogen as energy carrier. The trend will be reinforced in the longer term with the progressive shortage of natural hydrocarbon fuels. Fuel cells used in stationary, transport and portable applications will probably be the most efficient hydrogen converter and the most promising decentralized energy technology of the coming decades. In order to contribute to the reduction of greenhouse gas emissions, the massive use of hydrogen for transport and stationary applications calls for the development of production processes compatible with low CO 2 emissions, thus limiting the use of fossil fuels (natural gas, oil, coal, etc.) as reagent or energy sources. Furthermore, the progressive exhaustion of economic fossil fuel reserves will ultimately make it necessary to extract hydrogen from water through CO 2 -free processes. With this prospect in view, base-load nuclear energy, besides renewable energies, can play an important role to produce hydrogen through electrolysis in the medium term, as can high temperature thermo-chemical water dissociation processes in the longer term. Starting from current research in the field of fuel cells and hydrogen storage systems, the CEA intends to implement a large R and D programme on hydrogen, continuing previous research and covering the aspects of production, transport and related safety requirements. This endeavour is intended to reinforce the contribution of the CEA to the national and European research effort on non-fossil energy sources, and to create new opportunities of international collaboration and networking. (authors)

  8. India's nuclear power programme present status, future prospects and related issues

    International Nuclear Information System (INIS)

    Prasad, Y.S.R.

    1998-01-01

    India is poorly placed in terms of world energy resources, while 16% of world's population lives in India, only 6% of coal and 0.6% of oil and gas reserves exist in the country. Moreover, the distribution of primary commercial energy resources is quite skewed. However, India is endowed with vast reserves of thorium. The energy potential of our modest uranium resources and sizeable thorium resources has been estimated to be six times that of our total coal reserves. Though during last fifty years since independence, India has made tremendous progress in the energy sector where the use of commercial energy has increased by ten folds. Electricity used during the same period has increased by eighty times. In spite of such an impressive growth the country, due to population growth, finds itself in the almost lowest bracket with regard to per capita consumption which is many fold lower than the world average. India as of today is a net energy importing country. The demand for energy, in particular electricity that has established to be the most efficient and convenient source, is projected to grow at 7-8% per annum for coming two decades. In such a demand scenario it is imperative that all the resources of energy must be judiciously utilised. However, with the depletion of fossil fuels and resulting possible price shocks a long-term energy security is required for the country. The paper deals with the role nuclear power can play in meeting the country's short term and long term demands, progress made and related issues. (author)

  9. Overview of CEA studies on hydrogen production and related prospects for nuclear power

    International Nuclear Information System (INIS)

    Agator, J.M.; Guigon, A.; Serre-Combe, P.

    2001-01-01

    The anticipated growth of the world energy demand and the increasing concern about the emission of greenhouse gases, with the objectives of limitation fixed by the Kyoto protocol, prepare the ground for the development of hydrogenous fuels, and especially that of hydrogen as energy carrier. The trend will be reinforced in the longer term with the progressive shortage of natural hydrocarbon fuels. Fuel cells used in stationary, transport and portable applications will probably be the most efficient hydrogen converter and the most promising decentralized energy technology of the next decades. In order to contribute to the reduction of greenhouse gas emissions, a massive use of hydrogen for transport and stationary applications calls for the development of production processes compatible with low CO 2 emissions, thus limiting the use of fossil fuels (natural gas, oil, coal...) as reagent or energy sources. Furthermore, the progressive exhaustion of economic fossil fuel reserves will ultimately make it necessary to extract hydrogen from water through CO 2 free processes. With this prospect in view, base-load nuclear energy, besides renewable energies, can play an important role to produce hydrogen through electrolysis in the medium term, and also through high temperature thermochemical water dissociation processes in the longer term. Starting from current research in the field of fuel cans and hydrogen storage systems, the CEA intends to implement a large R and D programme on hydrogen also covering the aspects of production, transport and related safety requirements. This endeavour is intended to reinforce the contribution of the CEA to the national and European research effort on non-fossil energy sources, and to open new opportunities of international collaborations and networking. (authors)

  10. 20-Hydroxyecdysone stimulates nuclear accumulation of BmNep1, a nuclear ribosome biogenesis-related protein in the silkworm, Bombyx mori.

    Science.gov (United States)

    Ji, M-M; Liu, A-Q; Sima, Y-H; Xu, S-Q

    2016-10-01

    The pathway of communication between endocrine hormones and ribosome biogenesis critical for physiological adaptation is largely unknown. Nucleolar essential protein 1 (Nep1) is an essential gene for ribosome biogenesis and is functionally conserved in many in vertebrate and invertebrate species. In this study, we cloned Bombyx mori Nep1 (BmNep1) due to its high expression in silk glands of silkworms on day 3 of the fifth instar. We found that BmNep1 mRNA and protein levels were upregulated in silk glands during fourth-instar ecdysis and larval-pupal metamorphosis. By immunoprecipitation with the anti-BmNep1 antibody and liquid chromatography-tandem mass spectrometry analyses, it was shown that BmNep1 probably interacts with proteins related to ribosome structure formation. Immunohistochemistry, biochemical fractionation and immunocytochemistry revealed that BmNep1 is localized to the nuclei in Bombyx cells. Using BmN cells originally derived from ovaries, we demonstrated that 20-hydroxyecdysone (20E) induced BmNep1 expression and stimulated nuclear accumulation of BmNep1. Under physiological conditions, BmNep1 was also upregulated in ovaries during larval-pupal metamorphosis. Overall, our results indicate that the endocrine hormone 20E facilitates nuclear accumulation of BmNep1, which is involved in nuclear ribosome biogenesis in Bombyx. © 2016 The Royal Entomological Society.

  11. Nuclear abnormalities in cells from nasal epithelium: a promising assay to evaluate DNA damage related to air pollution in infants

    Directory of Open Access Journals (Sweden)

    Michelle Mergener

    2014-12-01

    Full Text Available OBJECTIVES: This study intends to provide a quick, easy, and inexpensive way to assess nuclear abnormalities such as micronuclei and bud frequencies; binucleated, karyorrhectic, karyolytic, pycnotic, and condensed chromatin cells in nasal scrapings of infants, which are particularly important for conducting genotoxic studies related to the inhaled atmosphere in pediatric populations. METHODS: Nasal swab samples were collected from 40 infants under 12 months of age using a small cytobrush. 2,000 cells from each infant sample were analyzed and classified according to the frequency of nuclear abnormalities. RESULTS: Rates of nuclear abnormalities found agree with values reported in other studies of neonates and children. This study found 0.13% of cells with micronuclei; 1.20% karyorrhexis; 0.03% pyknosis; 10.85% karyolysis; 1.11% condensed chromatin; 0.54 binucleated cells; and 0.02% nuclear bud. Differences were not observed between genders or environmental passive smoking, nor was any age correlation found. CONCLUSION: The assay proposed here is suitable for assessing the frequency of nuclear abnormalities from nasal cells in infants.

  12. Guide on a national system for collecting, assessing and disseminating information on safety-related events in nuclear power plants

    International Nuclear Information System (INIS)

    1983-02-01

    There is a wide spectrum of safety significance in the events that can occur during nuclear power plant operations. It is important that lessons be learned from safety-related events (hereinafter referred to as unusual events) so as to improve the safety of nuclear power plants. Hence formal procedures should be established for this purpose. The purpose of this document is to provide guidance to Member States for establishing a system (hereinafter referred to as a national system) for collecting, storing, retrieving, assessing and disseminating information on unusual events in nuclear power plants. The guidance given is based on experience gained in the use of existing national and international systems. This guide covers a national system that is part of a programme to improve nuclear power plant safety using experience gained from operating plants both within and outside the country. Implementing the recommendations in this guide would render any national system compatible with other national systems and facilitate the participation in the IAEA System for Reporting Unusual Events with Safety Significance (hereinafter referred to as the IAEA Incident Reporting System, IAEA-IRS) for more widespread dissemination of lessons learned from nuclear power plant operation

  13. Overview of Activities in U.S. Related to Continued Service of Nuclear Power Plant Concrete Structures

    International Nuclear Information System (INIS)

    Naus, Dan J.

    2011-01-01

    Safety-related nuclear power plant concrete structures are described and commentary on continued service assessments of these structures is provided. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status noted. A summary of operating experience related to U.S. nuclear power plant concrete structures is presented. Several candidate areas are identified where additional research would be of benefit to aging management of NPP concrete structures. Finally current ORNL activities related to aging-management of concrete structures are outlined: development of operating experience database, application of structural reliability theory, and compilation of elevated temperature concrete material property data and information.

  14. NIMBY, CLAMP, and the location of new nuclear-related facilities: U.S. national and 11 site-specific surveys.

    Science.gov (United States)

    Greenberg, Michael R

    2009-09-01

    Public and political opposition have made finding locations for new nuclear power plants, waste management, and nuclear research and development facilities a challenge for the U.S. government and the nuclear industry. U.S. government-owned properties that already have nuclear-related activities and commercial nuclear power generating stations are logical locations. Several studies and utility applications to the Nuclear Regulatory Commission suggest that concentrating locations at major plants (CLAMP) has become an implicit siting policy. We surveyed 2,101 people who lived within 50 miles of 11 existing major nuclear sites and 600 who lived elsewhere in the United States. Thirty-four percent favored CLAMP for new nuclear power plants, 52% for waste management facilities, and 50% for new nuclear laboratories. College educated, relatively affluent male whites were the strongest CLAMP supporters. They disproportionately trusted those responsible for the facilities and were not worried about existing nuclear facilities or other local environmental issues. Notably, they were concerned about continuing coal use. Not surprisingly, CLAMP proponents tended to be familiar with their existing local nuclear site. In short, likely CLAMP sites have a large and politically powerful core group to support a CLAMP policy. The challenge to proponents of nuclear technologies will be to sustain this support and expand the base among those who clearly are less connected and receptive to new nearby sites.

  15. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

    2004-07-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  16. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    International Nuclear Information System (INIS)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

    2004-01-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  17. Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority

    International Nuclear Information System (INIS)

    1982-12-01

    Supplement No. 6 to the Safety Evaluation Report (SER) related to the operation of the Tennessee Valley Authority's Sequoyah Nuclear Plant, Units 1 and 2, located in Hamilton County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The purpose of this supplement is to update the staff's evaluations of the issues related to the hydrogen mitigation system identified in the SER and previous supplements as needing resolution

  18. Nuclear education and training related issues: Needs and lessons learned in national and international context

    International Nuclear Information System (INIS)

    Lubomir, Sklenka

    2010-01-01

    The paper is focused on nuclear education and training at research reactors and universities. Lack of experts and high educated and skilled professionals in nuclear engineering in the world caused by fast aging of the NPPs and research reactors staff and expected ''nuclear renaissance'' brings a new needs to the universities and research reactors. During the last few years some new trends in nuclear education became visible. Customers expect high quality nuclear education in wide range of knowledge and the complex services, which forces universities and research reactors to bring new challenges in the domain of education and training. State-of-the-art experimental equipment and methodologies specifically developed for the education, networking and dose cooperation between universities and research reactors at national and international levels, and sharing the experimental facilities are the trends which can be noticed today all over the world. Research reactors are suitable for education of students at all academic levels (BSc, MSc and PhD) not only in nuclear engineering, but also in various non-nuclear engineering studies (power engineering, electrical engineering, natural sciences, medical sciences, physical sciences, etc.). An effective way on how to provide the education and training at the research reactor should be started by evaluation of the initial students' background and then adaptation of the educational methodology to that level. Networking and closer co-operation between universities at national and international level in nuclear education started in late nineties in Europe and within a few years several networks were establish. The European Nuclear Education Network (ENEN) as an European regional network with more than 40 European universities was inspiration for creating national networks in Europe (e.g. Belgium, UK, Czech Republic, etc.) and Non-European regional networks (Asia, North America, etc.). Research reactors play an important role in all

  19. Aging of concrete components and its significance relative to life extension of nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.

    1987-01-01

    Nuclear power currently supplies about 16% of the US electricity requirements, with the percentage expected to rise to 20% by 1990. Despite the increasing role of nuclear power in energy production, cessation of orders for new nuclear plants in combination with expiration of operating licenses for several plants in the next 15 to 20 years results in a potential loss of electrical generating capacity of 50 to 60 gigawatts during the time period 2005 to 2020. A potential timely and cost-effective solution to the problem of meeting future energy demand is available through extension of the service life of existing nuclear plants. Any consideration of plant life extension, however, must consider the concrete components in these plants, since they play a vital safety role. Under the USNRC Nuclear Plant Aging Research (NPAR) Program, a study was conducted to review operating experience and to provide background that will lead to subsequent development of a methodology for assessing and predicting the effects of aging on the performance of concrete-based structures. The approach followed was in conformance with the NPAR strategy

  20. Proposition of law relative to the follow of sanitary and environmental consequences of nuclear tests

    International Nuclear Information System (INIS)

    2007-07-01

    The present proposition of law has for object to answer the expectation of all the persons who have participated as military personnel or civilians in nuclear tests made by France between February 13., 1960 and January 27., 1996, or lived near the nuclear test sites of Sahara (Reggane and In Eker) or in French Polynesia. The same pathologies are noticed among the veteran or the populations having lived near the nuclear tests sites of the other nuclear countries which made the same experiments. It is the case in United States, in Great Britain, in Australia, in New Zealand and in Fiji. In these different countries having a democratic system similar to ours, the governments took concrete measures to accede to the demands of their nationals. It thus turns out that a legislative initiative would represent a strong message of gratitude towards all those who had to undergo aftereffects on their health and that of their descendants of the only fact of their participation in the nuclear experiments of France. (N.C.)

  1. Proposition of law relative to the sanitary follow up of French nuclear tests

    International Nuclear Information System (INIS)

    2008-03-01

    The present proposition of law has for object to answer the expectation of all the persons who have participated as military personnel or civilians in nuclear tests made by France between February 13., 1960 and January 27., 1996, or lived near the nuclear test sites of Sahara (Reggane) or in French Polynesia. The same pathologies are noticed among the veteran or the populations having lived near the nuclear tests sites of the other nuclear countries which made the same experiments. It is the case in United States, in Great Britain, in Australia, in New Zealand and in Fidgi. In these different countries having a democratic system similar to ours, the governments took concrete measures to accede to the demands of their nationals. It thus turns out that a legislative initiative would represent a strong message of gratitude towards all those who had to undergo aftereffects on their health and that of their descendants of the only fact of their participation in the nuclear experiments of France. (N.C.)

  2. Review of nuclear new build in relation to project structure, supply chain and financing - 15106

    International Nuclear Information System (INIS)

    Keppler, J.H.; Cometto, M.

    2015-01-01

    The construction of a new nuclear power plant is a major industrial project involving a number of complex economic, technical and regulatory challenges. This article focuses on 2 of the most important among them: first, sustainable financing which is primarily a function of interest rates and the stability of electricity prices and secondly, the management of a complex construction process and its supply chain. The analysis shows the much stronger dependence of nuclear energy on the stability of electricity prices when compared with a gas plant of the same size. Nevertheless the study underlines that at debt ratios below 60%, the risk for a debt-investor in a nuclear project is rather limited even for large electricity and permanent price fall. There exist a wide spectrum of different options for sharing the responsibilities between the ultimate operators of a nuclear power plant and the principal supplier. 3 main categories of contract are used for the construction of NPPs: the turnkey approach, the split-package approach and the multi-contract approach.In construction, where the emergence of a competitive, global supply chain is not yet ensured, the convergence of nuclear engineering codes and quality standards, as well as regulatory harmonisation remain a key step to promote both competition and public confidence

  3. Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

  4. Nuclear liability: Joint protocol relating to the application of the Vienna Convention and the Paris Convention, 1988

    International Nuclear Information System (INIS)

    1989-10-01

    The Joint Protocol Relating to the Application of the Vienna Convention and the Paris Convention was adopted by the Conference on the Relationship between the Paris Convention and the Vienna Convention, which met in Vienna, at the Headquarters of the International Atomic Energy Agency on 21 September 1988. The Joint Protocol establishes a link between the Paris Convention on Third Party Liability in the Field of Nuclear Energy of 1960 and the Vienna Convention on Civil Liability for Nuclear Damage of 1963. The Joint Protocol will extend to the States adhering to it the coverage of the two Conventions. It will also resolve potential conflicts of law, which could result from the simultaneous application of the two Conventions to the same nuclear accident. The Conference on the Relationship between the Paris Convention and the Vienna Convention was jointly organized by the International Atomic Energy Agency and the OECD Nuclear Energy Agency. This publication contains the text of the Final Act of the Conference in the six authentic languages, the Joint Protocol Relating to the Application of the Vienna Convention and the Paris Convention, also in the six authentic languages and an explanatory note, prepared by the IAEA and NEA Secretariats, providing background information on the content of the Joint Protocol

  5. Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

    International Nuclear Information System (INIS)

    1995-01-01

    A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

  6. Neuropsychological Aspects Observed in a Nuclear Plant Simulator and its Relation with Human Reliability Analysis

    International Nuclear Information System (INIS)

    Prado, E.A.P. do; Martins, M.; Pinheiro, A.; Silveira, J.

    2016-01-01

    This paper will discuss preliminary results of an evaluation methodology for the analysis and quantification of errors in manual (human) operation by training cognitive parameters and skill levels in the complex control system operation using Neuropsychophysiology and Neuro feedback equipment. The research was conducted using a game (nuclear power plant simulator) that simulates concepts of operation of a nuclear plant with a split sample evaluating aspects of learning and knowledge in the nuclear area. Operators were monitored using biomarkers (ECG, EEG, GSR, face detection and eye tracking) and the results were analyzed by Statistical multivariate techniques. An important component in the evaluation of complex systems is the human reliability during operation. Human reliability refers to the probability of the human element perform the tasks scheduled during the defined period for system operation when tested under specified environmental conditions, and additionally not to take any action detrimental to system operation.

  7. National character and communication. Attitude toward nuclear power plant and its public relations

    International Nuclear Information System (INIS)

    Hayashi, Chikio; Morikawa, Shinichi.

    1994-01-01

    The attitude structure toward nuclear power plant is analyzed with the attitudes toward relevant matters, for example image for nuclear power, knowledge of nuclear power, attitudes toward energy and environment, anxiety about various matters, cognition of risk, social and political attitudes and Japanese national character. Six types are revealed, that is to say, indifference group (13%), strongly favorable group (11%), strongly unfavorable group (9%), fairly favorable group (12%), fairly unfavorable group (5%), and intermediate group (50%). Strongly favorable and unfavorable groups are similar in some points and different in other points, for they are both rational whereas the former is optimistic in the attitude toward science and technology and less interested in environmental problems, and the latter is pessimistic in the attitude toward science and technology and extremely sensitive to environmental problems. The intermediate group has so-called Japanese -like characteristics. It is shown that the emotional persuasion and that based on fact presentation are particularly desirable for this group. (author)

  8. Analysis of articles in weekly magazines on scientific issues related to Fukushima nuclear power plant accident

    International Nuclear Information System (INIS)

    Sano, Kazumi; Kikuchi, Macoto

    2012-01-01

    The large area was polluted by the radioactive fallout released after the nuclear fuel meltdown of Fukushima first nuclear plant of Tokyo electric power company. The news media that reported the accident were required to have scientific knowledge on the structure of the nuclear reactor and the physics and health issues of the radioactivity. In this paper, we focus on how the weekly magazines reported this critical accident. The weekly magazines are not regarded as a neutral news media. Rather, their articles in general strongly reflect the editorial opinions. In this sense, the weekly magazines are 'biased media'. So, there are many points to discuss from the view point of the science communication. We analyze the articles appeared in the seven major weekly magazines published during the first half year after the earthquake. We found that the differences in the scientific literacy between magazines are reflected, for example, in selection of the experts who made comments in articles. (author)

  9. Relative population exposures from coal-fired and nuclear power plants in India

    Energy Technology Data Exchange (ETDEWEB)

    Ramachandran, T.V.; Lalit, B.Y.; Mishra, U.C.

    1987-01-01

    Coal combustion for electric power generation results in dispersal of fly ash, and hence an additional radiation dose to the population living in the neighbourhood of the coal-fired power plants due to natural radioactivity present in coal. The radiation hazards of coal based and nuclear power plants operating in India are given. The dose commitments to the population living within an 88.5 km radius of the thermal and nuclear power plants in India have been computed using the method outlined in an ORNL report. The estimated dose rates for these two types of power plant were compared. The present study shows that the radiation dose from coal-fired and nuclear power plants are comparable.

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

    International Nuclear Information System (INIS)

    Mueller, A.E.F.; Gasparian, A.E.; Calvet Filho, H.J.

    1980-01-01

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

  11. Details of criminological investigations of large-valued thefts related to nuclear materials (diversion safeguards program)

    International Nuclear Information System (INIS)

    Leachman, R.B.; Cornella, A.P.

    1972-06-01

    Studies were made of five areas of criminology which have great similarity to the case of nuclear materials. Actual cases of crimes were analyzed by experts in law enforcement and criminal justice. To identify fields of analogous criminology, possible characteristics of nuclear material thefts were considered: total value, high unit cost, limited marketability, special technology for handling, and licensing. The items considered to be analogous to nuclear materials in these aspects were: narcotics, data (as exists in computer memories, tapes, or discs), precious metal and gems, objects of art, and weapons. A criminology survey was conducted in which 509 individuals received one or more questionnaires soliciting opinion responses. Sixty-five questionnaires were returned. Eighty-four individuals replied by letter indicating inadequate knowledge of the crimes being surveyed. The questionnaire was supplemented by 18 interviews with criminal justice and industry personnel for more definitive information on diversion problems. Results of this survey are reported

  12. Criteria for safety-related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1980-01-01

    In the US, an effort has been underway for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. Insufficient data are available to provide quantitative guidelines for the standard. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak National Laboratory to develop the data base. A preliminary assessment completed in April, 1979 concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A program of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That program was recently initiated. The approach, results and conclusions of the preliminary assessment are reviewed and the planned research program of simulator studies is summarised. (author)

  13. National character and communication. Attitude toward nuclear power plant and its public relations

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, Chikio [Institute of Statistical Mathematics, Tokyo (Japan); Morikawa, Shinichi

    1995-10-01

    The attitude structure toward nuclear power plant is analyzed with the attitudes toward relevant matters, for example image for nuclear power, knowledge of nuclear power, attitudes toward energy and environment, anxiety about various matters, cognition of risk, social and political attitudes and Japanese national character. Six types are revealed, that is to say, indifference group (13%), strongly favorable group (11%), strongly unfavorable group (9%), fairly favorable group (12%), fairly unfavorable group (5%), and intermediate group (50%). Strongly favorable and unfavorable groups are similar in some points and different in other points, for they are both rational whereas the former is optimistic in the attitude toward science and technology and less interested in environmental problems, and the latter is pessimistic in the attitude toward science and technology and extremely sensitive to environmental problems. The intermediate group has so-called Japanese-like characteristics. It is shown that the emotional persuasion and that based on fact presentation are particularly desirable for this group. (author)

  14. National character and communication. Attitude toward nuclear power plant and its public relations

    International Nuclear Information System (INIS)

    Hayashi, Chikio; Morikawa, Shinichi.

    1995-01-01

    The attitude structure toward nuclear power plant is analyzed with the attitudes toward relevant matters, for example image for nuclear power, knowledge of nuclear power, attitudes toward energy and environment, anxiety about various matters, cognition of risk, social and political attitudes and Japanese national character. Six types are revealed, that is to say, indifference group (13%), strongly favorable group (11%), strongly unfavorable group (9%), fairly favorable group (12%), fairly unfavorable group (5%), and intermediate group (50%). Strongly favorable and unfavorable groups are similar in some points and different in other points, for they are both rational whereas the former is optimistic in the attitude toward science and technology and less interested in environmental problems, and the latter is pessimistic in the attitude toward science and technology and extremely sensitive to environmental problems. The intermediate group has so-called Japanese-like characteristics. It is shown that the emotional persuasion and that based on fact presentation are particularly desirable for this group. (author)

  15. National character and communication. Attitude toward nuclear power plant and its public relations

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, Chikio [Institute of Statistical Mathematics, Tokyo (Japan); Morikawa, Shinichi

    1994-05-01

    The attitude structure toward nuclear power plant is analyzed with the attitudes toward relevant matters, for example image for nuclear power, knowledge of nuclear power, attitudes toward energy and environment, anxiety about various matters, cognition of risk, social and political attitudes and Japanese national character. Six types are revealed, that is to say, indifference group (13%), strongly favorable group (11%), strongly unfavorable group (9%), fairly favorable group (12%), fairly unfavorable group (5%), and intermediate group (50%). Strongly favorable and unfavorable groups are similar in some points and different in other points, for they are both rational whereas the former is optimistic in the attitude toward science and technology and less interested in environmental problems, and the latter is pessimistic in the attitude toward science and technology and extremely sensitive to environmental problems. The intermediate group has so-called Japanese -like characteristics. It is shown that the emotional persuasion and that based on fact presentation are particularly desirable for this group. (author)

  16. Health and safety impacts related to the management of spent nuclear fuels

    International Nuclear Information System (INIS)

    Jilek, D.C.

    1996-01-01

    Under the Nuclear Waste Policy Act of 1982, as amended, the U.S. Department of Energy is responsible for managing the disposal of spent nuclear fuel from civilian nuclear power plants. Deployment of a multipurpose canister (MPC) system for dry storage of commercial spent nuclear fuel at reactor sites was determined to be an option for managing spent nuclear fuel until either a permanent repository or interim central storage facility (commonly called a Monitored Retrievable Storage Facility, or MRS) becomes available. Routine health and safety impacts to workers from handling and storage operations at nuclear facilities for four separate scenarios were evaluated for the MPC system: an on-time repository with an MRS; an on-time repository with no MRS; a delayed repository with an MRS; and a delayed repository with no MRS. In addition to evaluating the MPC system, five alternatives were analyzed. These included the No Action Alternative (NAA), Current Technology (CTr), the Transposable Storage Cask (TSC), the Dual-Purpose Canister (DPC), and the Small MPC (SmMPC). Health effects are expressed as collective doses in person- rem per year and risks as latent cancer fatalities per year for incident-free operations for each alternative and scenario. Results show that both dose and risks to workers vary as much as 68% among scenarios and alternatives. Although dose estimates and risks fall below limits for radiation dose to workers as specified in Title 10, Part 20, of the Code of Federal Regulations, additional measures could be applied to reduce potential doses and resultant health risk. 5 refs., 2 tabs

  17. Nuclear safety improvement activities related to WWER-440 units in Bulgaria

    International Nuclear Information System (INIS)

    Gantchev, T.

    1998-01-01

    The systematic evaluation of the deficiencies of the original design of the WWER reactors brought to the development of a Short Term Programme for Safety Upgrading and Modernisation of Kozloduy WWER-440 units. The implementation of this Programme was completed in 1997. The strive for continuos improvement of Kozloduy Nuclear Power Plant (NPP) safety level, the new requirements of the Bulgarian Nuclear Safety Authority and the public concern initiated the development of new Complex Programme for Safety Improvement (PRG'97), now in a process of implementation. (author)

  18. Composition models for the viscosity and chemical durability of West Valley related nuclear waste glasses

    International Nuclear Information System (INIS)

    Feng, X.; Saad, E.E.; Freeborn, W.P.; Macedo, P.B.; Pegg, I.L.; Sassoon, R.E.; Barkatt, A.; Finger, S.M.

    1988-01-01

    There are two important criteria that must be satisfied by a nuclear waste glass durability and processability. The chemical composition of the glass must be such that it does not dissolve or erode appreciably faster than the decay of the radioactive materials embedded in it. The second criterion, processability, means that the glass must melt with ease, must be easily pourable, and must not crystallize appreciably. This paper summarizes the development of simple models for predicting the durability and viscosity of nuclear waste glasses from their composition

  19. Incorporating ''fuzzy'' data and logical relations in the design of expert systems for nuclear reactors

    International Nuclear Information System (INIS)

    Guth, M.A.S.

    1987-01-01

    This paper applies the method of assigning probability in Dempster-Shafer Theory (DST) to the components of rule-based expert systems used in the control of nuclear reactors. Probabilities are assigned to premises, consequences, and rules themselves. This paper considers how uncertainty can propagate through a system of Boolean equations, such as fault trees or expert systems. The probability masses assigned to primary initiating events in the expert system can be derived from observing a nuclear reactor in operation or based on engineering knowledge of the reactor parts. Use of DST mass assignments offers greater flexibility to the construction of expert systems

  20. Verification and validation of software related to nuclear power plant instrumentation and control

    International Nuclear Information System (INIS)

    1999-01-01

    This report is produced in response to a recommendation of the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation. The report has objectives of providing practical guidance on the methods available for verification of the software and validation of computer based systems, and on how and when these methods can be effectively applied. It is meant for those who are in any way involved with the development, implementation, maintenance and use of software and computer based instrumentation and control systems in nuclear power plants. The report is intended to be used by designers, software producers, reviewers, verification and validation teams, assessors, plant operators and licensers of computer based systems