WorldWideScience

Sample records for base nuclear installations

  1. Power Installations based on Activated Nuclear Reactions of Fission and Synthesis

    CERN Document Server

    Grigoriev, Yuriy

    2016-01-01

    The general scheme of power installations based on nuclear reactions of fission and synthesis activated by external sources is analyzed. The external activation makes possible to support nuclear reactions at temperatures and pressures lower than needed for chain reactions, so simplifies considerably practical realization of power installations. The possibility of operation on subcritical masses allows making installations compact and safe at emergency situations. Installations are suitable for transmutation of radioactive nuclides, what solves the problem of utilization of nuclear waste products. It is proposed and considered schemes of power installations based on nuclear reactions of fission and fusion, activated by external sources, different from ADS systems. Variants of activation of nuclear reactions of fission (U-235, 238, Pu-239) and fusion (Li-6,7, B-10,11) are considered.

  2. The Swiss nuclear installations. Annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK`s supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration, in Switzerland, of final disposal facilities for radwaste and the interim radwaste storage facilities. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants` proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1994, is judged as good by HSK. (author) 11 figs., 13 tabs.

  3. The Swiss nuclear installations. Annual report 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-08-01

    Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK`s supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration of final disposal facilities for radwaste and the interim radwaste storage facilities in Switzerland. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants` proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1993, is judged as good by HSK. (author) 10 figs., 11 tabs.

  4. Nondestructive Evaluation of Functionally Graded Subsurface Damage on Cylinders in Nuclear Installations Based on Circumferential SH Waves

    Directory of Open Access Journals (Sweden)

    Zhen Qu

    2016-01-01

    Full Text Available Subsurface damage could affect the service life of structures. In nuclear engineering, nondestructive evaluation and detection of the evaluation of the subsurface damage region are of great importance to ensure the safety of nuclear installations. In this paper, we propose the use of circumferential horizontal shear (SH waves to detect mechanical properties of subsurface regions of damage on cylindrical structures. The regions of surface damage are considered to be functionally graded material (FGM and the cylinder is considered to be a layered structure. The Bessel functions and the power series technique are employed to solve the governing equations. By analyzing the SH waves in the 12Cr-ODS ferritic steel cylinder, which is frequently applied in the nuclear installations, we discuss the relationship between the phase velocities of SH waves in the cylinder with subsurface layers of damage and the mechanical properties of the subsurface damaged regions. The results show that the subsurface damage could lead to decrease of the SH waves’ phase velocity. The gradient parameters, which represent the degree of subsurface damage, can be evaluated by the variation of the SH waves’ phase velocity. Research results of this study can provide theoretical guidance in nondestructive evaluation for use in the analysis of the reliability and durability of nuclear installations.

  5. Development of a quality management system for Brazilian nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade]. E-mail: edkibrit@yahoo.com.br; Zouain, Desiree Moraes [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Div. de Planejamento e Inovacao Tecnologica]. E-mail: dmzouain@ipen.br

    2005-07-01

    The present work is a proposal for developing a quality management system for Brazilian nuclear installations, based on applicable standards. The standard ISO 9001:2000 [4] establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard IAEA 50-C/SG-Q [1] establishes general requirements for the implementation of a quality assurance system in nuclear installations. The standard CNEN-NN- 1.16 [5] establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The revision of standard IAEA 50-C/SG-Q [1], to be replaced by IAEA DS 338 [2] and IAEA DPP 349 [3], introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concept of 'Quality Assurance'. This approach is incorporated with the current tendency, because it guides the system to manage, in an integrated way, the requirements of quality, safety, health, environment, security and economics of the installation. The results of the characterization of the quality management systems established in the applicable standards are presented, with the determination of the common and conflicting points among them. Referring data to quality assurance program/quality management system in some nuclear installations of IAEA Member States are also presented. (author)

  6. Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

    Directory of Open Access Journals (Sweden)

    Wang Qiu-kuan

    2012-01-01

    Full Text Available The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation methods for nuclear installations and the applications of these instruments and methods.

  7. Radiation protection in Swiss nuclear installations; Strahlenschutz in Schweizer Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Hammer, J.; Brunell, M. [Eidgenoessisches Nuklearsicherheitsinspektorat ENSI, Brugg (Switzerland)

    2015-07-01

    Well developed measures on operational radiation protection within Swiss nuclear installations will be presented. The focus lays on competent authority actions. Results of the last ten years, including events on radiation issues, will be discussed. Finally a view on challenges for radiation protection personnel with respect to a renewed Swiss radiation protection legislation based on recent ICRP recommendations will be given.

  8. Reliability of sprinkler systems. Exploration and analysis of data from nuclear and non-nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Roenty, V.; Keski-Rahkonen, O.; Hassinen, J.P. [VTT Building and Transport, Espoo (Finland)

    2004-12-01

    Sprinkler systems are an important part of fire safety of nuclear installations. As a part of effort to make fire-PSA of our utilities more quantitative a literature survey from open sources worldwide of available reliability data on sprinkler systems was carried out. Since the result of the survey was rather poor quantitatively, it was decided to mine available original Finnish nuclear and non-nuclear data, since nuclear power plants present a rather small device population. Sprinklers are becoming a key element for the fire safety in modern, open non-nuclear buildings. Therefore, the study included both nuclear power plants and non-nuclear buildings protected by sprinkler installations. Data needed for estimating of reliability of sprinkler systems were collected from available sources in Finnish nuclear and non-nuclear installations. Population sizes on sprinkler system installations and components therein as well as covered floor areas were counted individually from Finnish nuclear power plants. From non-nuclear installations corresponding data were estimated by counting relevant things from drawings of 102 buildings, and plotting from that sample needed probability distributions. The total populations of sprinkler systems and components were compiled based on available direct data and these distributions. From nuclear power plants electronic maintenance reports were obtained, observed failures and other reliability relevant data were selected, classified according to failure severity, and stored on spreadsheets for further analysis. A short summary of failures was made, which was hampered by a small sample size. From non-nuclear buildings inspection statistics from years 1985.1997 were surveyed, and observed failures were classified and stored on spreadsheets. Finally, a reliability model is proposed based on earlier formal work, and failure frequencies obtained by preliminary data analysis of this work. For a model utilising available information in the non-nuclear

  9. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  10. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

  11. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-15

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  12. Managing radioactive waste produced at secret basic nuclear facilities; La gestion des dechets radioactifs issus des installations nucleaires de base secretes

    Energy Technology Data Exchange (ETDEWEB)

    Elluard, M.P. [Chef de projet a l' Autorite de Surete Nucleaire de Defense - Ministere de la Defense, 75 - Paris (France)

    2011-02-15

    The Delegate for Nuclear Safety and Radiation Protection for National Defence Installations and Activities (DSND) is attached to the French Minister of Defence and the Minister for Industry. The DSND's task is to study and propose to the relevant ministers the specific nuclear safety and radiation protection policy applicable to secret basic nuclear installations (SBNI) classified as such by decision of the Prime Minister. He supervises application of this policy. The DSND draws up the regulations relative to managing waste present within the boundaries of SBNIs in accordance with the guidelines set out in the Environmental Code. Thus, the Title VI of the Order of 26 September 2007 setting out the general technical regulations designed to prevent and limit pollution and external risks resulting from the operation of secret basic nuclear installations recalls the requirement for all SBNI operators to take every precaution necessary to reduce the volume and the radiological, chemical and biological toxicity of all waste produced at its installations and to optimise its management, whilst giving priority to recycling and processing rather than final disposal, which is to be reserved for final waste. The DSND supervises and monitors safety at every stage in radioactive waste management: production, processing, storage, transportation and disposal. (author)

  13. Report on nuclear installations safety and security control. Rapport sur le controle de la surete et de la securite des installations nucleaires. Surete des installations. Securite et information

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C.; Serusclat, F.

    1990-01-01

    This report of the parliamentary office for evaluation of scientific and technological choices bearing on the safety and security of nuclear installations is divided into 2 volumes bearing on: - Volume I: nuclear installations safety. - nuclear safety and international organizations. - works separation: Finland, Belgium and Federal Republic of Germany. - French organization. - Volume II: security and information. - French nuclear security. - Public information.

  14. Determination of the standards of the thermo-physiological tolerance for working in basic nuclear installation in TIVA protective clothing; Determination des normes de tolerance thermophysiologique pour le travail en installation nucleaire de base en tenue TIVA

    Energy Technology Data Exchange (ETDEWEB)

    Casanova, P.; Daret, J.L. [AREVA NC- etablissement de La Hague, service de sante au travail, 50444 Beaumont-Hague Cedex (France); Besnard, Y.; Clerc, N.; Savourey, G.; Launay, J.C. [IRBA, Antenne La Tronche CRSSA, 24 avenue du marquis de Gresivaudan, BP 87, 38702 La Tronche Cedex (France)

    2011-04-15

    The purpose of this study was to determine the duration limited exposure (DLE) for working in a contaminated zone in a basic nuclear installation using the new ventilated TIVA protective clothing. Five subjects underwent a treadmill exercise (3.5 km/h, 3% of slope) of up to 2 h in a climatic chamber at 25, 35, and 45 deg. C. Cardiac frequency, rectal temperature and skin temperature were continuously recorded. The dehydration level was measured by the loss of weight during the exercise. At 25 deg. C, thermal and cardiovascular thresholds are not reached; the risk is dehydration if the exercise is prolonged. In contrast, the thresholds for Tre at 39 deg. C (97 {+-} 29 and 69 {+-} 28 min for 35 and 45 deg. C, respectively) and for the increase in Tre (+1.5 deg. C) are reached earlier (84 {+-} 38 min and 57 {+-} 21 min at 35 and 45 deg. C, respectively). This leads to a higher heat storage (42.2 {+-} 22.9 W/m{sup 2} and 63.7 {+-} 29.4 W/m{sup 2}, at 35 and 45 deg. C, respectively), which constitutes a higher risk of heat illnesses. The dehydration level is 2% of the weight for the tests at 35 and 45 deg. C. As a consequence, DLE for working in a contaminated zone in a basic nuclear installation in environmental conditions and using the new ventilated TIVA protective clothing, as encountered in our experiments, are proposed to avoid hyperthermic accidents. (authors)

  15. Financing of Liabilities Beyond the Service Life of Nuclear Installations

    Directory of Open Access Journals (Sweden)

    L. Havlíček

    2006-01-01

    Full Text Available Operation of a nuclear installation is connected with the creation of long-term liabilities for spent fuel management and disposal, and also decommissioning of the installation (power plant, storages. This means that the operator will have to expend considerable amount of financial resources over a long period after the closure of installation. These financial resources will have to be created during operation of the installation. Related costs to be expended in future must be fully included in the price of electricity, in order to ensure fair competition among different operators. Financial resources for future coverage of liabilities must be continuously invested in order to compensate for inflation and to gain some real interest.Any failure by the operator to comply with its liabilities poses an economic and potentially an environmental hazard for operator’s country. Due attention must therefore be paid to assessing connected costs, defining liabilities and ensuring appropriate regulatory oversight. Appropriate measures must be well defined and firmly anchored in the legislation of countries operating nuclear installations. This paper reviews the basic principles that should ensure operator’s compliance their liabilities, and maps the current situation in the Czech Republic. 

  16. Public participation processes related to nuclear research installations: what are the driving factors behind participation intention?

    Science.gov (United States)

    Turcanu, Catrinel; Perko, Tanja; Laes, Erik

    2014-04-01

    This article addresses organised public participation processes related to installations for nuclear research. The aim was to determine predictors that could provide an empirical insight into the motivations underlying people's intended level of involvement. The results highlight attitude towards participation and moral norm as the strongest predictors for participation intention. Other significant predictors were time constraints, attitude towards nuclear energy, subjective and descriptive norms, and knowledge. An opposing relationship is noted between participation intention and attitude towards nuclear energy. At the same time, people who are more knowledgeable about the nuclear domain seem more willing to get involved. The analysis also revealed that financial benefits do not influence people's intended involvement in participation processes related to nuclear research installations. The results reported here are based on empirical data from a large-scale public opinion survey (N = 1020) carried out in Belgium during May-June 2011.

  17. Evaluation guideline for the study of the radiological impact of based nuclear installations (INB) presented in support of releases authorization demands; Guide d'examen pour l'etude de l'impact radiologique d'une installation nucleaire de base (INB) fournie a l'appui des demandes d'autorisation de rejets

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, M.; Despres, A.; Supervil, S.; Conte, D.; Hubert, P.; Oudiz, A.; Champion, D

    2002-10-01

    In the case of a license demand for the effluents release and water taking for a nuclear installation, the operating must realize a study of the nuclear effluents radiological impact on the environment and the public health. In this context, the study presents technical and methodological specifications which led the Direction of the Nuclear Installations Safety (DSIN) and the General Direction of the Health (DGS) to ask the IPSN the elaboration of a guideline to help these studies evaluation. The guideline presents the regulatory context, the description of the installations, the treatment and the control processes, the rules of management, the description of the environment, the estimation of the radiological impacts and the environment control system definition. (A.L.B.)

  18. Dismantling of nuclear facilities; Demantelement des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Tallec, M. [CEA Marcoule, Dept. des Projets d' Assainissement-Demantelement, 30 (France); Kus, J.P. [Electricite de Fance (EDF/CIDEN), 69 - Villeurbanne (France)

    2009-01-15

    Nuclear facilities have a long estimable lifetime but necessarily limited in time. At the end of their operation period, basic nuclear installations are the object of cleansing operations and transformations that will lead to their definitive decommissioning and then to their dismantling. Because each facility is somewhere unique, cleansing and dismantling require specific techniques. The dismantlement consists in the disassembly and disposing off of big equipments, in the elimination of radioactivity in all rooms of the facility, in the demolition of buildings and eventually in the reconversion of all or part of the facility. This article describes these different steps: 1 - dismantling strategy: main de-construction guidelines, expected final state; 2 - industries and sites: cleansing and dismantling at the CEA, EDF's sites under de-construction; 3 - de-construction: main steps, definitive shutdown, preparation of dismantling, electromechanical dismantling, cleansing/decommissioning, demolition, dismantling taken into account at the design stage, management of polluted soils; 4 - waste management: dismantlement wastes, national policy of radioactive waste management, management of dismantlement wastes; 5 - mastery of risks: risk analysis, conformability of risk management with reference documents, main risks encountered at de-construction works; 6 - regulatory procedures; 7 - international overview; 8 - conclusion. (J.S.)

  19. Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico; Establecimiento del marco regulador nuclear para el proceso de cierre de instalaciones nucleares en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2015-09-15

    Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

  20. Fessenheim INB 75 basic nuclear facilities. 2009 annual report; Installations nucleaires de base (INB) de Fessenheim INB 75. Rapport annuel 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the basic nuclear facilities of Fessenheim INB 75, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

  1. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes; Prise en compte du risque sismique a la conception des ouvrages de genie civil d'installations nucleaires de base a l'exception des stockages a long terme des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

  2. 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....

  3. MODELING ATMOSPHERIC RELEASES OF TRITIUM FROM NUCLEAR INSTALLATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Okula, K

    2007-01-17

    Tritium source term analysis and the subsequent dispersion and consequence analyses supporting the safety documentation of Department of Energy nuclear facilities are especially sensitive to the applied software analysis methodology, input data and user assumptions. Three sequential areas in tritium accident analysis are examined in this study to illustrate where the analyst should exercise caution. Included are: (1) the development of a tritium oxide source term; (2) use of a full tritium dispersion model based on site-specific information to determine an appropriate deposition scaling factor for use in more simplified, broader modeling, and (3) derivation of a special tritium compound (STC) dose conversion factor for consequence analysis, consistent with the nature of the originating source material. It is recommended that unless supporting, defensible evidence is available to the contrary, the tritium release analyses should assume tritium oxide as the species released (or chemically transformed under accident's environment). Important exceptions include STC situations and laboratory-scale releases of hydrogen gas. In the modeling of the environmental transport, a full phenomenology model suggests that a deposition velocity of 0.5 cm/s is an appropriate value for environmental features of the Savannah River Site. This value is bounding for certain situations but non-conservative compared to the full model in others. Care should be exercised in choosing other factors such as the exposure time and the resuspension factor.

  4. From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World's First nuclear power plant

    Science.gov (United States)

    Rachkov, V. I.; Kalyakin, S. G.; Kukharchuk, O. F.; Orlov, Yu. I.; Sorokin, A. P.

    2014-05-01

    Successful commissioning in the 1954 of the World's First nuclear power plant constructed at the Institute for Physics and Power Engineering (IPPE) in Obninsk signaled a turn from military programs to peaceful utilization of atomic energy. Up to the decommissioning of this plant, the AM reactor served as one of the main reactor bases on which neutron-physical investigations and investigations in solid state physics were carried out, fuel rods and electricity generating channels were tested, and isotope products were bred. The plant served as a center for training Soviet and foreign specialists on nuclear power plants, the personnel of the Lenin nuclear-powered icebreaker, and others. The IPPE development history is linked with the names of I.V. Kurchatov, A.I. Leipunskii, D.I. Blokhintsev, A.P. Aleksandrov, and E.P. Slavskii. More than 120 projects of various nuclear power installations were developed under the scientific leadership of the IPPE for submarine, terrestrial, and space applications, including two water-cooled power units at the Beloyarsk NPP in Ural, the Bilibino nuclear cogeneration station in Chukotka, crawler-mounted transportable TES-3 power station, the BN-350 reactor in Kazakhstan, and the BN-600 power unit at the Beloyarsk NPP. Owing to efforts taken on implementing the program for developing fast-neutron reactors, Russia occupied leading positions around the world in this field. All this time, IPPE specialists worked on elaborating the principles of energy supertechnologies of the 21st century. New large experimental installations have been put in operation, including the nuclear-laser setup B, the EGP-15 accelerator, the large physical setup BFS, the high-pressure setup SVD-2; scientific, engineering, and technological schools have been established in the field of high- and intermediate-energy nuclear physics, electrostatic accelerators of multicharge ions, plasma processes in thermionic converters and nuclear-pumped lasers, physics of compact

  5. Fatigue damage of nuclear facilities; Endommagement par fatigue des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

  6. Designing Software-Based Interactive Installations

    DEFF Research Database (Denmark)

    Andreasen, Troels; Juul, Niels Christian; Rosendahl, Mads

    2014-01-01

    What. This chapter focuses on software engineering principles with specific emphasis on interactive installations providing embodied, tangible, and immersive experiences for the user. Such installations may deliver light, image, sound, and movement through actuators and may provide interaction...... installations and support the description of the approach with a single case- a bumper car competition. Why. To some extent, standard techniques for software development can be adapted for interactive installations. However, there is a need to emphasize the unique aspects of installations, bringing tangible...... architecture as well as esthetic experience, artistic expression, and leisure aspects into focus. The approach presented here has this intended purpose. Where. Building on experience from conventional software development and with inspiration from interaction design and creative programming, this chapter...

  7. The Optimization of Radioactive Waste Management in the Nuclear Installation Decommissioning Process

    Energy Technology Data Exchange (ETDEWEB)

    Zachar, Matej; Necas, Vladimir [Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Ilkovicova 3, 812 19 Bratislava (Slovakia)

    2008-07-01

    The paper presents a basic characterization of nuclear installation decommissioning process especially in the term of radioactive materials management. A large amount of solid materials and secondary waste created after implementation of decommissioning activities have to be managed considering their physical, chemical, toxic and radiological characteristics. Radioactive materials should be, after fulfilling all the conditions defined by the authorities, released to the environment for the further use. Non-releasable materials are considered to be a radioactive waste. Their management includes various procedures starting with pre-treatment activities, continuing with storage, treatment and conditioning procedures. Finally, they are disposed in the near surface or deep geological repositories. Considering the advantages and disadvantages of all possible ways of releasing the material from nuclear installation area, optimization of the material management process should be done. Emphasis is placed on the radiological parameters of materials, availability of waste management technologies, waste repositories and on the radiological limits and conditions for materials release or waste disposal. Appropriate optimization of material flow should lead to the significant savings of money, disposal capacities or raw material resources. Using a suitable calculation code e.g. OMEGA, the evaluation of the various material management scenarios and selection of the best one, based on the multi-criterion analysis, should be done. (authors)

  8. The Contribution of Paleoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

    Science.gov (United States)

    Decker, Kurt; Guerrieri, Luca; Fukushima, Yoshimitsu

    2015-04-01

    In the framework of site evaluation/re-evaluation procedures for nuclear power plants (NPP), paleoseismology plays an essential role not only for Fault Displacement Hazard Assessment (FDHA) but also for Seismic Hazard Assessment (SHA). The relevance of paleoseismology is recommended in the reference IAEA Safety Guide (IAEA SSG-9) and has been dramatically confirmed in recent time especially after the accident at the Fukushima Daiichi NPP caused by the disastrous great Tohoku earthquake and tsunami occurred on 11 March 2011. After this event, the IAEA International Seismic Safety Center promoted a technical document aimed at encouraging and supporting Member States, especially from newcomer countries, to include paleoseismic investigations into the geologic database, highlighting the value of earthquake geology studies and paleoseismology for nuclear safety and providing standard methodologies to perform such investigations. In detail, paleoseismic investigations in the context of site evaluation of nuclear installations have the following main objectives: i) identification of seismogenic structures based on the recognition of effects of past earthquakes in the regional area; ii) improvement of the completeness of earthquake catalogs, through the identification and dating of ancient moderate to large earthquakes, whose trace has been preserved in the geologic records; iii) estimation of the maximum seismic potential associated with an identified seismogenic structure/source, typically on the basis of the amount of displacement per event (evaluable in paleoseismic trenches), as well as of the geomorphic and stratigraphic features interpretable as the cumulative effect of repeated large seismic events (concept of "seismic landscape"); iv) rough calibration of probabilistic seismic hazard assessment (PSHA), by using the recurrence interval of large earthquakes detectable by paleoseismic investigations, and providing a "reality check" based on direct observations of

  9. Thermal-hydraulic tests of a recirculation cooling installation for the Rostov nuclear power station

    Science.gov (United States)

    Balunov, B. F.; Balashov, V. A.; Il'in, V. A.; Krayushnikov, V. V.; Lychakov, V. D.; Meshalkin, V. V.; Ustinov, A. N.; Shcheglov, A. A.

    2013-09-01

    Results obtained from thermal-hydraulic tests of the recirculation cooling installation used as part of the air cooling system under the containments of the Rostov nuclear power station Units 3 and 4 are presented. The operating modes of the installation during normal operation (air cooling on the surface of finned tubes), under the conditions of anticipated operational occurrences (air cooling and steam condensation from a steam-air mixture), and during an accident (condensation of pure steam) are considered. Agreement is obtained between the results of tests and calculations carried out according to the recommendations given in the relevant regulatory documents. A procedure of carrying out thermal calculation for the case of steam condensation from a steam-air mixture on the surface of fins is proposed. The possibility of efficient use of the recirculation cooling installation in the system for reducing emergency pressure under the containment of a nuclear power station is demonstrated.

  10. Post-installed concrete anchors in nuclear power plants: Performance and qualification

    Energy Technology Data Exchange (ETDEWEB)

    Mahrenholtz, Philipp, E-mail: philipp@mahrenholtz.net; Eligehausen, Rolf

    2015-06-15

    Graphical abstract: - Highlights: • Review of qualification and design regulations for anchors in nuclear power plants. • First complete set of nuclear anchor load–displacement data and its evaluation ever. • Demonstration of robust test behavior of a qualified post-installed anchor product. - Abstract: In nuclear power plants (NPPs), post-installed anchors are widely used for structural and non-structural connections to concrete. In many countries, anchor products employed for safety relevant applications have to be approved by the authorities. For the high safety standards in force for NPPs, special requirements have to be met to allow for extreme design situations. This paper presents an experimental test program conducted to evaluate the performance of anchors according to the German Guideline for Anchorages in Nuclear Power Plants and Nuclear Technology Installations (DIBt KKW Leitfaden, 2010). After a brief introduction to anchor behavior and the regulative context, the results of tension and shear tests carried out on undercut anchors are discussed. Robust load capacities and relatively small displacements determined for demanding load and crack cycling tests demonstrated the suitability of anchors qualified according to a state-of-the-art qualification guideline.

  11. Inventory of chemical releases of nuclear installations in the North-Cotentin; Inventaire des rejets chimiques des installations nucleaires du Nord-Cotentin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-15

    The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

  12. Installation of Ohio's First Electrolysis-Based Hydrogen Fueling Station

    Science.gov (United States)

    Scheidegger, Brianne T.; Lively, Michael L.

    2012-01-01

    This paper describes progress made towards the installation of a hydrogen fueling station in Northeast Ohio. In collaboration with several entities in the Northeast Ohio area, the NASA Glenn Research Center is installing a hydrogen fueling station that uses electrolysis to generate hydrogen on-site. The installation of this station is scheduled for the spring of 2012 at the Greater Cleveland Regional Transit Authority s Hayden bus garage in East Cleveland. This will be the first electrolysis-based hydrogen fueling station in Ohio.

  13. Childhood leukaemia risks: from unexplained findings near nuclear installations to recommendations for future research.

    Science.gov (United States)

    Laurier, D; Grosche, B; Auvinen, A; Clavel, J; Cobaleda, C; Dehos, A; Hornhardt, S; Jacob, S; Kaatsch, P; Kosti, O; Kuehni, C; Lightfoot, T; Spycher, B; Van Nieuwenhuyse, A; Wakeford, R; Ziegelberger, G

    2014-09-01

    Recent findings related to childhood leukaemia incidence near nuclear installations have raised questions which can be answered neither by current knowledge on radiation risk nor by other established risk factors. In 2012, a workshop was organised on this topic with two objectives: (a) review of results and discussion of methodological limitations of studies near nuclear installations; (b) identification of directions for future research into the causes and pathogenesis of childhood leukaemia. The workshop gathered 42 participants from different disciplines, extending widely outside of the radiation protection field. Regarding the proximity of nuclear installations, the need for continuous surveillance of childhood leukaemia incidence was highlighted, including a better characterisation of the local population. The creation of collaborative working groups was recommended for consistency in methodologies and the possibility of combining data for future analyses. Regarding the causes of childhood leukaemia, major fields of research were discussed (environmental risk factors, genetics, infections, immunity, stem cells, experimental research). The need for multidisciplinary collaboration in developing research activities was underlined, including the prevalence of potential predisposition markers and investigating further the infectious aetiology hypothesis. Animal studies and genetic/epigenetic approaches appear of great interest. Routes for future research were pointed out.

  14. Decree n. 2007-534 of the 4. april 2007 allowing the creation of the base nuclear installation named Flamanville 3, including a EPR type reactor, on the site of Flamanville (Manche); Decret no 2007-534 du 10 avril 2007 autorisant la creation de l'installation nucleaire de base denommee Flamanville 3, comportant un reacteur nucleaire de type EPR, sur le site de Flamanville (Manche)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

    This decree gives the authorization to EDF to create on the site of Flamanville a nuclear installation including a PWR type reactor for a power of 4500 MW and devoted to the electric production. This reactor will can use uranium oxide or a mixture of uranium oxide and plutonium oxide. Considerations concerning the safety are given, as well as the control of the impact of this exploitation on the populations and the environment. (N.C.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-12

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

  16. Safety of nuclear installations. An international comparison; Sicherung kerntechnischer Anlagen. Ein internationaler Vergleich

    Energy Technology Data Exchange (ETDEWEB)

    Renner, Andrea; Diwes, Andreas; Reingardt, Martin [Westinghouse Electric Germany GmbH (Germany)

    2010-05-15

    Safeguarding of nuclear power plants against disruptive actions or other external hazards is part of the plant design and presumption of an operation license. The general principle is defense in depth involving different security zones with separate barriers. The safeguards for nuclear installations are organized in three areas of responsibility: governmental measures (police, military), technical (detectors, scanners, illuminations, camera tracking, concrete barriers) and personnel measures (access control, security personnel, alarm) of the operating company. International responsibilities results from the treaty on the non-proliferation of nuclear weapons and several IAEA documents. The authors discuss the national regulations in Germany, Switzerland, United Kingdom and USA. Older NPPs that are not in compliance with actual safety standards will be a topic of increasing importance.

  17. The high-temperature sodium coolant technology in nuclear power installations for hydrogen power engineering

    Science.gov (United States)

    Kozlov, F. A.; Sorokin, A. P.; Alekseev, V. V.; Konovalov, M. A.

    2014-05-01

    In the case of using high-temperature sodium-cooled nuclear power installations for obtaining hydrogen and for other innovative applications (gasification and fluidization of coal, deep petroleum refining, conversion of biomass into liquid fuel, in the chemical industry, metallurgy, food industry, etc.), the sources of hydrogen that enters from the reactor plant tertiary coolant circuit into its secondary coolant circuit have intensity two or three orders of magnitude higher than that of hydrogen sources at a nuclear power plant (NPP) equipped with a BN-600 reactor. Fundamentally new process solutions are proposed for such conditions. The main prerequisite for implementing them is that the hydrogen concentration in sodium coolant is a factor of 100-1000 higher than it is in modern NPPs taken in combination with removal of hydrogen from sodium by subjecting it to vacuum through membranes made of vanadium or niobium. Numerical investigations carried out using a diffusion model showed that, by varying such parameters as fuel rod cladding material, its thickness, and time of operation in developing the fuel rods for high-temperature nuclear power installations (HT NPIs) it is possible to exclude ingress of cesium into sodium through the sealed fuel rod cladding. However, if the fuel rod cladding loses its tightness, operation of the HT NPI with cesium in the sodium will be unavoidable. Under such conditions, measures must be taken for deeply purifying sodium from cesium in order to minimize the diffusion of cesium into the structural materials.

  18. Virtual dosimetry applied to the physical security of a nuclear installation

    Energy Technology Data Exchange (ETDEWEB)

    Santo, Andre Cotelli do E.; Mol, Antonio C.A.; Machado, Daniel M.; Chelles, Daniel R.; Goncalves, Deise G.S., E-mail: cotelli.andre@gmail.com, E-mail: mol@ien.gov.br, E-mail: machado.mol@gmail.com, E-mail: daniel.chelles@gmail.com, E-mail: deise.galvao@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    An important activity to be held in radiation protection is the location of radioactive sources. The present work was devoted to the development of a virtual dosimetry tool for locating and detecting such sources. To this end, was created a three-dimensional virtual model of the Instituto de Engenharia Nuclear - IEN, endowed with virtual characters (avatars), capable of move and interact with the environment, radiation detectors (fixed and mobile) and radioactive sources. Aiming to assist in planning physical security of nuclear installations, the tool developed allows the detection simulation of individuals carrying radioactive sources through detectors installed at strategic points of the site. In addition, it is possible to detect and locate sources by handling portable detectors, operated by characters within the virtual environment. The results obtained show the behavior of the radiation detectors on continuous profile of radioactive sources, allowing calculate the dose rate at any position of the virtual environment. Thus, this work can assist in the training of security officers, as well as in evaluating the radiological safety of the nuclear site. (author)

  19. Contributions by emissions from nuclear installations to concentrations of radionuclides in milk

    CERN Document Server

    Green, N

    1983-01-01

    A year-long study has been carried out to determine whether milk produced near nuclear sites contains concentrations of radionuclides that can be attributed to discharges from the installations, and, as a consequence, whether there is enhanced exposure of those members of the public who consume this milk. Eight creameries were chosen and monthly samples of milk were taken for analysis. The concentrations of caesium-137 and strontium-90 were measured and compared with results from a national survey conducted as part of the Board's environmental radioactivity surveillance programme. No effect attributable to discharges from the nuclear establishments was identified. The activity concentrations ranged between 0.1 and 3 times the national average; the variation relates mainly to rainfall in the area, although other factors may also have an effect. However, milk contributes only a small fraction of the total dietary intake of caesium-137 and strontium-90, and so the exposure of persons consuming the milk varies on...

  20. Radionuclide monitoring in molluscs inhabiting intertidal region near a nuclear installation, Gulf of Mannar, India.

    Science.gov (United States)

    Khan, M Feroz; Wesley, S Godwin

    2012-02-01

    Protection of non-human biota from ionizing contaminants, especially in the vicinity of nuclear installations is a very important aspect for nuclear engineers and ecologists. In this view, a baseline data on the activity concentration of (210)Po and (210)Pb were quantified in different tissues of molluscs inhabiting the intertidal region along the coast of Kudankulam. The activity concentration was noticed higher in the organs associated with digestion and metabolism. Filter feeding bivalve molluscs registered the maximum activity of (210)Po in their whole body compared to grazing gastropods. (210)Po:(210)Pb ratio was calculated to be greater than unity in most of the analysed tissues. The ecological sensitivity of molluscs to the radiation exposure and the safeness of the environment was analysed by calculating the external and internal dose rate. The hazard quotient for molluscs was lesser than the global bench mark dose rate of 10 μGyh(-1).

  1. Electrical Installation and Maintenance: A Competency-Based Curriculum Manual.

    Science.gov (United States)

    Ball, Peggy, Ed.; And Others

    Described is a competency-based community college curriculum for programs in electrical installation and maintenance. The initial curriculum development project involved identifying career opportunities, determining the skills (tasks) required for each job, and analyzing each task for necessary competencies and performance criteria. Project…

  2. Third party liability of nuclear installation decommissioning with Russian nuclear submarines as an example: insurance versus technologies

    Energy Technology Data Exchange (ETDEWEB)

    Gavrilov, S.D. [PREKSAT Ltd., Moscow (Russian Federation); Derevyankin, A.A. [Reseaarch and Development Institute of Nuclear Power Engineering, Moscow (Russian Federation); Khamyanov, L.P. [All-Russian Research Institute on NPP Operation, Moscow (Russian Federation); Kovalenko, V.N. [Ministry for Nuclear Energy Of Russian, Moscow (Russian Federation); Kovalivich, O.M. [Research and Technological Center for Nuclear and Radiation Safety of Supervisory, Nuclear Energy State Commitee of Russia, Moscow (Russian Federation); Smirnov, P.L. [Nuclear Safety Institute of Russian Academy of Sciences, Moscow (Russian Federation)

    2001-07-01

    Third party and environment of civil liability damage caused by incidents at military nuclear installations, for instance at decommissioned NPS (nuclear powered submarines), may be divided into three main trends: -) Liability of NPS without high-enriched irradiated nuclear fuel (SNF) for its self-submersion (radiation incident); -) Liability of NPS with SNF aboard for its self-submersion (radiation incident); and -) Liability of floating NPS for its SNF discharge (nuclear accident). Without step-by-step transition from the Russian Federation guaranties to insurance and making allowance for liability limits according to the Vienna Convention approach, the sizes of the financial guarantee for the civil liability of the NPS owner (Russian state), in US dollars of 2000, are approximately assessed as the following: -) storing decommissioned NPS or a floating module without SNF - from 12 to 25 thousand dollars per year (per one submarine or module); -) storing decommissioned NPS with SNF inside reactors cores - from 25 to 40 thousand dollars per year; -) assembly-by-assembly removing SNF from reactors' core of decommissioned NPS - up to 1.5 million dollars for undamaged reactor per the discharging period; -) SNF removing within reactor using the filled in-space reactor's core by liquid-phased hardened or dispersed solid-phase materials from decommissioned NPS - from 30 to 50 thousand dollars for undamaged reactor per the discharging period. Both rates and sums for NPS with damaged reactors are to be estimated for the each damaged reactor and NPS at all. It is necessary to perform the measures reducing the risk of nuclear accidents of NPS with undamaged SNF and NPS with damaged reactors in possibly short time. It will allow not only to cut risks by ten times and more, but also to accumulate necessary insurance reserves faster. These measures can be partially or completely executed using the preventing measures reserves assigned to all decommissioned Russian NPS

  3. Guide relative to the modalities of statements and to the codification of criteria relative to the significant events involving the safety, the radiation protection or the environment applicable to the base nuclear installations and to the transport of radioactive matters; Guide relatif aux modalites de declaration et a la codification des criteres relatifs aux evenements significatifs impliquant la surete, la radioprotection ou l'environnement applicable aux installations nucleaires de base et au transport de matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    It is necessary to analyze the events detected on an installation in order to be sure that an already occurred event does not be repeated, by taking into account the appropriate remedial measures, to avoid a worsen situation could occur by analyzing the potential consequences of precursory events of more serious ones, to promote the correct practices to improve the safety. The present guide has for vocation to define the arrangements enforceable to nuclear operators about the statements modalities of such events when these ones concern the safety of nuclear facilities, transport of radioactive matters, radiation protection or environmental protection. In any case it can substitute to the specific obligations coming from the work code, public health code and environment code, licensing decrees about releases. (N.C.)

  4. Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2008 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-04-15

    This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by the Inspectorate in 2008. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions, personnel and provides an assessment of operations from the safety point of view. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management, earthquake damage analysis and agreements on nuclear safety. The underground disposal of highly-radioactive nuclear wastes and work done in the rock laboratories are discussed, as are proposals for additional nuclear power stations.

  5. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Saleh, Lydia Ilaiza, E-mail: lydiailaiza@gmail.com; Ryong, Kim Tae [KEPCO International Nuclear Graduate School (KINGS) 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 689-882 (Korea, Republic of)

    2015-04-29

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  6. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    Science.gov (United States)

    Saleh, Lydia Ilaiza; Ryong, Kim Tae

    2015-04-01

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  7. Regulatory oversight report 2012 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2012 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) assesses and monitors nuclear facilities in Switzerland. These include the five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) and the nuclear facilities at the Paul Scherrer Institute (PSI), at the Federal Institute of Technology in Lausanne (EPFL) and at the University of Basel. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety in the relevant facilities. It ensures that the facilities comply with the regulations and operate as required by law. Its regulatory responsibilities also include the transport of radioactive materials from and to nuclear facilities and the preparations for a deep geological repository for nuclear waste. ENSI maintains its own emergency organisation. It formulates and updates its own guidelines which stipulate the criteria for evaluating the current activities and future plans of the operators of nuclear facilities. ENSI produces regular reports on its regulatory activities and nuclear safety in Swiss nuclear facilities. It fulfils its statutory obligation to provide the public with information on particular events and findings in nuclear facilities. In 2012, the five nuclear power plants in Switzerland were all operated safely. 34 events were reported; on the international INES scale of 0 to 7, ENSI rated 33 events as Level 0 and 1 as Level 1. ENSI evaluates the safety of each nuclear power plant as part of a systematic safety evaluation taking account of both reportable events and other findings, in particular the results of more than 400 inspections conducted by ENSI during 2012. ZWILAG consists of several interim storage halls, a conditioning plant and an incineration/melting plant. At the end of 2012, the cask storage hall contained 40 transport/storage casks

  8. Chinese Nuclear Science Basic Data Base (CNSBDB)

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    A new research project on "Development of the Chinese Nuclear Science Basic Database (CNSBDB)for Fundamental Researches of Nuclear Physics and Interrelated Subjects, and Requirements of NuclearPower and Nuclear Technologies Application" has been commenced. The CNSBDB contains thefollowing eight segments: 1) Information on Nuclear Science (INFO); 2) Nuclear Structure Data Base(NSDB); 3) Nuclear Decay Data Base (NDDB); 4) Nuclear Reaction Data Base (NRDB); 5) Nuclear

  9. Renewable energy sources and nuclear installations; Erneuerbare Energien und neue Nuklearanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Hirschberg, S.; Bauer, Ch.; Burgherr, P.; Stucki, S.; Vogel, F.; Biollaz, S.; Schulz, T.; Durisch, W.; Hardegger, P.; Foskolos, K.; Meier, A.; Schenler, W.

    2005-02-15

    This comprehensive work report for the Swiss Federal Office of Energy (SFOE) made by the Paul Scherrer Institute PSI takes a look at work done in connection with the updating of the office's Energy Perspectives. In particular, the topic of electricity is reviewed in the light of pending important decisions in the area of nuclear energy and the newer renewable sources of energy. The report makes an attempt to estimate the effect on Swiss power production that the new renewables and new nuclear installations could have in the next 30-40 years and to what costs this could be done and which obstacles would have to overcome. The renewable energy sources include small hydro, wind, photovoltaics, solar thermal power plants, biogas, geothermal energy, wave-power and solar chemistry. The methods used include literature study and contacts with internal PSI experts on the various areas involved. The most important system characteristics were noted and learning curves for the various technologies were taken into account. Ecological and social factors were also considered

  10. Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport; Decret no 2007-1557 du 2 novembre 2007 relatif aux installations nucleaires de base et au controle, en matiere de surete nucleaire, du transport de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-11-15

    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.)

  11. Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2007 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-04-15

    This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on.

  12. Regulatory oversight report 2012 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2012 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) assesses and monitors nuclear facilities in Switzerland. These include the five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) and the nuclear facilities at the Paul Scherrer Institute (PSI), at the Federal Institute of Technology in Lausanne (EPFL) and at the University of Basel. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety in the relevant facilities. It ensures that the facilities comply with the regulations and operate as required by law. Its regulatory responsibilities also include the transport of radioactive materials from and to nuclear facilities and the preparations for a deep geological repository for nuclear waste. ENSI maintains its own emergency organisation. It formulates and updates its own guidelines which stipulate the criteria for evaluating the current activities and future plans of the operators of nuclear facilities. ENSI produces regular reports on its regulatory activities and nuclear safety in Swiss nuclear facilities. It fulfils its statutory obligation to provide the public with information on particular events and findings in nuclear facilities. In 2012, the five nuclear power plants in Switzerland were all operated safely. 34 events were reported; on the international INES scale of 0 to 7, ENSI rated 33 events as Level 0 and 1 as Level 1. ENSI evaluates the safety of each nuclear power plant as part of a systematic safety evaluation taking account of both reportable events and other findings, in particular the results of more than 400 inspections conducted by ENSI during 2012. ZWILAG consists of several interim storage halls, a conditioning plant and an incineration/melting plant. At the end of 2012, the cask storage hall contained 40 transport/storage casks

  13. Regulatory oversight report 2011 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2011 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-06-15

    The Swiss Federal Nuclear Safety Inspectorate ENSI, acting as the regulatory body of the Swiss Confederation, assesses and monitors nuclear facilities in Switzerland. These include five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI) and the two universities of Basel and Lausanne. ENSI ensures that the facilities comply with regulations and operate according to the law. Its regulatory responsibilities also include the transport of radioactive materials to and from nuclear facilities and the preparations for a deep geologic repository for nuclear waste. It maintains its own emergency organisation, which is an integral part of a national emergency structure. Building on the legislative framework, ENSI also formulates and updates its own guidelines. It provides the public with information on particular events and findings in nuclear facilities. In 2011, all five nuclear power reactors in Switzerland (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt) were operated safely and ENSI concluded that they had complied with their approved operating conditions. There were 27 reportable events in the nuclear power plants in Switzerland: 7 at Beznau, 5 at Goesgen, 11 at Leibstadt und 4 at Muehleberg. On the international INES scale of 0 to 7, ENSI rated 26 events as Level 0. One event, at the Muehleberg nuclear power plant, was rated as INES Level 1. This related to a potential blockage of the emergency water intake system in the event of extreme flooding. The operator BKW shut down the Muehleberg plant ahead of the scheduled maintenance date and upgraded the system. ZWILAG consists of several interim storage halls, a conditioning plant and a plasma plant (incineration/melting plant). At the end of 2011, the cask storage hall contained 34 transport/storage casks with fuel assemblies and vitrified residue packages

  14. Presentation of additional assessments of nuclear installation safety with respect to the Fukushima accident; Presentation des evaluations complementaires de la surete des installations nucleaires au regard de l'accident de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document presents the project of additional assessments of French nuclear installation safety after the Fukushima accident. It evokes the European and French contexts for these additional assessments, describes their organisation, and discusses the content of the project specifications. Then it lists the installations and sites to be assessed in 2011, those to be assessed in 2012, those to be assessed according to demands by the ASN. These installations are operated by EDF, the CEA, AREVA, Cisbio International, IONISOS, or the ANDRA

  15. Nuclear installations safety and protection: thirty years of researches on earthquakes at the IRSN; Surete et protection des installations nucleaires: trente ans de recherches a l'IRSN sur les seismes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-03-01

    Every years more than one hundred earthquakes occur in France. Taking into account this risk is essential for the safety of nuclear installations. In this context the IRSN develops research programs on earthquakes and realizes evolutions of safety procedures. This paper presents three sheets of researches realized by the IRSN on earthquakes risk assessment in the nuclear installations design and exploitation and the example of the Saint-Die earthquake. (A.L.B.)

  16. ETSON views on R and D priorities for implementation of the 2014 Euratom Directive on safety of nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Van Dorsselaere, Jean-Pierre [IRSN/PSN, Saint-Paul-lez-Durance (France); Mustoe, Jeremy; Power, Steve [Amec Foster Wheeler RSD, Birchwood Park, Warrington (United Kingdom); Adorni, Martina [Bel V, Brussels (Belgium); Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany); Nieminen, Anna [VTT Technical Research Centre of Finland Ltd. (Finland)

    2016-11-15

    Following the Fukushima-Daiichi accident in 2011, the Council Directive 2014/87/Euratom has reinforced the previous 2009 Directive that had established a Community framework for the safety of nuclear installations. In particular, one new article introduces a high-level EU-wide safety objective of preventing accidents through defence- in-depth and avoiding radioactive releases outside a nuclear installation. For achieving this objective, the research necessary outcomes are mainly a better knowledge of the involved physical phenomena and its capitalization in methodologies and tools such as simulation codes. ETSON, the European Technical Safety Organisation Network, had already identified in its Position Paper in 2011 the main R and D priorities. The present paper underlines that most of these priorities, with a few updates due to progress of knowledge, remain consistent with the objectives of this new Directive. And it illustrates the ETSON involvement through examples of on-going or planned R and D national and international projects.

  17. 78 FR 61401 - Entergy Nuclear Operations, Inc.; Big Rock Point; Independent Spent Fuel Storage Installation

    Science.gov (United States)

    2013-10-03

    ... Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001..., and 10 CFR part 50, allows ENO to possess and store spent nuclear fuel at the permanently shutdown and... Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety...

  18. Inelastic seismic behavior of post-installed anchors for nuclear safety related structures: Generation of experimental database

    Energy Technology Data Exchange (ETDEWEB)

    Mahadik, Vinay, E-mail: vinay.mahadik@iwb.uni-stuttgart.de; Sharma, Akanshu; Hofmann, Jan

    2016-02-15

    Highlights: • Experiments for evaluating seismic behavior of anchors were performed. • Two undercut anchor products in use in nuclear facilities were considered. • Monotonic tension, shear and cycling tension tests at different crack widths. • Crack cycling tests at constant, in-phase and out-of phase tension loads. • Characteristics for the two anchors as a function of crack width were identified. - Abstract: Post installed (PI) anchors are often employed for connections between concrete structure and components or systems in nuclear power plants (NPP) and related facilities. Standardized practices for nuclear related structures demand stringent criteria, which an anchor has to satisfy in order to qualify for use in NPP related structures. In NPP and related facilities, the structure–component interaction in the event of an earthquake depends on the inelastic behavior of the concrete structure, the component system and also the anchorage system that connects them. For analysis, anchorages are usually assumed to be rigid. Under seismic actions, however, it is known that anchors may undergo significant plastic displacement and strength degradation. Analysis of structure–component interaction under seismic loads calls for numerical models simulating inelastic behavior of anchorage systems. A testing program covering different seismic loading scenarios in a reasonably conservative manner is required to establish a basis for generating numerical models of anchorage systems. Currently there is a general lack of modeling techniques to consider the inelastic behavior of anchorages in structure–component interaction under seismic loads. In this work, in view of establishing a basis for development of numerical models simulating the inelastic behavior of anchors, seismic tests on two different undercut anchors qualified for their use in NPP related structures were carried out. The test program was primarily based on the DIBt-KKW-Leitfaden (2010) guidelines

  19. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages; Instalacion de un nuevo tipo de reactor nuclear en Mexico: ventajas y desventajas

    Energy Technology Data Exchange (ETDEWEB)

    Jurado P, M.; Martin del Campo M, C. [FI-UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: mjp_green@hotmail.com

    2005-07-01

    In this work the main advantages and disadvantages of the installation of a new type of nuclear reactor different to the BWR type reactor in Mexico are presented. A revision of the advanced reactors is made that are at the moment in operation and of the advanced reactors that are in construction or one has already planned its construction in the short term. Specifically the A BWR and EPR reactors are analyzed. (Author)

  20. Release of radioisotopes and activated materials from nuclear installations and facilities

    Energy Technology Data Exchange (ETDEWEB)

    Manfredi, P.F.; Millaud, J. E.

    2001-11-21

    This report discusses the problems of release of items from facilities and installations where radiation-based activities have been carried out. Several situations are reviewed and their release problems are discussed in detail. Particular attention is devoted to the assessment of the activity of the items to be released. A correct assessment of the activity will help the decision about the final use of the items removed from the radiation-related facility, either re-use, entering the public market, recycling, disposal and storage under different procedures. Even the final destination of the building which hosted the facility needs to be decided on the basis of an accurate assessment of the residual activity. The assessment of the activity, besides being fundamental in guaranteeing a safe approach to the procedures related to the release may result in a substantial profit. This is the case of items whose level of activity is so low that they can be put on the public market, reused or recycled for final product subject to very stringent radiation safety requirements. It will be shown that detector techniques play a fundamental role in the release process. In particular, the low-level counting techniques are fundamental in establishing whether or not the unrestrained release is feasible or not.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-04-01

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

  2. A program for occupational radiological protection in a nuclear installation linked to a NORM/TENORM phosphate

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Wagner de S.; Py Junior, Delcy de A. [Industrias Nucleares do Brasil (INB), Pocos de Caldas, MG (Brazil). Unidade de Tratamento de Minerios. Coordenacao de Protecao Radiologica], e-mail: wspereira@inb.gov.br, e-mail: delcy@inb.gov.br; Kelecom, Alphonse [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil). Inst. de Biologia. Curso de Pos-Graduacao em Biologia Marinha], e-mail: kelecom@uol.com.br; Mortagua, Valter [Industrias Nucleares do Brasil (INB), Jurubatuba, SP (Brazil). Usina de Interlagos (USIN). Coordenacao da Unidade de Sao Paulo], e-mail: valtermortagua@inb.gov.br

    2009-07-01

    Mining that has natural radionuclides associated with the ore is known as NORM mining. The Santa Quiteria Unit (USQ) is included in this category. It is a NORM phosphate mine that belongs to the Nuclear Industries of Brazil. This unit is divided into two areas: the phosphate mining and production (conventional mining facility, CMF-USQ) and a production of uranium diuranate (nuclear facility, NF-USQ). The NF-USQ must follow the Brazilian legislation for nuclear installation (NF). This legislation is under the responsibility of the Nuclear Energy National Commission - CNEN, the nuclear regulatory agency in Brazil. Brazilian law on NF requires the facility to have a system of radioprotection and also requires the existence of a radiation protection service (RPS), composed of trained professionals and coordinated by a radioprotection supervisor (RS), accredited by CNEN, which manages the implementation of the occupational radiation protection program (ORPP). This work reports on the design of the ORPP for the NF-USQ associated with CMF-USQ, and on the minimum requirements for a RPS and the kinds of monitoring to be carried out. It also aims to classify the areas as for radioprotection aspects, and to indicate the number and qualifications of the radioprotection staff. Moreover, the work also informs the equipment necessary to the operation of the RPS and other relevant parameters. Finally, it explains the models used in estimating doses for occupationally exposed individuals (OEI) and for individuals of the public (IP), and also the derived limits proposed by the operator for the NFUSQ. The NF-USQ will have 51 OEI, of which 11 belonging to the RS, one being the RPS accredited by CNEN. The NF will be composed of 12 areas, 10 being free areas, one will be supervised and one will be a controlled area. Individual and area monitoring will be carried out. The derived limits proposed by the operator are shown in table 1. These derived limits are calculated based on the limit

  3. Dynamic Analysis of Nuclear Waste Generation Based on Nuclear Fuel Cycle Transition Scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, S. R. [University of Science and Technology, Daejeon (Korea, Republic of); Ko, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    According to the recommendations submitted by the Public Engagement Commission on Spent Nuclear Fuel Management (PECOS), the government was advised to pick the site for an underground laboratory and interim storage facilities before the end of 2020 followed by the related research for permanent and underground disposal of spent fuel after 10 years. In the middle of the main issues, the factors of environmentally friendly and safe way to handle nuclear waste are inextricable from nuclear power generating nation to ensure the sustainability of nuclear power. For this purposes, the closed nuclear fuel cycle has been developed regarding deep geological disposal, pyroprocessing, and burner type sodium-cooled fast reactors (SFRs) in Korea. Among two methods of an equilibrium model and a dynamic model generally used for screening nuclear fuel cycle system, the dynamic model is more appropriate to envisage country-specific environment with the transition phase in the long term and significant to estimate meaningful impacts based on the timedependent behavior of harmful wastes. This study aims at analyzing the spent nuclear fuel generation based on the long-term nuclear fuel cycle transition scenarios considered at up-to-date country specific conditions and comparing long term advantages of the developed nuclear fuel cycle option between once-through cycle and Pyro-SFR cycle. In this study, a dynamic analysis was carried out to estimate the long-term projection of nuclear electricity generation, installed capacity, spent nuclear fuel arising in different fuel cycle scenarios based on the up-to-date national energy plans.

  4. The influence of EI-21 redox ion-exchange resins on the secondary-coolant circuit water chemistry of vehicular nuclear power installations

    Science.gov (United States)

    Moskvin, L. N.; Rakov, V. T.

    2015-06-01

    The results obtained from testing the secondary-coolant circuit water chemistry of full-scale land-based prototype bench models of vehicular nuclear power installations equipped with water-cooled water-moderated and liquid-metal reactor plants are presented. The influence of copper-containing redox ionexchange resins intended for chemically deoxygenating steam condensate on the working fluid circulation loop's water chemistry is determined. The influence of redox ion-exchange resins on the water chemistry is evaluated by generalizing an array of data obtained in the course of extended monitoring using the methods relating to physicochemical analysis of the quality of condensate-feedwater path media and the methods relating to metallographic analysis of the state of a faulty steam generator's tube system surfaces. The deoxygenating effectiveness of the normal state turbine condensate vacuum deaeration system is experimentally determined. The refusal from applying redox ion-exchange resins in the condensate polishing ion-exchange filters is formulated based on the obtained data on the adverse effect of copper-containing redox ionexchange resins on the condensate-feedwater path water chemistry and based on the data testifying a sufficient effect from using the normal state turbine condensate vacuum deaeration system. Data on long-term operation of the prototype bench model of a vehicular nuclear power installation without subjecting the turbine condensate to chemical deoxygenation are presented.

  5. Environmental Assessment: Installation Development at Vance Air Force Base, Oklahoma

    Science.gov (United States)

    2007-04-01

    present throughout both installations, but more prevalent on Kegel man. The Service recommends incorporating migratory birds into your environmental...Attachment 2 Project Number 15 16 1.7 18 19 21 Description/ Location Physical Fitness Center/ HA WC Addition Kegel man Fire Station Repair

  6. Environmental Assessment Installation Development and Base Realignment and Closure Actions

    Science.gov (United States)

    2007-01-01

    Intergovernmental Coordination for Enviro nmental Planning Public Involvement LIST OF TABLES Annua l and Average Monthly T-38 Passes at SeaRay Range...environmentally-sound install ation, and a wellness-oriented, physica lly-fi t workforce. This is accomplished through fitness, smoking cessation

  7. The nuclear installations dismantling and the management of radioactive wastes; Le demantelement des installations nucleaires et la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    As other industrial activities, the nuclear industry causes risks. The risks bound to the dismantling operations are known and controlled. After a presentation of the dismantling and radioactive wastes challenge, this document proposes recommendations based on the first experiences of dismantling and wastes storage. It aims then to answer to the questions relative to the cost and the financing of the operations. Finally it wonders on the public information modalities. (A.L.B.)

  8. Project-based learning used for teaching electrical installations and lighting installations in architecture

    Directory of Open Access Journals (Sweden)

    Alicia Martinez Anton

    2011-04-01

    Full Text Available Purpose: This paper discusses the use of Project-Based Learning (PBL in the subject "Acondicionamiento y Servicios 2", which is taught at the Escuela de Arquitectura at the UPV.Design/methodology/approach: Case study.Findings: The results show that the goals (motivation, improved learning outcomes, independent learning and connection with professional practice, which led to the introduction of this kind of learning, have been achieved.Research limitations/implications: This work has been proved in two groups of a subject. Therefore, conclusions are specifically related to this context and generalization is not proved.Practical implications: Increase motivation, improved learning outcomes, independent learning and connection with professional practice.Originality/value: This work confirms previous studies about the useful of PBL in engineering matters.

  9. Opinion on the radio-ecological monitoring of waters around nuclear installations and on the management of old nuclear waste warehousing sites: 18 recommendations to improve information, transparency and dialogue with involved parties; Avis sur le suivi radioecologique des eaux autour des installations nucleaires et sur la gestion des anciens sites d'entreposage de dechets radioactifs. 18 recommandations pour ameliorer l'information, la transparence et la concertation avec les parties prenantes..

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    After a presentation of the different actors (agencies, institutions, companies) involved in the activities of the various French nuclear installations (base nuclear installations and those concerning the national defence), this report describes the radio-ecological monitoring performed around these nuclear sites: water surveillance on these sites and within their environment, regulatory requirements on effluents and surveillance, information provided by operators and by institutional organisations, assessment of the radio-ecological status of nuclear sites and of potential environmental and health impacts. It describes regulatory obligation in terms of public information, information and communication actions, and gives an assessment of the High committee about public information quality. It discusses ways to improve this quality for a higher transparency, to reinforce the role of local information commissions (CLI), and improve site monitoring. All these aspects are grouped in 18 recommendations.

  10. Installation Development Environmental Assessment Travis Air Force Base, California

    Science.gov (United States)

    2007-11-01

    area predominantly have a thermic soil temperature regime (the mean annual soil temperature is 15 degrees Celsius [°C] or higher but lower than 22°C...ranges from sea level to 660 feet (200 meters) in the foothills surrounding the Central Valley. The valley floor is almost flat, and relief is small...even along the borders of the area. The Final EA of Installation Development Travis AFB, CA November 2007 3-15 flatness of the valley floor

  11. On the reliability of fire detection and alarm systems. Exploration and analysis of data from nuclear and non-nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Nyyssoenen, T.; Rajakko, J.; Keski-Rahkonen, O. [VTT Building and Transport, Espoo (Finland)

    2005-01-01

    A literature review of reliability data of fire detection and alarm systems was made resulting to rough estimates of some failure frequencies. No theoretical or technical articles on the structure of reliability models of these installations were found. Inspection records of fire detection and alarm system installations by SPEK were studied, and transferred in electronic data base classifying observed failures in failure modes (59) and severity categories (3) guided by freely written records in the original data. The results of that work are presented without many comments in tabular form in this paper. A small sample of installations was collected, and number of components in them was counted to derive some distributions for determination of national populations of various components based on know total amount of installations. From NPPs (Loviisa, Olkiluoto and Barsebaeck) failure reports were analysed, and observed failures of fire detection and alarm systems were classified by severity and detection mode. They are presented here in tabular form for the original and new addressable systems. Populations were counted individually, but for all installations needed documents were not available. Therefore, presented failure frequencies are just first estimates, which will be refined later. (orig.)

  12. Compressed Natural Gas Installation. A Video-Based Training Program for Vehicle Conversion. Instructor's Edition.

    Science.gov (United States)

    Oklahoma State Dept. of Vocational and Technical Education, Stillwater. Curriculum and Instructional Materials Center.

    This instructor's guide contains the materials required to teach four competency-based course units of instruction in installing compressed natural gas (CNG) systems in motor vehicles. It is designed to accompany an instructional videotape (not included) on CNG installation. The following competencies are covered in the four instructional units:…

  13. Plutonium: resuspension of aerosols in nuclear installations: bibliographic survey; Le plutonium: mise en suspension d'aerosols dans les installations nucleaires: synthese bibliographique

    Energy Technology Data Exchange (ETDEWEB)

    Guetat, Ph.; Monfort, M.; Armand, P. [CEA Bruyeres-le-Chatel, Dept. Analyse Surveillance Environnement, Service Radioanalyse Chimie Environnement, 91 (France); Alloul-Marmor, L. [Societe APTUS, 78 - Versailles (France)

    2006-07-01

    This document presents an analysis and a bibliographical synthesis of the studies on resuspension factors for plutonium. It aims at helping the engineers of safety to specify the scenarios of accidents which relate to their activities and to bring elements justified for the definition of their term-source 'installation' in the safety reports of the installations. (authors)

  14. Nuclear facilities: repair and replacement technologies; Installations nucleaires: technologies de reparation et de remplacement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The oldest operating reactors are more than 35 years old and are now facing major maintenance operations. The first replacement of a pressurizer took place in autumn 2005 at the St-Lucie plant (Usa) while steam generators have been currently replaced since 1983. Nuclear industry has to adapt to this new market by proposing innovative technological solutions in the reactor maintenance field. This document gathers the 9 papers presented at the conference. The main improvements concern repair works on internal components of PWR-type reactors, the replacement of major components of the primary coolant circuit and surface treatments to limit the propagation of damages. The first paper shows that adequate design and feedback experience are good assets to manage the ageing of a nuclear unit. Another paper shows that a new repair method of a relief valve can avoid its replacement. (A.C.)

  15. Calibration of burnup monitor of spent nuclear fuel installed at Rokkasho reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Oeda, Kaoru; Matoba, Masaru; Wakabayashi, Genichiro [Kyushu Univ., Fukuoka (Japan). Faculty of Engineering; Naito, Hirofumi; Hirota, Masanari [Nuclear Fuel Industries Ltd., Tokyo (Japan); Morizaki, Hidetoshi; Kumanomido, Hironori; Natsume, Koichiro [Toshiba Corp., Tokyo (Japan)

    2001-05-01

    The spent nuclear fuel storage pool of Rokkasho reprocessing plant adopts the burnup credit' conception. Spent fuel assemblies are measured every one by one, by burnup monitors, and stored to a storage rack which is designed with specified residual enrichment. For nuclear criticality control, it is necessary for the burnup monitor that the measured value includes a kind of margin, which consists of errors of the monitor. In this paper, we describe the error of the burnup monitors, and the way of taking of the margin. From the result of calibration of the burnup monitor carried out from July through November, 1999, we describe that the way of taking of the margin is validated. And comments about possibility of error reduction are remarked. (author)

  16. Analysing on Installation Features of Pre-installed Equipment of Nuclear Power Engineering%核电工程预装设备的安装方法探讨

    Institute of Scientific and Technical Information of China (English)

    徐晖

    2016-01-01

    This article takes Fangjiashan nuclear power project as example, it analyzes and elaborates the installation characteristics of pre-installed equipments of nuclear power project. It focuses on the installation process of pre-installed equipment, equipment product protection and other aspects. And it sums and feeds back the main problems that were faced during the construction, which has a certain reference value, it also provides some lessons of experience for the subsequent AP1000 nuclear power project by using the open-top construction method.%本文以方家山核电工程为例,对核电项目预装设备安装的特点进行了分析和阐述,着重介绍了预装设备安装工艺、设备成品保护等方面内容,并就施工过程中面临的主要问题进行了总结和反馈,具有一定参考价值,也为后续AP1000核电项目采用“开顶法”施工提供一些借鉴经验。

  17. Compatibility Decisions, Endogenous Installed Home Bases and the Third-Market Competition

    OpenAIRE

    Walz, Uwe; Woeckener, Bernd

    2003-01-01

    This Paper analyses the compatibility decisions of two regional monopolistic suppliers of a network-effect good who first build up installed bases in their respective home region and then compete in a third market. We show that with weak network effects, installed home bases always are higher under compatibility and suppliers always opt for compatibility. With strong network effects, home markets are covered, and given a sufficiently high home-market size advantage both the favoured supplier ...

  18. Process of Judging Significant Modifications for Different Transportation Systems compared to the Approach for Nuclear Installations

    Directory of Open Access Journals (Sweden)

    Nicolas Petrek

    2015-12-01

    Full Text Available The implementation of the CSM regulation by the European Commission in 2009 which harmonizes the risk assessment process and introduces a rather new concept of judging changes within the European railway industry. This circumstance has risen the question how other technology sectors handle the aspect of modifications and alterations. The paper discusses the approaches for judging the significance of modifications within the three transport sectors of European railways, aviation and maritime transportation and the procedure which is used in the area of nuclear safety. We will outline the similarities and differences between these four methods and discuss the underlying reasons. Finally, we will take into account the role of the European legislator and the fundamental idea of a harmonization of the different approaches.

  19. Seismic hazard analysis of nuclear installations in France. Current practice and research

    Energy Technology Data Exchange (ETDEWEB)

    Mohammadioun, B. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

    1997-03-01

    The methodology put into practice in France for the evaluation of seismic hazard on the sites of nuclear facilities is founded on data assembled country-wide over the past 15 years, in geology, geophysics and seismology. It is appropriate to the regional seismotectonic context (interplate), characterized notably by diffuse seismicity. Extensive use is made of information drawn from historical seismicity. The regulatory practice described in the RFS I.2.c is reexamined periodically and is subject to up-dating so as to take advantage of new earthquake data and of the results gained from research work. Acquisition of the basic data, such as the identification of active faults and the quantification of site effect, which will be needed to achieve improved preparedness versus severe earthquake hazard in the 21st century, will necessarily be the fruit of close international cooperation and collaboration, which should accordingly be actively promoted. (J.P.N.)

  20. Design of a mobile neutron radiography installation based on a compact sealed tube neutron generator

    Institute of Scientific and Technical Information of China (English)

    MaWei-Chao; YaoAn-Ju; 等

    1997-01-01

    A series of optimum conditions are taken into account in the construction of neutron radiography(NR) installation based on a sealed tube neutron generator capable of gnerating 1010 n/s with 14MeV.The characteristics of NNU screens,a kind of self-made 6LiF.ZnS(Ag)scintillation intensifying screen are presented.Finally,some neutron radiographies taken by this NR installation and NNU screens are given.

  1. 极低水平放射性废物管控区就地处置的可行性研究%Feasible Research on VLLW Disposal in Control Area of Nuclear Installation

    Institute of Scientific and Technical Information of China (English)

    孔劲松; 郭卫群

    2013-01-01

    Based on the basic requirements on the VLLW landfill disposal specified by the national codes and standards,a on-site disposal of VLLW in the control area of nuclear installation was proposed.A detail analysis of the advantages and disadvantages about the disposal method and the problem to be solved were described.Results showed that the on-site disposal of VLLW in the control area of nuclear installation was feasible in practice.%根据国家相关法规、标准对极低水平放射性废物(VLLW)填埋处置的基本要求,提出VLLW管控区就地处置方法,并详细分析该方法的利弊及尚需解决的问题.VLLW管控区就地处置具有实践的可行性.

  2. PANTHERE, simulation software of dose flow rates for complex nuclear installations; Panthere - logiciel pour la simulation des debits de dose pour installations nucleaires complexes

    Energy Technology Data Exchange (ETDEWEB)

    Longeot, M.; Dupont, B.; Coatanea, C. [EDF/SEPTEN/TE, 12-14 avenue Dutrievoz, 69628 Villeurbanne Cedex (France); Schumm, S.; Zweers, M. [EDF/R and D/SINETICS, 1, avenue du General de Gaulle, 92141 Clamart Cedex (France); Malvagi, F.; Trama, J.C. [CEA Saclay, SERMA, 91 - Gif-sur-Yvette (France)

    2010-07-01

    The authors present the PANTHERE simulation software developed by EDF-SEPTEN to determine gamma dose flow rate in any point of complex industrial installations. They present the current industrial version (PANTHEREV1) and its different applications, and more particularly an investigation in the field of qualification of hardware under irradiation in case of severe accident. They present the currently under development version (PANTHEREV2) which will be exploited in 2011

  3. Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

    2013-03-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

  4. Installed Base Registration of Decentralised Solar Panels with Applications in Crisis Management

    Science.gov (United States)

    Aarsen, R.; Janssen, M.; Ramkisoen, M.; Biljecki, F.; Quak, W.; Verbree, E.

    2015-08-01

    In case of a calamity in the Netherlands - e.g. a dike breach - parts of the nationwide electric network can fall out. In these occasions it would be useful if decentralised energy sources of the Smart Grid would contribute to balance out the fluctuations of the energy network. Decentralised energy sources include: solar energy, wind energy, combined heat and power, and biogas. In this manner, parts of the built environment - e.g. hospitals - that are in need of a continuous power flow, could be secured of this power. When a calamity happens, information about the Smart Grid is necessary to control the crisis and to ensure a shared view on the energy networks for both the crisis managers and network operators. The current situation of publishing, storing and sharing data of solar energy has been shown a lack of reliability about the current number, physical location, and capacity of installed decentralised photovoltaic (PV) panels in the Netherlands. This study focuses on decentralised solar energy in the form of electricity via PV panels in the Netherlands and addresses this challenge by proposing a new, reliable and up-to-date database. The study reveals the requirements for a registration of the installed base of PV panels in the Netherlands. This new database should serve as a replenishment for the current national voluntary registration, called Production Installation Register of Energy Data Services Netherland (EDSN-PIR), of installed decentralised PV panel installations in the Smart Grid, and provide important information in case of a calamity.

  5. Programmable DSP-Based Multi-Bunch Feedback - Operating Experience from Six Installations

    Energy Technology Data Exchange (ETDEWEB)

    Fox, John D

    2000-05-15

    A longitudinal instability control system, originally developed for the PEP-II, DAPHNE and ALS machines has in the last two years been commissioned for use at the PLS and BESSY-II light sources. All of the installations are running identical hardware and use a common software distribution package. This common structure is beneficial in sharing expertise among the labs, and allows rapid commissioning of each new installation based on well-understood diagnostic and operational techniques. While the installations share the common instability control system, there are significant differences in machine dynamics between the various colliders and light sources. These differences require careful specification of the feedback algorithm and system configuration at each installation to achieve good instability control and useful operational margins. This paper highlights some of the operational experience at each installation, using measurements from each facility to illustrate the challenges unique to each machine. The authors experience on the opportunities and headaches of sharing development and operational expertise among labs on three continents is also offered.

  6. Emergency Preparedness technology support to the Health and Safety Executive (HSE), Nuclear Installations Inspectorate (NII) of the United Kingdom. Appendix A

    Energy Technology Data Exchange (ETDEWEB)

    O`Kula, K.R.

    1994-03-01

    The Nuclear Installations Inspectorate (NII) of the United Kingdom (UK) suggested the use of an accident progression logic model method developed by Westinghouse Savannah River Company (WSRC) and Science Applications International Corporation (SAIC) for K Reactor to predict the magnitude and timing of radioactivity releases (the source term) based on an advanced logic model methodology. Predicted releases are output from the personal computer-based model in a level-of-confidence format. Additional technical discussions eventually led to a request from the NII to develop a proposal for assembling a similar technology to predict source terms for the UK`s advanced gas-cooled reactor (AGR) type. To respond to this request, WSRC is submitting a proposal to provide contractual assistance as specified in the Scope of Work. The work will produce, document, and transfer technology associated with a Decision-Oriented Source Term Estimator for Emergency Preparedness (DOSE-EP) for the NII to apply to AGRs in the United Kingdom. This document, Appendix A is a part of this proposal.

  7. Evaluation of the impact and the releases of operating nuclear facilities; Evaluation de l'impact et des rejets des installations nucleaires en fonctionnement normal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The monitoring of nuclear installations releases, the associated impacts evaluation and the radiation monitoring of the environment are of an increase interest since the last ten years. Theses two days, organized by the environment section of the SFRP (French Society of Radiation Protection), aim to discuss the following topics: the development of the methods to improve radioactive elements and toxic substances releases in the environment; the structure of the environment control and the objectives of this control; the association of the local actors to the releases monitoring and to the environment control; the perspectives of evolution in matter of nuclear facilities releases management. (A.L.B.)

  8. Procedure of calculation of the spatial distribution of temperatures and heat fluxes in the steam generator of a nuclear power installation with an RBEC fast-neutron reactor

    Science.gov (United States)

    Frolov, A. A.; Sedov, A. A.

    2016-08-01

    A method for combined 3D/1D-modeling of thermohydraulics of a once-through steam generator (SG) based on the joint analysis of three-dimensional thermo- and hydrodynamics of a single-phase heating coolant in the intertube space and one-dimensional thermohydraulics of steam-generating channels (tubes) with the use of well-known friction and heat-transfer correlations under various boiling conditions is discussed. This method allows one to determine the spatial distribution of temperatures and heat fluxes of heat-exchange surfaces of SGs with a single-phase heating coolant in the intertube space and with steam generation within tubes. The method was applied in the analytical investigation of typical operation of a once-through SG of a nuclear power installation with an RBEC fast-neutron heavy-metal reactor that is being designed by Kurchatov Institute in collaboration with OKB GIDROPRESS and Leipunsky Institute of Physics and Power Engineering. Flow pattern and temperature fields were obtained for the heavy-metal heating coolant in the intertube space. Nonuniformities of heating of the steam-water coolant in different heat-exchange tubes and nonuniformities in the distribution of heat fluxes at SG heat-exchange surfaces were revealed.

  9. The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

    2006-07-01

    The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

  10. INSTALLING AN ERP SYSTEM WITH A METHODOLOGY BASED ON THE PRINCIPLES OF GOAL DIRECTED PROJECT MANAGEMENT

    Directory of Open Access Journals (Sweden)

    Ioannis Zafeiropoulos

    2010-01-01

    Full Text Available This paper describes a generic methodology to support the process of modelling, adaptation and implementation (MAI of Enterprise Resource Planning Systems (ERPS based on the principles of goal directed project management (GDPM. The proposed methodology guides the project manager through specific stages in order to successfully complete the ERPS implementation. The development of the proper MAI methodology is deemed necessary because it will simplify the installation process of ERPS. The goal directed project management method was chosen since it provides a way of focusing all changes towards a predetermined goal. The main stages of the methodology are the promotion and preparation steps, the proposal, the contract, the implementation and the completion. The methodology was applied as a pilot application by a major ERPS development company. Important benefits were the easy and effective guidance for all installation and analysis stages, the faster installation for the ERPS and the control and cost reduction for the installation, in terms of time, manpower, technological equipment and other resources.

  11. INSTALLING AN ERP SYSTEM WITH A METHODOLOGY BASED ON THE PRINCIPLES OF GOAL DIRECTED PROJECT MANAGEMENT

    Directory of Open Access Journals (Sweden)

    Ioannis Zafeiropoulos

    2009-12-01

    Full Text Available This paper describes a generic methodology to support the process of modelling, adaptation and implementation (MAI of Enterprise Resource Planning Systems (ERPS based on the principles of goal directed project management (GDPM. The proposed methodology guides the project manager through specific stages in order to successfully complete the ERPS implementation. The development of the proper MAI methodology is deemed necessary because it will simplify the installation process of ERPS. The goal directed project management method was chosen since it provides a way of focusing all changes towards a predetermined goal. The main stages of the methodology are the promotion and preparation steps, the proposal, the contract, the implementation and the completion. The methodology was applied as a pilot application by a major ERPS development company. Important benefits were the easy and effective guidance for all installation and analysis stages, the faster installation for the ERPS and the control and cost reduction for the installation, in terms of time, manpower, technological equipment and other resources.

  12. INSTALLED BASE REGISTRATION OF DECENTRALISED SOLAR PANELS WITH APPLICATIONS IN CRISIS MANAGEMENT

    Directory of Open Access Journals (Sweden)

    R. Aarsen

    2015-08-01

    Full Text Available In case of a calamity in the Netherlands - e.g. a dike breach - parts of the nationwide electric network can fall out. In these occasions it would be useful if decentralised energy sources of the Smart Grid would contribute to balance out the fluctuations of the energy network. Decentralised energy sources include: solar energy, wind energy, combined heat and power, and biogas. In this manner, parts of the built environment - e.g. hospitals - that are in need of a continuous power flow, could be secured of this power. When a calamity happens, information about the Smart Grid is necessary to control the crisis and to ensure a shared view on the energy networks for both the crisis managers and network operators. The current situation of publishing, storing and sharing data of solar energy has been shown a lack of reliability about the current number, physical location, and capacity of installed decentralised photovoltaic (PV panels in the Netherlands. This study focuses on decentralised solar energy in the form of electricity via PV panels in the Netherlands and addresses this challenge by proposing a new, reliable and up-to-date database. The study reveals the requirements for a registration of the installed base of PV panels in the Netherlands. This new database should serve as a replenishment for the current national voluntary registration, called Production Installation Register of Energy Data Services Netherland (EDSN-PIR, of installed decentralised PV panel installations in the Smart Grid, and provide important information in case of a calamity.

  13. Environmental Assessment of Installation Development at Joint Base San Antonio-Lackland, Texas

    Science.gov (United States)

    2013-02-01

    unemployed civilians and members of the armed forces. San Antonio’s economy is based on services, commercial trade, government employment, tourism ...of JBSA-Lackland known as Hotel Row, which includes Buildings 9110, 9210, 9310 and 9410, would be demolished. Each 215,824 ft2 dormitory was...Medical, Administrative Renovation of the parking lot at Luke Gate, installation of a speed table, and construction of a new inbound lane

  14. Performance Based Failure Criteria of the Base Isolation System for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Han; Kim, Min Kyu; Choi, In Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The realistic approach to evaluate the failure state of the base isolation system is necessary. From this point of view, several concerns are reviewed and discussed in this study. This is the preliminary study for the performance based risk assessment of a base isolated nuclear power plant. The items to evaluate the capacity and response of an individual base isolator and a base isolation system were briefly outlined. However, the methodology to evaluate the realistic fragility of a base isolation system still needs to be specified. For the quantification of the seismic risk for a nuclear power plant structure, the failure probabilities of the structural component for the various seismic intensity levels need to be calculated. The failure probability is evaluated as the probability when the seismic response of a structure exceeds the failure criteria. Accordingly, the failure mode of the structural system caused by an earthquake vibration should be defined first. The type of a base isolator appropriate for a nuclear power plant structure is regarded as an elastometric rubber bearing with a lead core. The failure limit of the lead-rubber bearing (LRB) is not easy to be predicted because of its high nonlinearity and a complex loading condition by an earthquake excitation. Furthermore, the failure mode of the LRB system installed below the nuclear island cannot be simply determined because the basemat can be sufficiently supported if the number of damaged isolator is not much.

  15. Installation and Commissioning of RCP Cartridge for Nuclear Power Stations%核电厂主泵密封系统的安装与调试

    Institute of Scientific and Technical Information of China (English)

    霍亚邦; 王玉旭

    2011-01-01

    The installation process and method for the cooling pump sealing system of CPR1000 nuclear power plant reactor is studied, and various cases occurred during the installation and commisioning of RCP sealing systems are analyzed. The scheme for flushing of the nuclear loop in the various cases is developed to provide a reference for the installation and commissioning of RCP sealing system in the coming CPR1000 project.%研究CPR1000堆型核电厂反应堆冷却剂泵(RCP)密封安装工艺流程及方法,对RCP密封系统安装和调试过程中的各种情况进行分析,制定各种情况下核回路冲洗采取的特殊处理方案,为后续CPR1000项目RCP密封系统安装调试提供参考.

  16. A risk based approach to re-assessment of existing North Sea installations

    Energy Technology Data Exchange (ETDEWEB)

    Sharp, J.V.; Kam, J.C.; Birkinshaw, M. [Health and Safety Executive, London (United Kingdom). Offshore Safety Div.

    1995-12-31

    Reassessment of installations on the UK Continental Shelf is an important control measure in assuring continuing structural integrity. At present this is achieved via the certification process. Risk based regulations have now been introduced requiring a safety case for each installation; these will be supported by the introduction of additional regulations. Preparation of the safety case requires the identification of major accidental hazards and a demonstration of how the associated risks are to be controlled. Structures installed some time ago have been designed to codes and standards, for which the design requirements may have since changed as a result of more data becoming available. Examples are given for both the static and fatigue strength of tubular joints. Other important factors include the design wave height and the air gap. System behavior and reserve strength are important in justifying performance and an acceptance criterion for reserve strength is included in the draft section 17. Recent HSE studies on benchmarking pushover type software have shown that current industry practice can lead to significant variations in prediction of reserve strength. The key factors required for a risk based approach to reassessment are discussed, associated with the need that the structural integrity should be maintained through the life cycle to a level that the risks to personnel are as low as reasonably practicable.

  17. DEVELOPMENT OF A MATHEMATICAL MODEL OF INSTALLATION OF SELF-CONTAINED HEATING BASED ON SOLAR THERMAL COLLECTOR

    OpenAIRE

    Kartashev, Alexander; Safonov, Evgeniy; Kartasheva, Marina

    2011-01-01

    The mathematical model describing the operation of the installation of selfcontained heating and hot water supply based on solar thermal collector with the system of accumulation of heat energy, monitoring and control of thermal conditions of building is developed. Modeling of operation of the installation in different conditions is realized.

  18. U.S. Forward Operating Base Applications of Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, George W. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  19. Study on the establishment of nuclear education and training network based on the nuclear knowledge management

    Energy Technology Data Exchange (ETDEWEB)

    Lee, U. J.; Han, K. W.; Jeon, P. I.; Kim, Y. T.; Nam, Y. M.; Won, J. Y.; Kim, H. K. [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    The preservation and succession of nuclear knowledge are essential for the sustainable development of nuclear energy. Nuclear knowledge management is inseparably related with education and training, also should be considered as future oriented activities for the next generation. Nevertheless mankind has enormously benefited worldwide from the use of the nuclear energy over the last half a century, nuclear energy has faced with difficulties from the public. The current nuclear workforce is getting older, less of youth are studying nuclear science and engineering. These issues should be discussed together with the government, research institutes, universities, and industries in terms of the preservation and succession of nuclear knowledge. Therefore, education and training of nuclear technology is requested to develop its role with cooperation of the national level, furthermore of regional and interregional level. This paper provides the methodology of the establishment of a regional network of nuclear education and training based on the nuclear knowledge management.

  20. Nuclear installations in the baltic sea region and the stake holders cooperation: a crucial step towards energy security, environmental sustainability and political stability in the region

    Energy Technology Data Exchange (ETDEWEB)

    Zakaria, M.; Mandere, N.; Olsson, L. [Lund Univ., Centre for Sustainability Studies (LUCSUS) (Sweden)

    2006-07-01

    Radiation hazards are trans-boundary. The prevention of accidents must be managed locally. But the awareness, preparedness, and the responsibilities in the case of emergencies must be managed at the local and regional level, and must rely on close interaction between the local and regional levels. The Baltic Sea Region contains over 40 nuclear reactors contributing to energy security, but also posing a potential threat to human, environmental, and political security. The aim of this paper is to integrate the four fields of security: health, environment, energy, and political by analysing awareness, preparedness responsibility and decision making related to nuclear installations. With increasing political, economical, cultural and physical (in term of energy infrastructure) integration, the region needs to take a comprehensive approach to create adequate structure for managing risks and thereby promote security. (authors)

  1. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-09-01

    This is the final report on the INSP project entitled, ``Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant.

  2. Environmental Assessment of Installation Development at MacDill Air Force Base, Florida

    Science.gov (United States)

    2013-04-18

    potential for wildfires. Remnant natural forest communities on the installation consist of longleaf pine (Pinus palustris) and mixed hardwood species...installation. Both the bald eagle and the burrowing owl are residents on MacDill AFB (MAFB 2010a). The installation contains a few relic longleaf pines ...occidentalis NL SSC Common along waterfront and mangrove areas Red- cockaded woodpecker Picoides borealis E T Prefers longleaf pine stands

  3. Structural damage detection using sparse sensors installation by optimization procedure based on the modal flexibility matrix

    Science.gov (United States)

    Zare Hosseinzadeh, A.; Ghodrati Amiri, G.; Seyed Razzaghi, S. A.; Koo, K. Y.; Sung, S. H.

    2016-10-01

    This paper is aimed at presenting a novel and effective method to detect and estimate structural damage by introducing an efficient objective function which is based on Modal Assurance Criterion (MAC) and modal flexibility matrix. The main strategy in the proposed objective function relies on searching a geometrical correlation between two vectors. Democratic Particle Swarm Optimization (DPSO) algorithm, a modified version of original PSO approach, is used to minimize the objective function resulting in the assessment of damage in different structure types. Finally, the presented method is generalized for a condition in which a limited number of sensors are installed on the structure using Neumann Series Expansion-based Model Reduction (NSEMR) approach. To evaluate the efficiency of the proposed method, different damage patterns in three numerical examples of engineering structures are simulated and the proposed method is employed for damage identification. Moreover, the stability of the method is investigated by considering the effects of a number of important challenges such as effects of different locations for sensor installation, prevalent modeling errors and presence of random noises in the input data. It is followed by different comparative studies to evaluate not only the robustness of the proposed method, but also the necessity of using introduced techniques for problem solution. Finally, the applicability of the presented method in real conditions is also verified by an experimental study of a five-story shear frame on a shaking table utilizing only three sensors. All of the obtained results demonstrate that the proposed method precisely identifies damages by using only the first several modes' data, even when incomplete noisy modal data are considered as input data.

  4. Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Fessenheim - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  5. Studies of the generation mechanisms of steady vortex formations in the channels of nuclear-power installations for purposes of improving the reliability and safety of their work

    Science.gov (United States)

    Mitrofanova, O.

    2017-01-01

    The analysis of the results of experimental researches on revealing the mechanisms of vortex formation in channels of complex geometry in the neutral and conductive media is carried out. The directions of researches related to the study of mechanisms of vortex generation and accumulation of energy by large-scale vortex structures are considered for the possibility of predictions of the man-made accidents and catastrophic natural phenomena. The main goal of ongoing investigations is the solution of the task aimed at improving the safety of nuclear power installations and, in particular, of the fast neutron reactors with liquid-metal coolants, and the prevention of emergency modes arising from acoustic, magnetic and hydrodynamic resonance effects.

  6. Installation of Reactor Vessel in AP1000 Nuclear Unit%AP1000核电机组反应堆压力容器的安装

    Institute of Scientific and Technical Information of China (English)

    许跃武; 高宝宁

    2012-01-01

    Hoisting orientation, rotation and location adjustment of reactor vessel in Sanmen Power Unit 1 were illustrated. By calculating the hoisting height, weight and the wind load, analyzed the safety of "open top" way on lifting reactor vessel. The methods to measure and adjust the location, levelness and elevation were also introduced, which after reactor vessel in place. Furthermore, the installation of supports and keeper plates were discussed. It supply reference value for the same nuclear plant in the hoisting and installation of main components.%阐述了某核电1号机组反应堆压力容器吊装定位、筒体翻转和就位调整的过程.通过对吊装高度、重量及风载荷进行计算,分析“开顶法”吊装反应堆压力容器的安全性.介绍了反应堆压力容器就位后方位、水平度、标高的测量与调整方法,以及护板、支撑的安装.对同类核电站的主设备吊装具有一定参考价值.

  7. Study of a brazilian cask and its installation for PWR spent nuclear fuel dry storage; Estudo de um casco nacional e sua instalacao para armazenagem seca de combustivel nuclear queimado gerado em reatores PWR

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio

    2009-07-01

    Spent nuclear fuel (SNF) is removed from the nuclear reactor after the depletion on efficiency in generating energy. After the withdrawal from the reactor core, the SNF is temporarily stored in pools at the same site of the reactor. At this time, the generated heat and the short and medium lived radioactive elements decay to levels that allow removing SNF from the pool and sending it to temporary dry storage. In that phase, the fuel needs to be safely and efficiently stored, and then, it can be retrieved in a future, or can be disposed as radioactive waste. The amount of spent fuel increases annually and, in the next years, will still increase more, because of the construction of new nuclear plants. Today, the number of new facilities back up to levels of the 1970's, since it is greater than the amount of decommissioning in old installations. As no final decision on the back-end of the nuclear fuel cycle is foreseen in the near future in Brazil, either to recover the SNF or to consider it as radioactive waste, this material has to be isolated in some type of storage model existing around the world. In the present study it is shown that dry SNF storage is the best option. A national cask model for SNF as well these casks storage installation are proposed. It is a multidisciplinary study in which the engineering conceptual task was developed and may be applied to national SNF removed from the Brazilian power reactors, to be safely stored for a long time until the Brazilian authorities will decide about the site for final disposal. (author)

  8. Decision no. 2011-DC-0219 of the French nuclear safety authority from May 5, 2011, ordering the SOCATRI company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0219 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a SOCATRI de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the SOCATRI company, operator of the nuclear dismantling and waste processing plants of the Tricastin site (France). (J.S.)

  9. Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants

    Energy Technology Data Exchange (ETDEWEB)

    Mays, Gary T [ORNL; Belles, Randy [ORNL; Cetiner, Sacit M [ORNL; Howard, Rob L [ORNL; Liu, Cheng [ORNL; Mueller, Don [ORNL; Omitaomu, Olufemi A [ORNL; Peterson, Steven K [ORNL; Scaglione, John M [ORNL

    2012-06-01

    The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs). This research project is aimed at providing methodologies, information, and insights that inform the process for determining and optimizing candidate areas for new advanced nuclear power generation plants and consolidated ISFSIs to meet projected US electric power demands for the future.

  10. Decision no. 2011-DC-0213 of the French nuclear safety authority from May 5, 2011, ordering Electricite de France (EDF) company to proceed to a complementary safety evaluation of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0213 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a Electricite de France (EDF) de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to Electricite de France (EDF) company, operator of the French NPPs. (J.S.)

  11. Decision no. 2011-DC-0222 of the French nuclear safety authority from May 5, 2011, ordering the Comurhex company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0222 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a Comurhex de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to Comurhex company, operator of the Tricastin uranium conversion plant (France). (J.S.)

  12. Decision no. 2011-DC-0218 of the French nuclear safety authority from May 5, 2011, ordering the EURODIF SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0218 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a EURODIF SA de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the EURODIF SA company, operator of the George Besse I uranium enrichment plant of the Tricastin site (France). (J.S.)

  13. Decision no. 2011-DC-0214 of the French nuclear safety authority from May 5, 2011, ordering CIS bio international company to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0214 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a CIS bio international de proceder a une evaluation complementaire de la surete de son installation nucleaire de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to CIS bio international company, operator of the radiopharmaceuticals fabrication facility (INB 29) of Saclay (France). (J.S.)

  14. Decision no. 2011-DC-0215 of the French nuclear safety authority from May 5, 2011, ordering ITER Organization to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0215 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a ITER ORGANIZATION de proceder a une evaluation complementaire de la surete de son installation nucleaire de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the ITER Organization, operator of the ITER tokamak facility of Cadarache (France). (J.S.)

  15. Decision no. 2011-DC-0224 of the French nuclear safety authority from May 5, 2011, ordering the French atomic energy and alternative energies commission (CEA) to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0224 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant au Commissariat a l'Energie Atomique et aux energies alternatives (CEA) de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the French atomic energy commission (CEA). (J.S.)

  16. Decision no. 2011-DC-0220 of the French nuclear safety authority from May 5, 2011, ordering the FBFC company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0220 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a FBFC de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the FBFC (Franco-Belge de Fabrication du Combustible), a daughter fuel fabrication company of Areva NC (France). (J.S.)

  17. Decision no. 2011-DC-0216 of the French nuclear safety authority from May 5, 2011, ordering the Laue Langevin Institute to proceed to a complementary safety evaluation of its basic nuclear facility (high flux reactor - INB no. 67) in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0216 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a l'Institut Laue Langevin (ILL) de proceder a une evaluation complementaire de la surete de son installation nucleaire de base (Reacteur a Haut Flux - INB n.67) au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the Laue Langevin Institute, operator of the high flux research reactor (RHF) of Grenoble (France). (J.S.)

  18. Decision no. 2011-DC-0221 of the French nuclear safety authority from May 5, 2011, ordering the SET company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0221 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a la SET de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the SET company, operator of the Georges Besse II and RECII uranium enrichment plants of the Tricastin site (France). (J.S.)

  19. Decision no. 2011-DC-0217 of the French nuclear safety authority from May 5, 2011, ordering the AREVA NC group to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0217 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a AREVA NC de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the AREVA NC group. (J.S.)

  20. Decision no. 2011-DC-0223 of the French nuclear safety authority from May 5, 2011, ordering the MELOX SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0223 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a MELOX SA de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to MELOX SA company, operator of the Melox MOX fuel fabrication plant of Marcoule (France). (J.S.)

  1. Decree no. 2002-447 of the 27 march 2002 authorizing the Normandy society of preserve and sterilization to realize definitive shutdowns and dismantling operations of the nuclear installation no. 152 situated on the territory of Osmanville (Calvados); Decret no. 2002-447 du 27 mars 2002 autorisant le Societe normande de conserve et sterilisation a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no. 152 situee sur le territoire de la commune d'Osmanville (Calvados)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The decree presents the shutdown preliminary obligations, the installation quality, the prevention of radioactivity dissemination risk, the workers protection, the wastes management, the fire prevention. (A.L.B.)

  2. Characterization and disposal of ion exchange resins used in nuclear installations; Caracterizacion y disposicion de resinas de intercambio ionico utilizadas en instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Flores E, R.M.; Ortiz O, H.B.; Olguin G, M.T.; Emeterio H, M.; Garcia M, H. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2006-07-01

    To dispose of an appropriate way the used ion exchange resins so much in the pool water purification systems of the TRIGA Mark III reactor like in the JS6500 gamma irradiator, of the National Institute of Nuclear Research, were carried out a series of analytic nuclear techniques and complementary conventional to those recommended by the ASTM, with the object of to control and to manage 14 lots of worn out resins appropriately. For its were identified the radioactive isotopes, the resins type, the grade of chemical pollution and the physicochemical degradation of the same ones. The lots of resins that didn't contain radioactive isotopes its were regenerated in an usual way, as long as those that if they controlled them they selected options for its final disposition. The first selected option was the extraction method of ion radioactive isotopes, concentrating the elution product by evaporation. As second option it was carried out the resins stabilization damaged by micro-encapsulation by forged to ambient temperature, using an organic polymer. Previous to the immobilization the resins were pretreated by vacuum drying, pulverization and thermal drying, however before carrying out this last, it was carried out a thermal gravimetric analysis to determine the drying conditions of the resins avoiding its chemical decomposition. (Author)

  3. Ground-based Nuclear Detonation Detection (GNDD) Technology Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Casey, Leslie A.

    2014-01-13

    This GNDD Technology Roadmap is intended to provide guidance to potential researchers and help management define research priorities to achieve technology advancements for ground-based nuclear explosion monitoring science being pursued by the Ground-based Nuclear Detonation Detection (GNDD) Team within the Office of Nuclear Detonation Detection in the National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE). Four science-based elements were selected to encompass the entire scope of nuclear monitoring research and development (R&D) necessary to facilitate breakthrough scientific results, as well as deliver impactful products. Promising future R&D is delineated including dual use associated with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Important research themes as well as associated metrics are identified along with a progression of accomplishments, represented by a selected bibliography, that are precursors to major improvements to nuclear explosion monitoring.

  4. Investigation of stillbirth risk among the offspring of male radiation workers at the Sellafield nuclear installation, west Cumbria

    Energy Technology Data Exchange (ETDEWEB)

    Pearce, M.S

    2000-04-01

    Ionising radiation is a known mutagen, much of the evidence coming from studies on animals, and from studies of occupationally exposed workforces and those exposed after the atomic bombings of Hiroshima and Nagasaki. However, few studies have examined transgenerational effects of paternal exposure in humans. The workforce at the Sellafield nuclear reprocessing plant in west Cumbria, is the most highly exposed such workforce in Western Europe and North America. This epidemiological investigation set out to determine whether there was evidence of an association between stillbirth risk and paternal preconceptional exposure to external ionising radiation or internal radionuclides. Logistic regression was used to analyse the relationship between stillbirth risk and paternal preconceptional irradiation (ppi). Further modelling of the risk of stillbirth in relation to ppi was carried out using overdispersion and variance components models. The form of doseresponse was investigated using both threshold and broken-stick models, in addition to varying the power function of the dose term. To assess the effect of errors in the dose estimates for the immediate preconceptional period resulting from the derivation of doses for short intervals pro rata from annual dose summaries, a nested case-control study was also carried out. This used more precise estimates of external doses estimated directly from monthly film badges and internal doses from special dose assessments, which were very time consuming to collate and would have taken several years to compile for the entire workforce. A significant positive association was found between the risk of a child being stillborn and total external ppi (adjusted odds ratio per 100 mSv, 1.25 95% CI 1.04-1.46, p=0.019). The risk was higher for stillbirths with congenital anomaly and was highest for the nine stillbirths with neural tube defects, eight of which were anencephalic, the other spina bifida. Although, the possibility of an

  5. Virtual reality technology used to estimate radiation doses in nuclear installations; Utilizacao de ambientes virtuais na estimativa de dose de radiacao em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Augusto, Silas Cordeiro

    2008-03-15

    The physical integrity of people when walking in places subjected to radiation can be preserved by following some rules. Among these rules are safe limits of radiation level, proximity of radiation sources, time of exposition to radiation sources, and a combination of these factors. In this way, previous training and simulations of operation proceedings to be executed in places subjected to radiation help to better prepare the course in such places, minimizing the absorbed dose. On the other hand, virtual reality is a technology applicable in several areas, enabling the training and simulation of real places and hypothetical scenarios, with a good level of realism, but without danger if compared to the same activities in the real world. As a virtual environment does not presents any health risks, it is possible to train workers beforehand to several operation or maintenance scenarios. In this virtual environment, the dose tax distribution can be visualized, and the dose absorbed by the worker, represented and simulated in the virtual environment by a virtual character (avatar) can be shown. Therefore, the tasks to be done can be better planned, evaluating the workers actions and the performance so to reduce failures and health risks. Finally, this work presents a tool to build and navigate in virtual environments, enabling the training of activities in nuclear facilities. To that end is proposed a methodology to modify and adapt a free game engine. (author)

  6. Installing Omeka

    Directory of Open Access Journals (Sweden)

    Jonathan Reeve

    2016-07-01

    Full Text Available Omeka.net is a useful service for Omeka beginners, but there are a few reasons why you might want to install your own copy of Omeka. Reasons include: * Upgrades. By installing Omeka yourself, you can use the latest versions of Omeka as soon as they’re released, without having to wait for Omeka.net to upgrade their system. * Plugins and themes. You can install any plugin or theme you want, without being restricted to those provided by Omeka.net. * Customizations. You can buy a custom domain name, and customize your code to achieve your desired functionality. * Control. You have control over your own backups, and you can update the server yourself so that its security is always up-to-date. * Price. There are many low-cost Virtual Private Servers (VPSs now, some of which cost only $5 per month. * Storage. Many shared hosting providers now offer unlimited storage. This is useful if you have a large media library. In this tutorial, we’ll be entering a few commands on the command line. This tutorial assumes no prior knowledge of the command line, but if you want a concise primer, consult the Programming Historian introduction to BASH. There are other ways of installing Omeka, of course, some using exclusively GUI tools. Some hosting providers even offer “one-click installs” via their control panels. Many of those methods, however, will install older versions of Omeka which are then harder to upgrade and maintain. The method outlined below may not be the easiest way to install Omeka, but it will give you some good practice with using the command line, which is a skill that will be useful if you want to manually upgrade your install, or manually install other web frameworks. (For example, this installation method is very similar to WordPress’s “Five-Minute Install”. There are four steps to this process, and it should take about an hour.

  7. Probes for inspections of heat exchanges installed at nuclear power plants type PWR by eddy current method; Sondas para inspecao de trocadores de calor instalados em usinas nucleares tipo PWR pelo metodo de correntes parasitas

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Alonso F.O. [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Dept. de Enghenharia Mecanica]. E-mail: kauzz21@yahoo.com; Alencar, Donizete A. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mail: daa@cdtn.br

    2007-07-01

    From all non destructive examination methods usable to perform integrity evaluation of critical equipment installed at nuclear power plants (NPP), eddy current test (ET) may be considered the most important one, when examining heat exchangers. For its application, special probes and reference calibration standards are employed. In pressurized water reactor (PWR) NPPs, a particularly critical equipment is the steam generator (SG), a huge heat exchanger that contains thousands of U-bend thin wall tubes. Due to its severe working conditions (pressure and temperature), that component is periodically examined by means of ET. In this paper a revision of the operating fundamentals of the main ET probes, used to perform SG inspections is presented. (author)

  8. Post-Fukushima additional safety assessments: behaviour of French nuclear installations in case of extreme situations and relevance of improvement propositions; Evaluations complementaires de surete post-Fukushima: comportement des installations nucleaires francaises en cas de situations extremes et pertinence des propositions d'ameliorations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    After the Fukushima accident, additional safety assessments (ECS, evaluation complementaire de securite) have been commissioned to assess the resistance of French nuclear installations to extreme scenarios (earthquake, loss of electricity supply, and loss of cooling sources). This report is a synthesis of a more important one. It briefly describes the international context and notices that, in foreign countries, only power reactors are submitted to such additional safety assessments. It describes the approach adopted by the IRSN by considering that severe accidental situation are possible and may have characteristics exceeding the current referential. This approach enables the identification of safety functions which must maintained in these situations, and of some limitations of the current safety referential. The report then discusses the current status of installations, notices that actions are to be performed. It comments the results obtained in terms of installation robustness with respect to risks of earthquake or flooding, or those associated with other external hazards. It comments the analysis performed in case of total loss of cooling sources or of energy supplies in power reactors, in the EPR, and in some other nuclear installations (ILL, CEA's installations, AREVA's laboratories and factories). It finally comments the ability of operators in managing a crisis situation under these conditions, and briefly evokes the subcontracting issue

  9. An interactive audio-visual installation using ubiquitous hardware and web-based software deployment

    Directory of Open Access Journals (Sweden)

    Tiago Fernandes Tavares

    2015-05-01

    Full Text Available This paper describes an interactive audio-visual musical installation, namely MOTUS, that aims at being deployed using low-cost hardware and software. This was achieved by writing the software as a web application and using only hardware pieces that are built-in most modern personal computers. This scenario implies in specific technical restrictions, which leads to solutions combining both technical and artistic aspects of the installation. The resulting system is versatile and can be freely used from any computer with Internet access. Spontaneous feedback from the audience has shown that the provided experience is interesting and engaging, regardless of the use of minimal hardware.

  10. Capacitor-based detection of nuclear magnetization: nuclear quadrupole resonance of surfaces.

    Science.gov (United States)

    Gregorovič, Alan; Apih, Tomaž; Kvasić, Ivan; Lužnik, Janko; Pirnat, Janez; Trontelj, Zvonko; Strle, Drago; Muševič, Igor

    2011-03-01

    We demonstrate excitation and detection of nuclear magnetization in a nuclear quadrupole resonance (NQR) experiment with a parallel plate capacitor, where the sample is located between the two capacitor plates and not in a coil as usually. While the sensitivity of this capacitor-based detection is found lower compared to an optimal coil-based detection of the same amount of sample, it becomes comparable in the case of very thin samples and even advantageous in the proximity of conducting bodies. This capacitor-based setup may find its application in acquisition of NQR signals from the surface layers on conducting bodies or in a portable tightly integrated nuclear magnetic resonance sensor.

  11. Independent technical support for the frozen soil barrier installation and operation at the Fukushima Daiichi Nuclear Power Station (F1 Site)

    Energy Technology Data Exchange (ETDEWEB)

    Looney, Brian B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jackson, Dennis G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Christian D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-02-23

    TEPCO is implementing a number of water countermeasures to limit the releases and impacts of contaminated water to the surrounding environment. The diverse countermeasures work together in an integrated manner to provide different types, and several levels, of protection. In general, the strategy represents a comprehensive example of a “defense in depth” concept that is used for nuclear facilities around the world. One of the key countermeasures is a frozen soil barrier encircling the damaged reactor facilities. The frozen barrier is intended to limit the flow of water into the area and provide TEPCO the ability to reduce the amount of contaminated water that requires treatment and storage. The National Laboratory team supports the selection of artificial ground freezing and the incorporation of the frozen soil barrier in the contaminated water countermeasures -- the technical characteristics of a frozen barrier are relatively well suited to the Fukushima-specific conditions and the need for inflow reduction. Further, our independent review generally supports the TEPCO/Kajima design, installation strategy and operation plan.

  12. Installation Restoration Program Records Search for Richards-Gebaur Air Force Base, Missouri.

    Science.gov (United States)

    1983-03-01

    ingestion, inhalation, or assimilation into any organism, either directly from the environment or indirectly by ingestion through food chains, will or...Years at No. Organization Area of Knowledge Installation 25 ETM Tool Manufacturing 2 26 Retired AF Civil Engieneering 26 27 Transferred AF Civil

  13. 16 CFR Appendix I to Part 1402 - Recommended Outline for Instruction Booklet on “How To Safely Install Your CB Base Station Antenna”

    Science.gov (United States)

    2010-01-01

    ... on âHow To Safely Install Your CB Base Station Antennaâ I Appendix I to Part 1402 Commercial... ANTENNAS, TV ANTENNAS, AND SUPPORTING STRUCTURES Pt. 1402, App. I Appendix I to Part 1402—Recommended Outline for Instruction Booklet on “How To Safely Install Your CB Base Station Antenna” I....

  14. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination....... In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-01-01

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

  16. Environmental Assessment of Installation Development at Fairchild Air Force Base, Washington

    Science.gov (United States)

    2012-12-01

    would be used to provide an attractive and professional-looking installation and would include plants, shrubs, and trees to blend with the surrounding...atmospheric transport, precipitation, surface runoff and flow, and subsurface flow. Hydrology is affected by climatic factors such as temperature , wind... termites , carpenter bees, ants, spiders, bees, wasps, mice, ground squirrels, moles, and voles (FAFB 2011). Protected and Sensitive Species. Developed

  17. Instructions for Installing digiBASE Plug-in on a Terra Harvest Controller

    Science.gov (United States)

    2015-03-01

    The Battlefield Information Processing Branch of the US Army Research Laboratory developed a Terra Harvest / Open Standards for Unattended Sensors (OSUS...installation and configuration of the plug-in on a Terra Harvest controller. 15. SUBJECT TERMS Terra Harvest controller, open standards for unattended...Sample Terra Harvest Observations 9 List of Symbols, Abbreviations, and Acronyms 13 Distribution List 14 iv List of Figures Fig. 1 System

  18. Nacelle Chine Installation Based on Wind-Tunnel Test Using Efficient Global Optimization

    Science.gov (United States)

    Kanazaki, Masahiro; Yokokawa, Yuzuru; Murayama, Mitsuhiro; Ito, Takeshi; Jeong, Shinkyu; Yamamoto, Kazuomi

    Design exploration of a nacelle chine installation was carried out. The nacelle chine improves stall performance when deploying multi-element high-lift devices. This study proposes an efficient design process using a Kriging surrogate model to determine the nacelle chine installation point in wind-tunnel tests. The design exploration was conducted in a wind-tunnel using the JAXA high-lift aircraft model at the JAXA Large-scale Low-speed Wind Tunnel. The objective was to maximize the maximum lift. The chine installation points were designed on the engine nacelle in the axial and chord-wise direction, while the geometry of the chine was fixed. In the design process, efficient global optimization (EGO) which includes Kriging model and genetic algorithm (GA) was employed. This method makes it possible both to improve the accuracy of the response surface and to explore the global optimum efficiently. Detailed observations of flowfields using the Particle Image Velocimetry method confirmed the chine effect and design results.

  19. A Discrepancy-Based Methodology for Nuclear Training Program Evaluation.

    Science.gov (United States)

    Cantor, Jeffrey A.

    1991-01-01

    A three-phase comprehensive process for commercial nuclear power training program evaluation is presented. The discrepancy-based methodology was developed after the Three Mile Island nuclear reactor accident. It facilitates analysis of program components to identify discrepancies among program specifications, actual outcomes, and industry…

  20. MOX - TDB : Nuclear Thermodynamic DataBase

    OpenAIRE

    Cheynet, Bertrand

    2006-01-01

    37 pages; A thermodynamic database collecting critical assessments made for nuclear applications has been built since 2003 for the MOX fuel. MOX-TDB is a thermodynamic database for in-vessel applications coontaining : Ba-Fe-La-O-Pu-Ru-Sr-U-Zr + Ar-H. This database covers the entire field from metal to oxide domains.

  1. The dismantling of nuclear installations and the radioactive wastes management. Report of the President of the Republic followed by the answers of concerned administrations and organisms; Le demantelement des installations nucleaires et la gestion des dechets radioactifs. Rapport au President de la Republique suivi des reponses des administrations et des organismes interesses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    The discussed subjects concerns the situation and the challenges of the nuclear installations dismantling and the radioactive wastes management (main intervenors, panorama of the situation, rules applied to the dismantling and the radioactive wastes), the first experiences of dismantling and radioactive wastes disposal (experiences at the CEA and EDF, implementing of solutions for the disposal), interrogations and certainties (provision for future expenses, public information). (A.L.B.00.

  2. Designing a nuclear data base prototype using Oracle and Prolog

    Energy Technology Data Exchange (ETDEWEB)

    Paviotti-Corcuera, R.; Ford, C.E.; Perez, R.B.

    1988-11-01

    An ever-increasing demand exists for easily accessible nuclear data base systems. The purpose of this work is to analyze the feasibility of using artificial intelligence methods as tools to provide the necessary functionality to extract information from nuclear data files in a user-friendly manner. For the prototype of this work, a sample of data that can be later enlarged to a complete, evaluated nuclear data base has been used. To implement this prototype, two approaches have been followed: a conventional approach using the commercially available Oracle relational data base management system; and an artificial intelligence approach using the Prolog programming language. This prototypic work shows the feasibility of applying artificial intelligence methods to data bases, and represents a first step toward development of intelligent nuclear data base systems. The characteristics of the query language from both approaches make the second one preferable from a user's point of view. 23 refs., 7 tabs.

  3. RESULTS FROM A DEMONSTRATION OF RF-BASED UF6 CYLINDER ACCOUNTING AND TRACKING SYSTEM INSTALLED AT A USEC FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, Chris A [ORNL; Kovacic, Donald N [ORNL; Morgan, Jim [Innovative Solutions; Younkin, James R [ORNL; Carrick, Bernie [USEC, Inc.; Ken, Whittle [USEC, Inc.; Johns, R E [Pacific Northwest National Laboratory (PNNL)

    2008-09-01

    Approved industry-standard cylinders are used globally for storing and transporting uranium hexafluoride (UF{sub 6}) at uranium enrichment plants and processing facilities. To verify that no diversion or undeclared production of nuclear material involving UF{sub 6} cylinders at the facility has occurred, the International Atomic Energy Agency (IAEA) conducts periodic, labor-intensive physical inspections to validate facility records, cylinder identities, and cylinder weights. A reliable cylinder monitoring system that would improve overall inspector effectiveness would be a significant improvement to the current international safeguards inspection regime. Such a system could include real-time unattended monitoring of cylinder movements, situation-specific rules-based event detection algorithms, and the capability to integrate with other types of safeguards technologies. This type of system could provide timely detection of abnormal operational activities that may be used to ensure more appropriate and efficient responses by the IAEA. A system of this type can reduce the reliance on paper records and have the additional benefit of facilitating domestic safeguards at the facilities at which it is installed. A radio-frequency (RF)-based system designed to track uranium hexafluoride (UF{sub 6}) cylinders during processing operations was designed, assembled, and tested at the United States Enrichment Corporation (USEC) facility in Portsmouth, Ohio, to determine the operational feasibility and durability of RF technology. The overall objective of the effort was to validate the robustness of RF technology for potential use as a future international safeguards tool for tracking UF6 cylinders at uranium-processing facilities. The results to date indicate that RF tags represent a feasible technique for tracking UF{sub 6} cylinders in operating facilities. Additional work will be needed to improve the operational robustness of the tags for repeated autoclave processing and to

  4. Ship-Based Nuclear Energy Systems for Accelerating Developing World Socioeconomic Advance

    Science.gov (United States)

    Petroski, Robert; Wood, Lowell

    2014-07-01

    Technological, economic, and policy aspects of supplying energy to newly industrializing and developing countries using ship-deployed nuclear energy systems are described. The approach analyzed comprises nuclear installations of up to gigawatt scale deployed within currently mass-produced large ship hulls which are capable of flexibly supplying energy for electricity, water desalination and district heating-&-cooling with low latencies and minimized shoreside capital expenditures. Nuclear energy is uniquely suited for mobile deployment due to its combination of extraordinary energy density and high power density, which enable enormous supplies of energy to be deployed at extremely low marginal costs. Nuclear installations on ships also confer technological advantages by essentially eliminating risk from earthquakes, tsunamis, and floods; taking advantage of assured access to an effectively unlimited amount of cooling water, and involving minimal onshore preparations and commitments. Instances of floating nuclear power stations that have been proposed in the past, some of which are currently being pursued, have generally been based on conventional LWR technology, moreover without flexibility or completeness of power output options. We consider nuclear technology options for their applicability to the unique opportunities and challenges of a marine environment, with special attention given to low-pressure, high thermal margin systems with continuous and assured afterheat dissipation into the ambient seawater. Such systems appear promising for offering an exceptionally high degree of safety while using a maximally simple set of components. We furthermore consider systems tailored to Developing World contexts, which satisfy societal requirements beyond electrification, e.g., flexible sourcing of potable water and HVAC services, servicing time-varying user requirements, and compatibility with the full spectrum of local renewable energy supplies, specifically including

  5. Installation Restoration Program. Phase 1: Records Search, Pope Air Force Base, North Carolina

    Science.gov (United States)

    1985-05-01

    were noted. During the "energy crisis" in 1973-1974 the fuel usage dropped to 50 to 100 gallons per fire. However, it soon rose to the present 300 to... AVAILABILTY AND/OR SPECIAL DATE ACCESSIONED • ( CO.PY DISTRIBUTION STAMP INSPECTED 4 DATE RETURNED 90 09 113 018 DATE RECEIVED LN DTIC REGISTERED OR...Installation Hazardous Waste Activity Review 4-1 Industrial Operations (Shops) 4-2 Waste Accumulation and Storage Areas 4-14 Fuels Management 4-14 Spills and

  6. Measurement-Based Evaluation of Installed Filtration System Performance in Single-Family Homes

    Energy Technology Data Exchange (ETDEWEB)

    Chan, Wanyu Rengie; Singer, Brett C.

    2014-04-03

    This guide discusses important study design issues to consider when conducting an on-site evaluation of filtration system performance. The two most important dichotomies to consider in developing a study protocol are (1) whether systems are being evaluated in occupied or unoccupied homes and (2) whether different systems are being compared in the same homes or if the comparison is between systems installed in different homes. This document provides perspective and recommendations about a suite of implementation issues including the choice of particle measurement devices, selection of sampling locations, ways to control and/or monitor factors and processes that can impact particle concentrations, and data analysis approaches.

  7. Installation of potable water supply and heat supply at base of subsoil water

    Directory of Open Access Journals (Sweden)

    Denysova Alla Evseevna

    2016-01-01

    Full Text Available Removal of groundwater with further use of it for potable water supply and heat supply with the use of heat pump is an important problem. A new revolutionary approach to the decision of energy and water saving that provides rational accommodation of groundwater boreholes ensuring the required flow rate of water through the heat pump evaporator with simultaneously high intensity of heat exchange process is proposed. The method of calculation which allows determining the necessary depth of borehole, quantity of boreholes, in consideration of flow rate and temperature of subsoil water determining capacity of heat pump installation is worked out.

  8. Nuclear Safety Design Base for License Application

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-09-29

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111(b) [DIRS 173273] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113(b) and (c) [DIRS 173273] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period.

  9. NRV web knowledge base on low-energy nuclear physics

    Science.gov (United States)

    Karpov, V.; Denikin, A. S.; Alekseev, A. P.; Zagrebaev, V. I.; Rachkov, V. A.; Naumenko, M. A.; Saiko, V. V.

    2016-09-01

    Principles underlying the organization and operation of the NRV web knowledge base on low-energy nuclear physics (http://nrv.jinr.ru) are described. This base includes a vast body of digitized experimental data on the properties of nuclei and on cross sections for nuclear reactions that is combined with a wide set of interconnected computer programs for simulating complex nuclear dynamics, which work directly in the browser of a remote user. Also, the current situation in the realms of application of network information technologies in nuclear physics is surveyed. The potential of the NRV knowledge base is illustrated in detail by applying it to the example of an analysis of the fusion of nuclei that is followed by the decay of the excited compound nucleus formed.

  10. 3D Projection Installations

    DEFF Research Database (Denmark)

    Halskov, Kim; Johansen, Stine Liv; Bach Mikkelsen, Michelle

    2014-01-01

    Three-dimensional projection installations are particular kinds of augmented spaces in which a digital 3-D model is projected onto a physical three-dimensional object, thereby fusing the digital content and the physical object. Based on interaction design research and media studies, this article...... contributes to the understanding of the distinctive characteristics of such a new medium, and identifies three strategies for designing 3-D projection installations: establishing space; interplay between the digital and the physical; and transformation of materiality. The principal empirical case, From...... Fingerplan to Loop City, is a 3-D projection installation presenting the history and future of city planning for the Copenhagen area in Denmark. The installation was presented as part of the 12th Architecture Biennale in Venice in 2010....

  11. Statistical analysis of electromagnetic radiation measurements in the vicinity of GSM/UMTS base station installed on buildings in Serbia.

    Science.gov (United States)

    Koprivica, Mladen; Slavkovic, Vladimir; Neskovic, Natasa; Neskovic, Aleksandar

    2016-03-01

    As a result of dense deployment of public mobile base stations, additional electromagnetic (EM) radiation occurs in the modern human environment. At the same time, public concern about the exposure to EM radiation emitted by such sources has increased. In order to determine the level of radio frequency radiation generated by base stations, extensive EM field strength measurements were carried out for 664 base station locations, from which 276 locations refer to the case of base stations with antenna system installed on buildings. Having in mind the large percentage (42 %) of locations with installations on buildings, as well as the inevitable presence of people in their vicinity, a detailed analysis of this location category was performed. Measurement results showed that the maximum recorded value of total electric field strength has exceeded International Commission on Non-Ionizing Radiation Protection general public exposure reference levels at 2.5 % of locations and Serbian national reference levels at 15.6 % of locations. It should be emphasised that the values exceeding the reference levels were observed only outdoor, while in indoor total electric field strength in no case exceeded the defined reference levels.

  12. Optimum repair-level analysis (ORLA) and life cycle cost (LCC) models for the base and installation security system (BISS)

    Energy Technology Data Exchange (ETDEWEB)

    York, A.A.; Chipchak, J.S.

    1979-03-01

    Models for Optimum Repair-Level Analysis (ORLA) and Life Cycle Cost (LCC) analysis for Base and Installation Security System (BISS) equipment are described. The ORLA model determines the costs of alternative maintenance approaches for selection of the most economic maintenance approach. The LCC model determines the total cost to the Government for the development, acquisition, initial logistics support, and recurring support of a system over the projected inventory usage period. A unique feature of these models is the marriage of ORLA and ICC which enables LCC to utilize completely the most economic ORLA decision costs. This significantly reduces the overall LCC effort.

  13. Analysis and discussion on reports of additional safety assessment of nuclear installations with respect to the Fukushima accident; Analyse et commentaire des rapports d'evaluation complementaire de la surete des installations nucleaires au regard de l'accident de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Sene, Monique; Sene, Raymond

    2011-11-15

    This document proposes an analysis of the reports made by the different operators of nuclear installations within the frame of a safety audit of the French nuclear installations with respect to the Fukushima accident. Operators (mainly AREVA, the CEA and EDF) were asked to perform additional safety assessments. In a first part, the conclusions of EDF reports are analysed regarding the seismic risk, the flooding risk, the situation of some specific sites (Fessenheim, Tricastin), other phenomena (rains, winds), loss of electricity supplies and of cooling systems, severe accidents, hydrogen issue, chemical hazards, subcontractors, crisis management. Conclusions of AREVA reports are analysed for the different sites (Tricastin, La Hague, MELOX factory, Romans factory). Conclusions of CEA reports are analysed for the different concerned installations (ATPu, Masurca, Osiris, Phenix, Jules Horowitz reactor). A second part proposes a global analysis of EDF's additional safety assessment reports regarding earthquake, flooding, other extreme natural phenomena, loss of electricity supplies and cooling system, subcontracting conditions, crisis management, and radiation protection organisation. AREVA's and CEA's reports are then analysed in terms of report structure and content, and for the different concerned sites

  14. Demonstration of the 3D PANTHERE software for the simulation of gamma dose rates for complex nuclear installations; Demonstration du logiciel 3D panthere pour la simulation des debits de doses gamma pour installations nucleaires complexes

    Energy Technology Data Exchange (ETDEWEB)

    Longeot, M.; Dupont, B. [EDFISEPTENITE, 12-14 avenue Dutrievoz, 69628 Villeurbanne Cedex (France); Schumm, A.; Zweers, M. [EDF/R and D/SINETICS, 1 avenue du General de Gaulle, 92141 Clamart Cedex (France); Malvagi, F.; Trama, J.C. [CEA Saclay, SERMA, 91 - Gif-sur-Yvette (France)

    2010-07-01

    The authors present the two successive versions of the PANTHERE simulation software developed by EDF-SEPTEN to determine gamma dose flow rate in complex industrial installations. This software predicts dose rates and thus enables interventions in irradiating environment to be optimized. The authors report the demonstration of the industrial version (PANTHEREv1) and of the currently under development version (PANTHEREv2). They outline the evolutions brought to the first version to develop the second one such as the direct importation of CAD models, ergonomic improvements, etc.

  15. Sub-Critical Nuclear Reactor Based on FFAG-Accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hee Seok; Kang, Hung Sik; Lee, Tae Yeon [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)

    2011-10-15

    After the East-Japan earthquake and the subsequent nuclear disaster, the anti-nuclear mood has been wide spread. It is very unfortunate both for nuclear science community and for the future of mankind, which is threatened by two serious challenges, the global warming caused by the greenhouse effect and the shortage of energy cause by the petroleum exhaustion. While the nuclear energy seemed to be the only solution to these problems, it is clear that it has its own problems, one of which broke out so strikingly in Japan. There are also other problems such as the radiotoxic nuclear wastes that survive up to even tens of thousands years and the limited reserves of Uranium. To solve these problems of nuclear fission energy, accelerator-based sub-critical nuclear reactor was once proposed. (Its details will be explained below.) First of all, it is safe in a disaster such as an earthquake, because the deriving accelerator stops immediately by the earthquake. It also minimizes the nuclear waste problem by reducing the amount of the toxic waste and shortening their half lifetime to only a few hundred years. Finally, it solves the Uranium reserve problem because it can use Thorium as its fuel. The Thorium reserve is much larger than that of Uranium. Although the idea of the accelerator-driven nuclear reactor was proposed long time ago, it has not been utilized yet first by technical difficulty and economical reasons. The accelerator-based system needs 1 GeV, 10 MW power proton accelerator. A conventional linear accelerator would need several hundred m length, which is highly costly particularly in Korea because of the high land cost. However, recent technologies make it possible to realize that scale accelerator by a reasonable size. That is the fixed-field alternating gradient (FFAG) accelerator that is described in this article

  16. The detection of bulk explosives using nuclear-based techniques

    Energy Technology Data Exchange (ETDEWEB)

    Morgado, R.E.; Gozani, T.; Seher, C.C.

    1988-01-01

    In 1986 we presented a rationale for the detection of bulk explosives based on nuclear techniques that addressed the requirements of civil aviation security in the airport environment. Since then, efforts have intensified to implement a system based on thermal neutron activation (TNA), with new work developing in fast neutron and energetic photon reactions. In this paper we will describe these techniques and present new results from laboratory and airport testing. Based on preliminary results, we contended in our earlier paper that nuclear-based techniques did provide sufficiently penetrating probes and distinguishable detectable reaction products to achieve the FAA operational goals; new data have supported this contention. The status of nuclear-based techniques for the detection of bulk explosives presently under investigation by the US Federal Aviation Administration (FAA) is reviewed. These include thermal neutron activation (TNA), fast neutron activation (FNA), the associated particle technique, nuclear resonance absorption, and photoneutron activation. The results of comprehensive airport testing of the TNA system performed during 1987-88 are summarized. From a technical point of view, nuclear-based techniques now represent the most comprehensive and feasible approach for meeting the operational criteria of detection, false alarms, and throughput. 9 refs., 5 figs., 2 tabs.

  17. Compact Short-Pulsed Electron Linac Based Neutron Sources for Precise Nuclear Material Analysis

    Science.gov (United States)

    Uesaka, M.; Tagi, K.; Matsuyama, D.; Fujiwara, T.; Dobashi, K.; Yamamoto, M.; Harada, H.

    2015-10-01

    An X-band (11.424GHz) electron linac as a neutron source for nuclear data study for the melted fuel debris analysis and nuclear security in Fukushima is under development. Originally we developed the linac for Compton scattering X-ray source. Quantitative material analysis and forensics for nuclear security will start several years later after the safe settlement of the accident is established. For the purpose, we should now accumulate more precise nuclear data of U, Pu, etc., especially in epithermal (0.1-10 eV) neutrons. Therefore, we have decided to modify and install the linac in the core space of the experimental nuclear reactor "Yayoi" which is now under the decommission procedure. Due to the compactness of the X-band linac, an electron gun, accelerating tube and other components can be installed in a small space in the core. First we plan to perform the time-of-flight (TOF) transmission measurement for study of total cross sections of the nuclei for 0.1-10 eV energy neutrons. Therefore, if we adopt a TOF line of less than 10m, the o-pulse length of generated neutrons should be shorter than 100 ns. Electronenergy, o-pulse length, power, and neutron yield are ~30 MeV, 100 ns - 1 micros, ~0.4 kW, and ~1011 n/s (~103 n/cm2/s at samples), respectively. Optimization of the design of a neutron target (Ta, W, 238U), TOF line and neutron detector (Ce:LiCAF) of high sensitivity and fast response is underway. We are upgrading the electron gun and a buncher to realize higher current and beam power with a reasonable beam size in order to avoid damage of the neutron target. Although the neutron flux is limited in case of the X-band electron linac based source, we take advantage of its short pulse aspect and availability for nuclear data measurement with a short TOF system. First, we form a tentative configuration in the current experimental room for Compton scattering in 2014. Then, after the decommissioning has been finished, we move it to the "Yayoi" room and perform

  18. Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities; Analise de requisitos normativos para o desenvolvimento e a implementacao de um sistema de gestao da qualidade em instalacoes e atividades nucleares brasileiras

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo

    2008-07-01

    The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

  19. Towards many-body based nuclear reaction modelling

    Science.gov (United States)

    Hilaire, Stéphane; Goriely, Stéphane

    2016-06-01

    The increasing need for cross sections far from the valley of stability poses a challenge for nuclear reaction models. So far, predictions of cross sections have relied on more or less phenomenological approaches, depending on parameters adjusted to available experimental data or deduced from systematic expressions. While such predictions are expected to be reliable for nuclei not too far from the experimentally known regions, it is clearly preferable to use more fundamental approaches, based on sound physical principles, when dealing with very exotic nuclei. Thanks to the high computer power available today, all the ingredients required to model a nuclear reaction can now be (and have been) microscopically (or semi-microscopically) determined starting from the information provided by a nucleon-nucleon effective interaction. This concerns nuclear masses, optical model potential, nuclear level densities, photon strength functions, as well as fission barriers. All these nuclear model ingredients, traditionally given by phenomenological expressions, now have a microscopic counterpart implemented in the TALYS nuclear reaction code. We are thus now able to perform fully microscopic cross section calculations. The quality of these ingredients and the impact of using them instead of the usually adopted phenomenological parameters will be discussed. Perspectives for the coming years will be drawn on the improvements one can expect.

  20. Installation Restoration Program. Phase II, Stage 1. Problem Confirmation Study, Luke Air Force Base, Glendale, Arizona.

    Science.gov (United States)

    1984-11-01

    potable water in LAFB. Surface water from the Central Arizona Project (CAP) is available to the Base, but at a significantly higher cost than that of...available supplies of potable water which currently support the Base mission at LAFB. 1-16 1-16 SECTION 2 ENVIRONMENTAL SETTING 2.1 REGIONAL GEOLOGY Luke Air...the northern portion of the Base discharges toward the nearest natural surface water feature, the Agua Fria River. Figure 2-1 summarizes surface

  1. Reports by the Parliamentary Office for scientific and technological assessments. Thursday, May 19, 2011. The French nuclear installations in front of natural risks; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 19 mai 2011. Les installations nucleaires francaises face aux risques naturels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-05-15

    Members of the French Parliament, representatives of the French nuclear safety authority (ASN), of the Academy of Sciences, researchers, and associations argue on major natural risks and their evaluation, notably by referring to the earthquake and tsunami which caused the Fukushima accident. They discuss the predictability of these phenomena, and evoke the context and consequences of climate change. A representative of the Academy of Technologies discusses the risks of land-slips and dam failure, outlines that earthquakes only caused some cracks in dams, and evokes the legal context and organisation regarding dam safety. Possible effects of earthquakes in France are discussed. A second part addresses the way natural risks are taken into account in the protection of nuclear installations

  2. An experimental substantiation of the emergency cooldown system project for the KLT-40S reactor installation of a floating nuclear cogeneration station

    Science.gov (United States)

    Balunov, B. F.; Shcheglov, A. A.; Il'in, V. A.; Saikova, E. N.; Bol'Shukhin, M. A.; Bykh, O. A.; Khizbullin, A. M.; Sokolov, A. N.

    2011-05-01

    Results from thermal-hydraulic tests of a full-scale module of the emergency cooldown system for a KLT-40S reactor installation are presented. The validity of the solutions adopted in its design is shown. Recommendations for calculating the heat transfer coefficients during steam flow condensation and condensate cooling are given.

  3. Installation Restoration Program. Phase I. Records Search, Peterson Air Force Base, Colorado.

    Science.gov (United States)

    1985-08-05

    GUNN so" a. 105VI A [ads SALIDA to(, A- I Ponce, Tous 50 2 Haswell Creek AP ’all or & Ca , Lm enross Arlington Sargent, 1 10Park IF renc Sugar 6...headquartered at Ent Air Force Base near downtown Colorado Springs, thus reopening the base. When the 15th Air Force moved to California in December 1949

  4. Broken Arrows: Radiological hazards from nuclear warhead accidents (the Minot USAF base nuclear weapons incident)

    CERN Document Server

    Liolios, Theodore

    2009-01-01

    According to numerous press reports, in 2007 at Minot US Air Force Base six AGM-129 Advanced Cruise Missiles mistakenly armed with W80-1 thermonuclear warheads were loaded on a B-52H heavy bomber in place of six unarmed AGM-129 missiles that were awaiting transport to Barksdale US Air Force Base for disposal. The live nuclear missiles were not reported missing, and stood unsecured and unguarded while mounted to the aircraft for a period of 36 hours. The present work investigates the radiological hazards associated with a worst-case postulated accident that would disperse the nuclear material of the six warheads in large metropolitan cities. Using computer simulations approximate estimates are derived for the ensuing cancer mortality and land contamination after the accident. Health, decontamination and evacuation costs are also estimated in the framework of the linear risk model.

  5. Installation Restoration Program Records Search for March Air Force Base, California

    Science.gov (United States)

    1984-04-28

    which is bounded by the Jacinto Fault on the east and the Elsinore Fault on the west. Ground surface elevations within the March AFB bound- Z aries...approx- imately one mile south of the base. Lake Mathews, located approximately 10 miles west of the baze, is the terminal reservoir of this aqueduct...State Project water is brought into the Perris Valley via the California Aqueduct, which runs north and east of March Air Force Base. Lake Perris

  6. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement

    Science.gov (United States)

    Wasko, Frank

    Traditionally, electric utilities have been slow to change and very bureaucratic in nature. This culture, in and of itself, has now contributed to a high percentage of United States electric utilities operating uneconomical nuclear plants (Crooks, 2014). The economic picture behind owning and operating United States nuclear plants is less than favorable for many reasons including rising fuel, capital and operating costs (EUCG, 2012). This doctoral dissertation is specifically focused on life without nuclear power. The purpose of this dissertation is to create a model and guide that will provide electric utilities who currently operate or will operate uneconomical nuclear plants the opportunity to economically assess whether or not their nuclear plant should be retired. This economic assessment and stakeholder analysis will provide local government, academia and communities the opportunity to understand how Southern California Edison (SCE) embraced system upgrade import and "voltage support" opportunities to replace "base load" generation from San Onofre Nuclear Generating Station (SONGS) versus building new replacement generation facilities. This model and guide will help eliminate the need to build large replacement generation units as demonstrated in the SONGS case analysis. The application of The Nuclear Power Retirement Model and Guide will provide electric utilities with economic assessment parameters and an evaluation assessment progression needed to better evaluate when an uneconomical nuclear plant should be retired. It will provide electric utilities the opportunity to utilize sound policy, planning and development skill sets when making this difficult decision. There are currently 62 nuclear power plants (with 100 nuclear reactors) operating in the United States (EIA, 2014). From this group, 38 are at risk of early retirement based on the work of Cooper (2013). As demonstrated in my model, 35 of the 38 nuclear power plants qualify to move to the economic

  7. Installation Restoration Program Records Search for Bergstrom Air Force Base, Texas.

    Science.gov (United States)

    1983-07-01

    Johnson grass, buffalograss, Bermudagrass, fescue, and Texas wintergrass. Spring wildflowers , including Texas bluebonnet and indian paintbrush, are...kingfisher. The California jack rabbit is very common on the grassy areas of the base. Other mammals known to be present in the wooded ravines include

  8. Evaluation methodology for seismic base isolation of nuclear equipments

    Energy Technology Data Exchange (ETDEWEB)

    Ebisawa, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)); Uga, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))

    1993-08-01

    An evaluation methodology for seismic base isolated nuclear equipments is proposed. The evaluation can be classified into two steps. In the first step, the seismic functional failure probability during the lifetime of equipment without base isolation devices is quantified in order to decide the applicability of the base isolated structure. The second step is comparative and calculates the ratio of the seismic failure frequency of the equipment without base isolation devices to that with them in order to evaluate the effectiveness of the base isolated structure. The sample evaluation considers the case of high voltage type emergency transformer with ceramic tubes. (orig.)

  9. Installation Restoration Program Records Search for Holloman Air Force Base, New Mexico

    Science.gov (United States)

    1983-08-01

    track, the salt-tolerant arroyo and springs communities, and the extensive horticultural plantings on the base proper. The primary aquatic habitats on...since 1980. Primate research activities conducted in the past include cancer risk, drug therapy , disease studies and the evaluation of automobile...should provide ample pro- tection for personnel working at the site. To prevent ingestion, do not eat , drink, or smoke during visits to site. To prevent

  10. Installation Restoration Program. Phase II. Problem Confirmation and Quantification Study, Griffiss Air Force Base, Rome, New York.

    Science.gov (United States)

    1982-12-01

    major polychlorinated biphenyl spill in Youngs- Recipient of Lehigh University Presidential Prize yulle, Pennsylvania. Continuing Education -Urban...Boring Terminated @11.5’ Monitoring well • installed. See accompanying chart for installation details. N - No blows to drove.....2...." spoC .. 1 2 "wsth

  11. Developing competence based qualification system in the nuclear energy sector

    Energy Technology Data Exchange (ETDEWEB)

    Ceclan, Mihail [European Commission, Petten (Netherlands). Inst. for Energy and Transport

    2016-04-15

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  12. Radioactivity monitoring of areas near nuclear installations in Baden-Wuerttemberg. Annual report 2005; Ueberwachung der baden-wuerttembergischen Umgebung kerntechnischer Anlagen auf Radioaktivitaet. Jahresbericht 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-06-15

    The report presents results of radioactivity monitoring in the vicinity of nuclear facilities by the Land Authority of Environment, Monitoring, and Conservation (LUBW Baden-Wuerttemberg) in 2005. This covers the facilities of Karlsruhe Research Center, the nuclear reactors at Obrigheim, Neckarwestheim and Philippsburg, and the TRIGA research reactor at Heidelberg in the German state of Baden-Wuerttemberg. Further, there are the Swiss nuclear power stations at Beznau/Leibstadt and the ''Paul-Scherrer-Institut'' near Villingen as well as the French nuclear power station of Fessenheim. Monitoring comprised measurements of local gamma dose rates, aerosols and precipitations as well as radioactivity concentrations in soil, vegetation, vegetables, milk and milk products, surface water, sediments, fish, and freshwater. Samples were taken seasonally or continuously depending on the medium. Special regional features like vineyards were taken into account. The results showed only low concentrations of the long-lived nuclides emitted during surface nuclear weapons tests and the Tchernobyl accident. Also, traces of licensed discharge of radioactivity were found only scarcely and especially in aquatic vicinities. The concentrations measured were not harmful to the population. There was nothing to suggest higher activity concentrations exceeding the licensed limit. Since 2002, also interim spent fuel stores at Philippsburg and Neckarwestheim have been monitored. The data are contained in ther report. The local gamma dose rates and neutron doses are below the threshold limit value or only slightly higher. (orig.)

  13. Characterization of a Planetary Boundary Layer model to evaluate radionuclides releases in nuclear installations; Caracterizacao de um modelo de camada limite planetaria para avaliar liberacoes de radionuclideos em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Molnary, Leslie de

    1993-07-01

    A two layer bulk model is used to simulate numerically the time and spatial evolution of concentration of radionuclides in the Planetary Boundary Layer (PBL) for convective and stable conditions. In this model, the closure hypothesis are based on the integrated version of the Turbulent Kinetics Energy (TKE) equation (Smeda,1979). This type of model was adopted here because it is numerically simple to be applied operationally in routine and emergency support systems of atmospheric releases at nuclear power plants, and the hypothesis of the efficiency of the vertical mixing seems to be physically reasonable to simulated PBL evolution for high wind conditions and stable conditions in Subtropical latitudes regions. In order to validate the model to the nuclear power plants of the Centro Experimental Aramar (CEA), located in Ipero, State of Sao Paulo, Brazil, numerical simulations were carried out with initial and boundary conditions based on vertical profiles of temperature and horizontal wind speed and direction obtained from tethered balloon soundings, synoptic charts at 850 hPa and surface observations. Comparisons between a 24 hour long numerical simulation and observations indicate that the model is capable of reproduce the diurnal evolution of temperature and horizontal wind during the convective regime. During stable conditions, the slab model was able to simulate the intensity of the surface inversion as a difference between the mixed layer and surface temperatures. The simulated mixed layer height matches with observations during the convective and stable regime. A daytime release of radionuclides was simulated for CEA region and the results indicated that the maximum relative concentration reaches a distance about 15 Km in 1 hour, varing from 100 times background at the moment of the release to 15 times the background. For night releases, the maximum concentration reaches the same distance in 45 minutes, varing from 100 to 30 times the background values

  14. The ATALANTE installation; L'installation atalante

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    In the Atalante installation of the CEA/Marcoule, researches on the reprocessing of irradiated fuel from nuclear reactors, are performed. In the framework of the law (30 december 1991) on the public policy concerning the radioactive wastes management, the ATALANTE project has to proposed solutions for the long-dated management of these wastes and to help the reprocessing industry. The specifications of the installation and the research programs are detailed with a special interest for the glass durability and the plutonium purifying cycle. The public policy stakes are also recalled. (A.L.B.)

  15. The evaluation of the nuclear facilities safety at the CEA from 1999 to 2001; Le bilan de la surete des installations nucleaires du CEA du 1999 a 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-11-01

    The aim of this document is the presentation of an evaluation of the problems and the safety methods in the concerned period. The first chapter presents the nuclear safety in the CEA. The second chapter is devoted to the organization and the quality for the safety: liabilities, audits, relations with the safety authorities and with the public. The chapters three and four deal respectively with the methodological and technical abilities supporting the exploitation teams and with the nuclear safety projects. The last chapter presents the experiments and events from 1999 to 2001. (A.L.B.)

  16. Development and Testing of a Friction-Based Post-Installable Sensor for Subsea Fiber-Optic Monitoring Systems

    Science.gov (United States)

    Bentley, Nicole; Brower, David; Le, Suy Q.; Seaman, Calvin; Tang, Henry

    2017-01-01

    This paper presents the design and development of a friction-based coupling device for a fiber-optic monitoring system that can be deployed on existing subsea structures. This paper provides a summary of the design concept, prototype development, prototype performance testing, and design refinements of the device. The results of the laboratory testing of the first prototype performed at the National Aeronautics and Space Administration (NASA) Johnson Space Center (JSC) are included in this paper. Limitations of the initial design were identified and future design improvements were proposed. These new features will enhance the coupling of the device and improve the monitoring system measurement capabilities. A major challenge of a post-installed instrumentation monitoring system is to ensure adequate coupling between the instruments and the structure of interest for reliable measurements. Friction-based coupling devices have the potential to overcome coupling limitations caused by marine growth and soil contamination on subsea structures, flowlines or risers. The work described in this paper investigates the design of a friction-based coupling device (friction clamp), which is applicable for pipelines and structures that are suspended in the water column and those that are resting on the seabed. The monitoring elements consist of fiber-optic sensors that are bonded to a metal clamshell with a high-friction coating. The friction clamp has a single hinge design to facilitate the operation of the clamp and dual rows of opposing fasteners to distribute the clamping force on the structure. The friction clamp can be installed by divers in shallow depths or by remotely operated vehicles in deep-water applications. NASA-JSC was involved in the selection and testing of the friction coating, and in the design and testing of the prototype clamp device. Four-inch diameter and eight-inch diameter sub-scale friction clamp prototypes were built and tested to evaluate the strain

  17. Development and Testing of a Friction-Based Post-Installable Sensor for Subsea Fiber-Optic Monitoring System

    Science.gov (United States)

    Bentley, Nicole L.; Brower, David V.; Le, Suy Q.; Seaman, Calvin H.; Tang, Henry H.

    2017-01-01

    This paper presents the design and development of a friction-based coupling device for a fiber-optic monitoring system that can be deployed on existing subsea structures. This paper provides a summary of the design concept, prototype development, prototype performance testing, and design refinements of the device. The results of the laboratory testing of the first prototype performed at the National Aeronautics and Space Administration (NASA) Johnson Space Center (JSC) are included in this paper. Limitations of the initial design were identified and future design improvements were proposed. These new features will enhance the coupling of the device and improve the monitoring system measurement capabilities. A major challenge of a post-installed instrumentation monitoring system is to ensure adequate coupling between the instruments and the structure of interest for reliable measurements. Friction-based coupling devices have the potential to overcome coupling limitations caused by marine growth and soil contamination on subsea structures, flowlines or risers. The work described in this paper investigates the design of a friction-based coupling device (friction clamp), which is applicable for pipelines and structures that are suspended in the water column and those that are resting on the seabed. The monitoring elements consist of fiber-optic sensors that are bonded to a metal clamshell with a high-friction coating. The friction clamp has a single hinge design to facilitate the operation of the clamp and dual rows of opposing fasteners to distribute the clamping force on the structure. The friction clamp can be installed by divers in shallow depths or by remotely operated vehicles in deep-water applications. NASA-JSC was involved in the selection and testing of the friction coating, and in the design and testing of the prototype clamp device. Four-inch diameter and eight-inch diameter sub-scale friction clamp prototypes were built and tested to evaluate the strain

  18. Polarized nuclear target based on parahydrogen induced polarization

    Energy Technology Data Exchange (ETDEWEB)

    Budker, D., E-mail: dbudker@gmail.com [Department of Physics, University of California at Berkeley, Berkeley, CA 94720-7300 (United States); Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Ledbetter, M.P. [Department of Physics, University of California at Berkeley, Berkeley, CA 94720-7300 (United States); Appelt, S. [Central Institute for Electronics, Research Center Juelich, D-52425 Juelich (Germany); Bouchard, L.S. [Department of Chemistry and Biochemistry, California NanoSystems Institute, Biomedical Engineering IDP, Jonsson Comprehensive Cancer Center, University of California, Los Angeles, CA 90095 (United States); Wojtsekhowski, B. [Thomas Jefferson National Accelerator Facility, Newport News, VA 23606 (United States)

    2012-12-01

    We discuss a novel concept of a polarized nuclear target for accelerator fixed-target scattering experiments, which is based on parahydrogen induced polarization (PHIP). One may be able to reach a 33% free-proton polarization in the ethane molecule. The potential advantages of such a target include operation at zero magnetic field, fast ({approx}100Hz) polarization oscillation (akin to polarization reversal), and operation with large intensity of an electron beam. -- Highlights: Black-Right-Pointing-Pointer Novel concept for polarized nuclear targets. Black-Right-Pointing-Pointer The target features fast reversal and operates at near-zero magnetic field. Black-Right-Pointing-Pointer Based on the technique of parahydrogen induced polarization that is revolutionizing NMR and enables NMR/MRI without magnets. Black-Right-Pointing-Pointer Competitive figure-of-merit for polarized targets.

  19. Recent progress in EDF-based methods applied to nuclear properties

    Directory of Open Access Journals (Sweden)

    Khan E.

    2014-03-01

    Full Text Available Recent results obtained with energy density functional (EDF based methods are presented, focused on the nuclear phenomenology. EDF approaches aim for an universal description of the nuclear phenomena over the nuclear chart. Achievements from large to small nuclear systems are depicted: equation of state of nuclear matter, heavy and light nuclei. Dynamical aspects such as nuclear excitations, decay and reactions are also presented. EDF methods are progressing towards an unified and systematic description of the rich variety of the nuclear phenomena such as quantum liquid and cluster states, or nuclear structure and reactions.

  20. Polarized nuclear target based on parahydrogen induced polarization

    Energy Technology Data Exchange (ETDEWEB)

    D. Budker, M.P. Ledbetter, S. Appelt, L.S. Bouchard, B. Wojtsekhowski

    2012-12-01

    We discuss a novel concept of a polarized nuclear target for accelerator fixed-target scattering experiments, which is based on parahydrogen induced polarization (PHIP). One may be able to reach a 33% free-proton polarization in the ethane molecule. The potential advantages of such a target include operation at zero magnetic field, fast ({approx}100 HZ) polarization oscillation (akin to polarization reversal), and operation with large intensity of an electron beam.

  1. CNN's evaluation of the radiological monitoring special programs at the sites of nuclear installations; Evalluacion por el CSN de los programas especiales de vigilancia radiologica en los emplazamientos de las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lareyne, O.; Marugan Tovar, I.; Martinez Moreno, M.; Sanz Alduan, M. T.

    2011-07-01

    In 2008, occurred in the Spanish plants various events related to the existence on the sites of the Spanish nuclear facilities or areas dotted with radioactive contamination outside the buildings, events that were reported to the Nuclear Safety Council (CSN) in accordance with the provisions of the regulation, as a result of the analysis of those events, the CSN issued in July 2008, a complementary technique instruction requiring the implementation of environmental monitoring programs in outdoor areas within sites nuclear facilities. First, the CSN nuclear facilities referred to the programs and methodologies intended to perform such monitoring, and, in late 2009, reports of program results.

  2. Galloping-based piezo-aeroelastic energy harvester for wireless sensors to be installed on freight trains

    Science.gov (United States)

    Tomasini, Gisella; Giappino, Stefano; Costa, Andrea

    2016-04-01

    Energy harvesting from galloping oscillations of a bluff body can be used to supply power to a wireless sensor. In this paper we investigate the possibility to use a galloping-based piezo-aeroelastic energy harvester to supply power to a wireless sensors network installed on a freight train to measure the accelerations in correspondence of axle boxes. The monitoring system will be used to detect possible deteriorations of the running conditions that, in the worst cases, can lead to the vehicle derailment. Unlike other applications in this case the air speed relative to the body is due to the train motion and, for typical freight trains and standard running conditions, is equal to about 20 m/s. In the paper we discuss the design of the harvester on the basis of the constrains due to the application. Preliminary aerodynamic tests shows the limitation of the classical quasi-steady theory of galloping as a consequence of the interaction with the vortex shedding phenomenon.

  3. Sensitivity-Uncertainty Based Nuclear Criticality Safety Validation

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of New Mexico, Albuquerque, NM (United States). Nuclear Engineering Dept.

    2016-09-20

    These are slides from a seminar given to the University of Mexico Nuclear Engineering Department. Whisper is a statistical analysis package developed to support nuclear criticality safety validation. It uses the sensitivity profile data for an application as computed by MCNP6 along with covariance files for the nuclear data to determine a baseline upper-subcritical-limit for the application. Whisper and its associated benchmark files are developed and maintained as part of MCNP6, and will be distributed with all future releases of MCNP6. Although sensitivity-uncertainty methods for NCS validation have been under development for 20 years, continuous-energy Monte Carlo codes such as MCNP could not determine the required adjoint-weighted tallies for sensitivity profiles. The recent introduction of the iterated fission probability method into MCNP led to the rapid development of sensitivity analysis capabilities for MCNP6 and the development of Whisper. Sensitivity-uncertainty based methods represent the future for NCS validation – making full use of today’s computer power to codify past approaches based largely on expert judgment. Validation results are defensible, auditable, and repeatable as needed with different assumptions and process models. The new methods can supplement, support, and extend traditional validation approaches.

  4. 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.

  5. Nuclear Power Plant Operator Reliability Research Based on Fuzzy Math

    Directory of Open Access Journals (Sweden)

    Fang Xiang

    2011-01-01

    Full Text Available This paper makes use of the concept and theory of fuzzy number in fuzzy mathematics, to research for the response time of operator in accident of Chinese nuclear power plant. Through the quantitative analysis for the performance shape factors (PSFs which influence the response time of operators, the formula of the operator response time is obtained based on the possibilistic fuzzy linear regression model which is used for the first time in this kind of research. The research result shows that the correct research method can be achieved through the analysis of the information from a small sample. This method breaks through the traditional research method and can be used not only for the reference to the safe operation of nuclear power plant, but also in other areas.

  6. Cement-Based Materials for Nuclear Waste Storage

    CERN Document Server

    Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

    2013-01-01

    As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

  7. 16. national conference of the presidents of the local commissions of information (C.L.I.) around nuclear facilities; 16. conference nationale des presidents de commissions locales d'information (CLI) autour des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This conference contained two plenary sessions. The first one concerned the epidemiology with the following subjects: the epidemiology, its contributions and its limits; the epidemiological surveillance of cancers in France: role of registers within the device; the aggregates of leukaemia near the nuclear installations; perception and management of the risk; the point of view of the scientific committee of the A.N.C.L.I.; Followed a work in a workshop on the subjects relative to the functioning of the C.L.I. (Organization, relations, information) then the second plenary session with as subjects: organization and functioning of C.L.I., relations and links with A.N.C.L.I., information received and diffused by the C.L.I. (N.C.)

  8. Establishment of nuclear knowledge and information infrastructure; establishment of web-based database system for nuclear events

    Energy Technology Data Exchange (ETDEWEB)

    Park, W. J.; Kim, K. J. [Korea Atomic Energy Research Institute , Taejeon (Korea); Lee, S. H. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2001-05-01

    Nuclear events data reported by nuclear power plants are useful to prevent nuclear accidents at the power plant by examine the cause of initiating events and removal of weak points in the aspects of operational safety, and to improve nuclear safety in design and operation stages by backfitting operational experiences and practices 'Nuclear Event Evaluation Database : NEED' system distributed by CD-ROM media are upgraded to the NEED-Web (Web-based Nuclear Event Evaluation Database) version to manage event data using database system on network basis and the event data and the statistics are provided to the authorized users in the Nuclear Portal Site and publics through Internet Web services. The efforts to establish the NEED-Web system will improve the integrity of events data occurred in Korean nuclear power plant and the usability of data services, and enhance the confidence building and the transparency to the public in nuclear safety. 11 refs., 27 figs. (Author)

  9. Safety reassessment of nuclear installations: consequences for the 900 MWe-PWR type reactors. Safety reassessment of laboratories and nuclear industrial plant, application to a nuclear laboratory; Les reexamens de la surete des installations nucleaires: conclusions des reexamens de surete des tranches de 900 MWE. Le reexamen de surete des laboratoires et usines nucleaires, application au laboratoire d'examen des combustibles actifs

    Energy Technology Data Exchange (ETDEWEB)

    Dousson, D.; Guillard, M.; Charles, Th

    2002-10-01

    In 1987 EDF (Electricite de France) launched the first campaign of the reassessment of safety of 6 operating nuclear reactors (2 Fessenheim units and the 4 reactors of the Bugey plant). This reassessment was requested by the Safety Authority in order to: - check that the safety studies led by EDF are consistent with the real state of the reactors and - be sure that the feedback experience cumulated over years of operating life has been profitable. This work ended in 1995. In 1990 EDF launched the second campaign involving the remaining 28 units of the 900 MWe-PWR type reactors. The aim was the same as previously but this time the procedure has included the use of probabilistic studies of safety. This second campaign has now entered its final stage and has led to several measures concerning fire protection, seismic resistance, and protection against deep cold weather. The probabilistic studies have shown that the reliability of some systems important for safety might be improved, so some modifications have been proposed. These modifications concern the emergency feedwater supply of steam generators, the ventilation systems and the emergency turbine generator set. The second part of the document presents the reassessment of safety that has been performed on a CEA laboratory dedicated to the study of irradiated fuel rods. (A.C.)

  10. Primary system fission product release and transport: A state-of-the-art report to the committee on the safety of nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Wright, A.L. [Oak Ridge National Lab., TN (United States)

    1994-06-01

    This report presents a summary of the status of research activities associated with fission product behavior (release and transport) under severe accident conditions within the primary systems of water-moderated and water-cooled nuclear reactors. For each of the areas of fission product release and fission product transport, the report summarizes relevant information on important phenomena, major experiments performed, relevant computer models and codes, comparisons of computer code calculations with experimental results, and general conclusions on the overall state of the art. Finally, the report provides an assessment of the overall importance and knowledge of primary system release and transport phenomena and presents major conclusions on the state of the art.

  11. Theme day: corrosion and surface treatments in nuclear facilities. Proceedings; Journee Thematique: Corrosion et Traitements de surface dans les Installations Nucleaires. Recueil des presentations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    This document brings together the available presentations given at the theme day organized by the Bourgogne Nuclear Pole on the topic of corrosion and surface treatments in nuclear facilities. Eleven presentations (slides) are compiled in this document: 1 - Introduction - PNB centre of competitiveness and R and D activities (A. Mantovan, PNB); 2 - Corrosion damage (M. Foucault, Areva NP - Centre Technique Le Creusot); 3 - Corrosion mechanisms (R. Oltra, UB-ICB); 4 - Examples of expertise management (C. Duret-Thual, Institut de la corrosion/Corrosion Institute); 5 - General framework of surface treatments (C. Nouveau, ENSAM Cluny Paris Tech); 6 - Surfaces et interfaces characterisation - Part A (C. Langlade, Y. Gachon, UTBM and HEF); 7 - Surfaces et interfaces characterisation - Part B (C. Langlade, Y. Gachon, UTBM and HEF); 8 - Ion beam surface treatment (Y. Le Guellec, Quertech Ingenierie); 9 - Impact surface treatment (G. Saout, Sonats); 10 - Metal oxides Characterisation by US laser (R. Oltra, UB-ICB); 11 - Detection and Characterisation of intergranular corrosion (Y. Kernin, Stephane Bourgois, Areva Intercontrole)

  12. Measurements of nuclear data and possibility to construct the nuclear data production facility based on electron linac

    Energy Technology Data Exchange (ETDEWEB)

    Namkung, Won; Ko, In Soo; Cho, Moo Hyun; Kim, Gui Nyun; Lee, Young Seok; Kang, Heung Sik [Pohang University of Science and Technology, Pohang(Korea)

    2001-04-01

    In order to construct an infrastructure to produce nuclear data, we studied three main items; (1) Study on the possibility to construct a facility for nuclear data production, (2) Production of nuclear data for nuclear power plant, and (3) Pulsed neutron source based on a 100-MeV electron linac at Pohang Accelerator Laboratory (PAL). We confirmed the possibility to build a nuclear data production facility utilizing a 100-MeV electron linac at PAL and manpower who wanted to participate the nuclear data production experiments. In order to measure the nuclear data for nuclear power plant, we used several nuclear data production facilities in abroad. We measured total cross sections and neutron caprure cross sections for {sup nat}Dy and {sup nat}Hf using the pulsed neutron facility in the Research Reactor Institute, Kyoto University (KURRI). The neutron capture cross sections for {sup 161,162,163,164}Dy were measured at KURRI in the neutron energy region between 0.001 eV and several tens keV, and at the fast neutron facility in Tokyo Institute of Technology in the neutron energy region between 10 keV and 100 keV. We also measured the neutron capture cross sections and gamma multiplicity of {sup 232}Th at the IBR30 in Dubna, Russia. We have construct a pulsed neutron source using a 100-MeV electron linac at PAL. We measured neutron time-of-flight (TOF) spectra in order to check the characteristics of the pulsed neutron source. We also measured a neutron total cross sections of W and Cu. The pulsed neutron facility can be utilized in the education facility for nuclear data production and the test facility for the R and D purpose of the nuclear data production facility. 29 refs., 57 figs., 22 tabs. (Author)

  13. Predictive based monitoring of nuclear plant component degradation using support vector regression

    Energy Technology Data Exchange (ETDEWEB)

    Agarwal, Vivek [Idaho National Lab. (INL), Idaho Falls, ID (United States). Dept. of Human Factors, Controls, Statistics; Alamaniotis, Miltiadis [Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering; Tsoukalas, Lefteri H. [Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering

    2015-02-01

    Nuclear power plants (NPPs) are large installations comprised of many active and passive assets. Degradation monitoring of all these assets is expensive (labor cost) and highly demanding task. In this paper a framework based on Support Vector Regression (SVR) for online surveillance of critical parameter degradation of NPP components is proposed. In this case, on time replacement or maintenance of components will prevent potential plant malfunctions, and reduce the overall operational cost. In the current work, we apply SVR equipped with a Gaussian kernel function to monitor components. Monitoring includes the one-step-ahead prediction of the component’s respective operational quantity using the SVR model, while the SVR model is trained using a set of previous recorded degradation histories of similar components. Predictive capability of the model is evaluated upon arrival of a sensor measurement, which is compared to the component failure threshold. A maintenance decision is based on a fuzzy inference system that utilizes three parameters: (i) prediction evaluation in the previous steps, (ii) predicted value of the current step, (iii) and difference of current predicted value with components failure thresholds. The proposed framework will be tested on turbine blade degradation data.

  14. Novel fabrication of silicon carbide based ceramics for nuclear applications

    Science.gov (United States)

    Singh, Abhishek Kumar

    Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These materials include refractory alloys based on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as SiC--SiCf; carbon--carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor components is necessary for improved efficiency. Improving thermal conductivity of the fuel can lower the center-line temperature and, thereby, enhance power production capabilities and reduce the risk of premature fuel pellet failure. Crystalline silicon carbide has superior characteristics as a structural material from the viewpoint of its thermal and mechanical properties, thermal shock resistance, chemical stability, and low radioactivation. Therefore, there have been many efforts to develop SiC based composites in various forms for use in advanced energy systems. In recent years, with the development of high yield preceramic precursors, the polymer infiltration and pyrolysis (PIP) method has aroused interest for the fabrication of ceramic based materials, for various applications ranging from disc brakes to nuclear reactor fuels. The pyrolysis of preceramic polymers allow new types of ceramic materials to be processed at relatively low temperatures. The raw materials are element-organic polymers whose composition and architecture can be tailored and varied. The primary focus of this study is to use a pyrolysis based process to fabricate a host of novel silicon carbide-metal carbide or oxide composites, and to synthesize new materials based on mixed-metal silicocarbides that cannot be processed using conventional techniques. Allylhydridopolycarbosilane (AHPCS), which is an organometal polymer, was used as the precursor for silicon carbide. Inert gas pyrolysis of AHPCS produces near-stoichiometric amorphous

  15. Scaling of a break small in the hot field of the LSTF installation to a nuclear power plant; Escalado de una rotura pequena en la rama caliente de la instacions LSTF a una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Querol, A.; Gallardo, S.; Verdu, G.

    2014-07-01

    The objective of this work is to study if the phenomenology observed during in one break small in the hot branch of a small scale, such as Large Scale Test installation Facility (LSTF), can be extrapolated to a real plant. To do so, is considered the experiment 1-2 of the OECD/NEA rose, which simulates a break in the hot field of 1%, and the code project Thermo-hydraulic TRACE5 to reproduce the LSTF facility and a real plant and thus, power compare the results. They have been considered two models for the actual plant: a scaled model of the LSTF facility while preserving the relationship of power and volume of original LSTF and a typical model Westinghouse PWR of 3 loops. The results obtained show that the scaling LSTF and LSTF installation models reproduce the same behavior during the transient. However, with the Westinghouse model 3 ties there are important differences. The most important thing is that natural circulation does not play properly. The effect of the nodalization of U-tubes and the vessel has been in improving outcomes. The results obtained show that the nodalization of U-tubes affects the reproduction of natural circulation, while the nodalization of the vessel does not have a relevant effect. (Author)

  16. Ablation study of tungsten-based nuclear thermal rocket fuel

    Science.gov (United States)

    Smith, Tabitha Elizabeth Rose

    The research described in this thesis has been performed in order to support the materials research and development efforts of NASA Marshall Space Flight Center (MSFC), of Tungsten-based Nuclear Thermal Rocket (NTR) fuel. The NTR was developed to a point of flight readiness nearly six decades ago and has been undergoing gradual modification and upgrading since then. Due to the simplicity in design of the NTR, and also in the modernization of the materials fabrication processes of nuclear fuel since the 1960's, the fuel of the NTR has been upgraded continuously. Tungsten-based fuel is of great interest to the NTR community, seeking to determine its advantages over the Carbide-based fuel of the previous NTR programs. The materials development and fabrication process contains failure testing, which is currently being conducted at MSFC in the form of heating the material externally and internally to replicate operation within the nuclear reactor of the NTR, such as with hot gas and RF coils. In order to expand on these efforts, experiments and computational studies of Tungsten and a Tungsten Zirconium Oxide sample provided by NASA have been conducted for this dissertation within a plasma arc-jet, meant to induce ablation on the material. Mathematical analysis was also conducted, for purposes of verifying experiments and making predictions. The computational method utilizes Anisimov's kinetic method of plasma ablation, including a thermal conduction parameter from the Chapman Enskog expansion of the Maxwell Boltzmann equations, and has been modified to include a tangential velocity component. Experimental data matches that of the computational data, in which plasma ablation at an angle shows nearly half the ablation of plasma ablation at no angle. Fuel failure analysis of two NASA samples post-testing was conducted, and suggestions have been made for future materials fabrication processes. These studies, including the computational kinetic model at an angle and the

  17. Measures for Equipment Installation in Nuclear Power Plant CI Main Building%核电厂常规岛主厂房设备安装保证措施研究

    Institute of Scientific and Technical Information of China (English)

    武春霖; 金欣

    2014-01-01

    阐述了AP1000核电是目前世界上最先进的核电堆型之一,海水冷却的常规岛 CI (Conventional Island)主厂房多采用半地下结构,在CI主厂房内的凝汽器、发电机定子、汽水分离再热器、除氧器等设备的重量和外形尺寸均比常规火电的设备重和大,其吊装措施在CI主厂房设计时应综合考虑,对施工质量和工程进度都是有益的。介绍了某AP1000核电厂设备安装的CI主厂房设计与设备安装的配合,为相关工程建设、设计者提供参考。%AP1000 unit is one of the most advanced nuclear reactors at present. The main building of sea water cooling CI (Conventional Island) is mostly of the semi-underground structure. The weight and dimension of CI major equipment in the main building, such as condenser,generator stator,MSR and deaerator etc. are bigger than that of the fossil power plant. In order to ensurre the construction quality and schedule,the equipment installation plan should be considered sufficiently. This paper introduced the design of CI main building and its influence on equipment installation for further reference to other designers.

  18. Solar Installation Labor Market Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Friedman, B.; Jordan, P.; Carrese, J.

    2011-12-01

    The potential economic benefits of the growing renewable energy sector have led to increased federal, state, and local investments in solar industries, including federal grants for expanded workforce training for U.S. solar installers. However, there remain gaps in the data required to understand the size and composition of the workforce needed to meet the demand for solar power. Through primary research on the U.S. solar installation employer base, this report seeks to address that gap, improving policymakers and other solar stakeholders understanding of both the evolving needs of these employers and the economic opportunity associated with solar market development. Included are labor market data covering current U.S. employment, expected industry growth, and employer skill preferences for solar installation-related occupations. This study offers an in-depth look at the solar installation sectors. A study published by the Solar Foundation in October 2011 provides a census of labor data across the entire solar value chain.

  19. The European Nuclear Science network touches base at CERN

    CERN Multimedia

    Antonella Del Rosso

    2012-01-01

    ENSAR (European Nuclear Science and Applications Research) is an EU-supported project, which aims at fostering cooperation within the European low-energy nuclear physics community through the active sharing of expertise and best practices. The project also includes a transnational access programme to allow a large community of users to access the participating facilities, which include CERN’s ISOLDE. In the last week of April, CERN hosted the General Assembly and Programme Coordination Committee meetings, about 18 months after the project’s kick-off.   Participants in the ENSAR project. ENSAR involves 30 partner institutes, which include the seven large nuclear physics facilities in Europe. A large part of the European nuclear physics community is represented in ENSAR, in particular scientists who are performing research related to nuclear structure, nuclear astrophysics and applications of nuclear science. In 2010, the project was awarded 8 million euros from the Europe...

  20. Diagnosis and suggestions for the knowledge management applied to a nuclear installation: the uranium hexafluoride production unit; Diagnostico e sugestoes para a gestao do conhecimento aplicada a uma instalacao nuclear: a unidade de producao de hexafluoreto de uranio

    Energy Technology Data Exchange (ETDEWEB)

    Marchesini, Paulo Roberto de Andrade

    2008-07-01

    It has been more than 25 years since Brazilian Navy started applying resources and staff in a nuclear power program in which the main objective is the necessary technology for project and construction of a nuclear power reactor and nuclear fuel production for naval propulsion. A long period project tends to be susceptible to loss of essential parcels of knowledge. The objective of the present research is to identify actions and initiatives that may improve learning and dissemination of knowledge in an organization that develops complexes projects during a long period of time. The revision of the literature about Knowledge Management allowed the researcher to select a reference that indicates how people involved in a project gets the necessary information and knowledge for developing their activities and uses them to add value and to learn how to contribute for the organization, in order to prevent nature difficulties. The adopted methodology was a case study on the implantation of the {sup U}nidade de Hexafluoreto de Uranio{sup ,} which is being developed by the Centro Tecnologico da Marinha in Sao Paulo. With the application of structured and opened interviews, it was possible to identify some factors related with the attainment and dissemination of knowledge that can be developed. The result of this work was a proposal of action and initiatives that will improve the attainment of the knowledge, its structure and maintenance by the organization and the contribution by the people, of the knowledge acquired. (author)

  1. Weighted Nuclear Norm Minimization Based Tongue Specular Reflection Removal

    Directory of Open Access Journals (Sweden)

    Zhenchao Cui

    2015-01-01

    Full Text Available In computational tongue diagnosis, specular reflection is generally inevitable in tongue image acquisition, which has adverse impact on the feature extraction and tends to degrade the diagnosis performance. In this paper, we proposed a two-stage (i.e., the detection and inpainting pipeline approach to address this issue: (i by considering both highlight reflection and subreflection areas, a superpixel-based segmentation method was adopted for the detection of the specular reflection areas; (ii by extending the weighted nuclear norm minimization (WNNM model, a nonlocal inpainting method is proposed for specular reflection removal. Experimental results on synthetic and real images show that the proposed method is accurate in detecting the specular reflection areas and is effective in restoring tongue image with more natural texture information of tongue body.

  2. Rotationally Invariant Hamiltonians for Nuclear Spectra Based on Quantum Algebras

    CERN Document Server

    Bonatsos, D; Raychev, P P; Terziev, P A; Bonatsos, Dennis

    2002-01-01

    The rotational invariance under the usual physical angular momentum of the SUq(2) Hamiltonian for the description of rotational nuclear spectra is explicitly proved and a connection of this Hamiltonian to the formalisms of Amal'sky and Harris is provided. In addition, a new Hamiltonian for rotational spectra is introduced, based on the construction of irreducible tensor operators (ITO) under SUq(2) and use of q-deformed tensor products and q-deformed Clebsch-Gordan coefficients. The rotational invariance of this SUq(2) ITO Hamiltonian under the usual physical angular momentum is explicitly proved, a simple closed expression for its energy spectrum (the ``hyperbolic tangent formula'') is introduced, and its connection to the Harris formalism is established. Numerical tests in a series of Th isotopes are provided.

  3. Operator-based metric for nuclear operations automation assessment

    Energy Technology Data Exchange (ETDEWEB)

    Zacharias, G.L.; Miao, A.X.; Kalkan, A. [Charles River Analytics Inc., Cambridge, MA (United States)] [and others

    1995-04-01

    Continuing advances in real-time computational capabilities will support enhanced levels of smart automation and AI-based decision-aiding systems in the nuclear power plant (NPP) control room of the future. To support development of these aids, we describe in this paper a research tool, and more specifically, a quantitative metric, to assess the impact of proposed automation/aiding concepts in a manner that can account for a number of interlinked factors in the control room environment. In particular, we describe a cognitive operator/plant model that serves as a framework for integrating the operator`s information-processing capabilities with his procedural knowledge, to provide insight as to how situations are assessed by the operator, decisions made, procedures executed, and communications conducted. Our focus is on the situation assessment (SA) behavior of the operator, the development of a quantitative metric reflecting overall operator awareness, and the use of this metric in evaluating automation/aiding options. We describe the results of a model-based simulation of a selected emergency scenario, and metric-based evaluation of a range of contemplated NPP control room automation/aiding options. The results demonstrate the feasibility of model-based analysis of contemplated control room enhancements, and highlight the need for empirical validation.

  4. Evaluation of thorium based nuclear fuel. Extended summary

    Energy Technology Data Exchange (ETDEWEB)

    Franken, W.M.P.; Bultman, J.H.; Konings, R.J.M.; Wichers, V.A.

    1995-04-01

    Application of thorium based nuclear fuels has been evaluated with emphasis on possible reduction of the actinide waste. As a result three ECN-reports are published, discussing in detail: - The reactor physics aspects, by comparing the operation characteristics of the cores of Pressurized Water Reactors and Heavy Water Reactors with different fuel types, including equilibrium thorium/uranium free, once-through uranium fuel and equilibrium uranium/plutonium fuel, - the chemical aspects of thorium based fuel cycles with emphasis on fuel (re)fabrication and fuel reprocessing, - the possible reduction in actinide waste as analysed for Heavy Water Reactors with various types of thorium based fuels in once-through operation and with reprocessing. These results are summarized in this report together with a short discussion on non-proliferation and uranium resource utilization. It has been concluded that a substantial reduction of actinide radiotoxicity of the disposed waste may be achieved by using thorium based fuels, if very efficient partitioning and multiple recycling of uranium and thorium can be realized. This will, however, require large efforts to develop the technology to the necessary industrial scale of operation. (orig.).

  5. Z-Pinch fusion-based nuclear propulsion

    Science.gov (United States)

    Miernik, J.; Statham, G.; Fabisinski, L.; Maples, C. D.; Adams, R.; Polsgrove, T.; Fincher, S.; Cassibry, J.; Cortez, R.; Turner, M.; Percy, T.

    2013-02-01

    Fusion-based nuclear propulsion has the potential to enable fast interplanetary transportation. Due to the great distances between the planets of our solar system and the harmful radiation environment of interplanetary space, high specific impulse (Isp) propulsion in vehicles with high payload mass fractions must be developed to provide practical and safe vehicles for human space flight missions. The Z-Pinch dense plasma focus method is a Magneto-Inertial Fusion (MIF) approach that may potentially lead to a small, low cost fusion reactor/engine assembly [1]. Recent advancements in experimental and theoretical understanding of this concept suggest favorable scaling of fusion power output yield [2]. The magnetic field resulting from the large current compresses the plasma to fusion conditions, and this process can be pulsed over short timescales (10-6 s). This type of plasma formation is widely used in the field of Nuclear Weapons Effects testing in the defense industry, as well as in fusion energy research. A Z-Pinch propulsion concept was designed for a vehicle based on a previous fusion vehicle study called "Human Outer Planet Exploration" (HOPE), which used Magnetized Target Fusion (MTF) [3] propulsion. The reference mission is the transport of crew and cargo to Mars and back, with a reusable vehicle. The analysis of the Z-Pinch MIF propulsion system concludes that a 40-fold increase of Isp over chemical propulsion is predicted. An Isp of 19,436 s and thrust of 3812 N s/pulse, along with nearly doubling the predicted payload mass fraction, warrants further development of enabling technologies.

  6. Low-energy nuclear reactions with double-solenoid- based radioactive nuclear beam

    Indian Academy of Sciences (India)

    Valdir Guimarães

    2010-07-01

    The University of Notre Dame, USA (Becchetti et al, Nucl. Instrum. Methods Res. A505, 377 (2003)) and later the University of São Paulo, Brazil (Lichtenthaler et al, Eur. Phys. J. A25, S-01, 733 (2005)) adopted a system based on superconducting solenoids to produce low-energy radioactive nuclear beams. In these systems the solenoids act as thick lenses to collect, select, and focus the secondary beam into a scattering chamber. Many experiments with radioactive light particle beams (RNB) such as 6He, 7Be, 8Li, 8B have been performed at these two facilities. These low-energy RNB have been used to investigate low-energy reactions such as elastic scattering, transfer and breakup, providing useful information on the structure of light nuclei near the drip line and on astrophysics. Total reaction cross-sections, derived from elastic scattering analysis, have also been investigated for light system as a function of energy and the role of breakup of weakly bound or exotic nuclei is discussed.

  7. Analysis of the organisation implemented by a nuclear operator to carry out the safety of his installations: contribution of cases study; Analyse de l'organisation mise en place par un exploitant nucleaire pour assurer la surete de ses installations: l'apport des etudes de cas

    Energy Technology Data Exchange (ETDEWEB)

    Jeffroy, F.; Conte, D. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Boel, M. [Bertin Technologies, 78 - Montigny-le-Bretonneux (France)

    2006-07-01

    Sought to estimate if the organization implemented by a nuclear operator allowed him to provide the safety of its installations, we defined a step of analysis which approaches the organization on the formal plan of rules, structures and implemented resources, and on that one of its functioning understood through the actors collective activity. The functioning dynamics of the organization was approached from retrospective studies of case aiming to understand, from the actors contributions in the treatment of an event, the way whom the organization characteristics established resources or constraints for the actors. This approach of the organization through case studies, seems to us to have to be replaced in the debate opened at present in cognitive ergonomics, in sociology of organizations and in management. Numerous works indeed try to put in relation the activity of the 'first-line actors' and the decisions and the orientations taken at the strategic level, what supposes to be capable of articulating an analysis of the actors activity. (N.C.)

  8. Measurement of the Length of Installed Rock Bolt Based on Stress Wave Reflection by Using a Giant Magnetostrictive (GMS) Actuator and a PZT Sensor.

    Science.gov (United States)

    Luo, Mingzhang; Li, Weijie; Wang, Bo; Fu, Qingqing; Song, Gangbing

    2017-02-23

    Rock bolts, as a type of reinforcing element, are widely adopted in underground excavations and civil engineering structures. Given the importance of rock bolts, the research outlined in this paper attempts to develop a portable non-destructive evaluation method for assessing the length of installed rock bolts for inspection purposes. Traditionally, piezoelectric elements or hammer impacts were used to perform non-destructive evaluation of rock bolts. However, such methods suffered from many major issues, such as the weak energy generated and the requirement for permanent installation for piezoelectric elements, and the inconsistency of wave generation for hammer impact. In this paper, we proposed a portable device for the non-destructive evaluation of rock bolt conditions based on a giant magnetostrictive (GMS) actuator. The GMS actuator generates enough energy to ensure multiple reflections of the stress waves along the rock bolt and a lead zirconate titantate (PZT) sensor is used to detect the reflected waves. A new integrated procedure that involves correlation analysis, wavelet denoising, and Hilbert transform was proposed to process the multiple reflection signals to determine the length of an installed rock bolt. The experimental results from a lab test and field tests showed that, by analyzing the instant phase of the periodic reflections of the stress wave generated by the GMS transducer, the length of an embedded rock bolt can be accurately determined.

  9. Measurement of the Length of Installed Rock Bolt Based on Stress Wave Reflection by Using a Giant Magnetostrictive (GMS) Actuator and a PZT Sensor

    Science.gov (United States)

    Luo, Mingzhang; Li, Weijie; Wang, Bo; Fu, Qingqing; Song, Gangbing

    2017-01-01

    Rock bolts, as a type of reinforcing element, are widely adopted in underground excavations and civil engineering structures. Given the importance of rock bolts, the research outlined in this paper attempts to develop a portable non-destructive evaluation method for assessing the length of installed rock bolts for inspection purposes. Traditionally, piezoelectric elements or hammer impacts were used to perform non-destructive evaluation of rock bolts. However, such methods suffered from many major issues, such as the weak energy generated and the requirement for permanent installation for piezoelectric elements, and the inconsistency of wave generation for hammer impact. In this paper, we proposed a portable device for the non-destructive evaluation of rock bolt conditions based on a giant magnetostrictive (GMS) actuator. The GMS actuator generates enough energy to ensure multiple reflections of the stress waves along the rock bolt and a lead zirconate titantate (PZT) sensor is used to detect the reflected waves. A new integrated procedure that involves correlation analysis, wavelet denoising, and Hilbert transform was proposed to process the multiple reflection signals to determine the length of an installed rock bolt. The experimental results from a lab test and field tests showed that, by analyzing the instant phase of the periodic reflections of the stress wave generated by the GMS transducer, the length of an embedded rock bolt can be accurately determined. PMID:28241503

  10. Low-frequency nuclear magnetic resonance and nuclear quadrupole resonance spectrometer based on a dc superconducting quantum interference device

    Science.gov (United States)

    Fan, N. Q.; Clarke, John

    1991-06-01

    A sensitive spectrometer, based on a dc superconducting quantum interference device, for the direct detection of low-frequency pulsed nuclear magnetic resonance (NMR) and nuclear quadrupole resonance (NQR), is described. The frequency response extends from about 10 to 200 kHz, and the recovery time after the magnetic pulse is removed is typically 50 μs. As examples, NMR spectra are shown from Pt and Cu metal powders in a magnetic field of 6 mT, and NQR spectra are shown from 2D in a tunneling methyl group and 14N in NH4ClO4.

  11. LHC installation planning

    CERN Document Server

    Weisz, S

    2005-01-01

    installation of the general services, the installation of the cryogenic line (QRL), the installation of the machine elements and the hardware commissioning. While the installation of the general services is now almost finished (see presentation by Katy Foraz and Serge Grillot), several problems and delays with the QRL made it unavoidable to revise the installation strategy and to schedule a number tasks in parallel. A new compressed installation planning has been issued, that fulfils the strategic objectives and allows starting new activities with minimal delays in sectors 7-8 and 8-1. However, the shortcuts that are introduced increase the level of risk that we will have to face and the coordination of such a large and complex variety of simultaneous activities makes the project even more challenging. The document will describe how the input from the different equipment groups is taken into account by the master schedule planning team with respect to equipment availability and production as well as logistics...

  12. Applying activity-based costing to the nuclear medicine unit.

    Science.gov (United States)

    Suthummanon, Sakesun; Omachonu, Vincent K; Akcin, Mehmet

    2005-08-01

    Previous studies have shown the feasibility of using activity-based costing (ABC) in hospital environments. However, many of these studies discuss the general applications of ABC in health-care organizations. This research explores the potential application of ABC to the nuclear medicine unit (NMU) at a teaching hospital. The finding indicates that the current cost averages 236.11 US dollars for all procedures, which is quite different from the costs computed by using ABC. The difference is most significant with positron emission tomography scan, 463 US dollars (an increase of 96%), as well as bone scan and thyroid scan, 114 US dollars (a decrease of 52%). The result of ABC analysis demonstrates that the operational time (machine time and direct labour time) and the cost of drugs have the most influence on cost per procedure. Clearly, to reduce the cost per procedure for the NMU, the reduction in operational time and cost of drugs should be analysed. The result also indicates that ABC can be used to improve resource allocation and management. It can be an important aid in making management decisions, particularly for improving pricing practices by making costing more accurate. It also facilitates the identification of underutilized resources and related costs, leading to cost reduction. The ABC system will also help hospitals control costs, improve the quality and efficiency of the care they provide, and manage their resources better.

  13. Phylogeny of the Zygomycota based on nuclear ribosomal sequence data.

    Science.gov (United States)

    White, Merlin M; James, Timothy Y; O'Donnell, Kerry; Cafaro, Matías J; Tanabe, Yuuhiko; Sugiyama, Junta

    2006-01-01

    The Zygomycota is an ecologically heterogenous assemblage of nonzoosporic fungi comprising two classes, Zygomycetes and Trichomycetes. Phylogenetic analyses have suggested that the phylum is polyphyletic; two of four orders of Trichomycetes are related to the Mesomycetozoa (protists) that diverged near the fungal/animal split. Current circumscription of the Zygomycota includes only orders with representatives that produce zygospores. We present a molecular-based phylogeny including recognized representatives of the Zygomycetes and Trichomycetes with a combined dataset for nuclear rRNA 18S (SSU), 5.8S and 28S (LSU) genes. Tree reconstruction by Bayesian analyses suggests the Zygomycota is paraphyletic. Although 12 clades were identified only some of these correspond to the nine orders of Zygomycota currently recognized. A large superordinal clade, comprising the Dimargaritales, Harpellales, Kickxellales and Zoopagales, grouping together many symbiotic fungi, also is identified in part by a unique septal structure. Although Harpellales and Kickxellales are not monophyletic, these lineages are distinct from the Mucorales, Endogonales and Mortierellales, which appear more closely related to the Ascomycota + Basidiomycota + Glomeromycota. The final major group, the insect-associated Entomophthorales, appears to be polyphyletic. In the present analyses Basidiobolus and Neozygites group within Zygomycota but not with the Entomophthorales. Clades are discussed with special reference to traditional classifications, mapping morphological characters and ecology, where possible, as a snapshot of our current phylogenetic perspective of the Zygomycota.

  14. Planning of the development of the MMIS core technology based on nuclear-IT convergence

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Kim, Chang Hwoi; Hwang, In Koo [KAERI, Daejeon (Korea, Republic of); and others

    2012-01-15

    - Drive nuclear-IT convergence technologies such as middleware applied new concept nuclear instrumentation and control architecture, automated operation of future nuclear power plant, virtual reality/augmented reality, design and verification technology of a nuclear power plant main control room, software dependability, and cyber security technology - Write state-of-the-art report for the nuclear instrumentation and control based on IT convergence - A prototype which implemented related equipment and software subject to nuclear reactor operator that reside in the main control room (Reactor Operator, RO) order to a on-site operator (Local Operator, LO) and confirm the task performance matches the RO's intention - 'IT Convergence intelligent instrumentation and control technology' project planning for the Fourth Nuclear Power Research and Development in the long-term plan.

  15. Construction of APR1000 nuclear power information management system based on international standards

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Seung Hwan [Korea Electric Power Research Institute, Daejeon (Korea, Republic of); Song, Deok Yong; Han, Byung Sub [Enesys Co., Daejeon (Korea, Republic of); An, Kyung Ik; Hwang, Jin Sang [PartDB Co., Daejeon (Korea, Republic of)

    2010-10-15

    In recent years, due to speedy rise of international oil prices, orders of nuclear power plant construction have been in progress by many countries to solve the stable supply of power. Our country has continued to perform nuclear power construction. As only a few developed countries like Japan and European countries have its own nuclear power construction technology, competition among them is keen. Our country has awarded the contract of UAE nuclear power plants based on the accumulated nuclear power plant construction technologies so far. In this regard, KEPCO has recognized the needs of information management system to manage nuclear power information and proceeded the implementation of nuclear power information management system for export-model

  16. Electrical installation calculations advanced

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for advanced electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practiceA step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3For apprentices and electrical installatio

  17. Electrical installation calculations basic

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for basic electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practice. A step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3Fo

  18. Electrical installations and regulations

    CERN Document Server

    Whitfield, J F

    1966-01-01

    Electrical Installations and Regulations focuses on the regulations that apply to electrical installations and the reasons for them. Topics covered range from electrical science to alternating and direct current supplies, as well as equipment for providing protection against excess current. Cables, wiring systems, and final subcircuits are also considered, along with earthing, discharge lighting, and testing and inspection.Comprised of 12 chapters, this book begins with an overview of electrical installation work, traits of a good electrician, and the regulations governing installations. The r

  19. K- nuclear potentials based on chiral meson-baryon amplitudes

    Science.gov (United States)

    Mareš, J.; Cieplý, A.; Gazda, D.; Friedman, E.; Gal, A.

    2012-09-01

    K- nuclear optical potentials are constructed from in-medium subthreshold K¯N scattering amplitudes within a chirally motivated coupled-channel model. We demonstrate how the strong energy and density dependence of the scattering amplitudes at and below threshold leads to a deep K- nuclear potential VK- for kaonic atoms and K- nuclear quasibound states. Selfconsistent evaluations yield K- potential depths -ReVK- (ρ0) of order 100 MeV. Allowing for K- NN absorption, better agreement with K- atoms data is achieved, leading to increased potential depths, -ReVK- (ρ0) ˜ 175 MeV, in accord with density dependent potentials obtained in purely phenomenological fits. Self consistent dynamical calculations of K- nuclear quasibound states are reported and discussed, as well.

  20. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byungdoo; Kim, Inchul; Lee, Seungho; Kim, Hyunjo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level.

  1. Prof. Cristoforo Benvenuti stands in front of solar panels installed on the roof of Geneva airport. These panels, produced by the commpany SRB, are based on a technology developed at CERN by Cristoforo Benvenuti.

    CERN Multimedia

    Maximilien Brice

    2012-01-01

    Prof. Cristoforo Benvenuti stands in front of solar panels installed on the roof of Geneva airport. These panels, produced by the commpany SRB, are based on a technology developed at CERN by Cristoforo Benvenuti.

  2. Design, fabrication and installation of irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C. [and others

    1997-07-01

    The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs.

  3. Wind power installations in Switzerland - Regional planning basics and impact; Eoliennes en Suisse. Bases de planification pour l'amenagement du territoire et effets. Rapport de base

    Energy Technology Data Exchange (ETDEWEB)

    Ott, W.; Kaufmann, Y.; Steiner, P. [Econcept AG, Zuerich (Switzerland); Gilgen, K.; Sartoris, A. [IRAP-HSR, Institut fuer Raumentwicklung an der Hochschule fuer Technik Rapperswil, Rapperswil (Switzerland)

    2008-07-01

    This report published by the Swiss Federal Office of Energy (SFOE) takes a look at the basics of regional planning and its impact on the construction of wind-energy installations in Switzerland. The authors state that the planning and realisation of wind turbine installations is often time and resource consuming: this document presents and discusses the results obtained in a project that aimed to supply consolidated knowledge on project-relevant basics and their effect with respect to wind-energy installations. Experience gained in Switzerland and in other countries is discussed. This report on the basics of wind-energy planning with its detailed information formed the basis of a checklist described in a further report. In nine chapters, regional planning aspects, environment and landscape-relevant aspects, effects on the national and regional economies and social acceptance factors are discussed. Also, success-factors and possible solutions for the successful realisation of wind-energy projects are looked at.

  4. Chiral EFT based nuclear forces: Achievements and challenges

    CERN Document Server

    Machleidt, R

    2016-01-01

    During the past two decades, chiral effective field theory has become a popular tool to derive nuclear forces from first principles. Two-nucleon interactions have been worked out up to sixth order of chiral perturbation theory and three-nucleon forces up to fifth order. Applications of some of these forces have been conducted in nuclear few- and many-body systems---with a certain degree of success. But in spite of these achievements, we are still faced with great challenges. Among them is the issue of a proper uncertainty quantification of predictions obtained when applying these forces in {\\it ab initio} calculations of nuclear structure and reactions. A related problem is the order by order convergence of the chiral expansion. We start this review with a pedagogical introduction and then present the current status of the field of chiral nuclear forces. This is followed by a discussion of representative examples for the application of chiral two- and three-body forces in the nuclear many-body system includin...

  5. Development of DUPIC safeguards technology; development of web based nuclear material accounting program

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. T.; Choi, S. H.; Choi, S. J. [Kongju National University, Kongju (Korea)

    2002-04-01

    The purpose of this project is to develop the web-based digital image processing system with the client/server architecture based on TCP/IP to be able to search and manage image data at the remote place. This system provides a nuclear facility with the ability to track the movement of nuclear material and to control and account nuclear material at anywhere and anytime. Also, this system will be helpful to increase the efficiency of safeguards affairs. The developed web-based digital image processing system for tracking the movement of nuclear material and MC and A can be applied to DUPIC facility. The result of this project will eventually contribute to similar nuclear facilities as well as the effective implementation of DUPIC safeguards. In addition, it will be helpful to enhance international confidence build-up in the peaceful use of spent fuel material. 15 refs., 33 figs., 4 tabs. (Author)

  6. A review on the status of development in thorium-based nuclear fuels

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Woo; Na, S. H.; Lee, Y. W.; Kim, H. S.; Kim, S. H.; Joung, C.Y

    2000-02-01

    Thorium as an alternative nuclear energy source had been widely investigated in the 1950s-1960s because it is more abundant than uranium, but the studies of thorium nuclear fuel cycle were discontinued by political and economic reasons in the 1970s. Recently, however, renewed interest was vested in thorium-based nuclear fuel cycle because it may generate less long-lived minor actinides and has a lower radiotoxicity of high level wastes after reprocessing compared with the thorium fuel cycle. In this state-of the art report, thorium-based nuclear cycle. In this state-of the art report, thorium-based nuclear fuel cycle and fuel fabrication processes developed so far with different reactor types are reviewed and analyzed to establish basic technologies of thorium fuel fabrication which could meet our situation. (author)

  7. A Nuclear Reactor Transient Methodology Based on Discrete Ordinates Method

    Directory of Open Access Journals (Sweden)

    Shun Zhang

    2014-01-01

    Full Text Available With the rapid development of nuclear power industry, simulating and analyzing the reactor transient are of great significance for the nuclear safety. The traditional diffusion theory is not suitable for small volume or strong absorption problem. In this paper, we have studied the application of discrete ordinates method in the numerical solution of space-time kinetics equation. The fully implicit time integration was applied and the precursor equations were solved by analytical method. In order to improve efficiency of the transport theory, we also adopted some advanced acceleration methods. Numerical results of the TWIGL benchmark problem presented demonstrate the accuracy and efficiency of this methodology.

  8. Phylogeny of Anophelinae (Diptera: Culicidae) Based on Nuclear Ribosomal and Mitochondrial DNA Sequences

    Science.gov (United States)

    2002-01-01

    combining data from nuclear protein-encoding enes for phylogenetic analyses of Noctuoidea (Insecta: Lepidoptera ). Systematic Biology, 49, 202 224. Nixon... Systematic Entomology (2002) 27, 361 382 Phylogeny of Anophelinae (Diptera: Culicidae) based on nuclear ribosomal and mitochondrial DNA sequences...Entomologia M•dica, Departamento de Epidemiologia, Faculdade de Safide Pfiblica, Universidade de S•o Paulo, Brazil, -• Department of Systematic

  9. The virtual digital nuclear power plant: A modern tool for supporting the lifecycle of VVER-based nuclear power units

    Science.gov (United States)

    Arkadov, G. V.; Zhukavin, A. P.; Kroshilin, A. E.; Parshikov, I. A.; Solov'ev, S. L.; Shishov, A. V.

    2014-10-01

    The article describes the "Virtual Digital VVER-Based Nuclear Power Plant" computerized system comprising a totality of verified initial data (sets of input data for a model intended for describing the behavior of nuclear power plant (NPP) systems in design and emergency modes of their operation) and a unified system of new-generation computation codes intended for carrying out coordinated computation of the variety of physical processes in the reactor core and NPP equipment. Experiments with the demonstration version of the "Virtual Digital VVER-Based NPP" computerized system has shown that it is in principle possible to set up a unified system of computation codes in a common software environment for carrying out interconnected calculations of various physical phenomena at NPPs constructed according to the standard AES-2006 project. With the full-scale version of the "Virtual Digital VVER-Based NPP" computerized system put in operation, the concerned engineering, design, construction, and operating organizations will have access to all necessary information relating to the NPP power unit project throughout its entire lifecycle. The domestically developed commercial-grade software product set to operate as an independently operating application to the project will bring about additional competitive advantages in the modern market of nuclear power technologies.

  10. Software safety analysis practice in installation phase

    Energy Technology Data Exchange (ETDEWEB)

    Huang, H. W.; Chen, M. H.; Shyu, S. S., E-mail: hwhwang@iner.gov.t [Institute of Nuclear Energy Research, No. 1000 Wenhua Road, Chiaan Village, Longtan Township, 32546 Taoyuan County, Taiwan (China)

    2010-10-15

    This work performed a software safety analysis in the installation phase of the Lung men nuclear power plant in Taiwan, under the cooperation of Institute of Nuclear Energy Research and Tpc. The US Nuclear Regulatory Commission requests licensee to perform software safety analysis and software verification and validation in each phase of software development life cycle with Branch Technical Position 7-14. In this work, 37 safety grade digital instrumentation and control systems were analyzed by failure mode and effects analysis, which is suggested by IEEE standard 7-4.3.2-2003. During the installation phase, skew tests for safety grade network and point to point tests were performed. The failure mode and effects analysis showed all the single failure modes can be resolved by the redundant means. Most of the common mode failures can be resolved by operator manual actions. (Author)

  11. Choice of optimum size of installations for dual-purpose production of desalted water and electricity, using nuclear power; Le dimensionnement optimum des installations de production mixte d'eau sessalee et d'electricite faisant intervenir l'energie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Gaussens, J. [Commissariat a l' Energie Atomique, Paris (France)

    1966-07-01

    The author used a method starting with water and power demand curves; this leads to the rational allocation of production costs to water and power within a given market. The power demand curve is needed as it seems improbable to sell at a constant price the enormous quantity of electricity produced by a dual purpose plant. Criteria based on principles of classical economics, help to select objectively desalination methods and plant sizes. On these criteria, normative methods for tariffing action of water and power can be based, while adhering as closely as possible to structure of demand. Examples of such criteria are the maximum profit of the supplier or the maximum satisfaction of the consumers taken collectively. In the first case marginal costs must be equated to marginal revenue, in the second one marginal cost to marginal satisfaction (theory of surpluses). The plant size often determines the choice of desalination process. Therefore the shape of the water demand curve and the economic criterion adopted (public or private ownership, capital restrictions etc.) often determine in this way both size and type of plant. Before deciding on the desalination technique, market surveys and rather subtle economic analyses are therefore necessary. (author) [French] Le probleme est presente en introduisant la notion de courbes de demande d'eau et d'electricite, ce qui permet d'aboutir a un partage rationnel des couts de revient entre eau et electricite dans ]e cadre d'un marche. L'objet de l'etude est, a partir des principes de l'economie classique, de donner des criteres objectifs de selection des dimensions des installations et des techniques de dessalement et d'en deduire une methode normative de tarification des deux produits lies: eau et electricite, en collant autant que possible a la structure de la demande. Ces criteres sont en particulier, soit le maximum de benefice de l'exploitant, soit le maximum de satisfaction des

  12. INIS: A Computer-Based International Nuclear Information System.

    Science.gov (United States)

    Balakrishnan, M. R.

    1986-01-01

    Description of the International Nuclear Information System includes its history, organizational structure, subject classification scheme, thesaurus, input standards, and various products and services generated by the system. Appendices provide a list of participating countries, subjects covered by the system, and a sample output record.…

  13. An American Vital Interest: Preserving the Nuclear Enterprise Supplier Base

    Science.gov (United States)

    2012-02-15

    machined parts, and printed wire boards (PWBs). Honeywell maintains the nuclear enterprise’s Master Approved Supplier List containing all qualified...and technologies that have experienced significant decline include aerospace, semiconductors, PWBs, machine tools, and advanced materials (e.g...re-energized their relationship with Brush Wellman on Beryllium Supply, and undertaken energetic materials development with Roxcel. It is

  14. Nuclear decommissioning planning, execution and international experience

    CERN Document Server

    2012-01-01

    A title that critically reviews the decommissioning and decontamination processes and technologies available for rehabilitating sites used for nuclear power generation and civilian nuclear facilities, from fundamental issues and best practices, to procedures and technology, and onto decommissioning and decontamination case studies.$bOnce a nuclear installation has reached the end of its safe and economical operational lifetime, the need for its decommissioning arises. Different strategies can be employed for nuclear decommissioning, based on the evaluation of particular hazards and their attendant risks, as well as on the analysis of costs of clean-up and waste management. This allows for decommissioning either soon after permanent shutdown, or perhaps a long time later, the latter course allowing for radioactivity levels to drop in any activated or contaminated components. It is crucial for clear processes and best practices to be applied in decommissioning such installations and sites, particular where any ...

  15. The threat of nuclear terrorism: from analysis to precautionary measures

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, M

    2003-07-01

    Facing the nuclear terrorism risk, this document analyzes the nature of the threat of nuclear terrorism, the risk of attack on nuclear installations, the limited protection of nuclear installations against aircraft crashes, the case of nuclear reprocessing plants, the case of nuclear transport and proposes measures which should be taken without endangering the foundations of democracy. (A.L.B.)

  16. EUROSAFE forum 2013. Safe disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

    The proceedings of the EUROSAFE forum 2013 - safe disposal of nuclear waste include contributions to the following topics: Nuclear installation safety - assessment; nuclear installation safety - research; waste and decommissioning - dismantling; radiation protection, 3nvironment and emergency preparedness; security of nuclear installations and materials.

  17. Biggest semiconductor installed

    CERN Multimedia

    2008-01-01

    Scientists and technicians at the European Laboratory for Particle Physics, commonly known by its French acronym CERN (Centre Europen pour la Recherche Nuclaire), have completed the installation of the largest semiconductor silicon detector.

  18. Installing the World

    Institute of Scientific and Technical Information of China (English)

    1998-01-01

    THE art of installation is an art about concept," explains Qing Qing Chen. The artist wants her audience to look at the development of aesthetics from a pluralistic angle on life. Unlike the expressive format of "art in the frame," the art of installation belongs to the category of "non-framed art." The choice of materials used is as important to expression as the creator’s ideas. Whereas only certain materials can be

  19. Installation af opvaskemaskine

    DEFF Research Database (Denmark)

    Christiansen, J.; Skibstrup Eriksen, S.; Nielsen, F.

    Denne SBI-anvisning er et led i en serie om modernisering af installationerne i den ældre boligmasse. Den henvender sig til både beboere, husejere, VVS-installatører og andre interesserede. Anvisningen indeholder almene afsnit om valg og placering af opvaskemaskine, sagsforløb ved installation......, forhold til myndigheder, priser, finansieringsmuligheder m.m. Anvisningen indeholder endvidere tekniske afsnit om vandinstallation, afløb og elinstallation i forbindelse med installation af opvaskemaskine....

  20. Complex biopower installation

    Directory of Open Access Journals (Sweden)

    Tirshu M.

    2008-12-01

    Full Text Available It is presented the technological scheme of complex biopower installation for manufacture of the electric power, hot water and gas at use as raw material of manure, birds dung and firm organic waste products. The suggested technical solution provides practically 100 % use of energy of burnt gas due to the introduced feedback between power station and a bioreactor. Recommendations for the best use of installation in Republics Moldova are developed as well.

  1. Laser-Based Characterization of Nuclear Fuel Plates

    Energy Technology Data Exchange (ETDEWEB)

    James A. Smith; David L. Cottle; Barry H. Rabin

    2013-07-01

    Ensuring the integrity of fuel-clad and clad-clad bonding in nuclear fuels is important for safe reactor operation and assessment of fuel performance, yet the measurement of bond strengths in actual fuels has proved challenging. The laser shockwave technique (LST) originally developed to characterize structural adhesion in composites is being employed to characterize interface strength in a new type of plate fuel being developed at Idaho National Laboratory (INL). LST is a non-contact method that uses lasers for the generation and detection of large-amplitude acoustic waves and is well suited for application to both fresh and irradiated nuclear-fuel plates. This paper will report on initial characterization results obtained from fresh fuel plates manufactured by different processes, including hot isostatic pressing, friction stir welding, and hot rolling.

  2. Laser-based characterization of nuclear fuel plates

    Science.gov (United States)

    Smith, James A.; Cottle, Dave L.; Rabin, Barry H.

    2014-02-01

    Ensuring the integrity of fuel-clad and clad-clad bonding in nuclear fuels is important for safe reactor operation and assessment of fuel performance, yet the measurement of bond strengths in actual fuels has proved challenging. The laser shockwave technique (LST) originally developed to characterize structural adhesion in composites is being employed to characterize interface strength in a new type of plate fuel being developed at Idaho National Laboratory (INL). LST is a non-contact method that uses lasers for the generation and detection of large-amplitude acoustic waves and is well suited for application to both fresh and irradiated nuclear-fuel plates. This paper will report on initial characterization results obtained from fresh fuel plates manufactured by different processes, including hot isostatic pressing, friction stir welding, and hot rolling.

  3. Comparative study on storage and disposal of liquid waste in nuclear medicine diagnostic; Estudio comparativo sobre almacenamiento y eliminacion de residuos liquidos para diagnostico en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Vazquez Vazquez, R.; Sanchez Garcia, M.; Santamarina Vazquez, F.; Soto Bua, M.; Montoya Pastor, A.; Luna Vega, V.; Mosquera Suueiro, J.; Otero Martinez, C.; Lobato Busto, R.; Pombar Camean, M.

    2011-07-01

    The aim of this paper presents a comparative study on the total activity of material discharge to public sewers and the activity concentration in the final point of discharge, for a typical installation of Nuclear Medicine, in the case of having no deposit or storage of liquid radioactive waste from diagnostic techniques, based on actual data from the Nuclear Medicine Department of our hospital.

  4. Design, fabrication and installation of irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Bong Shick; Kim, Y. S.; Lee, C. Y. and others

    1999-03-01

    The principal contents of this project are to design, fabricate and install the steady-state fuel test loop in HANARO for nuclear technology development. Procurement and fabrication of main equipment, licensing and technical review for fuel test loop have been performed during 2 years(1997, 1998) for this project. Following contents are described in the report. - Procurement and fabrication of the equipment, piping for OPS - IPS manufacture - License - Technical review and evaluation of the FTL facility. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and review ofHANARO interface have been performed respectively. (author)

  5. A NEW RUSSIAN WASTE MANAGEMENT INSTALLATION

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, Andrew; Engxy, Thor; Endregard, Monica; Schwab, Patrick; Nazarian, Ashot; Krumrine, Paul; Backe, Steinar; Gorin, Stephen; Evans, Brent

    2003-02-27

    The Polyarninsky Shipyard (sometimes called Navy Yard No. 10 or the Shkval Shipyard) has been designated as the recipient for Solid Radioactive Waste (SRW) management facilities under the Arctic Military Environmental Cooperation (AMEC) Program. The existing SRW storage site at this shipyard is filled to capacity, which is forcing the shipyard to reduce its submarine dismantlement activities. The Polyarninsky Shipyard Waste Management Installation is planned as a combination of several AMEC projects. It will have several elements, including a set of hydraulic metal cutting tools, containers for transport and storage, the Mobile Pretreatment Facility (MPF) for Solid Radioactive Waste, the PICASSO system for radiation monitoring, and a Waste Storage Facility. Hydraulically operated cutting tools can cut many metal items via shearing so that dusts or particulates are not generated. The AMEC Program procured a cutting tool system, consisting of a motor and hydraulic pumping unit, a 38-mm conduit-cutting tool, a 100- mm pipe-cutting tool, and a spreading tool all mounted on a wheeled cart. The vendor modified the tool system for extremely cold conditions and Russian electrical standards, then delivered the tool system to the Polyarninsky shipyard. A new container for transportation and storage of SRW and been designed and fabricated. The first 400 of these containers have been delivered to the Northern Fleet of the Russian Navy for use at the Polyarninsky Shipyard Waste Management Installation. These containers are cylindrical in shape and can hold seven standard 200-liter drums. They are the first containers ever certified in Russia for the offsite transport of military SRW. These containers can be transported by truck, rail, barge, or ship. The MPF will be the focal point of the Polyarninsky Shipyard Waste Management Installation and a key element in meeting the nuclear submarine dismantlement and waste processing needs of the Russian Federation. It will receive raw

  6. Installation Restoration Program Phase II - Confirmation/Quantification. Stage 1. Davis-Monthan Air Force Base, Arizona.

    Science.gov (United States)

    1986-08-18

    and is presently a Tactical Air Command base. The base is situated in the Tucson basin, a basin, bordered by the Santa Catalina, Rincon , Santa Rita...the Santa Catalina, Rincon , Santa Rita, Tucson, Sierrita, Tortolita, and Empire Mountains and Black Mountain. The Tucson basin typifies the...I. W em em "m O’ _ _ , - It F. LUi FA 0 -.A y Il r - iti we -4 -0 I-, I-,.- *, , I o so 0 ’ 0 ___ - mI I Ili IsIT ’"." U " U , U - -= , , - - - -e

  7. Installation Development Environmental Assessment at Joint Base Andrews-Naval Air Facility Washington Prince George’s County, Maryland

    Science.gov (United States)

    2013-04-01

    two-lane, undivided road makes an 8.4-mile loop around the Base. Traffic during peak flow hours is heaviest at the Alabama Avenue/North Perimeter...JBA include common species of snakes, lizards, and turtles. Mammals known to occur at JBA are also those common in the region, including white-tailed

  8. Capping off installation

    CERN Multimedia

    2006-01-01

    Installation of the cathode strip chambers for the muon system on the CMS positive endcap has been completed. Technicians install one of the last muon system cathode strip chambers on the CMS positive endcap. Like successfully putting together the pieces of a giant puzzle, installation of the muon system cathode strip chambers on one of the CMS endcaps has been completed. Total installation of the cathode strip chambers (CSC) is now 91 percent complete; only one ring of chambers needs to be mounted on the remaining endcap to finish installation of the entire system. To guarantee a good fit for the 468 total endcap muon system CSCs, physicists and engineers from the collaboration spent about 10 years carefully planning the design. The endcap muon system's cables, boxes, pipes and other parts were designed and integrated using a 3D computerized model. 'It took a long time to do all the computer modelling, but in the long run it saved us an enormous amount of time because it meant that everything fit together,...

  9. Science based integrated approach to advanced nuclear fuel development - vision, approach, and overview

    Energy Technology Data Exchange (ETDEWEB)

    Unal, Cetin [Los Alamos National Laboratory; Pasamehmetoglu, Kemal [IDAHO NATIONAL LAB; Carmack, Jon [IDAHO NATIONAL LAB

    2010-01-01

    Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Rcactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems is critical. In order to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. The purpose of this paper is to identify the modeling and simulation approach in order to deliver predictive tools for advanced fuels development. The coordination between experimental nuclear fuel design, development technical experts, and computational fuel modeling and simulation technical experts is a critical aspect of the approach and naturally leads to an integrated, goal-oriented science-based R & D approach and strengthens both the experimental and computational efforts. The Advanced Fuels Campaign (AFC) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Integrated Performance and Safety Code (IPSC) are working together to determine experimental data and modeling needs. The primary objective of the NEAMS fuels IPSC project is to deliver a coupled, three-dimensional, predictive computational platform for modeling the fabrication and both normal and abnormal operation of nuclear fuel pins and assemblies, applicable to both existing and future reactor fuel designs. The science based program is pursuing the development of an integrated multi-scale and multi-physics modeling and simulation platform for nuclear fuels. This overview paper discusses the vision, goals and approaches how to develop and implement the new approach.

  10. Nuclear magnetic resonance-based quantification of organic diphosphates.

    Science.gov (United States)

    Lenevich, Stepan; Distefano, Mark D

    2011-01-15

    Phosphorylated compounds are ubiquitous in life. Given their central role, many such substrates and analogs have been prepared for subsequent evaluation. Prior to biological experiments, it is typically necessary to determine the concentration of the target molecule in solution. Here we describe a method where concentrations of stock solutions of organic diphosphates and bisphosphonates are quantified using (31)P nuclear magnetic resonance (NMR) spectroscopy with standard instrumentation using a capillary tube with a secondary standard. The method is specific and is applicable down to a concentration of 200 μM. The capillary tube provides the reference peak for quantification and deuterated solvent for locking.

  11. Installation Restoration Program. Phase 2. Confirmation/Quantification, Stage 2 for Seymour Johnson Air Force Base, North Carolina. Volume 2

    Science.gov (United States)

    1988-11-01

    4) Corrosion, incrustation , well Interference, and similar operation and maintenance problems (5) Observation well networks (6) Existing water...Type I Portland cement /bentonite slurry. (b) Check with the base point of contact (POC) to deteraine whether wells shall be completed flush or project...soil test boring, the borehole will be tremie-grouted to the surface using bentonite and neat cement grout according to NCNRCD abandonment

  12. Installation Restoration Program (IRP). Phase 2. Confirmation/Quantification. Stage 1. Buckley Air National Guard Base, Colorado.

    Science.gov (United States)

    1986-03-21

    UNLIMITED PREPARED FOR HEADQUARTERS AIR NATIONAL GUARD COMMAND SURGEON’S OFFICE (ANGSC/ SGB ) BIOENVIRONMENTAL ENGINEERING DIVISION C ANDREWS AIR FORCE...FOR BUCKIEY AIR NATIONAL GUARD BASE COLORADO HEADQUARTERS AIR NATIONAL GUARD COMMAND SURGEON’S OFFICE (ANGSC/ SGB ) BIOENVIRONMENTAL ENGINEERING...was at the standard. Verification should be done with a more sensitive analysis. , In order to determine whether ground water contamination is

  13. Installed Base as a Facilitator for User-Driven Innovation: How Can User Innovation Challenge Existing Institutional Barriers?

    Directory of Open Access Journals (Sweden)

    Synnøve Thomassen Andersen

    2012-01-01

    Full Text Available The paper addresses an ICT-based, user-driven innovation process in the health sector in rural areas in Norway. The empirical base is the introduction of a new model for psychiatric health provision. This model is supported by a technical solution based on mobile phones that is aimed to help the communication between professional health personnel and patients. This innovation was made possible through the use of standard mobile technology rather than more sophisticated systems. The users were heavily involved in the development work. Our analysis shows that by thinking simple and small-scale solutions, including to take the user’s needs and premises as a point of departure rather than focusing on advanced technology, the implementation process was made possible. We show that by combining theory on information infrastructures, user-oriented system development, and innovation in a three-layered analytical framework, we can explain the interrelationship between technical, organizational, and health professional factors that made this innovation a success.

  14. Python Introduction and Installation

    Directory of Open Access Journals (Sweden)

    William J. Turkel

    2012-07-01

    Full Text Available This first lesson in our section on dealing with Online Sources is designed to get you and your computer set up to start programming. We will focus on installing the relevant software – all free and reputable – and finally we will help you to get your toes wet with some simple programming that provides immediate results. In this opening module you will install the Python programming language, the Beautiful Soup HTML/XML parser, and a text editor. Screencaps provided here come from Komodo Edit, but you can use any text editor capable of working with Python. Here’s a list of other options: Python Editors. Once everything is installed, you will write your first programs, “Hello World” in Python and HTML.

  15. PET-based molecular nuclear neuro-imaging

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Ho [Gil Medical Center, Gachon (Korea, Republic of)

    2004-04-01

    Molecular nuclear neuro-imaging in CNS drug discovery and development can be divided into four categories that are clearly inter-related. (1) Neuroreceptor mapping to examine the involvement of specific neurotransmitter system in CNS diseases, drug occupancy characteristics and perhaps examine mechanisms of action;(2) Structural and spectroscopic imaging to examine morphological changes and their consequences;(3) Metabolic mapping to provide evidence of central activity and CNS fingerprinting the neuroanatomy of drug effects;(4) Functional mapping to examine disease-drug interactions. In addition, targeted delivery of therapeutic agents could be achieved by modifying stem cells to release specific drugs at the site of transplantation('stem cell pharmacology'). Future exploitation of stem cell biology, including enhanced release of therapeutic factors through genetic stem cell engineering might thus constitute promising pharmaceutical approaches to treating diseases of the nervous system. With continued improvements in instrumentation, identification of better imaging probes by innovative chemistry, molecular nuclear neuro-imaging promise to play increasingly important roles in disease diagnosis and therapy.

  16. Nuclear track-based biosensors with the enzyme laccase

    Energy Technology Data Exchange (ETDEWEB)

    García-Arellano, H. [Departamento de Ciencias Ambientales, División de Ciencias Biológicas y de la Salud, Universidad Autónoma Metropolitana-Lerma, Av. de las Garzas No. 10, Col. El Panteón, Lerma de Villada, Municipio de Lerma, Estado de México, C.P. 52005 (Mexico); Fink, D., E-mail: fink@xanum.uam.mx [Division de Ciencias Naturales e Ingeneria, Universidad Autónoma Metropolitana-Cuajimalpa, Artificios 40, Col. Hidalgo, Del. Álvaro Obregón C.P. 01120, México, D.F. (Mexico); Nuclear Physics Institute, 25068 Řež (Czech Republic); Muñoz Hernández, G. [Division de Ciencias Naturales e Ingeneria, Universidad Autónoma Metropolitana-Cuajimalpa, Artificios 40, Col. Hidalgo, Del. Álvaro Obregón C.P. 01120, México, D.F. (Mexico); Departamento de Fisica, Universidad Autónoma Metropolitana-Iztapalapa, PO Box 55-534, 09340 México, D.F. (Mexico); Vacík, J.; Hnatowicz, V. [Nuclear Physics Institute, 25068 Řež (Czech Republic); Alfonta, L. [Avram and Stella Goldstein-Goren Department of Biotechnology Engineering, Ben-Gurion University of the Negev, PO Box 653, Beer-Sheva 84105 (Israel)

    2014-08-15

    Highlights: • We construct a biosensor using polymer foils with laccase-clad etched nuclear tracks. • We use the biosensor for quantitation of phenolic compounds. • The biosensor can detect picomolar concentrations for some phenolic compounds. - Abstract: A new type of biosensors for detecting phenolic compounds is presented here. These sensors consist of thin polymer foils with laccase-clad etched nuclear tracks. The presence of suitable phenolic compounds in the sensors leads to the formation of enzymatic reaction products in the tracks, which differ in their electrical conductivities from their precursor materials. These differences correlate with the concentrations of the phenolic compounds. Corresponding calibration curves have been established for a number of compounds. The sensors thus produced are capable to cover between 5 and 9 orders of magnitude in concentration – in the best case down to some picomoles. The sensor's detection sensitivity strongly depends on the specific compound. It is highest for caffeic acid and acid blue 74, followed by ABTS and ferulic acid.

  17. Installation Restoration Program. Phase 2. Confirmation/Quantification. Stage 2. Volume 1. Luke Air Force Base, Arizona.

    Science.gov (United States)

    1988-06-15

    1940’s. The STP is located on Glendale Avenue, approximately 2 miles east of the Main Base, and adjacent to the Agua Fria River as shown in Figure 1-7...flow. The effluent from the STP is discharged into a canal that flows into lagoons in the dry Agua Fria River bed. The treated efflu- ent is routinely...alluvial unit). Major water use in the area is for agricultural irrigation. At pres- ent, groundwater is the sole source of potable water at Luke AFB

  18. Nuclear Weapons and Nuclear War. Papers Based on a Symposium of the Forum on Physics and Society of the American Physical Society, (Washington, D.C., April 1982).

    Science.gov (United States)

    Morrison, Philip; And Others

    Three papers on nuclear weapons and nuclear war, based on talks given by distinguished physicists during an American Physical Society-sponsored symposium, are provided in this booklet. They include "Caught Between Asymptotes" (Philip Morrison), "We are not Inferior to the Soviets" (Hans A. Bethe), and "MAD vs. NUTS" (Wolfgang K. H. Panofsky).…

  19. Report transparency and nuclear safety 2007 - CISBIO; Rapport transparence et securite nucleaire 2007 - CISBIO

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of CISBIO, nuclear base installation, for the year 2007. CISBIO realizes at Saclay most of the radiopharmaceuticals and drugs distributed in France for the nuclear medicine. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

  20. Electrical installation technology

    CERN Document Server

    Neidle, Michael

    1982-01-01

    Electrical Installation Technology, Third Edition covers the wide range of subjects that come under the headings of electrical science, installations, and regulations. The book discusses electromagnetism; inductance; static electricity; d.c. circuits; voltage drop and current rating; distribution; and wiring techniques. The text also describes o.c. motors and generators; a.c. motors, transformers; power-factor improvement; earthing and earth-leakage protection; testing; illumination; and the general principles of temperature and heat. Communication systems and equipment; electronics; and site

  1. Electrical installations technology

    CERN Document Server

    Whitfield, J F

    1968-01-01

    Electrical Installations Technology covers the syllabus of the City and Guilds of London Institute course No. 51, the "Electricians B Certificate”. This book is composed of 15 chapters that deal with basic electrical science and electrical installations. The introductory chapters discuss the fundamentals and basic electrical principles, including the concept of mechanics, heat, magnetic fields, electric currents, power, and energy. These chapters also explore the atomic theory of electric current and the electric circuit, conductors, and insulators. The subsequent chapter focuses on the chemis

  2. Radioactivity and radioprotection: the every day life in a nuclear installation. Press tour at CEA/GRENOBLE 18 november 1999; Radioactivite et radioprotection: la vie quotidienne dans une installation nucleaire. Voyage de presse au Centre CEA/CADARACHE 18 novembre 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    In the framework of the public information, this paper gives a general information on the radioactivity and the radioprotection at the CEA/Cadarache center. A first part is devoted to a presentation of the radioactivity with definitions and radiation effects on the human being and the environment. An other part presents the radioprotection activities and regulations. The last part deals with specific activities of the CEA/Cadarache: the CASCAD installations for spent fuels storage, the LECA Laboratory for the Examination of Active Fuels and a dismantling installation for big irradiated objects. Historical aspects of the CEA/Cadarache are also provided. (A.L.B.)

  3. Recent Canadian advances in nuclear-based hydrogen production and the thermochemical Cu-Cl cycle

    Energy Technology Data Exchange (ETDEWEB)

    Naterer, G. [Canada Research Chair Professor, University of Ontario Institute of Technology (UOIT), 2000 Simcoe Street, Oshawa, Ontario L1H 7K4 (Canada); Suppiah, S. [Manager, Hydrogen Isotopes Technology Branch, AECL, Chalk River, Ontario K0J 1J0 (Canada); Lewis, M. [Chemist, Chemical Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, Illinois 60439 (United States); Gabriel, K. [Associate Provost, Research, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Dincer, I.; Rosen, M.A. [Professor of Mechanical Engineering, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Fowler, M. [Assistant Professor of Chemical Engineering, University of Waterloo, 200 University Avenue, Waterloo, Ontario N2L 3G1 (Canada); Rizvi, G. [Assistant Professor of Mechanical Engineering, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Easton, E.B. [Assistant Professor of Chemistry, UOIT, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada); Ikeda, B.M.; Pioro, I. [Associate Professor, Faculty of Energy Systems and Nuclear Science, UOIT, 2000 Simcoe St., Oshawa, ON L1H 7K4 (Canada); Kaye, M.H.; Lu, L. [Assistant Professor, Faculty of Energy Systems and Nuclear Science, UOIT, 2000 Simcoe Street, Oshawa, Ontario L1H 7K4 (Canada); Spekkens, P. [Vice President of Science and Technology Development, Ontario Power Generation, 889 Brock Road, Pickering, Ontario (Canada); Tremaine, P. [Professor of Chemistry, University of Guelph, 50 Stone Road East, Guelph, Ontario N1G 2W1 (Canada); Mostaghimi, J. [Canada Research Chair Professor, Mechanical Engineering, University of Toronto, Toronto, Ontario M5S 3E5 (Canada); Avsec, J. [Assistant Professor, Faculty of Energy Technology, Univ. of Maribor, Hocevarjev trg 1, 8270 Krsko (Slovenia); Jiang, J. [Professor and NSERC/UNENE Senior Industrial Research Chair, Electrical and Computer Engineering, Univ. of Western Ontario, London, Ontario N6A 5B9 (Canada)

    2009-04-15

    This paper presents recent Canadian advances in nuclear-based production of hydrogen by electrolysis and the thermochemical copper-chlorine (Cu-Cl) cycle. This includes individual process and reactor developments within the Cu-Cl cycle, thermochemical properties, advanced materials, controls, safety, reliability, economic analysis of electrolysis at off-peak hours, and integrating hydrogen plants with Canada's nuclear power plants. These enabling technologies are being developed by a Canadian consortium, as part of the Generation IV International Forum (GIF) for hydrogen production from the next generation of nuclear reactors. (author)

  4. Applicability of base-isolation R D in non-reactor facilities to a nuclear reactor plant

    Energy Technology Data Exchange (ETDEWEB)

    Seidensticker, R.W.; Chang, Y.W.

    1990-01-01

    Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. The question, therefore, is to what extent can research and development (R D) for non-nuclear use be used to provide technological data needed for seismic isolation of a nuclear power plant. This question, of course is not unique to seismic isolation. Virtually every structural component, system, or piece of equipment used in nuclear power plants is also used in non- nuclear facilities. Experience shows that considerable effort is needed to adapt conventional technology into a nuclear power plant. Usually, more thorough analysis is required, material and fabrication quality-control requirements are more stringent as are controls on field installation. In addition, increased emphasis on maintainability and inservice inspection throughout the life of the plant is generally required to gain acceptance in nuclear power plant application. This paper reviews the R D programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs.

  5. Electric Vehicle Preparedness: Task 2, Identification of Vehicles for Installation of Data Loggers for Marine Corps Base Camp Lejeune

    Energy Technology Data Exchange (ETDEWEB)

    Schey, Stephen [Idaho National Lab. (INL), Idaho Falls, ID (United States); Francfort, Jim [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    In Task 1, a survey was completed of the inventory of non-tactical fleet vehicles at the Marine Corps Base Camp Lejeune (MCBCL) to characterize the fleet. This information and characterization was used to select vehicles for further monitoring, which involves data logging of vehicle movements in order to identify the vehicle’s mission and travel requirements. Individual observations of these selected vehicles provide the basis for recommendations related to PEV adoption. It also identifies whether a battery electric vehicle or plug-in hybrid electric vehicle (collectively referred to as PEVs) can fulfill the mission requirements and provides observations related to placement of PEV charging infrastructure. This report provides the list of vehicles selected by MCBCL and Intertek for further monitoring and fulfills the Task 2 requirements.

  6. Nuclear track-based biosensors with the enzyme laccase

    Science.gov (United States)

    García-Arellano, H.; Fink, D.; Muñoz Hernández, G.; Vacík, J.; Hnatowicz, V.; Alfonta, L.

    2014-08-01

    A new type of biosensors for detecting phenolic compounds is presented here. These sensors consist of thin polymer foils with laccase-clad etched nuclear tracks. The presence of suitable phenolic compounds in the sensors leads to the formation of enzymatic reaction products in the tracks, which differ in their electrical conductivities from their precursor materials. These differences correlate with the concentrations of the phenolic compounds. Corresponding calibration curves have been established for a number of compounds. The sensors thus produced are capable to cover between 5 and 9 orders of magnitude in concentration - in the best case down to some picomoles. The sensor's detection sensitivity strongly depends on the specific compound. It is highest for caffeic acid and acid blue 74, followed by ABTS and ferulic acid.

  7. Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

  8. The development of a neuroscience-based methodology for the nuclear energy learning/teaching process

    Energy Technology Data Exchange (ETDEWEB)

    Barabas, Roberta de C.; Sabundjian, Gaiane, E-mail: robertabarabas@usp.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    When compared to other energy sources such as fossil fuels, coal, oil, and gas, nuclear energy has perhaps the lowest impact on the environment. Moreover, nuclear energy has also benefited other fields such as medicine, pharmaceutical industry, and agriculture, among others. However, despite all benefits that result from the peaceful uses of nuclear energy, the theme is still addressed with prejudice. Education may be the starting point for public acceptance of nuclear energy as it provides pedagogical approaches, learning environments, and human resources, which are essential conditions for effective learning. So far nuclear energy educational researches have been conducted using only conventional assessment methods. The global educational scenario has demonstrated absence of neuroscience-based methods for the teaching of nuclear energy, and that may be an opportunity for developing new strategic teaching methods that will help demystifying the theme consequently improving public acceptance of this type of energy. This work aims to present the first step of a methodology in progress based on researches in neuroscience to be applied to Brazilian science teachers in order to contribute to an effective teaching/learning process. This research will use the Implicit Association Test (IAT) to verify implicit attitudes of science teachers concerning nuclear energy. Results will provide data for the next steps of the research. The literature has not reported a similar neuroscience-based methodology applied to the nuclear energy learning/teaching process; therefore, this has demonstrated to be an innovating methodology. The development of the methodology is in progress and the results will be presented in future works. (author)

  9. Transmutation of radioactive nuclear waste – present status and requirement for the problem-oriented nuclear data base

    Indian Academy of Sciences (India)

    Yu A Korovin; V V Artisyuk; A V Ignatyuk; G B Pilnov; A Yu Stankovsky; Yu E Titarenko; S G Yavshits

    2007-02-01

    Transmutation of long-lived actinides and fission products becomes an important issue of the overall nuclear fuel cycle assessment, both for existing and future reactor systems. Reliable nuclear data are required for analysis of associated neutronics. The present paper gives a review of the status of nuclear data analysis focusing on the waste transmutation problem.

  10. Concept of development of nuclear power based on LMFBR operation in open nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Toshinsky, G.I. [Inst. of Physics and Power Engineering, Obninsk (Russian Federation)

    1996-08-01

    The preliminary assessments performed show that it is reasonable to investigate in the future the possibilities of FBR efficient operation with the open NFC. To improve its safety it is expedient to use the lead-bismuth alloy as a coolant. In order to operate with depleted uranium make-up it is necessary to meet a number of requirements providing the reactor criticality due to plutonium build-up and BR > 1. These requirements are as follows: a large core (20--25 m{sup 3}); a high fuel volume fraction (> 60%); utilization of dense metallic fuel; a high fuel burn-up--at a level of 20% of h.a. Making use of these reactors should allow the NP fuel base to be extended more than 10 times without making NFC closed. It provides improving NP safety during a sufficiently long stage of its development.

  11. Study of visualized simulation and analysis of nuclear fuel cycle system based on multilevel flow model

    Institute of Scientific and Technical Information of China (English)

    LIU Jing-Quan; YOSHIKAWA Hidekazu; ZHOU Yang-Ping

    2005-01-01

    Complex energy and environment system, especially nuclear fuel cycle system recently raised social concerns about the issues of economic competitiveness, environmental effect and nuclear proliferation. Only under the condition that those conflicting issues are gotten a consensus between stakeholders with different knowledge background, can nuclear power industry be continuingly developed. In this paper, a new analysis platform has been developed to help stakeholders to recognize and analyze various socio-technical issues in the nuclear fuel cycle system based on the functional modeling method named Multilevel Flow Models (MFM) according to the cognition theory of human being. Its character is that MFM models define a set of mass, energy and information flow structures on multiple levels of abstraction to describe the functional structure of a process system and its graphical symbol representation and the means-end and part-whole hierarchical flow structure to make the represented process easy to be understood. Based upon this methodology, a micro-process and a macro-process of nuclear fuel cycle system were selected to be simulated and some analysis processes such as economics analysis, environmental analysis and energy balance analysis related to those flows were also integrated to help stakeholders to understand the process of decision-making with the introduction of some new functions for the improved Multilevel Flow Models Studio, and finally the simple simulation such as spent fuel management process simulation and money flow of nuclear fuel cycle and its levelised cost analysis will be represented as feasible examples.

  12. Drug and alcohol abuse: the bases for employee assistance programs in the nuclear-utility industry

    Energy Technology Data Exchange (ETDEWEB)

    Radford, L.R.; Rankin, W.L.; Barnes, V.; McGuire, M.V.; Hope, A.M.

    1983-07-01

    This report describes the nature, prevalence, and trends of drug and alcohol abuse among members of the US adult population and among personnel in non-nuclear industries. Analogous data specific to the nuclear utility industry are not available, so these data were gathered in order to provide a basis for regulatory planning. The nature, prevalence, and trend inforamtion was gathered using a computerized literature, telephone discussions with experts, and interviews with employee assistance program representatives from the Seattle area. This report also evaluates the possible impacts that drugs and alcohol might have on nuclear-related job performance, based on currently available nuclear utility job descriptions and on the scientific literature regarding the impairing effects of drugs and alcohol on human performance. Employee assistance programs, which can be used to minimize or eliminate job performance decrements resulting from drug or alcohol abuse, are also discussed.

  13. Nuclear-Spin Gyroscope Based on an Atomic Co-Magnetometer

    Science.gov (United States)

    Romalis, Michael; Komack, Tom; Ghost, Rajat

    2008-01-01

    An experimental nuclear-spin gyroscope is based on an alkali-metal/noblegas co-magnetometer, which automatically cancels the effects of magnetic fields. Whereas the performances of prior nuclear-spin gyroscopes are limited by sensitivity to magnetic fields, this gyroscope is insensitive to magnetic fields and to other external perturbations. In addition, relative to prior nuclear-spin gyroscopes, this one exhibits greater sensitivity to rotation. There is commercial interest in development of small, highly sensitive gyroscopes. The present experimental device could be a prototype for development of nuclear spin gyroscopes suitable for navigation. In comparison with fiber-optic gyroscopes, these gyroscopes would draw less power and would be smaller, lighter, more sensitive, and less costly.

  14. 探析核岛重要厂用水系统管道安装问题%Analysis of the Problem of Nuclear Island Important Plant Water Pipe Installation

    Institute of Scientific and Technical Information of China (English)

    杨裕芳

    2015-01-01

    The nuclear island of nuclear reactor in nuclear power plant containment and reactor systems collectively, the main function to use nuclear fission to produce steam. There are many complicated problems in the construction of the nuclear island plant water pipeline system, and need to related construction personnel to pay attention to and solve.%核岛是核电站安全壳内的核反应堆和与反应堆有关的各个系统的统称,主要功能为利用核裂变产生蒸汽。在核岛重要厂用水系统管道的施工中,存在许多比较复杂的问题,需要相关施工人员予以重视和解决。

  15. Leadership for Sustainable Installations

    Science.gov (United States)

    2011-04-01

    way into the lexicon of the Army and installation management ( Warnock , 2009). Accordingly, the Undersecretary of the Army is the Senior...business approach, the Report Documentation Page Form ApprovedOMB No. 0704-0188 Public reporting burden for the collection of information is estimated...needed, and completing and reviewing the collection of information . Send comments regarding this burden estimate or any other aspect of this collection

  16. Installing the ALICE detector

    CERN Multimedia

    Maximilien Brice

    2006-01-01

    The huge iron yoke in the cavern at Point 2 in the LHC tunnel is prepared for the installation of the ALICE experiment. The yoke is being reused from the previous L3 experiment that was located at the same point during the LEP project from 1989 to 2000. ALICE will be inserted piece by piece into the cradle where it will be used to study collisions between two beams of lead ions.

  17. First ALICE detectors installed!

    CERN Document Server

    2006-01-01

    Detectors to track down penetrating muon particles are the first to be placed in their final position in the ALICE cavern. The Alice muon spectrometer: in the foreground the trigger chamber is positioned in front of the muon wall, with the dipole magnet in the background. After the impressive transport of its dipole magnet, ALICE has begun to fill the spectrometer with detectors. In mid-July, the ALICE muon spectrometer team achieved important milestones with the installation of the trigger and the tracking chambers of the muon spectrometer. They are the first detectors to be installed in their final position in the cavern. All of the eight half planes of the RPCs (resistive plate chambers) have been installed in their final position behind the muon filter. The role of the trigger detector is to select events containing a muon pair coming, for instance, from the decay of J/ or Y resonances. The selection is made on the transverse momentum of the two individual muons. The internal parts of the RPCs, made o...

  18. DSP integrated, parameterized, FPGA based cavity simulator and controller for VUV-FEL. SIMCON ver.2.1. installation and configuration procedures - User's manual

    Energy Technology Data Exchange (ETDEWEB)

    Koprek, W.; Pucyk, P.; Czarski, T.; Pozniak, K.T.; Romaniuk, R.S. [Warsaw Univ. of Technology (Poland). Inst. of Electronic Systems

    2005-07-01

    The note describes integrated system of hardware controller and simulator of the resonant superconducting, narrowband niobium cavity, originally considered for the TTF and TESLA in DESY, Hamburg (now predicted for the VUV and X-Ray FEL). The controller bases on a programmable circuit Xilinx VirtexII V3000 embedded on a PCB XtremeDSP Development Kit by Nallatech. The FPGA circuit configuration was done in the VHDL language. The internal hardware multiplication components, present in Virtex II chips, were used, to improve the floating point calculation efficiency. The implementation was achieved of a device working in the real time, according to the demands of the LLRF control system for the TESLA Test Facility. The device under consideration will be referred to as superconducting cavity (SCCav) SIMCON throughout this work. This document is intended to be used by end users and operators. It describes step by step how to install SIMCON in specific configuration, how and what software to copy to computer. There is described set of basic Matlab functions for developers of control algorithms. This paper also contains brief description how to use Matlab function of one algorithm with its graphic user panels. (orig.)

  19. Radiation Protection Optimization for Removal and Installation of Nozzle Dams at Ningde Nuclear Powe r Plant%宁德核电厂蒸汽发生器装拆堵板的辐射防护最优化管理

    Institute of Scientific and Technical Information of China (English)

    邓克春; 郭飞; 杨岩; 杨小强

    2014-01-01

    蒸汽发生器一次侧水室装拆堵板是压水堆核电站大修的一项重要工作,具有较大的辐射风险。本文主要介绍了宁德核电站在安装和拆卸堵板工作中,实施辐射防护最优化的方法及效果。%The removal and installation of nozzle dams (RIND ) at primary water chamber of steam generator (SG ) is one of the essential maintenance jobs ,with high radiation risk during outage at a PWR nuclear power plant .This paper introduces the method and effect of implementing ALARA principle for RIND by radiation protection (RP) staff at Ningde nuclear power plant .

  20. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  1. Phylogeny of the bears (Ursidae) based on nuclear and mitochondrial genes.

    Science.gov (United States)

    Yu, Li; Li, Qing-wei; Ryder, O A; Zhang, Ya-ping

    2004-08-01

    The taxomic classification and phylogenetic relationships within the bear family remain argumentative subjects in recent years. Prior investigation has been concentrated on the application of different mitochondrial (mt) sequence data, herein we employ two nuclear single-copy gene segments, the partial exon 1 from gene encoding interphotoreceptor retinoid binding protein (IRBP) and the complete intron 1 from transthyretin (TTR) gene, in conjunction with previously published mt data, to clarify these enigmatic problems. The combined analyses of nuclear IRBP and TTR datasets not only corroborated prior hypotheses, positioning the spectacled bear most basally and grouping the brown and polar bear together but also provided new insights into the bear phylogeny, suggesting the sister-taxa association of sloth bear and sun bear with strong support. Analyses based on combination of nuclear and mt genes differed from nuclear analysis in recognizing the sloth bears as the earliest diverging species among the subfamily ursine representatives while the exact placement of the sun bear did not resolved. Asiatic and American black bears clustered as sister group in all analyses with moderate levels of bootstrap support and high posterior probabilities. Comparisons between the nuclear and mtDNA findings suggested that our combined nuclear dataset have the resolving power comparable to mtDNA dataset for the phylogenetic interpretation of the bear family. As can be seen from present study, the unanimous phylogeny for this recently derived family was still not produced and additional independent genetic markers were in need.

  2. 步进电机式汽车电子仪表的装针过程设计与控制%Process Design and Control of Pointer Installation of Auto Electronic Instrument Based on Stepper Motor

    Institute of Scientific and Technical Information of China (English)

    张彦平

    2012-01-01

    对步进电机式电子仪表的工作过程进行简要介绍,详细阐述其装针过程设计与控制。%The author briefly introduces the working process of electronic instrument based on stepper motor, elaborates the process design and control of its pointer installation.

  3. Cyber security best practices for the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Badr, I. [Rational IBM Software Group, IBM Corporation, Evanston, IL 60201 (United States)

    2012-07-01

    When deploying software based systems, such as, digital instrumentation and controls for the nuclear industry, it is vital to include cyber security assessment as part of architecture and development process. When integrating and delivering software-intensive systems for the nuclear industry, engineering teams should make use of a secure, requirements driven, software development life cycle, ensuring security compliance and optimum return on investment. Reliability protections, data loss prevention, and privacy enforcement provide a strong case for installing strict cyber security policies. (authors)

  4. Thoria-based nuclear fuels thermophysical and thermodynamic properties, fabrication, reprocessing, and waste management

    CERN Document Server

    Bharadwaj, S R

    2013-01-01

    This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. With the help of key databases, many of which were created by the authors, information is presented in the form of tables, figures, schematic diagrams and flow sheets, and photographs. This information will be useful for scientists and engineers working in the nuclear field, particularly for design and simulation, and for establishing the technology. One special feature is the inclusion of the latest information on thoria-based fuels, especially on the use of thorium in power generation, as it has less proliferation potential for nuclear weapons. Given its natural abundance, thorium offers a future alternative to uranium fuels in nuc...

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

    Energy Technology Data Exchange (ETDEWEB)

    Reventos, F.; Vives, E.; Brunet, A.; Sabate, R.; Calvino, F.; Batet, L.

    2014-07-01

    From its first edition, that took place in 2011-2012, the Masters degree in Nuclear Engineering from BarcelonaTECH has been using techniques of Project-Based Learning to fulfill the purpose of training nuclear engineers with a profile suitable for positions in the industry. The Master is sponsored by ENDESA and relies on the collaboration with institutions and companies. The Master is embedded in EMINE, the European Master in Innovation in Nuclear Energy, supported by KIC-InnoEnergy and the European Institute of Technology. (Author)

  6. Structural Code Considerations for Solar Rooftop Installations.

    Energy Technology Data Exchange (ETDEWEB)

    Dwyer, Stephen F.; Dwyer, Brian P.; Sanchez, Alfred

    2014-12-01

    Residential rooftop solar panel installations are limited in part by the high cost of structural related code requirements for field installation. Permitting solar installations is difficult because there is a belief among residential permitting authorities that typical residential rooftops may be structurally inadequate to support the additional load associated with a photovoltaic (PV) solar installation. Typical engineering methods utilized to calculate stresses on a roof structure involve simplifying assumptions that render a complex non-linear structure to a basic determinate beam. This method of analysis neglects the composite action of the entire roof structure, yielding a conservative analysis based on a rafter or top chord of a truss. Consequently, the analysis can result in an overly conservative structural analysis. A literature review was conducted to gain a better understanding of the conservative nature of the regulations and codes governing residential construction and the associated structural system calculations.

  7. Installation of the LHC transfer lines begins

    CERN Multimedia

    Patrice Loïez

    2003-01-01

    The first of 700 magnets has been installed in one of the two transfer tunnels built to transfer the SPS beam into the LHC. The start of this first installation phase of the LHC transfer lines provides the opportunity to launch a new and highly original modular system for transporting and installing all kinds of magnets in very narrow tunnels. The system is based on very compact bogies, up to four of which can be coupled together to form a convoy. The wheels are fitted with individual motors enabling them to swivel through an angle of 90° and the convoy to move laterally. In this way the magnet is delivered directly to its installation point, but beneath the beamline. It is then raised into its final position in the beamline using air cushions, which form an integrated part of the transport system. Here we see the transport vehicle alongside the magnet supports. Visible in the background is the first magnet in place.

  8. Development of a severe accident module of a nuclear power plant based in the MELCOR nuclear code and its incorporation to the room simulator; Desarrollo del modulo de accidentes severos de una central nucleoelectrica basado en el codigo nuclear MELCOR y su incorporacion al simulador de aula

    Energy Technology Data Exchange (ETDEWEB)

    Cortes M, F.S.; Ramos P, J.C.; Nelson E, P.; Chavez M, C. [Facultad de Ingenieria, Division de Ingenieria Electrica, Grupo de Ingenieria Nuclear, UNAM, Ciudad Universitaria, Distrito Federal (Mexico)]. E-mail: samuelcortes@correo.unam.mx

    2004-07-01

    This work describes the development of the Severe Accidents Module (MAS) based on the Code MELCOR and its incorporation to the Simulator of Classroom of the Group of Nuclear Engineering of the Engineering Faculty (GrINFI) of the National Autonomous University of Mexico (UNAM). The module of Severe Accidents has the purpose of counting with installed and operational capacity for the simulation of accident sequences with capacitation purposes, training, analysis and design. A shallow description of SimAula is presented, and the philosophy used to obtain the interactive version of MELCOR are discussed, as well as its implementation in the atmosphere of SimAula. Finally, after confirming the correct operation of the development of the tool, some possible topics are discussed for specific applications of the MAS. (Author)

  9. Proceedings of the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Benson, Jody [Editor; Patterson, Eileen F. [Editor

    2007-09-25

    These proceedings contain papers prepared for the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 25-27 September, 2007 in Denver, Colorado. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  10. Proceedings of the 2011 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Patterson, Eileen F. [Editor; Sandoval, Marisa N. [Editor

    2011-09-13

    These proceedings contain papers prepared for the Monitoring Research Review 2011: Ground-Based Nuclear Explosion Monitoring Technologies, held 13-15 September, 2011 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), National Science Foundation (NSF), and other invited sponsors. The scientific objectives of the research are to improve the United States' capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  11. Proceedings of the 2010 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A [Editor; Patterson, Eileen F [Editor

    2010-09-21

    These proceedings contain papers prepared for the Monitoring Research Review 2010: Ground-Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2010 in Orlando, Florida,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, National Science Foundation (NSF), Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  12. Proceedings of the 28th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Benson, Jody [Editor; Patterson, Eileen F. [Editor

    2006-09-19

    These proceedings contain papers prepared for the 28th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 19-21 September, 2006 in Orlando, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  13. Proceedings of the 30th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marv A [Los Alamos National Laboratory; Aguilar-chang, Julio [Los Alamos National Laboratory; Arrowsmith, Marie [Los Alamos National Laboratory; Arrowsmith, Stephen [Los Alamos National Laboratory; Baker, Diane [Los Alamos National Laboratory; Begnaud, Michael [Los Alamos National Laboratory; Harste, Hans [Los Alamos National Laboratory; Maceira, Monica [Los Alamos National Laboratory; Patton, Howard [Los Alamos National Laboratory; Phillips, Scott [Los Alamos National Laboratory; Randall, George [Los Alamos National Laboratory; Revelle, Douglas [Los Alamos National Laboratory; Rowe, Charlotte [Los Alamos National Laboratory; Stead, Richard [Los Alamos National Laboratory; Steck, Lee [Los Alamos National Laboratory; Whitaker, Rod [Los Alamos National Laboratory; Yang, Xiaoning [Los Alamos National Laboratory

    2008-09-23

    These proceedings contain papers prepared for the 30th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 23-25 September, 2008 in Portsmouth, Virginia. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States’ capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  14. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  15. Samus Toroid Installation Fixture

    Energy Technology Data Exchange (ETDEWEB)

    Stredde, H.; /Fermilab

    1990-06-27

    The SAMUS (Small Angle Muon System) toroids have been designed and fabricated in the USSR and delivered to D0 ready for installation into the D0 detector. These toroids will be installed into the aperture of the EF's (End Toroids). The aperture in the EF's is 72-inch vertically and 66-inch horizontally. The Samus toroid is 70-inch vertically by 64-inch horizontally by 66-inch long and weighs approximately 38 tons. The Samus toroid has a 20-inch by 20-inch aperture in the center and it is through this aperture that the lift fixture must fit. The toroid must be 'threaded' through the EF aperture. Further, the Samus toroid coils are wound about the vertical portion of the aperture and thus limit the area where a lift fixture can make contact and not damage the coils. The fixture is designed to lift along a surface adjacent to the coils, but with clearance to the coil and with contact to the upper steel block of the toroid. The lift and installation will be done with the 50 ton crane at DO. The fixture was tested by lifting the Samus Toroid 2-inch off the floor and holding the weight for 10 minutes. Deflection was as predicted by the design calculations. Enclosed are sketches of the fixture and it relation to both Toroids (Samus and EF), along with hand calculations and an Finite Element Analysis. The PEA work was done by Kay Weber of the Accelerator Engineering Department.

  16. Mineral mining installation

    Energy Technology Data Exchange (ETDEWEB)

    Plevak, L.; Weirich, W.

    1982-04-20

    A longwall mineral mining installation has a longwall conveyor and a plurality of roof support units positioned side-by-side at the goaf side of the conveyor. The hydraulic appliances of the roof support units, such as their hydraulic props, hydraulic advance rams and hydraulic control valves, are supplied with pressurized hydraulic fluid from hydraulic supply lines which run along the goaf side of the conveyor. A plurality of flat, platelike intermediate members are provided at the goaf side of the conveyor. These intermediate members are formed with internal ducts for feeding the hydraulic fluid from the supply lines to the hydraulic appliances of the roof support units.

  17. Nuclear clocks based on resonant excitation of gamma-transitions

    CERN Document Server

    Peik, Ekkehard

    2015-01-01

    We review the ideas and concepts for a clock that is based on a radiative transition in the nucleus rather than in the electron shell. This type of clock offers advantages like an insensitivity against field-induced systematic frequency shifts and the opportunity to obtain high stability from interrogating many nuclei in the solid state. Experimental work concentrates on the low-energy (about 8 eV) isomeric transition in Th-229. We review the status of the experiments that aim at a direct optical observation of this transition and outline the plans for high-resolution laser spectroscopy experiments.

  18. Study on the dynamic response analysis for evaluating the effectiveness of base isolation for nuclear components

    Energy Technology Data Exchange (ETDEWEB)

    Mori, Kazunari; Tsutsumi, Hideaki; Yamada, Hiroyuki; Ebisawa, Katsumi; Shibata, Katsuyuki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-07-01

    Introduction of the base isolation technique into the seismic design of nuclear power plant components as well as buildings has been expected as one of the effective countermeasure to reduce the seismic force applied to components. A research program on the base isolation of nuclear components has been carried out at the Japan Atomic Energy Research Institute (JAERI) since 1991. A methodology and a computer code (EBISA: Equipment Base Insolation System Analysis) for evaluating the failure frequency of the nuclear component with the base isolation were developed. In addition, a test program, which is concerned with the above development, aiming at improvement of failure frequency analysis models in the code has been conducted since 1996 to investigate the dynamic behavior and to verify the effectiveness of component base isolation systems. In the failure frequency analysis, methodology for evaluating the actual dynamic responses of the nuclear components with the base isolation in detail has been examined. In the methodology, the actual responses are computed by considering the scatter in mechanical properties of rock masses, reactor building and components under many earthquake motions with various frequency characteristics. The failure frequency of component is computed as the conditional probability where the actual response exceeds the capacity of components. It is a very important in the above methodology to investigates the dynamic response analysis method for the ground, reactor building and nuclear components as well as the scattering factors in the dynamic analysis. This report describes the accuracy of the dynamic response analysis method and analysis models, and the influence of scatters in properties of rock masses and reactor building on the dynamic response. (author)

  19. Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

    Energy Technology Data Exchange (ETDEWEB)

    Kimberlyn C. Mousseau

    2011-10-01

    The Nuclear Energy Computational Fluid Dynamics Advanced Modeling and Simulation (NE-CAMS) system is being developed at the Idaho National Laboratory (INL) in collaboration with Bettis Laboratory, Sandia National Laboratory (SNL), Argonne National Laboratory (ANL), Utah State University (USU), and other interested parties with the objective of developing and implementing a comprehensive and readily accessible data and information management system for computational fluid dynamics (CFD) verification and validation (V&V) in support of nuclear energy systems design and safety analysis. The two key objectives of the NE-CAMS effort are to identify, collect, assess, store and maintain high resolution and high quality experimental data and related expert knowledge (metadata) for use in CFD V&V assessments specific to the nuclear energy field and to establish a working relationship with the U.S. Nuclear Regulatory Commission (NRC) to develop a CFD V&V database, including benchmark cases, that addresses and supports the associated NRC regulations and policies on the use of CFD analysis. In particular, the NE-CAMS system will support the Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program, which aims to develop and deploy advanced modeling and simulation methods and computational tools for reliable numerical simulation of nuclear reactor systems for design and safety analysis. Primary NE-CAMS Elements There are four primary elements of the NE-CAMS knowledge base designed to support computer modeling and simulation in the nuclear energy arena as listed below. Element 1. The database will contain experimental data that can be used for CFD validation that is relevant to nuclear reactor and plant processes, particularly those important to the nuclear industry and the NRC. Element 2. Qualification standards for data evaluation and classification will be incorporated and applied such that validation data sets will result in well

  20. Security Design of Remote Maintenance Systems for Nuclear Power Plants Based on ISO/IEC 15408

    Science.gov (United States)

    Watabe, Ryosuke; Oi, Tadashi; Endo, Yoshio

    This paper presents a security design of remote maintenance systems for nuclear power plants. Based on ISO/IEC 15408, we list assets to be protected, threats to the assets, security objectives against the threats, and security functional requirements that achieve the security objectives. Also, we show relations between the threats and the security objectives, and relations between the security objectives and the security functional requirements. As a result, we concretize a necessary and sufficient security design of remote maintenance systems for nuclear power plants that can protect the instrumentation and control system against intrusion, impersonation, tapping, obstruction and destruction.

  1. Coherence and control of quantum registers based on electronic spin in a nuclear spin bath.

    Science.gov (United States)

    Cappellaro, P; Jiang, L; Hodges, J S; Lukin, M D

    2009-05-29

    We consider a protocol for the control of few-qubit registers comprising one electronic spin embedded in a nuclear spin bath. We show how to isolate a few proximal nuclear spins from the rest of the bath and use them as building blocks for a potentially scalable quantum information processor. We describe how coherent control techniques based on magnetic resonance methods can be adapted to these solid-state spin systems, to provide not only efficient, high fidelity manipulation but also decoupling from the spin bath. As an example, we analyze feasible performances and practical limitations in the realistic setting of nitrogen-vacancy centers in diamond.

  2. CNGS Reflector installed

    CERN Multimedia

    2006-01-01

    A major component that will help target the CNGS neutrino beam for its 732km journey through the earth's crust, from CERN to the Gran Sasso laboratory in Italy, has been installed in its final position. The transport of the huge magnetic horn reflector through the CNGS access gallery. A team from CNGS and TS/IC, and the contractors DBS, transported the magnetic horn reflector on 5th December, in a carefully conducted operation that took just under two hours. The reflector is 7m long, 1.6m in diameter and 1.6 tonnes in weight. With only a matter of centimetres to spare on either side, the reflector was transported through the CNGS access gallery, before being installed in the experiment's target chamber. The larger of two magnetic horns, the reflector will help refocus sprays of high energy pions and kaons emitted after a 0.5MW stream of protons from the Super Proton Synchrotron (SPS) strikes nucleons in a graphite target. The horns are toroidal magnetic lenses and work with high pulsed currents: 150 kA f...

  3. Influence of various parameters on effectiveness of seismic base isolation of nuclear equipment

    Energy Technology Data Exchange (ETDEWEB)

    Ebisawa, K. [Japan Atomic Research Inst., Ibaraki-ken (Japan); Kameoka, H. [CRC Research Inst., Chiba-chi (Japan); Takenouchi, I.; Kajiki, S. [Oiles Corp. (Japan)

    1995-12-31

    Authors developed a methodology and EBISA code for evaluating the applicability and the effectiveness of seismic base isolation of nuclear equipment. In order to investigate the influence of various parameters on the effectiveness of seismic base isolation, a sensitivity analysis was carried out for an emergency transformer with the base isolation devices. It was proved that seismic base isolation of equipment is very effective. This effectiveness can be influenced by the differences of the base isolation devices and the direction of the input seismic wave. (author). 7 refs., 3 figs., 3 tabs.

  4. Development and Enhancement of Web-based Nuclear Education System and It's Enhancement

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Sipyo; Lee, K. B.; Nam, Y. M; Kim, H. K.; Hwang, I. A.; Yang, S. W.; Nam, J. S.; Yoo, H. W.

    2012-02-15

    To deliver rapidly changing technologies effectively and economically, E-learning in the field of nuclear technology is being done gradually. In the first year of this project, 'Development and Enhancement of Web-based Nuclear Education System; we had established a server system, fitting-up several home pages in NTC(Nuclear Training and Education Center in KAERI) and newly developed LMS(Learning Management System). We had selected a MOODLE for it is one of popular open source in LMS field, and connected to the ANENT(Asian Nuclear in Education for Nuclear Technology) web portal, which is co-operating with IAEA/NKM. We had produced e-learning content mainly composed of the video clip that was taken by making a film of the lecturing in the course of training and education in NTC. The running time of the content is 100 hours totally. This e-learning content is going to reinforce by adding quiz and Q and A. Another activity is web-conferencing between NWU in South Africa and KAERI, which executed 4 times successfully. We are going to make a pre-course for the foreigners who will take part in our training and education course.

  5. CAD-based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC

    Science.gov (United States)

    Wu, Yican; Song, Jing; Zheng, Huaqing; Sun, Guangyao; Hao, Lijuan; Long, Pengcheng; Hu, Liqin

    2014-06-01

    Monte Carlo (MC) method has distinct advantages to simulate complicated nuclear systems and is envisioned as routine method for nuclear design and analysis in the future. High fidelity simulation with MC method coupled with multi-physical phenomenon simulation has significant impact on safety, economy and sustainability of nuclear systems. However, great challenges to current MC methods and codes prevent its application in real engineering project. SuperMC is a CAD-based Monte Carlo program for integrated simulation of nuclear system developed by FDS Team, China, making use of hybrid MC-deterministic method and advanced computer technologies. The design aim, architecture and main methodology of SuperMC were presented in this paper. SuperMC2.1, the latest version for neutron, photon and coupled neutron and photon transport calculation, has been developed and validated by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model. SuperMC is still in its evolution process toward a general and routine tool for nuclear system. Warning, no authors found for 2014snam.conf06023.

  6. High Repetition Rate, LINAC-based Nuclear Resonance Fluorescence FY 2009 Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Mathew Kinlaw; Scott Watson; James Johnson; Alan Hunt; Heather Seipel; Edward Reedy

    2009-10-01

    Nuclear Resonance Fluorescence (NRF), which is possible for nuclei with atomic numbers greater than helium (Z=2), occurs when a nuclear level is excited by resonant absorption of a photon and subsequently decays by reemission of a photon. The excited nuclear states can become readily populated, provided the incident photon’s energy is within the Doppler-broadened width of the energy level being excited. Utilizing continuous energy photon spectra, as is characteristic of a bremsstrahlung photon beam, as the inspection source, ensures that at least some fraction of the impinging beam will contribute to the population of the excited energy levels in the material of interest. Upon de-excitation, either to the ground state or to a lower-energy excited state, the emitted fluorescence photon’s energy will correspond to the energy difference between the excited state and the state to which it decays. As each isotope inherently contains unique nuclear energy levels, the NRF states for each isotope are also unique. By exploiting this phenomenon, NRF photon detection provides a well-defined signature for identifying the presence of individual nuclear species. This report summarizes the second year (Fiscal Year [FY] 2009) of a collaborative research effort between Idaho National Laboratory, Idaho State University’s Idaho Accelerator Center, and Pacific Northwest National Laboratory. This effort focused on continuing to assess and optimize NRF-based detection techniques utilizing a slightly modified, commercially available, pulsed medical electron accelerator.

  7. Installation of the LHC transfer lines begins

    CERN Multimedia

    Patrice Loïez

    2003-01-01

    The first of 700 magnets has been installed in one of the two transfer tunnels built to transfer the SPS beam into the LHC. The start of this first installation phase of the LHC transfer lines provides the opportunity to launch a new and highly original modular system for transporting and installing all kinds of magnets in very narrow tunnels. The system is based on very compact bogies, up to four of which can be coupled together to form a convoy. The wheels are fitted with individual motors enabling them to swivel through an angle of 90° and the convoy to move laterally. The first installation phase will continue until mid-April. In addition to the magnets, a beam dump facility also has to be installed. The second installation phase will take place later this year and should be completed in 2004, when the TI 8 transfer line is due to be tested. The second transfer line, in tunnel TI 2, should be ready in April 2007, once the LHC magnets have been transported through the downstream section of this tunnel. We...

  8. Installation of the LHC transfer lines begins

    CERN Multimedia

    Patrice Loïez

    2003-01-01

    The first of 700 magnets has been installed in one of the two transfer tunnels built to transfer the SPS beam into the LHC. The start of this first installation phase of the LHC transfer lines provides the opportunity to launch a new and highly original modular system for transporting and installing all kinds of magnets in very narrow tunnels. The system is based on very compact bogies, up to four of which can be coupled together to form a convoy. The wheels are fitted with individual motors enabling them to swivel through an angle of 90° and the convoy to move laterally. The first installation phase will continue until mid-April. In addition to the magnets, a beam dump facility also has to be installed. The second installation phase will take place later this year and should be completed in 2004, when the TI 8 transfer line is due to be tested. The second transfer line, in tunnel TI 2, should be ready in April 2007, once the LHC magnets have been transported through the downstream section of this tunnel. Th...

  9. Installation of the LHC transfer lines begins

    CERN Multimedia

    Patrice Loïez

    2003-01-01

    The first of 700 magnets has been installed in one of the two transfer tunnels built to transfer the SPS beam into the LHC. The start of this first installation phase of the LHC transfer lines provides the opportunity to launch a new and highly original modular system for transporting and installing all kinds of magnets in very narrow tunnels. The system is based on very compact bogies, up to four of which can be coupled together to form a convoy. The wheels are fitted with individual motors enabling them to swivel through an angle of 90° and the convoy to move laterally. The first installation phase will continue until mid-April. In addition to the magnets, a beam dump facility also has to be installed. The second installation phase will take place later this year and should be completed in 2004, when the TI 8 transfer line is due to be tested. The second transfer line, in tunnel TI 2, should be ready in April 2007, once the LHC magnets have been transported through the downstream section of this tunnel.Pho...

  10. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  11. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  12. Java/JNI/C/Fortran based HSVD/HLSVD custom plugins for the jMRUI software system: Development, installation and usage

    NARCIS (Netherlands)

    De Beer, R.; Van Ormondt, D.

    2015-01-01

    This work was done in the context of FP7 - PEOPLE Marie Curie Initial Training Network Project PITN-GA-2012-316679-TRANSACT. This report describes the development, installation and usage of the HSVD and HLSVD plugin for the jMRUI software system. The latter system is maintained by the TRANSACT EU p

  13. 基于RHEL5的各类软件安装方法攻略%The Strategy of Installing Software Based on RHEL 5

    Institute of Scientific and Technical Information of China (English)

    李国忠

    2013-01-01

      对于Linux初学者来说,有时安装一个很小的应用软件恐怕都是一件很让人头疼的事,因为在Linux下安装软件不像在Windows中那样简单。在RHEL(RedHat Enterprise Linux)中安装RPM软件包可以通过执行rpm或yum命令来实现,也可以借助软件包管理工具来管理软件,安装源代码软件则必须先配置好编译环境,否则很难成功。%As a Linux beginner, sometimes the instal ation of smal application software is a headache. Because to instal software in Linux system is not simple as in the Windows system.To install the RPM software package in RHEL system can be done by using the rpm or yum command or by the software package management tools.To instal the source code software, you must configure the compiler environment firstly, otherwise, it is hard to succeed.

  14. Schedule of conditions for the personnel formation of category A or B working in nuclear facilities; Cahier des charges pour la formation du personnel de categorie A ou B travaillant dans les installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document describes the main provisions concerning the formation and the radiation and conventional risks protection of A or B category personnel, working in nuclear facilities. It contents the application domain, the applicable documents, the liability, the formation organizations, the formation to the risk prevention, the retraining and the Passerelles formations. (A.L.B.)

  15. Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

    Energy Technology Data Exchange (ETDEWEB)

    Rich Johnson; Kimberlyn C. Mousseau; Hyung Lee

    2011-09-01

    NE-KAMS knowledge base will assist computational analysts, physics model developers, experimentalists, nuclear reactor designers, and federal regulators by: (1) Establishing accepted standards, requirements and best practices for V&V and UQ of computational models and simulations, (2) Establishing accepted standards and procedures for qualifying and classifying experimental and numerical benchmark data, (3) Providing readily accessible databases for nuclear energy related experimental and numerical benchmark data that can be used in V&V assessments and computational methods development, (4) Providing a searchable knowledge base of information, documents and data on V&V and UQ, and (5) Providing web-enabled applications, tools and utilities for V&V and UQ activities, data assessment and processing, and information and data searches. From its inception, NE-KAMS will directly support nuclear energy research, development and demonstration programs within the U.S. Department of Energy (DOE), including the Consortium for Advanced Simulation of Light Water Reactors (CASL), the Nuclear Energy Advanced Modeling and Simulation (NEAMS), the Light Water Reactor Sustainability (LWRS), the Small Modular Reactors (SMR), and the Next Generation Nuclear Power Plant (NGNP) programs. These programs all involve computational modeling and simulation (M&S) of nuclear reactor systems, components and processes, and it is envisioned that NE-KAMS will help to coordinate and facilitate collaboration and sharing of resources and expertise for V&V and UQ across these programs. In addition, from the outset, NE-KAMS will support the use of computational M&S in the nuclear industry by developing guidelines and recommended practices aimed at quantifying the uncertainty and assessing the applicability of existing analysis models and methods. The NE-KAMS effort will initially focus on supporting the use of computational fluid dynamics (CFD) and thermal hydraulics (T/H) analysis for M&S of nuclear

  16. Proceedings of the 27th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marvin A. [Editor; Benson, Jody [Editor; Patterson, Eileen F. [Editor

    2005-09-20

    These proceedings contain papers prepared for the 27th Seismic Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 20-22 September, 2005 in Rancho Mirage, California. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  17. Proceedings of the 2009 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wetovsky, Marv A [Los Alamos National Laboratory; Aguilar - Chang, Julio [Los Alamos National Laboratory; Anderson, Dale [Los Alamos National Laboratory; Arrowsmith, Marie [Los Alamos National Laboratory; Arrowsmith, Stephen [Los Alamos National Laboratory; Baker, Diane [Los Alamos National Laboratory; Begnaud, Michael [Los Alamos National Laboratory; Harste, Hans [Los Alamos National Laboratory; Maceira, Monica [Los Alamos National Laboratory; Patton, Howard [Los Alamos National Laboratory; Phillips, Scott [Los Alamos National Laboratory; Randall, George [Los Alamos National Laboratory; Rowe, Charlotte [Los Alamos National Laboratory; Stead, Richard [Los Alamos National Laboratory; Steck, Lee [Los Alamos National Laboratory; Whitaker, Rod [Los Alamos National Laboratory; Yang, Xiaoning ( David ) [Los Alamos National Laboratory

    2009-09-21

    These proceedings contain papers prepared for the Monitoring Research Review 2009: Ground -Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2009 in Tucson, Arizona,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Test Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States’ capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  18. Proceedings of the 25th Seismic Research Review -- Nuclear Explosion Monitoring: Building the Knowledge Base

    Energy Technology Data Exchange (ETDEWEB)

    Chavez, Francesca C. [Editor; Mendius, E. Louise [Editor

    2003-09-23

    These proceedings contain papers prepared for the 25th Seismic Research Review -- Nuclear Explosion Monitoring: Building the Knowledge Base, held 23-25 September, 2003 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  19. Cold nuclear fusion reactor and nuclear fusion rocket

    Directory of Open Access Journals (Sweden)

    Huang Zhenqiang

    2013-10-01

    Full Text Available "Nuclear restraint inertial guidance directly hit the cold nuclear fusion reactor and ion speed dc transformer" [1], referred to as "cold fusion reactor" invention patents, Chinese Patent Application No. CN: 200910129632.7 [2]. The invention is characterized in that: at room temperature under vacuum conditions, specific combinations of the installation space of the electromagnetic field, based on light nuclei intrinsic magnetic moment and the electric field, the first two strings of the nuclei to be bound fusion on the same line (track of. Re-use nuclear spin angular momentum vector inherent nearly the speed of light to form a super strong spin rotation gyro inertial guidance features, to overcome the Coulomb repulsion strong bias barrier to achieve fusion directly hit. Similar constraints apply nuclear inertial guidance mode for different speeds and energy ion beam mixing speed, the design of ion speed dc transformer is cold fusion reactors, nuclear fusion engines and such nuclear power plants and power delivery systems start important supporting equipment, so apply for a patent merger

  20. Laser-based analytical monitoring in nuclear-fuel processing plants

    Energy Technology Data Exchange (ETDEWEB)

    Hohimer, J.P.

    1978-09-01

    The use of laser-based analytical methods in nuclear-fuel processing plants is considered. The species and locations for accountability, process control, and effluent control measurements in the Coprocessing, Thorex, and reference Purex fuel processing operations are identified and the conventional analytical methods used for these measurements are summarized. The laser analytical methods based upon Raman, absorption, fluorescence, and nonlinear spectroscopy are reviewed and evaluated for their use in fuel processing plants. After a comparison of the capabilities of the laser-based and conventional analytical methods, the promising areas of application of the laser-based methods in fuel processing plants are identified.

  1. Improved installation prototype for measurement of low argon-37 activity

    Science.gov (United States)

    Pakhomov, Sergei; Dubasov, Yuri

    2015-04-01

    On-site Inspection (OSI) is a key element of verification of State Parties' compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). An on-site inspection is launched to establish whether or not a nuclear explosion has been carried out. One of the most significant evidence of n underground nuclear explosion (UNE) is detection above background concentrations of argon-37 in near surface air. Argon-37 is formed in large amounts at interaction of neutrons of UNE with the potassium which is a part of the majority of rocks. Its estimated contents for the 100th days after explosion with a energy of 1000 t of TNT near a surface can vary from 1 to 1000 mBq/m3. The background concentrations of argon-37 in subsoil air vary 1 do100 mBq/m3. Traditionally, for argon-37 activity measurement the gas-proportional counters are used. But at Khlopin Radium institute the developments of the new type of highly sensitive and low-background installation capable to provide the required range of measurements of the argon-37 concentration are conducted. The liquid scintillation method of the registration of the low-energetic argon-37 electrons is the basic installation principle and as scintillator, the itself condensed air argon sample is used. Registration of scintillations of liquid argon is made by means of system from 3 PMT which cathodes are cooled near to the temperature of liquid nitrogen together with the measuring chamber in which placed the quartz glass ampule, containing the measured sample of the liquefied argon. For converse the short wavelength photons (λ = 127 nm) of liquid argon scintillations to more long-wave, corresponding to the range of PMT sensitivity, the polymer film with tetra-phenyl-butadiene (TPB) is provided. Even the insignificant impurities of nitrogen, oxygen and others gaseous in the liquid argon samples can to cause the quenching of scintillation, especially their slow components. To account this effect and it influence on change of registration

  2. H.323 Based Collaborative Environment for High Energy and Nuclear Physics

    Institute of Scientific and Technical Information of China (English)

    TeijiNakamura; KiyoharuHashimoto; 等

    2001-01-01

    After having evaluated various H.323 products for these two years,KEK and Japanese HENP community started to move from ISDN(H.320)-based video conferencing environment into IP(H.323)-based one.Primary reason for the move is to cut down the ever increasing ISDN communication cost.At the same time the H.323 can offer us more powerful collaborative environment.In order to make KEK to be a center for the H.323-based collaborative environment in Japan,Picture Tel's LIVE GATEWAY as a H.320/H.323 gateway ,which is essential for the smooth transition,Cisco IP/VA 3510 as a H.323/MCU,and Cisco 2610 as a gatekeeper were installed at KEK in March 2001,And the transition started.In this paper,we'll describe the collaborative environment which our users can have,together with its operational results.

  3. WEBsite of monitoring solar installations; Portal WEB de funcionamiento de instalaciones solares

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, G.; Perez-Solano, M. J.

    2004-07-01

    This article shows an Internet Website of monitoring solar installations. It describes the most interesting characteristics of these installations and includes measures of their working variables. These values are presented in graphics and summarised reports. The solar installations are divided in four groups: Solar Thermal Installations, Domestic Solar Systems, Isolated Photovoltaic Installations and Grid Connected Photovoltaic Installations, however, in this article, the operation and the contents of this Website will be described based on the group of Solar Thermal Installations. This article describes the main page of the website and the necessary procedures to access to an installation, as well as the different screens related to this group. (Author)

  4. Nuclear characteristics of the endometrial cytology: liquid-based versus conventional preparation.

    Science.gov (United States)

    Norimatsu, Yoshiaki; Shigematsu, Yumie; Sakamoto, Shingo; Ohsaki, Hiroyuki; Yanoh, Kenji; Kawanishi, Namiki; Kobayashi, Tadao K

    2013-02-01

    The aim of this study was to assess the utility of liquid-based cytologic preparation (LP) compared with conventional preparation (CP) for the assessment of nuclear findings in endometrial glandular and stromal breakdown (EGBD) which may be misdiagnosed as carcinoma in EGBD cases. The material consists of cytologic smears including 20 cases of proliferative endometrium (PE), 20 cases of EGBD, and 20 cases of endometrioid adenocarcinoma grade1 (G1) for which histopathological diagnosis was obtained by endometrial curettage at the JA Suzuka General Hospital. Nuclear findings were examined in PE cells, EGBD-stromal cells, EGBD-metaplastic cells, and G1 cells, respectively. It was examined about the following items; (1) nuclear shape; (2) A long/minor axis ratio in cell nuclei; (3) an area of cell nuclei; (4) overlapping nuclei. Results are as follows: (1) nuclear shape; as for the reniform shape of EGBD-stromal cells and spindle shape of EGBD-metaplastic cells, the ratio of the LP method was a higher value than the CP method. (2) The long axis and area of cell nuclei; LP in all groups was a recognizable tendency for nuclear shrinkage. (3) The long/minor axis ratio in cell nuclei; only EGBD-metaplastic cells recognize a significant difference between CP and LP. (4) Overlapping nuclei; LP was a higher value in comparison with CP in the other groups except PE cells, and the degree of overlapping nuclei was enhanced about three times. Therefore, although a cell of LP has a shrinking tendency, (1) it is excellent that LP preserves a characteristic of nuclear shape than CP; (2) a cellular characteristic becomes clearer, because three-dimensional architecture of LP is preserved of than CP. As for the standard preparation method for endometrial cytology samples, we considered that a concrete introduction of the LP method poses no problems.

  5. Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Solonin, M.I.; Polyakov, A.S.; Zakharkin, B.S.; Smelov, V.S.; Nenarokomov, E.A.; Mukhin, I.V. [SSC, RF, A.A. Bochvar ALL-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

    2000-07-01

    To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

  6. Law n. 2006-686 of the 13 June 2006 relative to the transparency and the security in the nuclear (1); Loi n. 2006-686 du 13 juin 2006 relative a la transparence et a la securite en matiere nucleaire (1)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document presents the 64 articles of the law n.2006-686 on the nuclear security. It concerns the regulation in matter of safety and transparency, the Authority of Nuclear Safety, the public information, the base nuclear installations and the radioactive substances transport, the risks prevention and the penalties. (A.L.B.)

  7. Installing and Testing a Server Operating System

    Directory of Open Access Journals (Sweden)

    Lorentz JÄNTSCHI

    2003-08-01

    Full Text Available The paper is based on the experience of the author with the FreeBSD server operating system administration on three servers in use under academicdirect.ro domain.The paper describes a set of installation, preparation, and administration aspects of a FreeBSD server.First issue of the paper is the installation procedure of FreeBSD operating system on i386 computer architecture. Discussed problems are boot disks preparation and using, hard disk partitioning and operating system installation using a existent network topology and a internet connection.Second issue is the optimization procedure of operating system, server services installation, and configuration. Discussed problems are kernel and services configuration, system and services optimization.The third issue is about client-server applications. Using operating system utilities calls we present an original application, which allows displaying the system information in a friendly web interface. An original program designed for molecular structure analysis was adapted for systems performance comparisons and it serves for a discussion of Pentium, Pentium II and Pentium III processors computation speed.The last issue of the paper discusses the installation and configuration aspects of dial-in service on a UNIX-based operating system. The discussion includes serial ports, ppp and pppd services configuration, ppp and tun devices using.

  8. Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option nuclear reactor; Cahier des charges specifiques pour la formation du personnel de categorie A ou B travaillant dans les installations nucleaires. Option reacteur nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document describes the specific dispositions relative to the nuclear reactor domain, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the nuclear reactor and of the retraining, the Passerelle formation, are presented. (A.L.B.)

  9. Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option nuclear reactor-borne; Cahier des charges specifiques pour la formation du personnel de categorie A ou B travaillant dans les installations nucleaires. Option reacteur nucleaire embarque

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document describes the specific dispositions relative to the nuclear reactor-borne domain, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the nuclear reactor-borne and of the retraining, the Passerelle formation, are presented. (A.L.B.)

  10. Quantum Computing Using Pulse-Based Electron-Nuclear Double Resonance (endor):. Molecular Spin-Qubits

    Science.gov (United States)

    Sato, Kazuo; Nakazawa, Shigeki; Rahimi, Robabeh D.; Nishida, Shinsuke; Ise, Tomoaki; Shimoi, Daisuke; Toyota, Kazuo; Morita, Yasushi; Kitagawa, Masahiro; Carl, Parick; Höfner, Peter; Takui, Takeji

    2009-06-01

    Electrons with the spin quantum number 1/2, as physical qubits, have naturally been anticipated for implementing quantum computing and information processing (QC/QIP). Recently, electron spin-qubit systems in organic molecular frames have emerged as a hybrid spin-qubit system along with a nuclear spin-1/2 qubit. Among promising candidates for QC/QIP from the materials science side, the reasons for why electron spin-qubits such as molecular spin systems, i.e., unpaired electron spins in molecular frames, have potentialities for serving for QC/QIP will be given in the lecture (Chapter), emphasizing what their advantages or disadvantages are entertained and what technical and intrinsic issues should be dealt with for the implementation of molecular-spin quantum computers in terms of currently available spin manipulation technology such as pulse-based electron-nuclear double resonance (pulsed or pulse ENDOR) devoted to QC/QIP. Firstly, a general introduction and introductory remarks to pulsed ENDOR spectroscopy as electron-nuclear spin manipulation technology is given. Super dense coding (SDC) experiments by the use of pulsed ENDOR are also introduced to understand differentiating QC ENDOR from QC NMR based on modern nuclear spin technology. Direct observation of the spinor inherent in an electron spin, detected for the first time, will be shown in connection with the entanglement of an electron-nuclear hybrid system. Novel microwave spin manipulation technology enabling us to deal with genuine electron-electron spin-qubit systems in the molecular frame will be introduced, illustrating, from the synthetic strategy of matter spin-qubits, a key-role of the molecular design of g-tensor/hyperfine-(A-)tensor molecular engineering for QC/QIP. Finally, important technological achievements of recently-emerging CD ELDOR (Coherent-Dual ELectron-electron DOuble Resonance) spin technology enabling us to manipulate electron spin-qubits are described.

  11. Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Hui Zhang; Raman P. Singh

    2008-11-30

    Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys base on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiCf-SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor componets is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.

  12. New radiological material detection technologies for nuclear forensics: Remote optical imaging and graphene-based sensors.

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, Richard Karl [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Martin, Jeffrey B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wiemann, Dora K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Choi, Junoh [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Howell, Stephen W. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    We developed new detector technologies to identify the presence of radioactive materials for nuclear forensics applications. First, we investigated an optical radiation detection technique based on imaging nitrogen fluorescence excited by ionizing radiation. We demonstrated optical detection in air under indoor and outdoor conditions for alpha particles and gamma radiation at distances up to 75 meters. We also contributed to the development of next generation systems and concepts that could enable remote detection at distances greater than 1 km, and originated a concept that could enable daytime operation of the technique. A second area of research was the development of room-temperature graphene-based sensors for radiation detection and measurement. In this project, we observed tunable optical and charged particle detection, and developed improved devices. With further development, the advancements described in this report could enable new capabilities for nuclear forensics applications.

  13. Implicit attitudes toward nuclear power and mobile phone base stations: support for the affect heuristic.

    Science.gov (United States)

    Siegrist, Michael; Keller, Carmen; Cousin, Marie-Eve

    2006-08-01

    The implicit association test (IAT) measures automatic associations. In the present research, the IAT was adapted to measure implicit attitudes toward technological hazards. In Study 1, implicit and explicit attitudes toward nuclear power were examined. Implicit measures (i.e., the IAT) revealed negative attitudes toward nuclear power that were not detected by explicit measures (i.e., a questionnaire). In Study 2, implicit attitudes toward EMF (electro-magnetic field) hazards were examined. Results showed that cell phone base stations and power lines are judged to be similarly risky and, further, that base stations are more closely related to risk concepts than home appliances are. No differences between experts and lay people were observed. Results of the present studies are in line with the affect heuristic proposed by Slovic and colleagues. Affect seems to be an important factor in risk perception.

  14. Fast 4$\\pi$ track reconstruction in nuclear emulsion detectors based on GPU technology

    CERN Document Server

    Ariga, A

    2013-01-01

    Fast 4$\\pi$ solid angle particle track recognition has been a challenge in particle physics for a long time, especially in using nuclear emulsion detectors. The recent advances in computing technology opened the way for its realization. A fast 4$\\pi$ solid angle particle track reconstruction based on GPU technology combined with a multithread programming is reported here with a detailed comparison between GPU-based and CPU-based programming. A 60 times faster processing of 3D emulsion detector data, corresponding to processing of 15 cm$^2$ emulsion surface scanned per hour, has been achieved by GPUs with an excellent tracking performance.

  15. New Kohn-Sham density functional based on microscopic nuclear and neutron matter equations of state

    Science.gov (United States)

    Baldo, M.; Robledo, L. M.; Schuck, P.; Viñas, X.

    2013-06-01

    A new version of the Barcelona-Catania-Paris energy functional is applied to a study of nuclear masses and other properties. The functional is largely based on calculated ab initio nuclear and neutron matter equations of state. Compared to typical Skyrme functionals having 10-12 parameters apart from spin-orbit and pairing terms, the new functional has only 2 or 3 adjusted parameters, fine tuning the nuclear matter binding energy and fixing the surface energy of finite nuclei. An energy rms value of 1.58 MeV is obtained from a fit of these three parameters to the 579 measured masses reported in the Audi and Wapstra [Nucl. Phys. ANUPABL0375-947410.1016/j.nuclphysa.2003.11.003 729, 337 (2003)] compilation. This rms value compares favorably with the one obtained using other successful mean field theories, which range from 1.5 to 3.0 MeV for optimized Skyrme functionals and 0.7 to 3.0 for the Gogny functionals. The other properties that have been calculated and compared to experiment are nuclear radii, the giant monopole resonance, and spontaneous fission lifetimes.

  16. Alpha Stable Distribution Based Morphological Filter for Bearing and Gear Fault Diagnosis in Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Xinghui Zhang

    2015-01-01

    Full Text Available Gear and bearing play an important role as key components of rotating machinery power transmission systems in nuclear power plants. Their state conditions are very important for safety and normal operation of entire nuclear power plant. Vibration based condition monitoring is more complicated for the gear and bearing of planetary gearbox than those of fixed-axis gearbox. Many theoretical and engineering challenges in planetary gearbox fault diagnosis have not yet been resolved which are of great importance for nuclear power plants. A detailed vibration condition monitoring review of planetary gearbox used in nuclear power plants is conducted in this paper. A new fault diagnosis method of planetary gearbox gears is proposed. Bearing fault data, bearing simulation data, and gear fault data are used to test the new method. Signals preprocessed using dilation-erosion gradient filter and fast Fourier transform for fault information extraction. The length of structuring element (SE of dilation-erosion gradient filter is optimized by alpha stable distribution. Method experimental verification confirmed that parameter alpha is superior compared to kurtosis since it can reflect the form of entire signal and it cannot be influenced by noise similar to impulse.

  17. Response of base-isolated nuclear structures to extreme earthquake shaking

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, Manish, E-mail: mkumar2@buffalo.edu; Whittaker, Andrew S.; Constantinou, Michael C.

    2015-12-15

    Highlights: • Response-history analysis of nuclear structures base-isolated using lead–rubber bearings is performed. • Advanced numerical model of lead–rubber bearing is used to capture behavior under extreme earthquake shaking. • Results of response-history analysis obtained using simplified and advanced model of lead–rubber bearings are compared. • Heating of the lead core and variation in buckling load and axial stiffness affect the response. - Abstract: Seismic isolation using low damping rubber and lead–rubber bearings is a viable strategy for mitigating the effects of extreme earthquake shaking on safety-related nuclear structures. The mechanical properties of these bearings are not expected to change substantially in design basis shaking. However, under shaking more intense than design basis, the properties of the lead cores in lead–rubber bearings may degrade due to heating associated with energy dissipation, some bearings in an isolation system may experience net tension, and the compression and tension stiffness may be affected by the lateral displacement of the isolation system. The effects of intra-earthquake changes in mechanical properties on the response of base-isolated nuclear power plants (NPPs) are investigated using an advanced numerical model of a lead–rubber bearing that has been verified and validated, and implemented in OpenSees. A macro-model is used for response-history analysis of base-isolated NPPs. Ground motions are selected and scaled to be consistent with response spectra for design basis and beyond design basis earthquake shaking at the site of the Diablo Canyon Nuclear Generating Station. Ten isolation systems of two periods and five characteristic strengths are analyzed. The responses obtained using simplified and advanced isolator models are compared. Strength degradation due to heating of lead cores and changes in buckling load most significantly affect the response of the base-isolated NPP.

  18. Recapturing Graphite-Based Fuel Element Technology for Nuclear Thermal Propulsion

    Energy Technology Data Exchange (ETDEWEB)

    Trammell, Michael P [ORNL; Jolly, Brian C [ORNL; Miller, James Henry [ORNL; Qualls, A L [ORNL; Harrison, Thomas J [ORNL

    2013-01-01

    ORNL is currently recapturing graphite based fuel forms for Nuclear Thermal Propulsion (NTP). This effort involves research and development on materials selection, extrusion, and coating processes to produce fuel elements representative of historical ROVER and NERVA fuel. Initially, lab scale specimens were fabricated using surrogate oxides to develop processing parameters that could be applied to full length NTP fuel elements. Progress toward understanding the effect of these processing parameters on surrogate fuel microstructure is presented.

  19. Likelihood-Based Association Analysis for Nuclear Families and Unrelated Subjects with Missing Genotype Data

    OpenAIRE

    Dudbridge, Frank

    2008-01-01

    Missing data occur in genetic association studies for several reasons including missing family members and uncertain haplotype phase. Maximum likelihood is a commonly used approach to accommodate missing data, but it can be difficult to apply to family-based association studies, because of possible loss of robustness to confounding by population stratification. Here a novel likelihood for nuclear families is proposed, in which distinct sets of association parameters are used to model the pare...

  20. An analysis of nuclear charge radii based on the empirical formula

    Institute of Scientific and Technical Information of China (English)

    LI Ru-Heng; HU Yong-Mao; LI Mao-Cai

    2009-01-01

    Several nuclear charge radii had been calculated based on the law of A1/3 and isospin dependence Z1/3 formula which had been used to describe the charge radii data. It is achieved that the isospin dependence Z1/3 formula is superior to the generally accepted A1/3 law through mean root square deviation analysis, that is, the Z1/3 formula is more effective to describe the charge radii data.

  1. Mineral mining installation

    Energy Technology Data Exchange (ETDEWEB)

    Weirich, W.

    1984-01-24

    A longwall mineral mining installation has a conveyor and a plurality of roof support units positioned side-by-side on the goaf side of the conveyor. Each roof support unit has a roof shield having an advanceable shield extension. Each unit has a first hydraulic ram for extending its shield extension, and a second hydraulic ram for advancing the conveyor. The extension of each first ram is controlled in dependence upon the retraction of one of the second rams (either the second ram of the same unit or that of an adjacent unit). This control is effected by controlling the supply of pressurized hydraulic fluid to the first rams. In one embodiment this is carried out by a control valve which has a springloaded plunger which engages with a series of equispaced cams on the movable cylinder of the associated second ram. In another embodiment, the piston rods of the rams are provided with series of equispaced magnets. The cylinders of the rams are provided with sensors, which sense the magnets and generate control signals. A control box is provided to direct the control signals to control valves associated with the rams, so that the first rams are extended by the same distance as that through which the second rams are retracted.

  2. Mineral mining installation

    Energy Technology Data Exchange (ETDEWEB)

    Becker, K.; Rosenberg, H.; Weirich, W.

    1981-12-29

    A longwall mineral mining installation has a conveyor and a plurality of roof support units positioned side-by-side on the goaf side of the conveyor. Each roof support unit has a roof shield having an advanceable shield extension. Each unit has a first hydraulic ram for extending its shield extension, and a second hydraulic ram for advancing the conveyor. The extension of each first ram is controlled in dependence upon the retraction of one of the second rams (Either the second ram of the same unit or that of an adjacent unit). This control is effected by controlling the supply of pressurized hydraulic fluid to the first rams. In one embodiment this is carried out by a control valve which has a spring-loaded plunger which engages with a series of equispaced cams on the movable cylinder of the associated second ram. In another embodiment, the piston rods of the rams are provided with series of equispaced magnets. The cylinders of the rams are provided with sensors, which sense the magnets and generate control signals. A control box is provided to direct the control signals to control valves associated with the rams, so that the first rams are extended by the same distance as that through which the second rams are retracted.

  3. ROS Installation and Commissioning

    CERN Multimedia

    Gorini, B

    The ATLAS Readout group (a sub-group of TDAQ) has now completed the installation and commissioning of all of the Readout System (ROS) units. Event data from ATLAS is initially handled by detector specific hardware and software, but following a Level 1 Accept the data passes from the detector specific Readout Drivers (RODs) to the ROS, the first stage of the central ATLAS DAQ. Within the final ATLAS TDAQ system the ROS stores the data and on request makes it available to the Level 2 Trigger (L2) processors and to the Event Builder (EB) as required. The ROS is implemented as a large number of PCs housing custom built cards (ROBINs) and running custom multi-threaded software. Each ROBIN card (shown below) contains buffer memories to store the data, plus a field programmable gate array ( FPGA ) and an embedded PowerPC processor for management of the memories and data requests, and is implemented as a 64-bit 66 MHz PCI card. Both the software and the ROBIN cards have been designed and developed by the Readout g...

  4. Underground nuclear astrophysics at the Dresden Felsenkeller

    Energy Technology Data Exchange (ETDEWEB)

    Bemmerer, Daniel; Ilgner, Christoph; Junghans, Arnd R.; Mueller, Stefan; Rimarzig, Bernd; Schwengner, Ronald; Szuecs, Tamas; Wagner, Andreas [Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Dresden (Germany); Cowan, Thomas E.; Gohl, Stefan; Grieger, Marcel; Reinicke, Stefan; Roeder, Marko; Schmidt, Konrad; Stoeckel, Klaus; Takacs, Marcell P.; Wagner, Louis [Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Dresden (Germany); Technische Universitaet Dresden (Germany); Reinhardt, Tobias P.; Zuber, Kai [Technische Universitaet Dresden (Germany)

    2015-07-01

    Favored by the low background underground, accelerator-based experiments are an important tool to study nuclear astrophysics reactions involving stable charged particles. This technique has been used with great success at the 0.4 MV LUNA accelerator in the Gran Sasso laboratory in Italy. However, the nuclear reactions of helium and carbon burning and the neutron source reactions for the astrophysical s-process require higher beam energies, as well as the continuation of solar fusion studies. As a result, NuPECC strongly recommended the installation of one or more higher-energy underground accelerators. Such a project is underway in Dresden. A 5 MV Pelletron accelerator is currently being refurbished by installing an ion source on the high voltage terminal, enabling intensive helium beams. The preparation of the underground site is funded, and the civil engineering project is being updated. The science case, operational strategy and project status are reported.

  5. Synthesis of Model Based Robust Stabilizing Reactor Power Controller for Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Arshad Habib Malik

    2011-04-01

    Full Text Available In this paper, a nominal SISO (Single Input Single Output model of PHWR (Pressurized Heavy Water Reactor type nuclear power plant is developed based on normal moderator pump-up rate capturing the moderator level dynamics using system identification technique. As the plant model is not exact, therefore additive and multiplicative uncertainty modeling is required. A robust perturbed plant model is derived based on worst case model capturing slowest moderator pump-up rate dynamics and moderator control valve opening delay. Both nominal and worst case models of PHWR-type nuclear power plant have ARX (An Autoregressive Exogenous structures and the parameters of both models are estimated using recursive LMS (Least Mean Square optimization algorithm. Nominal and worst case discrete plant models are transformed into frequency domain for robust controller design purpose. The closed loop system is configured into two port model form and H? robust controller is synthesized. The H?controller is designed based on singular value loop shaping and desired magnitude of control input. The selection of desired disturbance attenuation factor and size of the largest anticipated multiplicative plant perturbation for loop shaping of H? robust controller form a constrained multi-objective optimization problem. The performance and robustness of the proposed controller is tested under transient condition of a nuclear power plant in Pakistan and found satisfactory.

  6. Proceedings of the first international seminar on seismic base isolation for nuclear power facilities

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The First International Seminar on Seismic Base Isolation of Nuclear Power Facilities was organized by the authors of this paper. It was held in San Francisco, California, USA, on August 21--22, 1989, in conjunction with the tenth International Conference on Structural Mechanics in Reactor Technology (SMiRT-10). The purpose of the seminar was to provide an international forum for discussion on the application of base isolation to nuclear power plants and of its effectiveness in reducing seismic loads and permitting standard plant designs. It also provided an opportunity for technical interchange between base isolation system designers, structural engineers, and nuclear power plant engineers. Seismic isolation is certainly one of the most significant earthquake engineering developments in recent years. This was clearly demonstrated by the very large attendance at this seminar and the various papers presented. Isolation system act as filters that reduce the seismic forces and increase the ability of isolated structures and their contents to withstand the damaging effects of earthquake motions. Each individual paper has been cataloged separately.

  7. The installation CLAB, Sweden ATC; La instalacion CLAB, el ATC de Suiza

    Energy Technology Data Exchange (ETDEWEB)

    Vico, E.

    2010-07-01

    The installation CLAB, plays an important role in system management and storage of spent nuclear fuel in Sweden. It is a centralized temporary storage (ATC) type pool, located on the site of the Oskarshamn nuclear power plant. It's in operation since 1985 and can store more than 20,000 fuel elements from nuclear power plants and research reactors. (Author)

  8. Installation of the LHC transfer lines begins

    CERN Multimedia

    Patrice Loïez

    2003-01-01

    The first of 700 magnets has been installed in one of the two transfer tunnels built to transfer the SPS beam into the LHC. The start of this first installation phase of the LHC transfer lines provides the opportunity to launch a new and highly original modular system for transporting and installing all kinds of magnets in very narrow tunnels. The system is based on very compact bogies, up to four of which can be coupled together to form a convoy. The wheels are fitted with individual motors enabling them to swivel through an angle of 90° and the convoy to move laterally. In this way the magnet is delivered directly to its installation point, but beneath the beamline. It is then raised into its final position in the beamline using air cushions, which form an integrated part of the transport system.Photos 01, 02: Pictured with the newly installed magnet and transport system in the transfer line tunnel are LHC project leader Lyn Evans (second left, white helmet); Volker Mertens, responsible for the LHC injecti...

  9. Installation of the LHC transfer lines begins

    CERN Multimedia

    Patrice Loïez

    2003-01-01

    The first of 700 magnets has been installed in one of the two transfer tunnels built to transfer the SPS beam into the LHC. The start of this first installation phase of the LHC transfer lines provides the opportunity to launch a new and highly original modular system for transporting and installing all kinds of magnets in very narrow tunnels. The system is based on very compact bogies, up to four of which can be coupled together to form a convoy. The wheels are fitted with individual motors enabling them to swivel through an angle of 90° and the convoy to move laterally. In this way the magnet is delivered directly to its installation point, but beneath the beamline. It is then raised into its final position in the beamline using air cushions, which form an integrated part of the transport system.Photo 01: Pictured with the newly installed magnet and transport system in the transfer line tunnel are (left to right) Volker Mertens, responsible for the LHC injection and transfer lines; personnel involved in tr...

  10. Progress of a research program on seismic base isolation of nuclear components

    Energy Technology Data Exchange (ETDEWEB)

    Ebisawa, K.; Ando, K.; Shibata, K. [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan)

    2000-05-01

    Development of an evaluation code and related test program have been conducted to provide the technical base of the seismic base isolation of nuclear components. In the Phase I (FY1991-FY1995) of the research, a methodology and a computer code Ver.1 for evaluating the effect of seismic base isolation of nuclear components were developed. Case study was carried out on the effectiveness of base isolation of emergency transformer. Difference of input earthquake motion, type of isolation device and influence of the soil property were studied. Case study of a cost/benefit analysis in introducing the base isolation to emergency transformer was tried as an application of the computer code. As the Phase II (FY1996-FY2000), in order to obtain the test data of component base isolation systems, a verification test program, in which the test utilizing the real earthquake and the test by a shaking table are to be carried out, has been initiated since FY1996. In the tests, dynamic response and failure mode of base isolation systems will be examined. This paper overviews the progress of Phase I and II researches. (orig.)

  11. V-Model based Configuration Management Program for New-Build Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Kyungik [PartDB Co. Ltd., Daejeon (Korea, Republic of); Cho, Yoon Sang [KHNP Co. Ltd., Daejeon (Korea, Republic of); Freeland, Kent R. [Industrial Analysts Incorporated, New Hampshire (United States)

    2014-05-15

    As NPP operators undertook design basis reconstitution efforts, they began to realize that the design basis is a foundation for Configuration Management (CM). This realization was made evident in the magnitude of the problems that were being observed. This experience also raised serious questions about how the information being developed to produce the design basis documents would be kept up to date in the future. A process to reconstitute the design basis is likely to be ineffective if CM controls are not in place. The right IT solution for CM depends upon a number of factors, including the nuclear power plant culture, budget, target technology, and the nuclear power plant owner/operator's standards, requirements and limitations for its generating fleet. Comprehensive CM Program for NPP is the single greatest strategy to meet the commitment to nuclear excellence. The safety and viability of nuclear power, particularly at the fleet level, depends upon the development of positive design control and design basis to better understanding plant operating dynamics and margin management, along with technology to control the realization of such design in the physical plant. However the most of plant facilities are modified many times, often without suitable support needed to confirm with their design base and to update their engineering data, maintenance rules and operating procedures. This lack of equilibrium between the requirements, design information and physical plant still remains a important issue. This study focuses on how to manage the configuration information of NPP using systems engineering V-model approach, and proposes data model to manage the configuration information in relation to manage their life cycle. Comprehensive CM Program and IMS for NPP life cycle support is the greatest strategy to meet the commitment to nuclear safety.

  12. NVR-BIP: Nuclear Vector Replacement using Binary Integer Programming for NMR Structure-Based Assignments.

    Science.gov (United States)

    Apaydin, Mehmet Serkan; Çatay, Bülent; Patrick, Nicholas; Donald, Bruce R

    2011-05-01

    Nuclear magnetic resonance (NMR) spectroscopy is an important experimental technique that allows one to study protein structure and dynamics in solution. An important bottleneck in NMR protein structure determination is the assignment of NMR peaks to the corresponding nuclei. Structure-based assignment (SBA) aims to solve this problem with the help of a template protein which is homologous to the target and has applications in the study of structure-activity relationship, protein-protein and protein-ligand interactions. We formulate SBA as a linear assignment problem with additional nuclear overhauser effect constraints, which can be solved within nuclear vector replacement's (NVR) framework (Langmead, C., Yan, A., Lilien, R., Wang, L. and Donald, B. (2003) A Polynomial-Time Nuclear Vector Replacement Algorithm for Automated NMR Resonance Assignments. Proc. the 7th Annual Int. Conf. Research in Computational Molecular Biology (RECOMB), Berlin, Germany, April 10-13, pp. 176-187. ACM Press, New York, NY. J. Comp. Bio., (2004), 11, pp. 277-298; Langmead, C. and Donald, B. (2004) An expectation/maximization nuclear vector replacement algorithm for automated NMR resonance assignments. J. Biomol. NMR, 29, 111-138). Our approach uses NVR's scoring function and data types and also gives the option of using CH and NH residual dipolar coupling (RDCs), instead of NH RDCs which NVR requires. We test our technique on NVR's data set as well as on four new proteins. Our results are comparable to NVR's assignment accuracy on NVR's test set, but higher on novel proteins. Our approach allows partial assignments. It is also complete and can return the optimum as well as near-optimum assignments. Furthermore, it allows us to analyze the information content of each data type and is easily extendable to accept new forms of input data, such as additional RDCs.

  13. Nuclear risk management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This paper gives the list of contributions to Eurosafe 2001 which was organised around two round tables on the first day and five seminars on the second day. The first round table dealt with the technical, organisational and societal aspects of risk management aimed at the prevention of accidents in nuclear power plants. The second round table focused on radiological risks from the normal operation of nuclear installations. Special consideration has been given to the involvement of stakeholders. The five seminars were held in order to provide opportunities for comparing experiences and learning about recent activities of IRSN, GRS and their partners in the European Union and Eastern Europe: - Safety assessment and analysis of nuclear installations; -Nuclear safety research; -Environment and radiation protection; - Waste management; - Nuclear material security. (author)

  14. Report by the AERES on the unit: Unit of researches on neutron transport and radioactivity confinement in nuclear installations under the supervision of the establishments and bodies: IRSN; Rapport de l'AERES sur l'unite: Unite de recherches en neutronique et confinement de la radioactivite dans les installations nucleaires sous tutelle des etablissements et organismes: IRSN

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    This report is a kind of audit report on a research laboratory whose activity is organized in three departments: neutron transport and criticality (themes: numerical methods, maths and statistics related to the simulation of neutral particle propagation, nuclear data, uncertainty propagation and bias estimation, code qualification and associated experimental programs, neutron transport in reactors and fuel cycle, criticality accidents), radionuclide transfer in radioactive waste disposals (site identification strategy, hydro-mechanical phenomena affecting storage performance, physical-chemical evolution factors, storage modelling), and metrology and confinement of radioactive gases and aerosols. The authors discuss an assessment of the unit activities in terms of strengths and opportunities, aspects to be improved and recommendations, productions and publications. A more detailed assessment is presented for each department in terms of scientific quality, influence and attractiveness (awards, recruitment capacity, capacity to obtain financing and to tender, participation to international programs), strategy and governance, and project

  15. Fessenheim plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident; Fessenheim - Rapport d'evaluation complementaire de la surete des installations nucleaires au regard de l'accident de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-15

    This CSA (Complementary Safety Assessment) analyses the robustness of the Fessenheim plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

  16. Evolutionary relationships within the lamioid tribe Synandreae (Lamiaceae) based on multiple low-copy nuclear loci

    Science.gov (United States)

    Roy, Tilottama; Catlin, Nathan S.; Garner, Drake M.G.; Cantino, Philip D.; Scheen, Anne-Cathrine

    2016-01-01

    The subfamily Lamioideae (Lamiaceae) comprises ten tribes, of which only Stachydeae and Synandreae include New World members. Previous studies have investigated the phylogenetic relationships among the members of Synandreae based on plastid and nuclear ribosomal DNA loci. In an effort to re-examine the phylogenetic relationships within Synandreae, the current study incorporates data from four low-copy nuclear loci, PHOT1, PHOT2, COR, and PPR. Our results confirm previous studies based on chloroplast and nuclear ribosomal markers in supporting the monophyly of tribe Synandreae, as well as sister relationships between Brazoria and Warnockia, and between that pair of genera and a monophyletic Physostegia. However, we observe incongruence in the relationships of Macbridea and Synandra. The placement of Synandreae within Lamioideae is poorly resolved and incongruent among different analyses, and the sister group of Synandreae remains enigmatic. Comparison of the colonization and migration patterns corroborates a single colonization of the New World by Synandreae during the Late Miocene/Tortonian age. This is in contrast to the only other lamioid tribe that includes New World members, Stachydeae, which colonized the New World at least twice—during the mid-Miocene and Pliocene. Edaphic conditions and intolerance of soil acidity may be factors that restricted the distribution of most genera of Synandreae to southeastern and south–central North America, whereas polyploidy could have increased the colonizing capability of the more wide-ranging genus, Physostegia. PMID:27547537

  17. Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

  18. Radiation induced dissolution of UO 2 based nuclear fuel - A critical review of predictive modelling approaches

    Science.gov (United States)

    Eriksen, Trygve E.; Shoesmith, David W.; Jonsson, Mats

    2012-01-01

    Radiation induced dissolution of uranium dioxide (UO 2) nuclear fuel and the consequent release of radionuclides to intruding groundwater are key-processes in the safety analysis of future deep geological repositories for spent nuclear fuel. For several decades, these processes have been studied experimentally using both spent fuel and various types of simulated spent fuels. The latter have been employed since it is difficult to draw mechanistic conclusions from real spent nuclear fuel experiments. Several predictive modelling approaches have been developed over the last two decades. These models are largely based on experimental observations. In this work we have performed a critical review of the modelling approaches developed based on the large body of chemical and electrochemical experimental data. The main conclusions are: (1) the use of measured interfacial rate constants give results in generally good agreement with experimental results compared to simulations where homogeneous rate constants are used; (2) the use of spatial dose rate distributions is particularly important when simulating the behaviour over short time periods; and (3) the steady-state approach (the rate of oxidant consumption is equal to the rate of oxidant production) provides a simple but fairly accurate alternative, but errors in the reaction mechanism and in the kinetic parameters used may not be revealed by simple benchmarking. It is essential to use experimentally determined rate constants and verified reaction mechanisms, irrespective of whether the approach is chemical or electrochemical.

  19. Methodology for gathering nuclear energy literature; Metodologia de coleta para alimentacao de uma base de dados em energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, Maria B.M.A.

    1996-12-31

    Several activities related to gathering information and documents -conventional and non-conventional primary literature - to include in a bibliographic nuclear energy database are described and arranged, using as model the communication and information process in science and technology and the analysis of the indexed documents in the database. Methodological steps are identified and a collecting system model is presented. 112 refs., 4 tabs.

  20. A Sustainable Nuclear Fuel Cycle Based on Laser Inertial Fusion Energy

    Energy Technology Data Exchange (ETDEWEB)

    Moses, E; Diaz de la Rubia, T; Storm, E; Latkowski, J; Farmer, J; Abbott, R; Kramer, K; Peterson, P; Shaw, H; Lehman II, R

    2009-05-22

    The National Ignition Facility (NIF), a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, will soon be completed at the Lawrence Livermore National Laboratory. Experiments designed to accomplish the NIF's goal will commence in 2010, using laser energies of 1 to 1.3 MJ. Fusion yields of the order of 10 to 35 MJ are expected soon thereafter. They propose that a laser system capable of generating fusion yields of 35 to 75 MJ at 10 to 15 Hz (i.e., {approx} 350- to 1000-MW fusion and {approx} 1.3 to 3.6 x 10{sup 20} n/s), coupled to a compact subdritical fission blanket, could be used to generate several GW of thermal power (GWth) while avoiding carbon dioxide emissions, mitigating nuclear proliferation concerns and minimizing the concerns associated with nuclear safety and long-term nuclear waste disposition. this Laser Inertial Fusion Energy (LIFE) based system is a logical extension of the NIF laser and the yields expec ted from the early ignition experiments on NIF. The LIFE concept is a once-through,s elf-contained closed fuel cycle and would have the following characteristics: (1) eliminate the need for spent fuel chemical separation facilities; (4) maintain the fission blanket subcritical at all times (k{sub eff} < 0.90); and (5) minimize future requirements for deep underground geological waste repositories and minimize actinide content in the end-of-life nuclear waste below the Department of Energy's (DOE's) attractiveness Level E (the lowest). Options to burn natural or depleted U, Th, U/Th mixtures, Spent Nuclear Fuel (SNF) without chemical separations of weapons-attractive actinide streams, and excess weapons Pu or highly enriched U (HEU) are possible and under consideration. Because the fission blanket is always subcritical and decay heat removal is possible via passive mechanisms, the technology is inherently safe. Many technical challenges must be met, but

  1. Cyclotron-based nuclear science. Progress report, April 1, 1979-March 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    Research at the cyclotron institute is summarized. These major areas are covered: nuclear structure; nuclear reactions and scattering; polarization studies; interdisciplinary nuclear science; instrumentation and systems development; and publications. (GHT)

  2. Strengthening safety compliance in nuclear power operations: a role-based approach.

    Science.gov (United States)

    Martínez-Córcoles, Mario; Gracia, Francisco J; Tomás, Inés; Peiró, José M

    2014-07-01

    Safety compliance is of paramount importance in guaranteeing the safe running of nuclear power plants. However, it depends mostly on procedures that do not always involve the safest outcomes. This article introduces an empirical model based on the organizational role theory to analyze the influence of legitimate sources of expectations (procedures formalization and leadership) on workers' compliance behaviors. The sample was composed of 495 employees from two Spanish nuclear power plants. Structural equation analysis showed that, in spite of some problematic effects of proceduralization (such as role conflict and role ambiguity), procedure formalization along with an empowering leadership style lead to safety compliance by clarifying a worker's role in safety. Implications of these findings for safety research are outlined, as well as their practical implications.

  3. Entropy-based adaptive nuclear texture features are independent prognostic markers in a total population of uterine sarcomas.

    Science.gov (United States)

    Nielsen, Birgitte; Hveem, Tarjei Sveinsgjerd; Kildal, Wanja; Abeler, Vera M; Kristensen, Gunnar B; Albregtsen, Fritz; Danielsen, Håvard E

    2015-04-01

    Nuclear texture analysis measures the spatial arrangement of the pixel gray levels in a digitized microscopic nuclear image and is a promising quantitative tool for prognosis of cancer. The aim of this study was to evaluate the prognostic value of entropy-based adaptive nuclear texture features in a total population of 354 uterine sarcomas. Isolated nuclei (monolayers) were prepared from 50 µm tissue sections and stained with Feulgen-Schiff. Local gray level entropy was measured within small windows of each nuclear image and stored in gray level entropy matrices, and two superior adaptive texture features were calculated from each matrix. The 5-year crude survival was significantly higher (P Entropy-based adaptive nuclear texture was an independent prognostic marker for crude survival in multivariate analysis including relevant clinicopathological features (HR = 2.1, P = 0.001), and should therefore be considered as a potential prognostic marker in uterine sarcomas.

  4. Dictionary of nuclear engineering

    Energy Technology Data Exchange (ETDEWEB)

    Sube, R.

    1985-01-01

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

  5. Goal conflicts management in the control and operation of nuclear power plant; La gestion des conflits d'objectifs dans la conduite et l'exploitation d'installations nucleires

    Energy Technology Data Exchange (ETDEWEB)

    Letzkus, P

    2004-11-15

    The goal conflicts constitute classes of situation or behaviors which can be translated, in the human activity, by skirting or variations with the rules...Their consequences can be serious, in particular in nuclear industry. In addition, the analyses of incidents do not make it always possible to integrate complex factors like individual attitudes, organisational or design features which push the operators to take risks to achieve their activity. This research first of all presents indicators which make it possible to go up with the causes of these variations. In the second place, a model of management of the activity illustrates why it is observed that people can adopt strategies or behaviors whose finalities seem to be opposed to the context. For that, it allots to emotional dimension a role of modulator intervening on the cognitive mechanisms managing an operational situation. (author)

  6. The TN Gemini: a packing for the transport of wastes coming from the dismantling of nuclear facilities; Le TN Gemini: un emballage de transport pour les dechets technologiques issus de la deconstruction des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Vuong, J. [TN International, Groupe Areva, Tour Areva, Paris La Defense (France)

    2011-11-15

    The TN Gemini package has been designed by 'TN International' and has been agreed since 1997 as a type-B package with great capacity, its useful dimensions are 4.51 m * 1.84 m * 2.00 m (L*l*h). Its big size enables the TN Gemini package to transport large components with no need to cut them like glove boxes or large parts of contaminated metallic components coming from the dismantling of nuclear facilities. Its great resistance to fire is an asset for transporting wastes releasing inflammable gases. This package has been used intensively in U.K. for the retrieval of PCO (plutonium contaminated objects) from the waste repository of Drigg. (A.C.)

  7. Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process

    Energy Technology Data Exchange (ETDEWEB)

    E. R. Johnson; R. E. Best

    2009-12-28

    The research described in this report was performed under a grant from the U.S. Department of Energy (DOE) to describe and compare the merits of two advanced alternative nuclear fuel cycles -- named by this study as the “UREX+3c fuel cycle” and the “Alternative Fuel Cycle” (AFC). Both fuel cycles were assumed to support 100 1,000 MWe light water reactor (LWR) nuclear power plants operating over the period 2020 through 2100, and the fast reactors (FRs) necessary to burn the plutonium and minor actinides generated by the LWRs. Reprocessing in both fuel cycles is assumed to be based on the UREX+3c process reported in earlier work by the DOE. Conceptually, the UREX+3c process provides nearly complete separation of the various components of spent nuclear fuel in order to enable recycle of reusable nuclear materials, and the storage, conversion, transmutation and/or disposal of other recovered components. Output of the process contains substantially all of the plutonium, which is recovered as a 5:1 uranium/plutonium mixture, in order to discourage plutonium diversion. Mixed oxide (MOX) fuel for recycle in LWRs is made using this 5:1 U/Pu mixture plus appropriate makeup uranium. A second process output contains all of the recovered uranium except the uranium in the 5:1 U/Pu mixture. The several other process outputs are various waste streams, including a stream of minor actinides that are stored until they are consumed in future FRs. For this study, the UREX+3c fuel cycle is assumed to recycle only the 5:1 U/Pu mixture to be used in LWR MOX fuel and to use depleted uranium (tails) for the makeup uranium. This fuel cycle is assumed not to use the recovered uranium output stream but to discard it instead. On the other hand, the AFC is assumed to recycle both the 5:1 U/Pu mixture and all of the recovered uranium. In this case, the recovered uranium is reenriched with the level of enrichment being determined by the amount of recovered plutonium and the combined amount

  8. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.

    2001-08-24

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I&C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I&C system upgrades of present-day nuclear power plants, as well as I&C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I&C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC

  9. Expedient Protocols for the Installation of Pyrimidine Based Privileged Templates on 2-Position of Pyrrolo[2,1-c][1,4]-benzodiazepine Nucleus Linked Through a p-phenoxyl Spacer

    Directory of Open Access Journals (Sweden)

    Anshu Agarwal

    2012-01-01

    Full Text Available Exceedingly facile single step expedient protocols based on the versatility and reactivity of corresponding intermediates : [2-(dimethylaminomethylene ketone] (5 and chalcone (6, derived from 2-(p-acetyl phenoxyl substituted analogue of pyrrolo[2,1-c][1,4]-benzodiazepine (4, have been developed to provide an easy installation of the pyrimidine based privileged templates at 2-position of pyrrolo[2,1-c][1,4]-benzodiazepine through a p-phenoxyl spacer, by utilizing the synthetic strategy depicted in schemes-1 and 2.

  10. ASSESSMENT OF THE RELEVANCE OF DISPLACEMENT BASED DESIGN METHODS/CRITERIA TO NUCLEAR PLANT STRUCTURES.

    Energy Technology Data Exchange (ETDEWEB)

    HOFMAYER,C.; MILLER,C.; WANG,Y.; COSTELLO,J.

    2001-08-12

    Revisions to the USNRC Regulatory Guides and Standard Review Plan Sections devoted to earthquake engineering practice are currently in process. The intent is to reflect changes in engineering practice that have evolved in the twenty years that have passed since those criteria were originally published. Additionally, field observations of the effects of the Northridge (1994) and Kobe (1995) earthquakes have inspired some reassessment in the technical community about certain aspects of design practice. In particular, questions have arisen about the effectiveness of basing earthquake resistant designs on resistance to seismic forces and, then evaluating tolerability of the expected displacements. Therefore, a research effort was undertaken to examine the implications for NRC's seismic practice of the move, in the earthquake engineering community, toward using expected displacement rather than force (or stress) as the basis for assessing design adequacy. The results of the NRC sponsored research on this subject are reported in this paper. A slow trend toward the utilization of displacement based methods for design was noted. However, there is a more rapid trend toward the use of displacement based methods for seismic evaluation of existing facilities. A document known as FEMA 273, has been developed and is being used as the basis for the design of modifications to enhance the seismic capability of existing non-nuclear facilities. The research concluded that displacement based methods, such as given in FEMA 273, may be useful for seismic margin studies of existing nuclear power stations. They are unlikely to be useful for the basic design of new stations since nuclear power stations are designed to remain elastic during a seismic event. They could, however, be useful for estimating the margins associated with that design.

  11. Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems

    Directory of Open Access Journals (Sweden)

    Zhe Dong

    2016-01-01

    Full Text Available The modular high temperature gas-cooled reactor (MHTGR is a typical small modular reactor (SMR that offers simpler, standardized and safer modular design by being factory built, requiring smaller initial capital investment, and having a shorter construction period. Thanks to its small size, the MHTGRs could be beneficial in providing electric power to remote areas that are deficient in transmission or distribution and in generating local power for large population centers. Based on the multi-modular operation scheme, the inherent safety feature of the MHTGRs can be applicable to large nuclear plants of any desired power rating. The MHTGR-based nuclear steam supplying system (NSSS is constituted by an MHTGR, a side-by-side arranged helical-coil once-through steam generator (OTSG and some connecting pipes. Due to the side-by-side arrangement, there is a tight coupling effect between the MHTGR and OTSG. Moreover, there always exists the parameter perturbation of the NSSSs. Thus, it is meaningful to study the model-free coordinated control of MHTGR-based NSSSs for safe, stable, robust and efficient operation. In this paper, a new model-free coordinated control strategy that regulates the nuclear power, MHTGR outlet helium temperature and OTSG outlet overheated steam temperature by properly adjusting the control rod position, helium flowrate and feed-water flowrate is established for the MHTGR-based NSSSs. Sufficient conditions for the globally asymptotic closed-loop stability is given. Finally, numerical simulation results in the cases of large range power decrease and increase illustrate the satisfactory performance of this newly-developed model-free coordinated NSSS control law.

  12. Molecular phylogeny and evolution of Scomber (Teleostei: Scombridae) based on mitochondrial and nuclear DNA sequences

    Institute of Scientific and Technical Information of China (English)

    CHENG Jiao; GAO Tianxiang; MIAO Zhenqing; YANAGIMOTO Takashi

    2011-01-01

    A molecular phylogenetic analysis of the genus Scomber was conducted based on mitochondrial (COI, Cyt b and control region) and nuclear (5S rDNA) DNA sequence data in multigene perspective. A variety of phylogenetic analytic methods were used to clarify the current taxonomic classification and to assess phylogenetic relationships and the evolutionary history of this genus. The present study produced a well-resolved phylogeny that strongly supported the monophyly of Scomber. We confirmed that S. japonicus and S. colias were genetically distinct. Although morphologically and ecologically similar to S. colias, the molecular data showed that S. japonicus has a greater molecular affinity with S. australasicus, which conflicts with the traditional taxonomy. This phyiogenetic pattern was corroborated by the mtDNA data, but incompletely by the nuclear DNA data. Phylogenetic concordance between the mitochondrial and nuclear DNA regions for the basal nodes supports an Atlantic origin for Scomber. The present-day geographic ranges of the species were compared with the resultant molecular phylogeny derived from partition Bayesian analyses of the combined data sets to evaluate possible dispersal routes of the genus. The present-day geographic distribution of Scomber species might be best ascribed to multiple dispersal events. In addition, our results suggest that phylogenies derived from multiple genes and long sequences exhibited improved phylogenetic resolution, from which we conclude that the phylogenetic reconstruction is a reliable representation of the evolutionary history of Scomber.

  13. Scintillation-only Based Pulse Shape Discrimination for Nuclear and Electron Recoils in Liquid Xenon

    CERN Document Server

    Ueshima, K; Hiraide, K; Hirano, S; Kishimoto, Y; Kobayashi, K; Koshio, Y; Liu, J; Martens, K; Moriyama, S; Nakahata, M; Nishiie, H; Ogawa, H; Sekiya, H; Shinozaki, A; Suzuki, Y; Takeda, A; Yamashita, M; Fujii, K; Murayama, I; Nakamura, S; Otsuka, K; Takeuchi, Y; Fukuda, Y; Nishijima, K; Motoki, D; Itow, Y; Masuda, K; Nishitani, Y; Uchida, H; Tasaka, S; Ohsumi, H; Kim, Y D; Kim, Y H; Lee, K B; Lee, M K

    2011-01-01

    In a dedicated test setup at the Kamioka Observatory we studied pulse shape discrimination (PSD) in liquid xenon (LXe) for dark matter searches. PSD in LXe was based on the observation that scintillation light from electron events was emitted over a longer period of time than that of nuclear recoil events, and our method used a simple ratio of early to total scintillation light emission in a single scintillation event. Requiring an efficiency of 50% for nuclear recoil retention we reduced the electron background to 7.7\\pm1.1(stat)\\pm1.2 0.6(sys)\\times10-2 at energies between 4.8 and 7.2 keVee and to 7.7\\pm2.8(stat)\\pm2.5 2.8(sys)\\times10-3 at energies between 9.6 and 12 keVee for a scintillation light yield of 20.9 p.e./keV. Further study was done by masking some of that light to reduce this yield to 4.6 p.e./keV, the same method results in an electron event reduction of 2.4\\pm0.2(stat)\\pm0.3 0.2(sys)\\times10-1 for the lower of the energy regions above. We also observe that in contrast to nuclear recoils the ...

  14. Nuclear reactor power for a space-based radar. SP-100 project

    Science.gov (United States)

    Bloomfield, Harvey; Heller, Jack; Jaffe, Leonard; Beatty, Richard; Bhandari, Pradeep; Chow, Edwin; Deininger, William; Ewell, Richard; Fujita, Toshio; Grossman, Merlin

    1986-01-01

    A space-based radar mission and spacecraft, using a 300 kWe nuclear reactor power system, has been examined, with emphasis on aspects affecting the power system. The radar antenna is a horizontal planar array, 32 X 64 m. The orbit is at 61 deg, 1088 km. The mass of the antenna with support structure is 42,000 kg; of the nuclear reactor power system, 8,300 kg; of the whole spacecraft about 51,000 kg, necessitating multiple launches and orbital assembly. The assembly orbit is at 57 deg, 400 km, high enough to provide the orbital lifetime needed for orbital assembly. The selected scenario uses six Shuttle launches to bring the spacecraft and a Centaur G upper-stage vehicle to assembly orbit. After assembly, the Centaur places the spacecraft in operational orbit, where it is deployed on radio command, the power system started, and the spacecraft becomes operational. Electric propulsion is an alternative and allows deployment in assembly orbit, but introduces a question of nuclear safety.

  15. General framework and basis of decommissioning of nuclear facilities; Marco general y bases de los desmantelamientos de las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Santiago, J. L.; Martin, N.; Correa, C.

    2013-07-01

    This article summarizes the legal framework defining the strategies, the main activities and the basic responsibilities and roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the most relevant projects and activities already developed and/or ongoing nowadays, which have positioned Spain within the small group of countries having an integrated and proved experience and know how in this particular field. (Author)

  16. A Denoising Based Autoassociative Model for Robust Sensor Monitoring in Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Ahmad Shaheryar

    2016-01-01

    Full Text Available Sensors health monitoring is essentially important for reliable functioning of safety-critical chemical and nuclear power plants. Autoassociative neural network (AANN based empirical sensor models have widely been reported for sensor calibration monitoring. However, such ill-posed data driven models may result in poor generalization and robustness. To address above-mentioned issues, several regularization heuristics such as training with jitter, weight decay, and cross-validation are suggested in literature. Apart from these regularization heuristics, traditional error gradient based supervised learning algorithms for multilayered AANN models are highly susceptible of being trapped in local optimum. In order to address poor regularization and robust learning issues, here, we propose a denoised autoassociative sensor model (DAASM based on deep learning framework. Proposed DAASM model comprises multiple hidden layers which are pretrained greedily in an unsupervised fashion under denoising autoencoder architecture. In order to improve robustness, dropout heuristic and domain specific data corruption processes are exercised during unsupervised pretraining phase. The proposed sensor model is trained and tested on sensor data from a PWR type nuclear power plant. Accuracy, autosensitivity, spillover, and sequential probability ratio test (SPRT based fault detectability metrics are used for performance assessment and comparison with extensively reported five-layer AANN model by Kramer.

  17. Nuclear Norm Based Matrix Regression with Applications to Face Recognition with Occlusion and Illumination Changes.

    Science.gov (United States)

    Yang, Jian; Luo, Lei; Qian, Jianjun; Tai, Ying; Zhang, Fanlong; Xu, Yong

    2017-01-01

    Recently, regression analysis has become a popular tool for face recognition. Most existing regression methods use the one-dimensional, pixel-based error model, which characterizes the representation error individually, pixel by pixel, and thus neglects the two-dimensional structure of the error image. We observe that occlusion and illumination changes generally lead, approximately, to a low-rank error image. In order to make use of this low-rank structural information, this paper presents a two-dimensional image-matrix-based error model, namely, nuclear norm based matrix regression (NMR), for face representation and classification. NMR uses the minimal nuclear norm of representation error image as a criterion, and the alternating direction method of multipliers (ADMM) to calculate the regression coefficients. We further develop a fast ADMM algorithm to solve the approximate NMR model and show it has a quadratic rate of convergence. We experiment using five popular face image databases: the Extended Yale B, AR, EURECOM, Multi-PIE and FRGC. Experimental results demonstrate the performance advantage of NMR over the state-of-the-art regression-based methods for face recognition in the presence of occlusion and illumination variations.

  18. Using GIS data and satellite derived irradiance to optimize siting of PV installations in Switzerland

    Science.gov (United States)

    Kahl, Annelen; Nguyen, Viet-Anh; Bartlett, Stuart; Sossan, Fabrizio; Lehning, Michael

    2016-04-01

    For a successful distribution strategy of PV installations, it does not suffice to choose the locations with highest annual total irradiance. Attention needs to be given to spatial correlation patterns of insolation to avoid large system-wide variations, which can cause extended deficits in supply or might even damage the electrical network. One alternative goal instead is to seek configurations that provide the smoothest energy production, with the most reliable and predictable supply. Our work investigates several scenarios, each pursuing a different strategy for a future renewable Switzerland without nuclear power. Based on an estimate for necessary installed capacity for solar power [Bartlett, 2015] we first use heuristics to pre-select realistic placements for PV installations. Then we apply optimization methods to find a subset of locations that provides the best possible combined electricity production. For the first part of the selection process, we use a DEM to exclude high elevation zones which would be difficult to access and which are prone to natural hazards. Then we use land surface cover information to find all zones with potential roof area, deemed suitable for installation of solar panels. The optimization employs Principal Component Analysis of satellite derived irradiance data (Surface Incoming Shortwave Radiation (SIS), based on Meteosat Second Generation sensors) to incorporate a spatial aspect into the selection process that does not simply maximize annual total production but rather provides the most robust supply, by combining regions with anti-correlated cloud cover patterns. Depending on the initial assumptions and constraints, the resulting distribution schemes for PV installations vary with respect to required surface area, annual total and lowest short-term production, and illustrate how important it is to clearly define priorities and policies for a future renewable Switzerland.

  19. High Level Requirements for the Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)

    Energy Technology Data Exchange (ETDEWEB)

    Rich Johnson; Hyung Lee; Kimberlyn C. Mousseau

    2011-09-01

    The US Department of Energy, Office of Nuclear Energy (DOE-NE), has been tasked with the important mission of ensuring that nuclear energy remains a compelling and viable energy source in the U.S. The motivations behind this mission include cost-effectively meeting the expected increases in the power needs of the country, reducing carbon emissions and reducing dependence on foreign energy sources. In the near term, to ensure that nuclear power remains a key element of U.S. energy strategy and portfolio, the DOE-NE will be working with the nuclear industry to support safe and efficient operations of existing nuclear power plants. In the long term, to meet the increasing energy needs of the U.S., the DOE-NE will be investing in research and development (R&D) and working in concert with the nuclear industry to build and deploy new, safer and more efficient nuclear power plants. The safe and efficient operations of existing nuclear power plants and designing, licensing and deploying new reactor designs, however, will require focused R&D programs as well as the extensive use and leveraging of advanced modeling and simulation (M&S). M&S will play a key role in ensuring safe and efficient operations of existing and new nuclear reactors. The DOE-NE has been actively developing and promoting the use of advanced M&S in reactor design and analysis through its R&D programs, e.g., the Nuclear Energy Advanced Modeling and Simulation (NEAMS) and Consortium for Advanced Simulation of Light Water Reactors (CASL) programs. Also, nuclear reactor vendors are already using CFD and CSM, for design, analysis, and licensing. However, these M&S tools cannot be used with confidence for nuclear reactor applications unless accompanied and supported by verification and validation (V&V) and uncertainty quantification (UQ) processes and procedures which provide quantitative measures of uncertainty for specific applications. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation

  20. The Living Textbook of Nuclear Chemistry: A Peer-Reviewed, Web-Based, Education Resource

    Science.gov (United States)

    Loveland, W.; Gallant, A.; Joiner, C.

    2004-01-01

    The recent developments in nuclear chemistry education are presented and an attempt is made to collect supplemental materials relating to the study and practice of nuclear chemistry. The Living Textbook of Nuclear Chemistry functions as an authoritative Web site with supplemental material for teaching nuclear and radiochemistry.

  1. Dynamic flowgraph modeling of process and control systems of a nuclear-based hydrogen production plant

    Energy Technology Data Exchange (ETDEWEB)

    Al-Dabbagh, Ahmad W. [Faculty of Engineering and Applied Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario (Canada); Lu, Lixuan [Faculty of Energy Systems and Nuclear Science, Faculty of Engineering and Applied Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario (Canada)

    2010-09-15

    Modeling and analysis of system reliability facilitate the identification of areas of potential improvement. The Dynamic Flowgraph Methodology (DFM) is an emerging discrete modeling framework that allows for capturing time dependent behaviour, switching logic and multi-state representation of system components. The objective of this research is to demonstrate the process of dynamic flowgraph modeling of a nuclear-based hydrogen production plant with the copper-chlorine (Cu-Cl) cycle. Modeling of the thermochemical process of the Cu-Cl cycle in conjunction with a networked control system proposed for monitoring and control of the process is provided. This forms the basis for future component selection. (author)

  2. Current status and prospects of nuclear physics research based on tracking techniques

    Science.gov (United States)

    Alekseev, V. A.; Alexandrov, A. B.; Bagulya, A. V.; Chernyavskiy, M. M.; Goncharova, L. A.; Gorbunov, S. A.; Kalinina, G. V.; Konovalova, N. S.; Okatyeva, N. M.; Pavlova, T. A.; Polukhina, N. G.; Shchedrina, T. V.; Starkov, N. I.; Tioukov, V. E.; Vladymirov, M. S.; Volkov, A. E.

    2017-01-01

    Results of nuclear physics research made using track detectors are briefly reviewed. Advantages and prospects of the track detection technique in particle physics, neutrino physics, astrophysics and other fields are discussed on the example of the results of the search for direct origination of tau neutrino in a muon neutrino beam within the framework of the international experiment OPERA (Oscillation Project with Emulsion-tRacking Apparatus) and works on search for superheavy nuclei in nature on base of their tracks in meteoritic olivine crystals. The spectra of superheavy elements in galactic cosmic rays are presented. Prospects of using the track detection technique in fundamental and applied research are reported.

  3. Integrated data base report--1995: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    The information in this report summarizes the U.S. Department of Energy (DOE) data base for inventories, projections, and characteristics of domestic spent nuclear fuel and radioactive waste. This report is updated annually to keep abreast of continual waste inventory and projection changes in both the government and commercial sectors. Baseline information is provided for DOE program planning purposes and to support DOE program decisions. Although the primary purpose of this document is to provide background information for program planning within the DOE community, it has also been found useful by state and local governments, the academic community, and some private citizens.

  4. Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

    Energy Technology Data Exchange (ETDEWEB)

    Hou, Xue Yan; Li, Shu; Li, Qing [China Nuclear Power Operation Technology Co., Wuhan (China)

    2011-08-15

    Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier.

  5. Fuzzy-logic-based safety verification framework for nuclear power plants.

    Science.gov (United States)

    Rastogi, Achint; Gabbar, Hossam A

    2013-06-01

    This article presents a practical implementation of a safety verification framework for nuclear power plants (NPPs) based on fuzzy logic where hazard scenarios are identified in view of safety and control limits in different plant process values. Risk is estimated quantitatively and compared with safety limits in real time so that safety verification can be achieved. Fuzzy logic is used to define safety rules that map hazard condition with required safety protection in view of risk estimate. Case studies are analyzed from NPP to realize the proposed real-time safety verification framework. An automated system is developed to demonstrate the safety limit for different hazard scenarios.

  6. Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process

    Energy Technology Data Exchange (ETDEWEB)

    E. R. Johnson; R. E. Best

    2009-12-28

    The research described in this report was performed under a grant from the U.S. Department of Energy (DOE) to describe and compare the merits of two advanced alternative nuclear fuel cycles -- named by this study as the “UREX+3c fuel cycle” and the “Alternative Fuel Cycle” (AFC). Both fuel cycles were assumed to support 100 1,000 MWe light water reactor (LWR) nuclear power plants operating over the period 2020 through 2100, and the fast reactors (FRs) necessary to burn the plutonium and minor actinides generated by the LWRs. Reprocessing in both fuel cycles is assumed to be based on the UREX+3c process reported in earlier work by the DOE. Conceptually, the UREX+3c process provides nearly complete separation of the various components of spent nuclear fuel in order to enable recycle of reusable nuclear materials, and the storage, conversion, transmutation and/or disposal of other recovered components. Output of the process contains substantially all of the plutonium, which is recovered as a 5:1 uranium/plutonium mixture, in order to discourage plutonium diversion. Mixed oxide (MOX) fuel for recycle in LWRs is made using this 5:1 U/Pu mixture plus appropriate makeup uranium. A second process output contains all of the recovered uranium except the uranium in the 5:1 U/Pu mixture. The several other process outputs are various waste streams, including a stream of minor actinides that are stored until they are consumed in future FRs. For this study, the UREX+3c fuel cycle is assumed to recycle only the 5:1 U/Pu mixture to be used in LWR MOX fuel and to use depleted uranium (tails) for the makeup uranium. This fuel cycle is assumed not to use the recovered uranium output stream but to discard it instead. On the other hand, the AFC is assumed to recycle both the 5:1 U/Pu mixture and all of the recovered uranium. In this case, the recovered uranium is reenriched with the level of enrichment being determined by the amount of recovered plutonium and the combined amount

  7. Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  8. A practical approach for implementing risk-based inservice testing of pumps at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, R.S. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Maret, D.; Seniuk, P.; Smith, L.

    1996-12-01

    The American Society of Mechanical Engineers (ASME) Center for Research and Technology Development`s (CRTD) Research Task Force on Risk-Based Inservice Testing has developed guidelines for risk-based inservice testing (IST) of pumps and valves. These guidelines are intended to help the ASME Operation and Maintenance (OM) Committee to enhance plant safety while focussing appropriate testing resources on critical components. This paper describes a practical approach for implementing those guidelines for pumps at nuclear power plants. The approach, as described in this paper, relies on input, direction, and assistance from several entities such as the ASME Code Committees, United States Nuclear Regulatory Commission (NRC), and the National Laboratories, as well as industry groups and personnel with applicable expertise. Key parts of the risk-based IST process that are addressed here include: identification of important failure modes, identification of significant failure causes, assessing the effectiveness of testing and maintenance activities, development of alternative testing and maintenance strategies, and assessing the effectiveness of alternative testing strategies with present ASME Code requirements. Finally, the paper suggests a method of implementing this process into the ASME OM Code for pump testing.

  9. An Agent-Based Modeling Framework and Application for the Generic Nuclear Fuel Cycle

    Science.gov (United States)

    Gidden, Matthew J.

    Key components of a novel methodology and implementation of an agent-based, dynamic nuclear fuel cycle simulator, Cyclus , are presented. The nuclear fuel cycle is a complex, physics-dependent supply chain. To date, existing dynamic simulators have not treated constrained fuel supply, time-dependent, isotopic-quality based demand, or fuel fungibility particularly well. Utilizing an agent-based methodology that incorporates sophisticated graph theory and operations research techniques can overcome these deficiencies. This work describes a simulation kernel and agents that interact with it, highlighting the Dynamic Resource Exchange (DRE), the supply-demand framework at the heart of the kernel. The key agent-DRE interaction mechanisms are described, which enable complex entity interaction through the use of physics and socio-economic models. The translation of an exchange instance to a variant of the Multicommodity Transportation Problem, which can be solved feasibly or optimally, follows. An extensive investigation of solution performance and fidelity is then presented. Finally, recommendations for future users of Cyclus and the DRE are provided.

  10. DAQ INSTALLATION IN USC COMPLETED

    CERN Multimedia

    A. Racz

    After one year of work at P5 in the underground control rooms (USC55-S1&S2), the DAQ installation in USC55 is completed. The first half of 2006 was dedicated to the DAQ infrastructures installation (private cable trays, rack equipment for a very dense cabling, connection to services i.e. water, power, network). The second half has been spent to install the custom made electronics (FRLs and FMMs) and place all the inter-rack cables/fibers connecting all sub-systems to central DAQ (more details are given in the internal pages). The installation has been carried out by DAQ group members, coming from the hardware and software side as well. The pictures show the very nice team spirit !

  11. Installation of the Gbar LINAC

    CERN Multimedia

    Maximilien, Brice

    2017-01-01

    Installation of the GBAR linac in its shielding bunker. The electrons accelerated to 10 MeV toward a target will produce the positrons that are necessary to form anti hydrogen with the antiprotons coming from the ELENA decelerator.

  12. The Status of LIGO Installation and Commissioning

    Science.gov (United States)

    Raab, Frederick J.

    2002-12-01

    LIGO is engaged in installation and commissioning in Hanford and Livingston. We are commissioning the first instance of any subsystem installed, applying lessons learned to later installations. We have installed all seismic stacks, installed lasers and input optics at both observatories and we have operated both of the 2-km Fabry-Perot cavities at Hanford, with lock times up to 10 hrs.

  13. Enhanced base excision repair capacity in carotid atherosclerosis may protect nuclear DNA but not mitochondrial DNA

    DEFF Research Database (Denmark)

    Skarpengland, Tonje; B. Dahl, Tuva; Skjelland, Mona

    2016-01-01

    Lesional and systemic oxidative stress has been implicated in the pathogenesis of atherosclerosis, potentially leading to accumulation of DNA base lesions within atherosclerotic plaques. Although base excision repair (BER) is a major pathway counteracting oxidative DNA damage, our knowledge on BER...... and accumulation of DNA base lesions in clinical atherosclerosis is scarce. Here, we evaluated the transcriptional profile of a wide spectrum of BER components as well as DNA damage accumulation in atherosclerotic and non-atherosclerotic arteries. BER gene expression levels were analyzed in 162 carotid plaques, 8...... genes in atherosclerosis may contribute to lesional nuclear DNA stability but appears insufficient to maintain mtDNA integrity, potentially influencing mitochondrial function in cells within the atherosclerotic lesion....

  14. Suitcase to Audit Solar Installations

    Energy Technology Data Exchange (ETDEWEB)

    Alberdi, J.; Barcala, J.M.; Blas de, J.; Molinero, A.; Navarrete, J.J.; Yuste, C.

    2001-07-01

    The audit suitcase was proposed by BESEL to introduce in the solar energy market a new tool which can make an evaluation of solar installation efficiency. Non-invasive sensors and low power components permit both easy installation of the devices and data storage for a period as long as ten days. This project was funded by the contract JOR3-CT98-7030 of the European Union JOULE III program. (Author)

  15. Countering Terrorism on Military Installations

    Science.gov (United States)

    1977-07-29

    enforcement purposes. Installation Provost Marshal should review the installation Tables of Distribucion and Allowances to determine commercial items of law...terrorist acts occurring within the 50 U.S. states, territor- ies, and possessions (including the Panama Canal Zone) rests with the Federal Bureadu...nence of the threat is difficult to predict. Today I estimate the threat as relatively low. S- In the Panama Canal Zone there could be three threats. One

  16. Design of a heterogeneous subcritical nuclear reactor with molten salts based on thorium; Diseno de un reactor nuclear subcritico heterogeneo con sales fundidas a base de torio

    Energy Technology Data Exchange (ETDEWEB)

    Medina C, D.; Hernandez A, P.; Letechipia de L, C.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico); Sajo B, L., E-mail: dmedina_c@hotmail.com [Universidad Simon Bolivar, Laboratorio de Fisica Nuclear, Apdo. Postal 89000, Caracas 1080-A (Venezuela, Bolivarian Republic of)

    2015-09-15

    This paper presents the design of a heterogeneous subcritical nuclear reactor with molten salts based on thorium, with graphite moderator and a {sup 252}Cf source, whose dose levels at the periphery allows its use in teaching and research activities. The design was realized by the Monte Carlo method, where the geometry, dimensions and the fuel was varied in order to obtain the best design. The result was a cubic reactor of 110 cm of side, with graphite moderator and reflector. In the central part having 9 ducts of 3 cm in diameter, eight of them are 110 cm long, which were placed on the Y axis; the separation between each duct is 10 cm. The central duct has 60 cm in length and this contains the {sup 252}Cf source, also there are two irradiation channels and the other six contain a molten salt ({sup 7}LiF - BeF{sub 2} - ThF{sub 4} - UF{sub 4}) as fuel. For the design the k{sub eff} was calculated, neutron spectra and ambient dose equivalent. In the first instance the above was calculated for a virgin fuel, was called case 1; then a percentage of {sup 233}U was used and the percentage of Th was decreased and was called case 2. This with the purpose of comparing two different fuels operating within the reactor. For the two irradiation ducts three positions are used: center, back and front, in each duct in order to have different flows. (Author)

  17. Comprehensive data base of high-level nuclear waste glasses: September 1987 status report: Volume 2, Additional appendices

    Energy Technology Data Exchange (ETDEWEB)

    Kindle, C.H.; Kreiter, M.R.

    1987-12-01

    The Materials Characterization Center (MCC) is assembling a comprehensive data base (CDB) of experimental data collected for high-level nuclear waste package components. The status of the CDB is summarized in Volume I of this report. Volume II contains appendices that present data from the data base and an evaluation of glass durability models applied to the data base.

  18. New insights on the history of canids in Oceania based on mitochondrial and nuclear data.

    Science.gov (United States)

    Cairns, Kylie M; Wilton, Alan N

    2016-10-01

    How and when dingoes arrived in Oceania poses a fascinating question for scientists with interest in the historical movements of humans and dogs. The dingo holds a unique position as top terrestrial predator of Australia and exists in a wild state. In the first geographical survey of genetic diversity in the dingo using whole mitochondrial genomes, we analysed 16,428 bp in 25 individuals from five separate populations. We also investigated 13 nuclear loci to compare with the mitochondrial population history patterns. Phylogenetic analyses based upon mitochondrial DNA and nuclear DNA support the hypothesis that there are at least two distinct populations of dingo, one of which occurs in the northwest and the other in the southeast of the continent. Conservative molecular dating based upon mitochondrial DNA suggest that the lineages split approximately 8300 years before present, likely outside Australia but within Oceania. The close relationship between dingoes and New Guinea Singing Dogs suggests that plausibly dingoes spread into Australia via the land bridge between Papua New Guinea and Australia although seafaring introductions cannot be rejected. The geographical distribution of these divergent lineages suggests there were multiple independent dingo immigrations. Importantly, the observation of multiple dingo populations suggests the need for revision of existing conservation and management programs that treat dingoes as a single homogeneous population.

  19. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States); Antonescu, C.E. [Nuclear Regulatory Commission, Rockville, MD (United States)

    1997-10-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program.

  20. Nonproliferation impacts assessment for the management of the Savannah River Site aluminum-based spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    On May 13, 1996, the US established a new, 10-year policy to accept and manage foreign research reactor spent nuclear fuel containing uranium enriched in the US. The goal of this policy is to reduce civilian commerce in weapons-usable highly enriched uranium (HEU), thereby reducing the risk of nuclear weapons proliferation. Two key disposition options under consideration for managing this fuel include conventional reprocessing and new treatment and packaging technologies. The Record of Decision specified that, while evaluating the reprocessing option, ``DOE will commission or conduct an independent study of the nonproliferation and other (e.g., cost and timing) implications of chemical separation of spent nuclear fuel from foreign research reactors.`` DOE`s Office of Arms Control and Nonproliferation conducted this study consistent with the aforementioned Record of Decision. This report addresses the nonproliferation implications of the technologies under consideration for managing aluminum-based spent nuclear fuel at the Savannah River Site. Because the same technology options are being considered for the foreign research reactor and the other aluminum-based spent nuclear fuels discussed in Section ES.1, this report addresses the nonproliferation implications of managing all the Savannah River Site aluminum-based spent nuclear fuel, not just the foreign research reactor spent nuclear fuel. The combination of the environmental impact information contained in the draft EIS, public comment in response to the draft EIS, and the nonproliferation information contained in this report will enable the Department to make a sound decision regarding how to manage all aluminum-based spent nuclear fuel at the Savannah River Site.

  1. 基于 ANSYS 的软体排动水沉排受力分析%ANSYS-based Analysis on Actions of Compound Geotextile Being installed in Dynamic Water

    Institute of Scientific and Technical Information of China (English)

    张益智; 张焕岭; 许战军

    2013-01-01

    软体排因其排布具有隔离、反滤作用及整体具有一定的柔性可适应凹凸不平的地形,材料使用寿命长、施工方便等特点,被广泛应用于河道的护底及护岸、海岸的护滩、泄水建筑物后部的防冲等。在软体排施工中,为了防止沉排时因受力过大导致排体撕裂、铺排船倾覆等的发生,要严格控制软体排船舷处拉力。对于静水中沉排时软体排船舷处拉力的研究,已基本趋于成熟化,有精确的解析解,但对动水中沉排时软体排拉力多采用试验方法得出经验公式来计算。文章在静水中沉排时软体排受力基础上建立动水中软体排计算有限模型,并通过具体算例得出动水中软体排拉力变化的一些规律。%The soft geotextile is widely utilized for bottom protection of river course, river bank protection, sea bank apron and scouring pro-tection of the rear sections of outlet structures as it can play the roles of isolation, filter and flexibility which can satisfy the uneven landforms. This geotextile also features long service life and construction convenience.The tension on the geotextile at shipboard shall be controlled strictly in the geotextile installation so as to avoid the geotextile being torn up or the ship being overturned because of the large tension while the geotextile is being installed.The study on the tension at the shipboard while the geotextile is installed in the static water is becoming ma-ture and precise analysis and calculations are available.But the tension at the shipboard while the geotextile is installed in the dynamic water is calculated by applying the empirical formula which is from test methods.In this paper, the finite element model for calculation of the soft geotextile installation in the dynamic water is constructed based on the action on the geotextile being installed in the static water.Through specific calculation, some laws on variation of action on the

  2. Nuclear counting filter based on a centered Skellam test and a double exponential smoothing

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, Romain; Kondrasovs, Vladimir; Dumazert, Jonathan; Rohee, Emmanuel; Normand Stephane [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, F-91191 Gif-sur-Yvette, (France)

    2015-07-01

    Online nuclear counting represents a challenge due to the stochastic nature of radioactivity. The count data have to be filtered in order to provide a precise and accurate estimation of the count rate, this with a response time compatible with the application in view. An innovative filter is presented in this paper addressing this issue. It is a nonlinear filter based on a Centered Skellam Test (CST) giving a local maximum likelihood estimation of the signal based on a Poisson distribution assumption. This nonlinear approach allows to smooth the counting signal while maintaining a fast response when brutal change activity occur. The filter has been improved by the implementation of a Brown's double Exponential Smoothing (BES). The filter has been validated and compared to other state of the art smoothing filters. The CST-BES filter shows a significant improvement compared to all tested smoothing filters. (authors)

  3. Computer–Based Procedures for Nuclear Power Plant Field Workers: Preliminary Results from Two Evaluation Studies

    Energy Technology Data Exchange (ETDEWEB)

    Katya L Le Blanc; Johanna H Oxstrand

    2013-10-01

    The Idaho National Laboratory and participants from the U.S. nuclear industry are collaborating on a research effort aimed to augment the existing guidance on computer-based procedure (CBP) design with specific guidance on how to design CBP user interfaces such that they support procedure execution in ways that exceed the capabilities of paper-based procedures (PBPs) without introducing new errors. Researchers are employing an iterative process where the human factors issues and interface design principles related to CBP usage are systematically addressed and evaluated in realistic settings. This paper describes the process of developing a CBP prototype and the two studies conducted to evaluate the prototype. The results indicate that CBPs may improve performance by reducing errors, but may increase the time it takes to complete procedural tasks.

  4. Factoring-based method for the design of a nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Guzman-Arriaga, Rafael; Espinosa-Paredes, Gilberto [Division de Ciencias Basicas e Ingenieria, Universidad Autonoma Metropolitana-Iztapalapa, Av. San Rafael Atlixco 186 Col. Vicentina, Mexico 09340, D. F. (Mexico)

    2010-05-15

    In this work a simple method for a fuel lattice design is presented. The method is focused on finding the radial distribution of the fuel rods having different fissile contents to obtain a prescribed neutron multiplication factor k{sub {infinity}} to a certain discharge burnup and to minimize the rod power peaking. This method is based on the factorization of the fissile content of each fuel bar and the performance of this novel method was demonstrated with a fuel design composed of enriched uranium for a typical boiling water reactor (BWR). The results show that the factoring-based method for the design of a nuclear fuel converges to a minimum rod power peaking and a prescribed k{sub {infinity}} in few iterations. A comparative analysis shows that the proposed method is more efficient than existing methods. (author)

  5. High temperature oxidation behavior of ODS iron-base alloys for nuclear energy application

    Energy Technology Data Exchange (ETDEWEB)

    Li, M.; Zhou, Z.; Liao, L.; Chen, W.; Ge, C. [Univ. of Science and Technology Beijing, School of Materials Science and Engineering, Beijing (China)

    2010-07-01

    Oxide dispersion strengthened (ODS) iron based alloys are considered as promising high temperature structural material for advanced nuclear energy systems due to its higher creep strength and radiation damage resistance than conventional commercial steels. In this study, the oxidation behavior of ODS iron based alloys with different Cr content (12-18%) was investigated by exposing samples at high temperature of 700℃ and 1000℃ in atmosphere environment, the exposure time is up to 500 h. Results showed that 14Cr and 18Cr ODS alloys exhibited better oxidation resistance than 12Cr ODS alloys. For the same chromium content, the oxidation resistance of ODS alloys are better than that of non-ODS alloys. (author)

  6. Public inquiry related to the request by EDF of a definitive stopping and complete dismantling of the hardware storage installation of the Monts d'Arree nuclear power plant (INB n.162). Opinion and conclusions of the inquiry commission; Enquete publique relative a la demande, presentee par EDF, de mise a l'arret definitif et de demantelement complet de l'installation d'entreposage de materiels de la centrale nucleaire des Monts d'Arree (INB n.162). Avis et conclusions de la commission d'enquete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-03-15

    After a recall of the project of stopping and dismantling of the hardware storage installation (INB n.162) which had been created after the stopping and dismantling of the Monts d'Arree heavy water nuclear reactor (INB n.28), this report analyzes the results of the public inquiry, and highlights the arguments of those in favour of this project and those opposed to it. Then, it states the Inquiry Commission's opinion which addresses the request for a national public debate, the project justification, the inquiry file, the site radiological status, the site radiological control during works, the impacts of dismantling, the various risks (for the population and the workers, in terms of fire risks), the issue of radioactive wastes, economic aspects (costs, jobs, local economy, tourism and site image), and site reconversion

  7. Scintillation-only based pulse shape discrimination for nuclear and electron recoils in liquid xenon

    Energy Technology Data Exchange (ETDEWEB)

    Ueshima, K., E-mail: ueshima@suketto.icrr.u-tokyo.ac.jp [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Abe, K.; Hiraide, K.; Hirano, S. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Kishimoto, Y. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Institute for the Physics and Mathematics of the Universe, University of Tokyo, Kashiwa, Chiba 277-8582 (Japan); Kobayashi, K.; Koshio, Y. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Liu, J.; Martens, K. [Institute for the Physics and Mathematics of the Universe, University of Tokyo, Kashiwa, Chiba 277-8582 (Japan); Moriyama, S.; Nakahata, M. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Institute for the Physics and Mathematics of the Universe, University of Tokyo, Kashiwa, Chiba 277-8582 (Japan); Nishiie, H.; Ogawa, H.; Sekiya, H.; Shinozaki, A. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Suzuki, Y. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Institute for the Physics and Mathematics of the Universe, University of Tokyo, Kashiwa, Chiba 277-8582 (Japan); Takeda, A. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Yamashita, M. [Kamioka Observatory, Institute for Cosmic Ray Research, University of Tokyo, Kamioka, Hida, Gifu 506-1205 (Japan); Institute for the Physics and Mathematics of the Universe, University of Tokyo, Kashiwa, Chiba 277-8582 (Japan); and others

    2011-12-11

    In a dedicated test setup at the Kamioka Observatory we studied pulse shape discrimination (PSD) in liquid xenon (LXe) for dark matter searches in the absence of an externally applied electric field. PSD in LXe was based on the observation that scintillation light from electron events was emitted over a longer period of time than that of nuclear recoil events, and our method used a simple ratio of early to total scintillation light emission in a single scintillation event. Requiring an efficiency of 50% for nuclear recoil retention we reduced the electron background by a factor of 7.7{+-}1.1(stat){+-}{sub 0.6}{sup 1.2}(sys) Multiplication-Sign 10{sup -2} at energies between 4.8 and 7.2 keV{sub ee} and 7.7{+-}2.8(stat){+-}{sub 2.8}{sup 2.5}(sys) Multiplication-Sign 10{sup -3} at energies between 9.6 and 12 keV{sub ee} for a scintillation light yield of 20.9 photoelectrons/keV{sub ee}. Further study was done by masking some of that light to reduce this yield to 4.6 photoelectrons/keV{sub ee}. Under these conditions the same method results in an electron event reduction by a factor of 2.4{+-}0.2(stat){+-}{sub 0.2}{sup 0.3}(sys) Multiplication-Sign 10{sup -1} for the lower of the energy regions above. We also observe that in contrast to nuclear recoils the fluctuations in our early to total ratio for electron events are larger than expected from statistical fluctuations.

  8. 基于U盘安装技术的Linux系统搭建%Linux System Building Based on U Disk Installation Technology

    Institute of Scientific and Technical Information of China (English)

    乔治锡; 张倩莉

    2011-01-01

    随着上网本的普及和台式机电脑主板性能的提升,用U盘装系统越来越流行了。U盘不仅体积小,携带方便,使用寿命比光盘更长,而且还更新更容易,节约资源。本文给出了制作Linux系统U盘启动盘的方法,以及U盘引导安装Linux系统的过程。%With the popularity of the Internet and desktop computer motherboard performance improvement,U-disk loading system with more and more popular.U disk is not only small,easy to carry, a longer life than CDs,but also easier to update and save resources.In this paper, making U-disk Linux system boot disk method,as well as U-disk Linux system to boot the installation process.

  9. Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    Lin Chengge; Li Shulan

    2009-01-01

    @@ China's nuclear power industry experienced such three stages as initiation, moderate development and active development. So far, there have been 11 nuclear power units in service in the Chinese mainland with a total installed capacity of 9 100 MW. In addition, there are 24 units being constructed or to be constructed as listed in the 11th Five-Year Plan.

  10. Developments of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2003-03-15

    The objective of this research is to develop an efficient evaluation technology and to investigate applicability of newly-developed technology, such as internet-based cyber platform, to operating power plants. Development of efficient evaluation systems for Nuclear Power Plant components, based on structural integrity assessment techniques, are increasingly demanded for safe operation with the increasing operating period of Nuclear Power Plants. The following five topics are covered in this project: development of assessment method for wall-thinned nuclear piping based on pipe test; development of structural integrity program for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for mam components of NPP; development of internet-based cyber platform and integrity program for primary components of NPP; effect of aging on strength of dissimilar welds.

  11. THE NATURAL COLD ACCUMULATOR AND VACUUM INSTALLATION FOR MILK COOLING IN REPUBLIC OF MOLDOVA

    Directory of Open Access Journals (Sweden)

    Cretu V.

    2010-04-01

    Full Text Available Based on theoretical and experimental research of the milk cooling process was elaborated mathematical model of accumulator with natural cold and vacuum installations, which allows determining the operating system installations, mentioned from environmental parameters.

  12. Methodology for inspection parametrization of radioprotection at radioactive installations: a research agenda; Metodologia para parametrizacao de inspecoes de radioprotecao em instalacoes radioativas: uma agenda de pesquisa

    Energy Technology Data Exchange (ETDEWEB)

    Filgueiras, Bruno Costa [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Sauerbronn, Fernanda F., E-mail: fernanda.sauerbronn@facc.ufrj.b [Universidade Federal do Rio de Janeiro (FACC/UFRJ), RJ (Brazil). Faculdade de Administracao e Ciencias Contabeis

    2011-10-26

    This paper establishes a research agenda based on documental and bibliographic research for radioprotection inspection parametrization at radioactive installations, which is one of the constitutional attributions of Brazilian Nuclear Energy Commission. Such proposal, aiming to guarantee that the evaluation of normative requests of radiation protection generated a quantitative result, useful for various institutions in the safety and regulation areas, bringing relevant contribution for the sector

  13. The Science of Nuclear Materials: A Modular, Laboratory-based Curriculum

    Energy Technology Data Exchange (ETDEWEB)

    Cahill, C.L., E-mail: cahill@gwu.edu [Department of Chemistry and Elliott School of International Affairs, The George Washington University, Washington, DC 20052 (United States); Feldman, G.; Briscoe, W.J. [Department of Physics, The George Washington University, Washington, DC 20052 (United States)

    2014-06-15

    The development of a curriculum for nuclear materials courses targeting students pursuing Master of Arts degrees at The George Washington University is described. The courses include basic concepts such as radiation and radioactivity as well as more complex topics such the nuclear fuel cycle, nuclear weapons, radiation detection and technological aspects of non-proliferation.

  14. Simulation of Ni-63 based nuclear micro battery using Monte Carlo modeling

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Ho; Kim, Ji Hyun [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2013-10-15

    The radioisotope batteries have an energy density of 100-10000 times greater than chemical batteries. Also, Li ion battery has the fundamental problems such as short life time and requires recharge system. In addition to these things, the existing batteries are hard to operate at internal human body, national defense arms or space environment. Since the development of semiconductor process and materials technology, the micro device is much more integrated. It is expected that, based on new semiconductor technology, the conversion device efficiency of betavoltaic battery will be highly increased. Furthermore, the radioactivity from the beta particle cannot penetrate a skin of human body, so it is safer than Li battery which has the probability to explosion. In the other words, the interest for radioisotope battery is increased because it can be applicable to an artificial internal organ power source without recharge and replacement, micro sensor applied to arctic and special environment, small size military equipment and space industry. However, there is not enough data for beta particle fluence from radioisotope source using nuclear battery. Beta particle fluence directly influences on battery efficiency and it is seriously affected by radioisotope source thickness because of self-absorption effect. Therefore, in this article, we present a basic design of Ni-63 nuclear battery and simulation data of beta particle fluence with various thickness of radioisotope source and design of battery.

  15. A new physics-based method for detecting weak nuclear signals via spectral decomposition

    Energy Technology Data Exchange (ETDEWEB)

    Chan, Kung-Sik, E-mail: kung-sik-chan@uiowa.edu [Department of Statistics and Actuarial Science, University of Iowa, Iowa City, IA 52242 (United States); Li, Jinzheng, E-mail: jinzheng-li@uiowa.edu [Department of Statistics and Actuarial Science, University of Iowa, Iowa City, IA 52242 (United States); Eichinger, William, E-mail: william-eichinger@uiowa.edu [Department of Civil and Environmental Engineering, University of Iowa, Iowa City, IA 52242 (United States); Bai, Erwei, E-mail: er-wei-bai@uiowa.edu [Department of Electrical and Computer Engineering, University of Iowa, Iowa City, IA 52242 (United States)

    2012-03-01

    We propose a new physics-based method to determine the presence of the spectral signature of one or more nuclides from a poorly resolved spectra with weak signatures. The method is different from traditional methods that rely primarily on peak finding algorithms. The new approach considers each of the signatures in the library to be a linear combination of subspectra. These subspectra are obtained by assuming a signature consisting of just one of the unique gamma rays emitted by the nuclei. We propose a Poisson regression model for deducing which nuclei are present in the observed spectrum. In recognition that a radiation source generally comprises few nuclear materials, the underlying Poisson model is sparse, i.e. most of the regression coefficients are zero (positive coefficients correspond to the presence of nuclear materials). We develop an iterative algorithm for a penalized likelihood estimation that prompts sparsity. We illustrate the efficacy of the proposed method by simulations using a variety of poorly resolved, low signal-to-noise ratio (SNR) situations, which show that the proposed approach enjoys excellent empirical performance even with SNR as low as to -15 db.

  16. Develop an piezoelectric sensing based on SHM system for nuclear dry storage system

    Science.gov (United States)

    Ma, Linlin; Lin, Bin; Sun, Xiaoyi; Howden, Stephen; Yu, Lingyu

    2016-04-01

    In US, there are over 1482 dry cask storage system (DCSS) in use storing 57,807 fuel assemblies. Monitoring is necessary to determine and predict the degradation state of the systems and structures. Therefore, nondestructive monitoring is in urgent need and must be integrated into the fuel cycle to quantify the "state of health" for the safe operation of nuclear power plants (NPP) and radioactive waste storage systems (RWSS). Innovative approaches are desired to evaluate the degradation and damage of used fuel containers under extended storage. Structural health monitoring (SHM) is an emerging technology that uses in-situ sensory system to perform rapid nondestructive detection of structural damage as well as long-term integrity monitoring. It has been extensively studied in aerospace engineering over the past two decades. This paper presents the development of a SHM and damage detection methodology based on piezoelectric sensors technologies for steel canisters in nuclear dry cask storage system. Durability and survivability of piezoelectric sensors under temperature influence are first investigated in this work by evaluating sensor capacitance and electromechanical admittance. Toward damage detection, the PES are configured in pitch catch setup to transmit and receive guided waves in plate-like structures. When the inspected structure has damage such as a surface defect, the incident guided waves will be reflected or scattered resulting in changes in the wave measurements. Sparse array algorithm is developed and implemented using multiple sensors to image the structure. The sparse array algorithm is also evaluated at elevated temperature.

  17. Di-nucleon structures in homogeneous nuclear matter based on two- and three-nucleon interactions

    Energy Technology Data Exchange (ETDEWEB)

    Arellano, Hugo F. [University of Chile, Department of Physics - FCFM, Santiago (Chile); CEA, DAM, DIF, Arpajon (France); Isaule, Felipe [University of Chile, Department of Physics - FCFM, Santiago (Chile); Rios, Arnau [University of Surrey, Department of Physics, Faculty of Engineering and Physical Sciences, Guildford (United Kingdom)

    2016-09-15

    We investigate homogeneous nuclear matter within the Brueckner-Hartree-Fock (BHF) approach in the limits of isospin-symmetric nuclear matter (SNM) as well as pure neutron matter at zero temperature. The study is based on realistic representations of the internucleon interaction as given by Argonne v{sub 18}, Paris, Nijmegen I and II potentials, in addition to chiral N{sup 3}LO interactions, including three-nucleon forces up to N{sup 2}LO. Particular attention is paid to the presence of di-nucleon bound states structures in {sup 1}S{sub 0} and {sup 3}SD{sub 1} channels, whose explicit account becomes crucial for the stability of self-consistent solutions at low densities. A characterization of these solutions and associated bound states is discussed. We confirm that coexisting BHF single-particle solutions in SNM, at Fermi momenta in the range 0.13-0.3 fm{sup -1}, is a robust feature under the choice of realistic internucleon potentials. (orig.)

  18. Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis

    Directory of Open Access Journals (Sweden)

    Pasichnyk I.

    2013-03-01

    Full Text Available In the present contribution, an overview of the sampling based XSUSA method for sensitivity and uncertainty analysis with respect to nuclear data is given. The focus is on recent developments and applications of XSUSA. These applications include calculations for critical assemblies, fuel assembly depletion calculations, and steadystate as well as transient reactor core calculations. The analyses are partially performed in the framework of international benchmark working groups (UACSA – Uncertainty Analyses for Criticality Safety Assessment, UAM – Uncertainty Analysis in Modelling. It is demonstrated that particularly for full-scale reactor calculations the influence of the nuclear data uncertainties on the results can be substantial. For instance, for the radial fission rate distributions of mixed UO2/MOX light water reactor cores, the 2σ uncertainties in the core centre and periphery can reach values exceeding 10%. For a fast transient, the resulting time behaviour of the reactor power was covered by a wide uncertainty band. Overall, the results confirm the necessity of adding systematic uncertainty analyses to best-estimate reactor calculations.

  19. Transfer-induced fission in inverse kinematics: Impact on experimental and evaluated nuclear data bases

    Science.gov (United States)

    Farget, F.; Caamaño, M.; Ramos, D.; Rodrıguez-Tajes, C.; Schmidt, K.-H.; Audouin, L.; Benlliure, J.; Casarejos, E.; Clément, E.; Cortina, D.; Delaune, O.; Derkx, X.; Dijon, A.; Doré, D.; Fernández-Domınguez, B.; Gaudefroy, L.; Golabek, C.; Heinz, A.; Jurado, B.; Lemasson, A.; Paradela, C.; Roger, T.; Salsac, M. D.; Schmitt, C.

    2015-12-01

    Inverse kinematics is a new tool to study nuclear fission. Its main advantage is the possibility to measure with an unmatched resolution the atomic number of fission fragments, leading to new observables in the properties of fission-fragment distributions. In addition to the resolution improvement, the study of fission based on nuclear collisions in inverse kinematics beneficiates from a larger view with respect to the neutron-induced fission, as in a single experiment the number of fissioning systems and the excitation energy range are widden. With the use of spectrometers, mass and kinetic-energy distributions may now be investigated as a function of the proton and neutron number sharing. The production of fissioning nuclei in transfer reactions allows studying the isotopic yields of fission fragments as a function of the excitation energy. The higher excitation energy resulting in the fusion reaction leading to the compound nucleus 250Cf at an excitation energy of 45MeV is also presented. With the use of inverse kinematics, the charge polarisation of fragments at scission is now revealed with high precision, and it is shown that it cannot be neglected, even at higher excitation energies. In addition, the kinematical properties of the fragments inform on the deformation configuration at scission.

  20. Transfer-induced fission in inverse kinematics: Impact on experimental and evaluated nuclear data bases

    Energy Technology Data Exchange (ETDEWEB)

    Farget, F.; Schmidt, K.H.; Clement, E.; Delaune, O.; Derkx, X.; Dijon, A.; Golabek, C.; Lemasson, A.; Roger, T.; Schmitt, C. [CEA/DSM-CNRS/IN2P3, GANIL, Caen (France); Caamano, M.; Ramos, D.; Benlliure, J.; Cortina, D.; Fernandez-Dominguez, B.; Paradela, C. [Universidade de Santiago de Compostela, Santiago de Compostela (Spain); Rodriguez-Tajes, C. [CEA/DSM-CNRS/IN2P3, GANIL, Caen (France); Universidade de Santiago de Compostela, Santiago de Compostela (Spain); Audouin, L. [Universite Paris-Sud 11, CNRS/IN2P3, Institut de Physique Nucleaire, Orsay (France); Casarejos, E. [Universidade de Vigo, Vigo (Spain); Dore, D.; Salsac, M.D. [Centre de Saclay, CEA, Irfu, Gif-sur-Yvette (France); Gaudefroy, L. [CEA DAM Ile-de-France, BP 12, Bruyeres-le-Chatel (France); Heinz, A. [Chalmers Tekniska Hoegskola, Fundamental Fysik, Goeteborg (Sweden); Jurado, B. [Universite Bordeaux, CENBG, UMR 5797 CNRS/IN2P3, Gradignan (France)

    2015-12-15

    Inverse kinematics is a new tool to study nuclear fission. Its main advantage is the possibility to measure with an unmatched resolution the atomic number of fission fragments, leading to new observables in the properties of fission-fragment distributions. In addition to the resolution improvement, the study of fission based on nuclear collisions in inverse kinematics beneficiates from a larger view with respect to the neutron-induced fission, as in a single experiment the number of fissioning systems and the excitation energy range are widden. With the use of spectrometers, mass and kinetic-energy distributions may now be investigated as a function of the proton and neutron number sharing. The production of fissioning nuclei in transfer reactions allows studying the isotopic yields of fission fragments as a function of the excitation energy. The higher excitation energy resulting in the fusion reaction leading to the compound nucleus {sup 250}Cf at an excitation energy of 45MeV is also presented. With the use of inverse kinematics, the charge polarisation of fragments at scission is now revealed with high precision, and it is shown that it cannot be neglected, even at higher excitation energies. In addition, the kinematical properties of the fragments inform on the deformation configuration at scission. (orig.)

  1. Detection of Shielded Special Nuclear Material With a Cherenkov-Based Transmission Imaging System

    Science.gov (United States)

    Rose, Paul; Erickson, Anna; Mayer, Michael; Jovanovic, Igor

    2015-10-01

    Detection of shielded special nuclear material, SSNM, while in transit, offers a unique challenge. Typical cargo imaging systems are Bremsstrahlung-based and cause an abundance of unnecessary signal in the detectors and doses to the cargo contents and surroundings. Active interrogation with dual monoenergetic photons can unveil the illicit material when coupled with a high-contrast imaging system while imparting significantly less dose to the contents. Cherenkov detectors offer speed, resilience, inherent energy threshold rejection, directionality and scalability beyond the capability of most scintillators. High energy resolution is not a priority when using two well separated gamma rays, 4.4 and 15.1 MeV, generated from low energy nuclear reactions such as 11B(d,n- γ)12C. These gamma rays offer a measure of the effective atomic number, Z, of the cargo by taking advantage of the large difference in photon interaction cross sections, Compton scattering and pair production. This imaging system will be coupled to neutron detectors to provide unique signature of SNM by monitoring delayed neutrons. Our experiments confirm that the Cherenkov imaging system can be used with the monoenergetic source to relate transmission and atomic number of the scanned material.

  2. A Study on the Job Stress Assessment in Korean Nuclear Power Plants based on KOSS

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Seong Hwan; Lee, Yong Hee; Lee, Jung Woon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sung, Sook Hee; Jung, Kwang Hee; Jung, Yeon Sub [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2010-05-15

    Job stress is a harmful physical and emotional response that occurs when there is a poor match between job demands and the capabilities, resources, or needs of the worker. Stress-related disorders encompass a broad array of conditions, including psychological disorders (e.g., depression, anxiety, posttraumatic stress disorder) and other types of emotional strain (e.g., dissatisfaction, fatigue, tension, etc.), maladaptive behaviors (e.g., aggression, substance abuse), and cognitive impairment (e.g., concentration and memory problems). In turn, these conditions may lead to poor work performance or even injury. Job stress is also associated with various biological reactions that may lead ultimately to compromised health, such as cardiovascular disease or in extreme cases, death. In Korea, organizational job stress factors were investigated for the jobs in nuclear power plants that are operated based on procedures. Especially, the occupational stress scale for Korean employees (KOSS) was developed. The KOSS has 8 subscales by using a factor analysis and validation process in order to measure stress at work and to find methods for the prevention of stressors. In this point of view, the RHRI (Radiation Health Research Institute of KHNP (Korea Hydro and Nuclear Power) assessed how wellsuited employees were for their job during their health examination in 2009. In this study the present condition of employee's stress level is investigated to find a way to manage their stressors

  3. Installation of a modular building block photovoltaic concentrator array field

    Energy Technology Data Exchange (ETDEWEB)

    Sanders, J.A.; Cass, D.C.; Broadbent, S.

    1985-06-01

    A building block array field nominally rated at 25 kW has been installed in Albuquerque, New Mexico. The building block is a single source electrical circuit of six center pedestal two-axis tracking arrays connected in parallel and having a nominal operating voltage of 420 volts DC. Each array contains 60 point-focusing Fresnel lens photovoltaic concentrator modules connected in series for a nominal power output of 4.2 kW per array. The structural design uses a center pedestal two-axis cantilevered support tube with a closed loop sun sensor electronic control system. A master control provides manual override of the array field. The installation was accomplished without difficulty and demonstrated the ease of turnkey building block installation. The costs of 1 MW size fields is estimated to be $6.99 per watt installed based on the building block installation.

  4. Design issues on using FPGA-based I and C systems in nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Farias, Marcos S.; Carvalho, Paulo Victor R. de; Santos, Isaac Jose A.L. dos; Lacerda, Fabio de, E-mail: msantana@ien.gov.br, E-mail: paulov@ien.gov.br, E-mail: luquetti@ien.gov.br, E-mail: acerda@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Engenharia Nuclear

    2015-07-01

    The FPGA (field programmable gate array) is widely used in various fields of industry. FPGAs can be used to perform functions that are safety critical and require high reliability, like in automobiles, aircraft control and assistance and mission-critical applications in the aerospace industry. With these merits, FPGAs are receiving increased attention worldwide for application in nuclear plant instrumentation and control (I and C) systems, mainly for Reactor Protection System (RPS). Reasons for this include the fact that conventional analog electronics technologies are become obsolete. I and C systems of new Reactors have been designed to adopt the digital equipment such as PLC (Programmable Logic Controller) and DCS (Distributed Control System). But microprocessors-based systems may not be simply qualified because of its complex characteristics. For example, microprocessor cores execute one instruction at a time, and an operating system is needed to manage the execution of programs. In turn, FPGAs can run without an operating system and the design architecture is inherently parallel. In this paper we aim to assess these and other advantages, and the limitations, on FPGA-based solutions, considering the design guidelines and regulations on the use of FPGAs in Nuclear Plant I and C Systems. We will also examine some circuit design techniques in FPGA to help mitigate failures and provide redundancy. The objective is to show how FPGA-based systems can provide cost-effective options for I and C systems in modernization projects and to the RMB (Brazilian Multipurpose Reactor), ensuring safe and reliable operation, meeting licensing requirements, such as separation, redundancy and diversity. (author)

  5. Development of Web-Based Common Cause Failure (CCF) Database Module for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-young [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

    2015-05-15

    Probabilistic safety assessment (PSA) has been used to identify risk vulnerabilities and derive the safety improvement measures from construction to operation stages of nuclear power plants. In addition, risk insights from PSA can be applied to improve the designs and operation requirements of plants. However, reliability analysis methods for quantitative PSA evaluation have essentially inherent uncertainties, and it may create a distorted risk profiles because of the differences among the PSA models, plant designs, and operation status. Therefore, it is important to ensure the quality of the PSA model so that analysts identify design vulnerabilities and utilize risk information. Especially, the common cause failure (CCF) has been pointed out as one of major issues to be able to cause the uncertainty related to the PSA analysis methods and data because CCF has a large influence on the PSA results. Organization for economic cooperation and development /nuclear energy agent (OECD/NEA) has implemented an international common cause failure data exchange (ICDE) project for the CCF quality assurance through the development of the detailed analysis methodologies and data sharing. However, Korea Hydro and Nuclear Power company (KHNP) does not have the basis for the data gathering and analysis for CCF analyses. In case of methodology, the Alpha Factor parameter estimation, which can analyze uncertainties and estimate an interface factor (Impact Vector) with an ease, is ready to be applied rather than the Multi Greek Letter (MGL) method. This article summarizes the development of the plant-specific CCF database (DB) module considering the raw data collection and the analysis procedure based on the CCF parameter calculation method of ICDE. Although the portion affected by CCF in the PSA model is quite a large, the development efforts of the tools to collect and analyze data were insufficient. Currently, KHNP intends to improve PSA quality and ensure CCF data reliability by

  6. Nuclear threats in the vicinity of the Nordic countries. Final report of the Nordic Nuclear Safety Research project SBA-1

    Energy Technology Data Exchange (ETDEWEB)

    Eikelmann, I.M.H. [Norwegian Radiation Protection Authority (Norway)

    2002-11-01

    The acute phase of a nuclear accident and the possibility of high exposure of the populations are always the most important threats in the emergency preparedness work. Radioactive contamination from an accident can however also cause long term effects for land use and enhanced doses to special population groups and economic problems for agriculture, reindeer industry, hunting, tourism and recreation. For planning purposes it is always valuable to be aware of surrounding radiation hazards and other potential threats. Thus, mapping such threats in a Nordic context is an important factor in emergency preparedness in the area. This report presents a cross-disciplinary study from the NKS research program 1998-2001.The scope of the project was to prepare a 'base of knowledge' regarding possible nuclear threats in the vicinity of the Nordic countries. This base of knowledge will, by modere information technology as different websites, be made available to authorities, media and the population. The users of the websites can easily get information on different types of nuclear installations and threats. The users can get an overview of the situation and, if they so wish, make their own judgements. The project dealt with a geographical area including North-west Russia and the Baltic states. The results from the different activities in the project were generated in a web based database called the 'the base of knowledge'. Key words Nuclear threats, Nordic countries, nuclear power plants, nuclear ship, nuclear waste, literature database, base of knowledge, webaccessed information, atmospheric transport, decommissioning of submarines, nuclear installations, waste management, radioactive contamination in marine environment, radioactive sources, criticality analysis. (au)

  7. Computer-based procedure for field activities: Results from three evaluations at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Oxstrand, Johanna [Idaho National Lab. (INL), Idaho Falls, ID (United States); bly, Aaron [Idaho National Lab. (INL), Idaho Falls, ID (United States); LeBlanc, Katya [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    Nearly all activities that involve human interaction with the systems of a nuclear power plant are guided by procedures. The paper-based procedures (PBPs) currently used by industry have a demonstrated history of ensuring safety; however, improving procedure use could yield tremendous savings in increased efficiency and safety. One potential way to improve procedure-based activities is through the use of computer-based procedures (CBPs). Computer-based procedures provide the opportunity to incorporate context driven job aids, such as drawings, photos, just-in-time training, etc into CBP system. One obvious advantage of this capability is reducing the time spent tracking down the applicable documentation. Additionally, human performance tools can be integrated in the CBP system in such way that helps the worker focus on the task rather than the tools. Some tools can be completely incorporated into the CBP system, such as pre-job briefs, placekeeping, correct component verification, and peer checks. Other tools can be partly integrated in a fashion that reduces the time and labor required, such as concurrent and independent verification. Another benefit of CBPs compared to PBPs is dynamic procedure presentation. PBPs are static documents which limits the degree to which the information presented can be tailored to the task and conditions when the procedure is executed. The CBP system could be configured to display only the relevant steps based on operating mode, plant status, and the task at hand. A dynamic presentation of the procedure (also known as context-sensitive procedures) will guide the user down the path of relevant steps based on the current conditions. This feature will reduce the user’s workload and inherently reduce the risk of incorrectly marking a step as not applicable and the risk of incorrectly performing a step that should be marked as not applicable. As part of the Department of Energy’s (DOE) Light Water Reactors Sustainability Program

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  9. Nuclear analytical chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Brune, D.; Forkman, B.; Persson, B.

    1984-01-01

    This book covers the general theories and techniques of nuclear chemical analysis, directed at applications in analytical chemistry, nuclear medicine, radiophysics, agriculture, environmental sciences, geological exploration, industrial process control, etc. The main principles of nuclear physics and nuclear detection on which the analysis is based are briefly outlined. An attempt is made to emphasise the fundamentals of activation analysis, detection and activation methods, as well as their applications. The book provides guidance in analytical chemistry, agriculture, environmental and biomedical sciences, etc. The contents include: the nuclear periodic system; nuclear decay; nuclear reactions; nuclear radiation sources; interaction of radiation with matter; principles of radiation detectors; nuclear electronics; statistical methods and spectral analysis; methods of radiation detection; neutron activation analysis; charged particle activation analysis; photon activation analysis; sample preparation and chemical separation; nuclear chemical analysis in biological and medical research; the use of nuclear chemical analysis in the field of criminology; nuclear chemical analysis in environmental sciences, geology and mineral exploration; and radiation protection.

  10. Modular Integrated Monitoring System (MIMS) field test installations

    Energy Technology Data Exchange (ETDEWEB)

    Martinez, R.L.; Waymire, D.R. [Sandia National Labs., Albuquerque, NM (United States); Fuess, D.A. [Lawrence Livermore National Lab., CA (United States)] [and others

    1995-07-01

    The MIMS program is funded by the Department of Energy under the Office of Nonproliferation and National Security. The program objective is to develop cost effective, modular, multi-sensor monitoring systems. Both in-plant and ground based sensors are envisioned. It is also desirable to develop sensors/systems that can be fielded/deployed in a rapid fashion. A MIMS architecture was selected to allow modular integration of sensors and systems and is based on LonWorks technology, commercially developed by Echelon Corporation. The first MIMS fieldable hardware was demonstrated at Lawrence Livermore National Laboratory. The field test, known within the DOE as the Item Tracking and Transparency (IT&I) demonstration, involved the collaboration and cooperation of five DOE laboratories (Sandia (SNL), Lawrence Livermore (LLNL), Pacific Northwest (PNL), Los Alamos (LANL), and Oak Ridge (ORNL)). The IT&T demonstration involved the monitoring of special nuclear material as it was transported around the facility utilizing sensors from the participating labs. The scenario was programmed to ignore normal activity in the facility until entry into the room where the material was stored. A second demonstration, which involved three separate scenarios, was conducted at Idaho National Engineering Laboratory (INEL). The participants included representatives from SNL, LLNL, PNL, and INEL. DOE has selected INEL as the long term testbed for MIMS developed sensors, systems, and scenarios. This paper will describe the installation, intended purpose, and results of the field demonstrations at LLNL and INEL under the MIMS program.

  11. Nuclear Quadrupole Moments and Nuclear Shell Structure

    Science.gov (United States)

    Townes, C. H.; Foley, H. M.; Low, W.

    1950-06-23

    Describes a simple model, based on nuclear shell considerations, which leads to the proper behavior of known nuclear quadrupole moments, although predictions of the magnitudes of some quadrupole moments are seriously in error.

  12. An Evaluation of Installation Methods for STS-1 Seismometers

    Science.gov (United States)

    Holcomb, L. Gary; Hutt, Charles R.

    1992-01-01

    INTRODUCTION This report documents the results of a series of experiments conducted by the authors at the Albuquerque Seismological Laboratory (ASl) during the spring and summer of 1991; the object of these experiments was to obtain and document quantitative performance comparisons of three methods of installing STS-1 seismometers. Historically, ASL has installed STS-1 sensors by cementing their thick glass base plates to the concrete floor of the vault (see Peterson and Tilgner, 1985, p 44 and Figure 31, p 51 for the details of this installation technique). This installation technique proved to be fairly satisfactory for the China Digital Seismic Network and for several sets of STS-1 sensors installed in other locations since that time. However, the cementing operation is rather labor intensive and the concrete requires a lengthy (about 1 week) curing time during which the sensor installed on it is noisy. In addition it is difficult to assure that all air bubbles have been removed from the interface between the cement and the glass base plate. If air bubbles are present beneath the plate, horizontal sensors can be unacceptably noisy. Moving a sensor installed in this manner requires the purchase of a new glass base plate because the old plate normally can not be removed without breakage. Therefore, this study was undertaken with the aim of developing an improved method of installing STS-1's. The goals were to develop a method which requires less field site labor during the installation and assures a higher quality installation when finished. In addition, the improved installation technique should promote portability. Two alternate installation techniques were evaluated in this study. One method replaces the cement between the base plate and the vault floor with sand. This method has been used in the French Geoscope program and in several IRIS/IDA installations made by the University of California at San Diego (UCSD) and possibly others. It is easily implemented in

  13. Inverse Temperature Dependence of Nuclear Quantum Effects in DNA Base Pairs

    CERN Document Server

    Fang, Wei; Rossi, Mariana; Feng, Yexin; Li, Xin-Zheng; Michaelides, Angelos

    2016-01-01

    Despite the inherently quantum mechanical nature of hydrogen bonding, it is unclear how nuclear quantum effects (NQEs) alter the strengths of hydrogen bonds. With this in mind, we use ab initio path integral molecular dynamics to determine the absolute contribution of NQEs to the binding in DNA base pair complexes, arguably the most important hydrogen-bonded systems of all. We find that depending on the temperature, NQEs can either strengthen or weaken the binding within the hydrogen-bonded complexes. As a somewhat counterintuitive consequence, NQEs can have a smaller impact on hydrogen bond strengths at cryogenic temperatures than at room temperature. We rationalize this in terms of a competition of NQEs between low-frequency and high-frequency vibrational modes. Extending this idea, we also propose a simple model to predict the temperature dependence of NQEs on hydrogen bond strengths in general.

  14. Performance based seismic qualification of reinforced concrete nuclear materials processing facilities

    Energy Technology Data Exchange (ETDEWEB)

    Mertz, G.E.; Loceff, F.; Houston, T.; Rauls, G. [Westinghouse Savannah River Company, Aiken, SC (United States); Mulliken, J. [LPA Group Inc., SC (United States)

    1997-09-01

    A seismic qualification of a reinforced concrete nuclear materials processing facility using performance based acceptance criteria is presented. Performance goals are defined in terms of a minimum annual seismic failure frequency. Pushover analyses are used to determine the building`s ultimate capacity and relate the capacity to roof drift and joint rotation. Nonlinear dynamic analyses are used to quantify the building`s drift using a suite of ground motion intensities representing varying soil conditions and levels of seismic hazard. A correlation between joint rotation and building drift to damage state is developed from experimental data. The damage state and seismic hazard are convolved to determine annual seismic failure frequency. The results of this rigorous approach is compared to those using equivalent force methods and pushover techniques recommended by ATC-19 and FEMA-273.

  15. Magnetism and Superconductivity in Iron-based Superconductors as Probed by Nuclear Magnetic Resonance

    CERN Document Server

    Hammerath, Franziska

    2012-01-01

    Nuclear Magnetic Resonance (NMR) has been a fundamental player in the studies of superconducting materials for many decades. This local probe technique allows for the study of the static electronic properties as well as of the low energy excitations of the electrons in the normal and the superconducting state. On that account it has also been widely applied to Fe-based superconductors from the very beginning of their discovery in February 2008. This dissertation comprises some of these very first NMR results, reflecting the unconventional nature of superconductivity and its strong link to magnetism in the investigated compounds LaO1–xFxFeAs and LiFeAs.

  16. Taxonomic status and phylogenetic relationship of tits based on mitogenomes and nuclear segments.

    Science.gov (United States)

    Li, Xuejuan; Lin, Liliang; Cui, Aiming; Bai, Jie; Wang, Xiaoyang; Xin, Chao; Zhang, Zhen; Yang, Chao; Gao, Ruirui; Huang, Yuan; Lei, Fumin

    2016-11-01

    The phylogeny of tits has been studied using various molecular markers, but their phylogenetic relationships remain controversial. To further investigate their taxonomic status and phylogenetic relationships, the entire mitochondrial genomes (mitogenomes) and five nuclear segments were sequenced from 10 species of tits and two outgroups (Sylviparus modestus and Remiz consobrinus), followed by the comparison of mitogenomic characteristics and reconstruction of phylogenetic relationship based on the different datasets. The results revealed the following: the mitogenomes of 10 ingroup tits, each 16,758-16,799bp in length, displayed typical mitogenome organization and the gene order found in most previously determined Passeriformes mitogenomes; close relationships existed between Parus major and P. monticolus, between P. montanus and P. palustris, and between P. ater and P. venustulus; and Pseudopodoces humilis was a sister group to P. spilonotus, P. cyanus, or the clade containing P. major and P. monticolus.

  17. Improving the nuclear data base for non-proliferation and homeland security

    Energy Technology Data Exchange (ETDEWEB)

    Haight, Robert C [Los Alamos National Laboratory; Bitteker, Leo J [Los Alamos National Laboratory; Couture, Aaron J [Los Alamos National Laboratory; Devlin, Matthew J [Los Alamos National Laboratory; Fotiadis, Nikolaos [Los Alamos National Laboratory; Gavron, Avigdor [Los Alamos National Laboratory; Hill, Tony S [Los Alamos National Laboratory; Laptev, Alexander B [Los Alamos National Laboratory; Nelson, Ronald O [Los Alamos National Laboratory; O' donnell, John M [Los Alamos National Laboratory; Taddeucci, Terry N [Los Alamos National Laboratory; Tovesson, Fredrik K [Los Alamos National Laboratory; Ulmann, John L [Los Alamos National Laboratory; Wender, Stephen A [Los Alamos National Laboratory

    2009-01-01

    Many of the technical advances in non-proliferation and homeland security require calculations of transport of neutrons and gamma-rays through materials. The nuclear data base on which these calculations are made must be of high quality in order for the calculated responses to be credible. At the Los Alamos Neutron Science Center, three spallation neutron sources are being used to provide high-quality cross section and structure data with reactions induced by neutrons. Neutron transmission, neutron-induced fission and capture cross sections, neutron emission in fission, and gamma-ray production by neutrons are principal areas of research. Furthermore, these sources are also being used to validate calculations of the characterization and response of new detectors and detection techniques. Current research activities are summarized here.

  18. A novel acquisition method of nuclear spectrum based on pulse area analysis

    CERN Document Server

    Dongcang, Li; Lei, Yang; Zhong, Qi; Xiangting, Meng; Bitao, Hu

    2014-01-01

    A novel method based on pulse area analysis(PAA) was presented for acquisition nuclear spectrum by the digitizer. PAA method can be used as a substitute for the traditional method of pulse height analysis (PHA). In the PAA method a commercial digitizer was employed to sample and sum in the pulse, and the area of pulse is proportional to the energy of the detected radiation. The results of simulation and experiment indicate the great advantages of PAA method, especially when the count rate is high and shaping time constant is small. When shaping time constant is 0.5us, the energy resolution of PAA is about 66% better than that of PHA.

  19. 浅谈电厂新型防水卷材的施工%Installation of external current cathodic protection system for seawater filtration equipment in nuclear power station

    Institute of Scientific and Technical Information of China (English)

    楚增宝; 刘灿辉; 宋东升; 杨鲲

    2015-01-01

    BAC双面自粘防水卷材是一种复合双面自粘橡胶沥青防水卷材。它是由聚酯胎体(或玻纤胎体)、SBS改性沥青、自粘橡胶沥青胶料及隔离膜符合而成,卷材厚度有2mm、3mm、4mm三种结构。它具有粘结性高、可靠度强、延伸性好、耐候性能优良、可在潮湿基面铺贴等特点,即使卷材出现任何局部破坏,水都会被限定在很小范围内,不窜流,不渗漏。%BAC double- sided adhesive waterproof coiled material is a kind of composite double- sided adhesive rubber asphalt waterproof coiled material. It is made of polyester tire body (or fiberglass tire body), SBS modified asphalt, the sticky rubber asphalt rubber and isolation membrane meet and become, coil thickness 2 mm、3 mm、4 mm three kinds of structure. They have high co-hesiveness, strong reliability, good extensibility and excellent weather resistance, can be in damp base set of characteristics, even if the coil any local damage, who will be limited in a small range, interporosity flow, no leakage.

  20. Transboundary nuclear risks and legal entitlement to be protected under international law. Grenzueberschreitendes nukleares Risiko und voelkerrechtlicher Schutzanspruch

    Energy Technology Data Exchange (ETDEWEB)

    Handl, G.

    1992-01-01

    The study in hand examines the conditions supporting and governing the legal entitlement of a state affected by the potential hazards of a nuclear installation in a neighbouring state to be protected against such hazards, and to enforce such entitlement on a bilateral level, based on international law, in order to guarantee the integrity of the state's territory and its population. There are three basic items to be investigated: (1) the objective definition of the transboundary nuclear risk, which in the bilateral relationship between the risk-exposed state and the installation state creates a right to claim protection on the part of the exposed state; (2) the concrete definition of this bilateral entitlement to be protected from the nuclear risks, i.e. after an 'internationalization' of the decision-making processes underlying the erection and operation of nuclear installations and the subsequent waste management; (3) the international leagal obligations to be fulfilled to compensate for nuclear damage as a result of incidents or accidents in a nuclear installation. (orig./HP).

  1. Discriminating poststroke depression from stroke by nuclear magnetic resonance spectroscopy-based metabonomic analysis

    Directory of Open Access Journals (Sweden)

    Xiao J

    2016-08-01

    Full Text Available Jianqi Xiao,1,* Jie Zhang,2,* Dan Sun,3,* Lin Wang,4,* Lijun Yu,5 Hongjing Wu,5 Dan Wang,5 Xuerong Qiu5 1Department of Neurosurgery, The First Hospital of Qiqihar City, Qiqihar, 2Department of Internal Medicine, Central Hospital of Jiamusi City, Jiamusi, 3Department of Geriatrics, General Hospital of Daqing Oil Field, Daqing, 4Department of Nursing, 5Department of Neurology, The First Hospital of Qiqihar City, Qiqihar, Heilongjiang, People’s Republic of China *These authors contributed equally to this work Abstract: Poststroke depression (PSD, the most common psychiatric disease that stroke survivors face, is estimated to affect ~30% of poststroke patients. However, there are still no objective methods to diagnose PSD. In this study, to explore the differential metabolites in the urine of PSD subjects and to identify a potential biomarker panel for PSD diagnosis, the nuclear magnetic resonance-based metabonomic method was applied. Ten differential metabolites responsible for discriminating PSD subjects from healthy control (HC and stroke subjects were found, and five of these metabolites were identified as potential biomarkers (lactate, α-hydroxybutyrate, phenylalanine, formate, and arabinitol. The panel consisting of these five metabolites provided excellent performance in discriminating PSD subjects from HC and stroke subjects, achieving an area under the receiver operating characteristic curve of 0.946 in the training set (43 HC, 45 stroke, and 62 PSD subjects. Moreover, this panel could classify the blinded samples from the test set (31 HC, 33 stroke, and 32 PSD subjects with an area under the curve of 0.946. These results laid a foundation for the future development of urine-based objective methods for PSD diagnosis and investigation of PSD pathogenesis. Keywords: poststroke depression, PSD, stroke, nuclear magnetic resonance, NMR, metabonomic

  2. Influences of nuclear containment radius on the aircraft impact force based on the Riera function

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, T.; Wu, H., E-mail: abrahamhao@126.com; Fang, Q.; Gong, Z.M.

    2015-11-15

    Highlights: • A fine aircraft model of A320 was built and verified by available limited prototype impacting tests. • The influences of aircraft longitudinal crushing strength on the impact process were analyzed. • The influences of NPP containment radius on the impact force were numerically studied. • The Riera function was modified by considering the radius effect of NPP containment. - Abstract: The aircraft impact force directly influences the local failure and global response of the nuclear power plant (NPP) containment, while the existing theoretical models and the field tests were almost based on the flat target. In order to analyze the radius effect of the circular sectional containment on the impact force, a fine FE model of the commercial aircraft A320 was established and validated by the available limited full-scale F-4 Phantom impact experiment. In order to determine the force to crush the A320 FE model, the influences of aircraft longitudinal crushing strength on the impact process were analyzed based on the Riera function. Considering the containment decaying effect to aircraft impact velocity, the impact impulse was theoretically calculated, while the influences of the losses of mass and energy were not included. The numerical simulations of A320 aircrafts impacting on simplified NPP containments with different radii were conducted, which could well reproduce the airframe crushing and debris scattering. By comparison of the simulated impact impulses and the calculation values by the Riera function, the coefficients corresponding to different containment radii are derived and a fitting formula is obtained. Finally, an improved Riera function dependent on the dimensionless ratio of nuclear containment radius and aircraft wingspan is proposed.

  3. Calculation of an analytical memory for the installation of a PET-CT equipment in the Nuclear Medicine Department of the National Institute of Cancerology; Calculo de una memoria analitica para la instalacion de un equipo PET-CT en el Departamento de Medicina Nuclear del Instituto Nacional de Cancerologia

    Energy Technology Data Exchange (ETDEWEB)

    Trujillo Z, F.E.; Gomez A, E. [Instituto Nacional de Cancerologia, Departamento de Medicina Nuclear, 14000 Mexico D.F. (Mexico)

    2007-07-01

    The studies with a PET-CT equipment combines the metabolic information that provides the Positron Emission Tomography technique (PET), with the morphological data offered by the Computerized Tomography (CT). In Mexico, it will have the first PET-CT equipment, for a public service hospital. Since that makes use of radioactive material (emission of annihilation photons with 511 keV) and X rays, is necessary to calculate the necessary shielding for the PET-CT equipment room and for the area where it is managed or have presence of radioactive material (mainly fluorodeoxyglucose labelled with F-18, i.e. FDG-F18). It is presented a summary of the calculations and necessary considerations so that the shielding allows to fulfill with the official doses limits in Mexico (50 mSv/year for Occupationally Exposure Personnel, OEP and 5 mSv/year for public in general), taking into account the adjacent areas to the installation. It is concluded with the shielding thickness required for the walls and roof of the installation, having a maximum of 20 cm of concrete ({rho} = 2.35 g/cm{sup 3}) for the administration room of radioactive material to the patients and a minimum of 1 mm of lead for the room of the PET-CT equipment, having taken into account the dimensions of each area. (Author)

  4. Horn installed in CNGS tunnel

    CERN Multimedia

    Maximilien Brice

    2005-01-01

    The horn is installed for the CERN Neutrinos to Gran Sasso (CNGS) project. Protons collide with a graphite target producing charged particles that are focussed by the magnetic field in the horn. These particles will then pass into a decay tube where they decay into neutrinos, which travel towards a detector at Gran Sasso 732 km away in Italy.

  5. Temperature rise of installed FCC

    Science.gov (United States)

    Hankins, J. D.

    1976-01-01

    Report discusses temperature profiles of installed FCC for wood and tile surfaces. Three-conductor FCC was tested at twice nominal current-carrying capacity over bare floor and under carpet, with result indicating that temperature rise is not a linear function of current with FCC at this level.

  6. Evaluation of Nuclear Fission Barrier Parameters for 17 Nuclei

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    As well know that modern nuclear installations and applications have reached a high degree of sophistication. The effective safe and economical design of these technologies require detailed and reliable design calculations. The accuracy of these calculations is largely determined by the accuracy of the basic nuclear and atomic input parameters. In order to meet the needs on high energy fission cross section, fission spectra in waste disposal, transmutation, radioactive beams physics and so on, 17 nuclei fission barrier parameters were collected from the literature based on different experiments and

  7. Symmetry based frequency domain processing to remove harmonic noise from surface nuclear magnetic resonance measurements

    Science.gov (United States)

    Hein, Annette; Larsen, Jakob Juul; Parsekian, Andrew D.

    2017-02-01

    Surface nuclear magnetic resonance (NMR) is a unique geophysical method due to its direct sensitivity to water. A key limitation to overcome is the difficulty of making surface NMR measurements in environments with anthropogenic electromagnetic noise, particularly constant frequency sources such as powerlines. Here we present a method of removing harmonic noise by utilizing frequency domain symmetry of surface NMR signals to reconstruct portions of the spectrum corrupted by frequency-domain noise peaks. This method supplements the existing NMR processing workflow and is applicable after despiking, coherent noise cancellation, and stacking. The symmetry based correction is simple, grounded in mathematical theory describing NMR signals, does not introduce errors into the data set, and requires no prior knowledge about the harmonics. Modelling and field examples show that symmetry based noise removal reduces the effects of harmonics. In one modelling example, symmetry based noise removal improved signal-to-noise ratio in the data by 10 per cent. This improvement had noticeable effects on inversion parameters including water content and the decay constant T2*. Within water content profiles, aquifer boundaries and water content are more accurate after harmonics are removed. Fewer spurious water content spikes appear within aquifers, which is especially useful for resolving multilayered structures. Within T2* profiles, estimates are more accurate after harmonics are removed, especially in the lower half of profiles.

  8. Numerical simulation of installation of skirt foundations

    Energy Technology Data Exchange (ETDEWEB)

    Vangelsten, Bjoern Vidar

    1997-12-31

    Skirt foundation has been increasingly used for permanent offshore oil installations and anchors for drilling ships. Suction is commonly used in skirt foundation installing. If a large amount of suction is applied, the soil around the foundation may fail and the foundation become useless. This thesis studies failure due to high seepage gradients, aiming to provide a basis for reducing the risk of such failures. Skirt penetration model testing has shown that to solve the problem one must understand what is going on at the skirt tip during suction installation. A numerical model based on micro mechanics was developed as continuum hypothesis was seen to be unsuitable to describe the processes in the critical phases of the failure. The numerical model combines two-dimensional elliptical particles with the finite difference method for flow to model water flow in a granular material. The key idea is to formulate the permeability as a function of the porosity of the grain assembly and so obtain an interaction between the finite difference method on flow and the particle movement. A computer program, DYNELL, was developed and used to simulate: (1) weight penetration of a skirt wall, (2) combined suction and weight penetration of a skirt wall, and (3) critical gradient tests around a skirt wall to study failure mechanisms. The model calculations agree well with laboratory experiments. 16 refs., 124 figs., 21 tabs.

  9. Use of technical based in 3D models for development of design changes in operating nuclear power plants; Empleo de tecnicas basadas en modelos 3D para el desarrollo de modificaciones de diseno en centrales nucleares en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Munoz Portela, V.

    2012-07-01

    The present paper is to describe and analyze the use of these techniques and three-dimensional tools and results obtained with them, showing the extensive possibilities offered in this type of installation, based on the experience gained in recent years.

  10. On-Line Model-Based System For Nuclear Plant Monitoring

    Science.gov (United States)

    Tsoukalas, Lefteri H.; Lee, G. W.; Ragheb, Magdi; McDonough, T.; Niziolek, F.; Parker, M.

    1989-03-01

    A prototypical on-line model-based system, LASALLE1, developed at the University of Illinois in collaboration with the Illinois Department of Nuclear Safety (IDNS) is described. Its main purpose is to interpret about 300 signals, updated every two minutes at IDNS from the LaSalle Nuclear Power Plant, and to diagnose possible abnormal conditions. It is written in VAX/VMS OPS5 and operates on both the on-line and testing modes. In its knowledge base, operator and plant actions pertaining to the Emergency Operating Procedure(EOP) A-01, are encoded. This is a procedure driven by a reactor's coolant level and pressure signals; with the purpose of shutting down the reactor, maintaining adequate core cooling and reducing the reactor pressure and temperature to cold shutdown conditions ( about 90 to 200 °F). The monitoring of the procedure is performed from the perspective of Emergency Preparedness. Two major issues are addressed in this system. First, the management of the short-term or working memory of the system. LASALLE1 must reach its inferences, display its conclusion and update a message file every two minutes before a new set of data arrives from the plant. This was achieved by superimposing additional layers of control over the inferencing strategies inherent in OPS5, and developing special rules for the management of the used or outdated information. The second issue is the representation of information and its uncertainty. The concepts of information granularity and performance-level, which are based on a coupling of Probability Theory and the theory of Fuzzy Sets, are used for this purpose. The estimation of the performance-level incorporates a mathematical methodology which accounts for two types of uncertainty encountered in monitoring physical systems: Random uncertainty, in the form of of probability density functions generated by observations, measurements and sensors data and fuzzy uncertainty represented by membership functions based on symbolic

  11. A web-based resource for the nuclear science/technology high school curriculum - a summary

    Energy Technology Data Exchange (ETDEWEB)

    Ripley, C. [Atomic Energy of Canada Limited, Saint John, New Brunswick (Canada)], E-mail: ripleyc@aecl.ca

    2009-07-01

    On November 15, 2008, the CNA launched a new Nuclear Science Technology High School Curriculum Website. Located at www.cna.ca the site was developed over a decade, first with funding from AECL and finally by the CNA, as a tool to explain concepts and issues related to energy and in particular nuclear energy targeting the public, teachers and students in grades 9-12. It draws upon the expertise of leading nuclear scientists and science educators. Full lesson plans for the teacher, videos for discussion, animations, games, electronic publications, laboratory exercises and quick question and answer sheets will give the student greater knowledge, skills and attitudes necessary to solve problems and to critically examine issues in making decisions. Eight modules focus on key areas: Canada's Nuclear History, Atomic Theory, What is Radiation?, Biological Effects of Radiation, World Energy Sources, Nuclear Technology at Work, Safety (includes Waste Disposal) in the Nuclear Industry and Careers. (author)

  12. Installation of a Roof Mounted Photovoltaic System

    Science.gov (United States)

    Lam, M.

    2015-12-01

    In order to create a safe and comfortable environment for students to learn, a lot of electricity, which is generated from coal fired power plants, is used. Therefore, ISF Academy, a school in Hong Kong with approximately 1,500 students, will be installing a rooftop photovoltaic (PV) system with 302 solar panels. Not only will these panels be used to power a classroom, they will also serve as an educational opportunity for students to learn about the importance of renewable energy technology and its uses. There were four different options for the installation of the solar panels, and the final choice was made based on the loading capacity of the roof, considering the fact that overstressing the roof could prove to be a safety hazard. Moreover, due to consideration of the risk of typhoons in Hong Kong, the solar panel PV system will include concrete plinths as counterweights - but not so much that the roof would be severely overstressed. During and after the installation of the PV system, students involved would be able to do multiple calculations, such as determining the reduction of the school's carbon footprint. This can allow students to learn about the impact renewable energy can have on the environment. Another project students can participate in includes measuring the efficiency of the solar panels and how much power can be produced per year, which in turn can help with calculate the amount of money saved per year and when we will achieve economic parity. In short, the installation of the roof mounted PV system will not only be able to help save money for the school but also provide learning opportunities for students studying at the ISF Academy.

  13. 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.

  14. Study of seismic design bases and site conditions for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

  15. Installation Restoration Program, Phase 2. Confirmation/Quantification, Stage 2, Hancock Air National Guard Base, Syracuse, New York. Volume 2. Appendices

    Science.gov (United States)

    1989-06-01

    9347, 9167 3 3. MACOM Monitor 4. Base Civil Engineer POC MOD 3 SMSt James L Craig Maj Tenple Myers i ANGSC/ SGB 174 TAC Civil Engineering/DE Andrews...dwellings and sensitive I environments. ii) Description of hydrology of the site, include data from geophysical 3 studies (plots), boring logs...protection of sensitive aquatic resources. Analysis of existing research and future needs facilitated the development of a broad-based program plan for

  16. Application of experimental and numerical techniques to the transfer characterization of aero contaminant in installations; Application des techniques experimentales et numeriques a la caracterisation des transferts d'aerocontaminant dans les installations

    Energy Technology Data Exchange (ETDEWEB)

    Drecourt, S.; Laborde, J.C.; Lacan, J.; Witschger, O. [CEA/Fontenay-aux-Roses, Inst. de Protection et de Surete Nucleaire (IPSN), 92 (France)

    1998-07-01

    In the nuclear field, numerous studies based on the transfer of contamination in air are realised and concern as well the workers protection than the safety of installations: in particular, the ventilation, by its dynamic containment functions, surveillance in cleansing, is brought into operation in order to protect the operators and the outside environment facing a contaminant emission. The ventilation applies in normal conditions of operation and in accidental situations. In the two cases it is necessary to limit the propagation of contaminants and to be sure that a dispersion of contaminant be detected as quickly as possible. (N.C.)

  17. Application of Cable Installation and Management System for Substation Based on 3D Design and Information Platform%基于三维信息设计平台的变电站线缆敷设管理

    Institute of Scientific and Technical Information of China (English)

    岳云峰; 董仕镇; 贺艳芝; 黄旭丹

    2014-01-01

    Based on the 3D information design platform, the substation cable installation and management system is developed�Compare with the traditional design method, the dynamic optimization and comprehensive intallaion both indoor and outdoor are taken into consideration and the output of design is improved and cover more aspect of the intallion to solve the problems including the security economic and oderliness issues.%介绍基于三维信息设计平台开发了变电站线缆敷设管理系统的软件构成及功能,其在传统的敷设软件基础上进行优化改进,增加了动态规划功能和户内线缆敷设的综合考虑。

  18. Auxiliary feedwater system risk-based inspection guide for the H. B. Robinson nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Moffitt, N.E.; Lloyd, R.C.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States); Garner, L.W. [Nuclear Regulatory Commission, Washington, DC (United States)

    1993-08-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. H. B. Robinson was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the H. B. Robinson plant.

  19. Auxiliary feedwater system risk-based inspection guide for the South Texas Project nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Bumgardner, J.D.; Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

    1993-12-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. South Texas Project was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the South Texas Project plant.

  20. Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lloyd, R C; Moffitt, N E; Gore, B F; Vo, T V; Vehec, T A [Pacific Northwest Lab., Richland, WA (United States)

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant.

  1. Auxiliary feedwater system risk-based inspection guide for the McGuire nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Bumgardner, J.D.; Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

    1994-05-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. McGuire was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant.

  2. Discriminating poststroke depression from stroke by nuclear magnetic resonance spectroscopy-based metabonomic analysis.

    Science.gov (United States)

    Xiao, Jianqi; Zhang, Jie; Sun, Dan; Wang, Lin; Yu, Lijun; Wu, Hongjing; Wang, Dan; Qiu, Xuerong

    2016-01-01

    Poststroke depression (PSD), the most common psychiatric disease that stroke survivors face, is estimated to affect ~30% of poststroke patients. However, there are still no objective methods to diagnose PSD. In this study, to explore the differential metabolites in the urine of PSD subjects and to identify a potential biomarker panel for PSD diagnosis, the nuclear magnetic resonance-based metabonomic method was applied. Ten differential metabolites responsible for discriminating PSD subjects from healthy control (HC) and stroke subjects were found, and five of these metabolites were identified as potential biomarkers (lactate, α-hydroxybutyrate, phenylalanine, formate, and arabinitol). The panel consisting of these five metabolites provided excellent performance in discriminating PSD subjects from HC and stroke subjects, achieving an area under the receiver operating characteristic curve of 0.946 in the training set (43 HC, 45 stroke, and 62 PSD subjects). Moreover, this panel could classify the blinded samples from the test set (31 HC, 33 stroke, and 32 PSD subjects) with an area under the curve of 0.946. These results laid a foundation for the future development of urine-based objective methods for PSD diagnosis and investigation of PSD pathogenesis.

  3. (1)H nuclear magnetic resonance-based metabolomics study of earthworm Perionyx excavatus in vermifiltration process.

    Science.gov (United States)

    Wang, Lei; Huang, Xulei; Laserna, Anna Karen Carrasco; Li, Sam Fong Yau

    2016-10-01

    In this study, (1)H nuclear magnetic resonance (NMR)-based metabolomics approach was used to characterize the metabolic response of the earthworm Perionyx excavatus in continuous vermifiltration for two months under hydraulic loading rates of 1m(3)m(-2)d(-1) (VF1) and 1.5m(3)m(-2)d(-1) (VF1.5). Both VF1 and VF1.5 showed higher removal of chemical oxygen demand and total nitrogen than the biofilter without earthworms. Principal component analysis of the NMR spectra of earthworm metabolites showed significant separations between those not subjected to wastewater filtration (control) and VF1 or VF1.5. Temporal variations of earthworm biomass, and the identified metabolites that are significantly different between control, VF1 and VF1.5 revealed that worms underwent increasing metabolic activity within 20days in VF1 and 14days in VF1.5, then decreasing metabolic activity. The use of NMR-based metabolomics in monitoring earthworm metabolism was demonstrated to be a novel approach in studying engineered vermifiltration systems.

  4. Nuclear emission-based imaging in the study of brain function

    Science.gov (United States)

    Sossi, Vesna

    2016-09-01

    Nuclear emission - based imaging has been used in medicine for decades either in the form of Single Photon Emission Computerized Tomography (SPECT) or Positron Emission Tomography (PET). Both techniques are based on radiolabelling molecules of biological interest (radiotracers) with either a gamma (SPECT) or a positron (PET) emitting radionuclide. By detecting radiation from the radiolabels and reconstructing the acquired data it is possible to form an image of the radiotracer distribution in the body and thus obtain information on the biological process that the radiotracer is tagging. While most of the clinical applications of PET are in oncology, where the glucose analogue 18F-flurodeoxyglocose (FDG) is the most commonly used radiotracer, the importance of PET imaging for brain applications is rapidly increasing. Numerous radiotracers exist that can tag different neurotransmitter systems as well as abnormal protein aggregations that are known to underlie several brain diseases: amyloid deposition, a characteristic of Alzheimer's, and, more recently, tau deposition, which is deemed abnormal not only in dementia, but also in Parkinson's syndrome and traumatic brain injury. Imaging has shown that may brain diseases start decades before clinical symptoms, in part explaining the difficulty of developing adequate treatments. This talk will briefly summarize the role of PET imaging in the study of neurodegeneration and discuss the upcoming hybrid PET/MRI imaging instrumentation. NSERC, CIHR, MJFF.

  5. Auxiliary feedwater system risk-based inspection guide for the Fort Calhoun nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Moffitt, N.E.; Gore, B.F.; Vehec, T.A.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Fort Calhoun was selected as the sixth plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Fort Calhoun plant.

  6. Gold-nanoparticle-based assay for instantaneous detection of nuclear hormone receptor-response elements interactions.

    Science.gov (United States)

    Tan, Yen Nee; Su, Xiaodi; Liu, Edison T; Thomsen, Jane S

    2010-04-01

    Gold nanoparticles (AuNPs) are widely used as colorimetric probes for biosensing, relying on their unique particle size-dependent and/or interparticle distance-dependent extinction spectrum and solution color. Herein, we describe an AuNP-based colorimetric assay to detect binding interactions between nuclear hormone receptors and their corresponding DNA-binding elements, particularly the human estrogen receptors (ERalpha and ERbeta) and their cognate estrogen response elements (EREs). We found that the protein-DNA (ER-ERE) complexes can stabilize citrate anion-capped AuNPs against salt-induced aggregation to a larger extent than the protein (ER) or the DNA (ERE) alone, due to their unique molecular size and charge properties that provide a strong electrosteric protection. Moreover, our results show that the extent of stabilization is sequence-dependent and can distinguish a single base variation in the ERE associated with minor changes in protein-DNA binding affinity. With this assay, many important parameters of protein-DNA binding events (e.g., sequence selectivity, distinct DNA binding properties of protein subtypes, binding stoichiometry, and sequence-independent transient binding) can be determined instantly without using labels, tedious sample preparations, and sophisticated instrumentation. These benefits, in particular the high-throughput potential, could enable this assay to become the assay of choice to complement conventional techniques for large scale characterization of protein-DNA interactions, a key aspect in biological research.

  7. Design of a homogeneous subcritical nuclear reactor based on thorium with a source of californium 252; Diseno de un reactor nuclear subcritico homogeneo a base de Torio con una fuente de Californio 252

    Energy Technology Data Exchange (ETDEWEB)

    Delgado H, C. E.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico); Sajo B, L., E-mail: ce_delgado89@hotmail.com [Universidad Simon Bolivar, Laboratorio de Fisica Nuclear, Apdo. 89000, 1080A Caracas (Venezuela, Bolivarian Republic of)

    2015-10-15

    Full text: One of the energy alternatives to fossil fuels which do not produce greenhouse gases is the nuclear energy. One of the drawbacks of this alternative is the generation of radioactive wastes of long half-life and its relation to the generation of nuclear materials to produce weapons of mass destruction. An option to these drawbacks of nuclear energy is to use Thorium as part of the nuclear fuel which it becomes in U{sup 233} when capturing neutrons, that is a fissile material. In this paper Monte Carlo methods were used to design a homogeneous subcritical reactor based on thorium. As neutron reflector graphite was used. The reactor core is homogeneous and is formed of 70% light water as moderator, 12% of enriched uranium UO{sub 2}(NO{sub 3}){sub 4} and 18% of thorium Th(NO{sub 3}){sub 4} as fuel. To start the nuclear fission chain reaction an isotopic source of californium 252 was used with an intensity of 4.6 x 10{sup 7} s{sup -1}. In the design the value of the effective multiplication factor, whose value turned out k{sub eff} <1 was calculated. Also, the neutron spectra at different distances from the source and the total fluence were calculated, as well as the values of the ambient dose equivalent in the periphery of the reactor. (Author)

  8. Veronica: Chemical characters for the support of phylogenetic relationships based on nuclear ribosomal and plastid DNA sequence data

    DEFF Research Database (Denmark)

    Albach, Dirk C.; Jensen, Søren Rosendal; Özgökce, Fevzi;

    2005-01-01

    Molecular phylogenetic analyses have revealed many relationships in Veronica (Plantaginaceae) never anticipated before. However, phytochemical characters show good congruence with DNA-based analyses. We have analysed a combined data set of 49 species and subspecies derived from the nuclear riboso...

  9. Reliability of Arctic offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Bercha, F.G. [Bercha Group, Calgary, AB (Canada); Gudmestad, O.T. [Stavanger Univ., Stavanger (Norway)]|[Statoil, Stavanger (Norway)]|[Norwegian Univ. of Technology, Stavanger (Norway); Foschi, R. [British Columbia Univ., Vancouver, BC (Canada). Dept. of Civil Engineering; Sliggers, F. [Shell International Exploration and Production, Rijswijk (Netherlands); Nikitina, N. [VNIIG, St. Petersburg (Russian Federation); Nevel, D.

    2006-11-15

    Life threatening and fatal failures of offshore structures can be attributed to a broad range of causes such as fires and explosions, buoyancy losses, and structural overloads. This paper addressed the different severities of failure types, categorized as catastrophic failure, local failure or serviceability failure. Offshore tragedies were also highlighted, namely the failures of P-36, the Ocean Ranger, the Piper Alpha, and the Alexander Kieland which all resulted in losses of human life. P-36 and the Ocean Ranger both failed ultimately due to a loss of buoyancy. The Piper Alpha was destroyed by a natural gas fire, while the Alexander Kieland failed due to fatigue induced structural failure. The mode of failure was described as being the specific way in which a failure occurs from a given cause. Current reliability measures in the context of offshore installations only consider the limited number of causes such as environmental loads. However, it was emphasized that a realistic value of the catastrophic failure probability should consider all credible causes of failure. This paper presented a general method for evaluating all credible causes of failure of an installation. The approach to calculating integrated reliability involves the use of network methods such as fault trees to combine the probabilities of all factors that can cause a catastrophic failure, as well as those which can cause a local failure with the potential to escalate to a catastrophic failure. This paper also proposed a protocol for setting credible reliability targets such as the consideration of life safety targets and escape, evacuation, and rescue (EER) success probabilities. A set of realistic reliability targets for both catastrophic and local failures for representative safety and consequence categories associated with offshore installations was also presented. The reliability targets were expressed as maximum average annual failure probabilities. The method for converting these annual

  10. Integrated Process Monitoring based on Systems of Sensors for Enhanced Nuclear Safeguards Sensitivity and Robustness

    Energy Technology Data Exchange (ETDEWEB)

    Humberto E. Garcia

    2014-07-01

    This paper illustrates safeguards benefits that process monitoring (PM) can have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). In order to infer the possible existence of proliferation-driven activities, the objective of NMA-based methods is often to statistically evaluate materials unaccounted for (MUF) computed by solving a given mass balance equation related to a material balance area (MBA) at every material balance period (MBP), a particular objective for a PM-based approach may be to statistically infer and evaluate anomalies unaccounted for (AUF) that may have occurred within a MBP. Although possibly being indicative of proliferation-driven activities, the detection and tracking of anomaly patterns is not trivial because some executed events may be unobservable or unreliably observed as others. The proposed similarity between NMA- and PM-based approaches is important as performance metrics utilized for evaluating NMA-based methods, such as detection probability (DP) and false alarm probability (FAP), can also be applied for assessing PM-based safeguards solutions. To this end, AUF count estimates can be translated into significant quantity (SQ) equivalents that may have been diverted within a given MBP. A diversion alarm is reported if this mass estimate is greater than or equal to the selected value for alarm level (AL), appropriately chosen to optimize DP and FAP based on the particular characteristics of the monitored MBA, the sensors utilized, and the data processing method employed for integrating and analyzing collected measurements. To illustrate the application of the proposed PM approach, a protracted diversion of Pu in a waste stream was selected based on incomplete fuel dissolution in a dissolver unit operation, as this diversion scenario is considered to be problematic for detection using NMA-based methods alone. Results demonstrate benefits of conducting PM under a system

  11. Social impact theory based modeling for security analysis in the nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Tae Ho [Systemix Global Co. Ltd., Seoul (Korea, Republic of)

    2015-03-15

    The nuclear fuel cycle is investigated for the perspective of the nuclear non-proliferation. The random number generation of the Monte-Carlo method is utilized for the analysis. Five cases are quantified by the random number generations. These values are summed by the described equations. The higher values are shown in 52{sup nd} and 73{sup rd} months. This way could be a useful obligation in the license of the plant construction. The security of the nuclear fuel cycle incorporated with nuclear power plants (NPPs) is investigated using social impact theory. The dynamic quantification of the theory shows the non-secured time for act of terrorism which is considered for the non-secured condition against the risk of theft in nuclear material. For a realistic consideration, the meta-theoretical framework for modeling is performed for situations where beliefs, attributes or behaviors of an individual are influenced by those of others.

  12. CAST with its micromegas detector installed.

    CERN Multimedia

    Maximilien Brice

    2002-01-01

    The CERN Axion Solar Telescope (CAST) uses a prototype LHC dipole magnet to search for very weakly interacting neutral particles called axions, which should originate in the core of the Sun. The magnet converts the solar axions to photons which are then detected by an X-ray detector based on Micromegas technology. CAST's Micromegas detector has now been installed. Photos 01 02: General view of the CAST experiment with the Micromegas detector in place. Photo 03: Close-up of the micromegas set-up.

  13. Assessment in marine environment for a hypothetic nuclear accident based on the database of tidal harmonic constants.

    Science.gov (United States)

    Min, Byung-Il; Periáñez, Raúl; Park, Kihyun; Kim, In-Gyu; Suh, Kyung-Suk

    2014-10-15

    The eleven nuclear power plants in operation, under construction and a well-planned plant in the east coast of China generally use seawater for reactor cooling. In this study, an oceanic dispersion assessment system based on a database of tidal harmonic constants is developed. This system can calculate the tidal current without a large computational cost, and it is possible to calculate real-time predictions of pollutant dispersions in the ocean. Calculated amplitudes and phases have maximum errors of 10% and 20% with observations, respectively. A number of hypothetical simulations were performed according to varying of the release starting time and duration of pollutant for the six nuclear sites in China. The developed system requires a computational time of one hour for one month of real-time forecasting in Linux OS. Thus, it can use to evaluate rapidly the dispersion characteristics of the pollutants released into the sea from a nuclear accident.

  14. Remote sensing monitoring of thermal discharge in Daya Bay Nuclear Power Station based on HJ-1 infrared camera

    Science.gov (United States)

    Zhu, Li; Yin, Shoujing; Wu, Chuanqing; Ma, Wandong; Hou, Haiqian; Xu, Jing

    2014-11-01

    In this paper, the method of monitoring coastal areas affected by thermal discharge of nuclear plant by using remote sensing techniques was introduced. The proposed approach was demonstrated in Daya Bay nuclear plant based on HJ-B IRS data. A single channel water temperature inversion algorithm was detailed, considering the satellite zenith angle and water vapor. Moreover the reference background temperature was obtained using the average environmental temperature method. In the case study of Daya Bay nuclear plant, the spatial distribution of thermal pollution was analyzed by taking into account the influence of tidal, wind and so on. According to the findings of this study, the speed and direction of the ebb tide, is not conducive to the diffusion of thermal discharge of DNNP. The vertically thermal diffusion was limited by the shallow water depth near the outlet.

  15. Installation Restoration Program (IRP) Stage 3. McClellan Air Force Base. Operable Unit B. Preliminary Assessment Summary Report. Volume 3. Appendices C, D & E

    Science.gov (United States)

    1991-10-01

    Types of materials handled: PCBs Acids Bases Radionucleides Specific chemicals handled: ammonium hydroxide hydrochloric acid nitric acid potassium...on the ground at PRL 30, which includes Building 631. Period of operation: 1960 to 1980 Types of materials handled: Radionucleides "Solvents Specific... radionucleides were handled or disposed. The following sites should be considered for radioactivity screening as part of future remedial investigations: o Site

  16. Installation Restoration Program. Phase 2. Confirmation/Quantification Stage 1 for Minot Air Force Base, Minot, North Dakota. Volume 2. Appendices A through F

    Science.gov (United States)

    1988-10-01

    Grout the remainder of the annulus to the land surface with a Type I Portland cement /bentonite slurry. (2) Check with the base point of contact (POC...presence of hydrocarbons. Include the information In the boring logs. e. Tremie-grout all boreholes to the surface with a bentonite/ cement grout. It is...Corrosion, incrustation , well interference, and similar operation and maintenance problems (5) Observation well networks (6) Existing water sampling sites

  17. Molecular dynamics-based selectivity for Fast-Field-Cycling relaxometry by Overhauser and solid effect dynamic nuclear polarization

    Science.gov (United States)

    Neudert, Oliver; Mattea, Carlos; Stapf, Siegfried

    2017-03-01

    In the last decade nuclear spin hyperpolarization methods, especially Dynamic Nuclear Polarization (DNP), have provided unprecedented possibilities for various NMR techniques by increasing the sensitivity by several orders of magnitude. Recently, in-situ DNP-enhanced Fast Field Cycling (FFC) relaxometry was shown to provide appreciable NMR signal enhancements in liquids and viscous systems. In this work, a measurement protocol for DNP-enhanced NMR studies is introduced which enables the selective detection of nuclear spin hyperpolarized by either Overhauser effect or solid effect DNP. Based on field-cycled DNP and relaxation studies it is shown that these methods allow for the independent measurement of polymer and solvent nuclear spins in a concentrated solution of high molecular weight polybutadiene in benzene doped with α,γ-bisdiphenylene-β-phenylallyl radical. Appreciable NMR signal enhancements of about 10-fold were obtained for both constituents. Moreover, qualitative information about the dynamics of the radical and solvent was obtained. Selective DNP-enhanced FFC relaxometry is applied for the measurement of the 1H nuclear magnetic relaxation dispersion of both constituents with improved precision. The introduced method is expected to greatly facilitate NMR studies of complex systems with multiple overlapping signal contributions that cannot be distinguished by standard methods.

  18. Safeguards-by-Design: Guidance for Independent Spent Fuel Dry Storage Installations (ISFSI)

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard; Philip C. Durst

    2012-05-01

    This document summarizes the requirements and best practices for implementing international nuclear safeguards at independent spent fuel storage installations (ISFSIs), also known as Away-from- Reactor (AFR) storage facilities. These installations may provide wet or dry storage of spent fuel, although the safeguards guidance herein focuses on dry storage facilities. In principle, the safeguards guidance applies to both wet and dry storage. The reason for focusing on dry independent spent fuel storage installations is that this is one of the fastest growing nuclear installations worldwide. Independent spent fuel storage installations are typically outside of the safeguards nuclear material balance area (MBA) of the reactor. They may be located on the reactor site, but are generally considered by the International Atomic Energy Agency (IAEA) and the State Regulator/SSAC to be a separate facility. The need for this guidance is becoming increasingly urgent as more and more nuclear power plants move their spent fuel from resident spent fuel ponds to independent spent fuel storage installations. The safeguards requirements and best practices described herein are also relevant to the design and construction of regional independent spent fuel storage installations that nuclear power plant operators are starting to consider in the absence of a national long-term geological spent fuel repository. The following document has been prepared in support of two of the three foundational pillars for implementing Safeguards-by-Design (SBD). These are: i) defining the relevant safeguards requirements, and ii) defining the best practices for meeting the requirements. This document was prepared with the design of the latest independent dry spent fuel storage installations in mind and was prepared specifically as an aid for designers of commercial nuclear facilities to help them understand the relevant international requirements that follow from a country’s safeguards agreement with

  19. Overview of a FPGA-based nuclear instrumentation dedicated to primary activity measurements.

    Science.gov (United States)

    Bobin, C; Bouchard, J; Pierre, S; Thiam, C

    2012-09-01

    In National Metrology Institutes like LNE-LNHB, renewal and improvement of the instrumentation is an important task. Nowadays, the current trend is to adopt digital boards, which present numerous advantages over the standard electronics. The feasibility of an on-line fulfillment of nuclear-instrumentation functionalities using a commercial FPGA-based (Field-Programmable Gate Array) board has been validated in the case of TDCR primary measurements (Triple to Double Coincidence Ratio method based on liquid scintillation). The new applications presented in this paper have been included to allow either an on-line processing of the information or a raw-data acquisition for an off-line treatment. Developed as a complementary tool for TDCR counting, a time-to-digital converter specifically designed for this technique has been added. In addition, the description is given of a spectrometry channel based on the connection between conventional shaping amplifiers and the analog-to-digital converter (ADC) input available on the same digital board. First results are presented in the case of α- and γ-counting related to, respectively, the defined solid angle and well-type NaI(Tl) primary activity techniques. The combination of two different channels (liquid scintillation and γ-spectrometry) implementing the live-time anticoincidence processing is also described for the application of the 4πβ-γ coincidence method. The need for an optimized coupling between the analog chain and the ADC stage is emphasized. The straight processing of the signals delivered by the preamplifier connected to a HPGe detector is also presented along with the first development of digital filtering.

  20. Development of a standard data base for FBR core nuclear design. 8. Compilation of JUPITER analytical results

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, Makoto; Sugino, Kazuteru; Yokoyama, Kenji [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center; Sato, Wakaei; Numata, Kazuyuki; Iwai, Takehiko

    1997-11-01

    A standard data base for LMFBR core nuclear design has been developed to improve analytical methods and prediction accuracy of nuclear design for large fast breeder cores such as demonstration or commercial FBRs. To develop the data base, extensive work has been performed to accumulate and evaluate many kinds of results from fast reactor physics experiments and their analyses. The present report summarizes the analytical results of the JUPITER experiments, using the most recent nuclear data library (JENDL-3.2) and the latest analytical methods in a consistent manner. The total number of JUPITER C/E values obtained here exceeds 2,300, which cover most of the JUPITER data in the nuclear design data base. The analytical results will be combined with the sensitivity coefficients and experimental and analytical error values as a whole, and are expected to contribute the improvement of large FBR core design methods by means of a unified cross-section set for the demonstration FBR and various physical information. (J.P.N.). 236 refs.

  1. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2004-02-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA.

  2. People detection in nuclear plants by video processing for safety purpose

    Energy Technology Data Exchange (ETDEWEB)

    Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A., E-mail: calexandre@ien.gov.b, E-mail: mol@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN), Rio de Janeiro, RJ (Brazil); Seixas, Jose M.; Silva, Eduardo Antonio B., E-mail: seixas@lps.ufrj.b, E-mail: eduardo@lps.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Eletrica; Cota, Raphael E.; Ramos, Bruno L., E-mail: brunolange@poli.ufrj.b [Universidade Federal do Rio de Janeiro (EP/UFRJ), RJ (Brazil). Dept. de Engenharia Eletronica e de Computacao

    2011-07-01

    This work describes the development of a surveillance system for safety purposes in nuclear plants. The final objective is to track people online in videos, in order to estimate the dose received by personnel, during the execution of working tasks in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a real nuclear plant at Instituto de Engenharia Nuclear, Argonauta nuclear research reactor. Cameras have been installed within Argonauta's room, supplying the data needed. Both video processing and statistical signal processing techniques may be used for detection, segmentation and tracking people in video. This first paper reports people segmentation in video using background subtraction, by two different approaches, namely frame differences, and blind signal separation based on the independent component analysis method. Results are commented, along with perspectives for further work. (author)

  3. Assembly and Installation of the Daya Bay Antineutrino Detectors

    CERN Document Server

    Band, H R; Carr, R; Chen, X C; Chen, X H; Cherwinka, J J; Chu, M C; Draeger, E; Dwyer, D A; Edwards, W R; Gill, R; Goett, J; Greenler, L S; Gu, W Q; He, W S; Heeger, K M; Heng, Y K; Hinrichs, P; Ho, T H; Hoff, M; Hsiung, Y B; Jin, Y; Kang, L; Kettell, S H; Kramer, M; Kwan, K K; Kwok, M W; Lewis, C A; Li, G S; Li, N; Li, S F; Li, X N; Lin, C J; Littlejohn, B R; Liu, J L; Luk, K B; Luo, X L; Ma, X Y; McFarlane, M C; McKeown, R D; Nakajima, Y; Ochoa-Ricoux, J P; Pagac, A; Qian, X; Seilhan, B; Shih, K; Steiner, H; Tang, X; Themann, H; Tsang, K V; Tsang, R H M; Virostek, S; Wang, L; Wang, W; Wang, Z M; Webber, D M; Wei, Y D; Wen, L J; Wenman, D L; Wilhelmi, J; Wingert, M; Wise, T; Wong, H L H; Wu, F F; Xiao, Q; Yang, L; Zhang, Z J; Zhong, W L; Zhuang, H L

    2013-01-01

    The Daya Bay reactor antineutrino experiment is designed to make a precision measurement of the neutrino mixing angle theta13, and recently made the definitive discovery of its nonzero value. It utilizes a set of eight, functionally identical antineutrino detectors to measure the reactor flux and spectrum at baselines of 300 - 2000m from the Daya Bay and Ling Ao Nuclear Power Plants. The Daya Bay antineutrino detectors were built in an above-ground facility and deployed side-by-side at three underground experimental sites near and far from the nuclear reactors. This configuration allows the experiment to make a precision measurement of reactor antineutrino disappearance over km-long baselines and reduces relative systematic uncertainties between detectors and nuclear reactors. This paper describes the assembly and installation of the Daya Bay antineutrino detectors.

  4. Parameter analysis for a nuclear magnetic resonance gyroscope based on 133Cs–129Xe/131Xe

    Science.gov (United States)

    Zhang, Da-Wei; Xu, Zheng-Yi; Zhou, Min; Xu, Xin-Ye

    2017-02-01

    We theoretically investigate several parameters for the nuclear magnetic resonance gyroscope based on 133Cs–129Xe/131Xe. For a cell containing a mixture of 133Cs at saturated pressure, we investigate the optimal quenching gas (N2) pressure and the corresponding pump laser intensity to achieve 30% 133Cs polarization at the center of the cell when the static magnetic field B 0 is 5 {{μ }}{{T}} with different 129Xe/131Xe pressure. The effective field produced by spin-exchange polarized 129Xe or 131Xe sensed by 133Cs can also be discussed in different 129Xe/131Xe pressure conditions. Furthermore, the relationship between the detected signal and the probe laser frequency is researched. We obtain the optimum probe laser detuning from the D2 (6{}2{{S}}1/2\\to 6{}2{{P}}3/2) resonance with different 129Xe/131Xe pressure owing to the pressure broadening. Project supported by the National High Technology Research and Development Program of China (Grant No. 2014AA123401), the National Key Basic Research and Development Program of China (Grant Nos. 2016YFA0302103 and 2012CB821302), the National Natural Science Foundation of China (Grant 11134003), and Shanghai Excellent Academic Leaders Program of China (Grant No. 12XD1402400).

  5. Phylogenetic relationships of living and recently extinct bandicoots based on nuclear and mitochondrial DNA sequences.

    Science.gov (United States)

    Westerman, M; Kear, B P; Aplin, K; Meredith, R W; Emerling, C; Springer, M S

    2012-01-01

    Bandicoots (Peramelemorphia) are a major order of australidelphian marsupials, which despite a fossil record spanning at least the past 25 million years and a pandemic Australasian range, remain poorly understood in terms of their evolutionary relationships. Many living peramelemorphians are critically endangered, making this group an important focus for biological and conservation research. To establish a phylogenetic framework for the group, we compiled a concatenated alignment of nuclear and mitochondrial DNA sequences, comprising representatives of most living and recently extinct species. Our analysis confirmed the currently recognised deep split between Macrotis (Thylacomyidae), Chaeropus (Chaeropodidae) and all other living bandicoots (Peramelidae). The mainly New Guinean rainforest peramelids were returned as the sister clade of Australian dry-country species. The wholly New Guinean Peroryctinae was sister to Echymiperinae. The poorly known and perhaps recently extinct Seram Bandicoot (Rhynchomeles) is sister to Echymipera. Estimates of divergence times from relaxed-clock Bayesian methods suggest that living bandicoots originated in the late Oligocene or early Miocene, much earlier than currently thought based on fossils. Subsequent radiations within Peramelemorphia probably took place on the Australian mainland during the Miocene, with diversification of rainforest taxa on the newly emergent New Guinean landmasses through the middle-late Miocene and complete establishment of modern lineages by the early Pliocene.

  6. Systematic positions of Lamiophiomis and Paraphlomis (Lamiaceae) based on nuclear and chloroplast sequences

    Institute of Scientific and Technical Information of China (English)

    Yue-Zhi PAN; Li-Qin FANG; Gang HAO; Jie CAI; Xun GONG

    2009-01-01

    Genera Lamiophlomis and Paraphlomis were originally separated from genus Phlomis s.l. on the basis of particular morphological characteristics. However, their relationship was highly contentious, as evidenced by the literature. In the present paper, the systematic positions of Lamiophlomis, Paraphlomis, and their related genera were assessed based on nuclear internal transcribed spacer (ITS) and chloroplast rpl16 and trnL-F sequence data using maximum parsimony (MP) and Bayesian methods. In total, 24 species representing six genera of the ingroup and outgroup were sampled. Analyses of both separate and combined sequence data were conducted to resolve the systematic relationships of these genera. The results reveal that Lamiophlomis is nested within Phlomis sect. Phlomoides and its genetic status is not supported. With the inclusion of Lamiophlomis rotata in sect. Phlomoides, sections Phlomis and Phlomoides of Phlomis were resolved as monophyletic. Paraphlomis was supported as an inde-pendent genus. However, the resolution of its monophyly conflicted between MP and Bayesian analyses, suggesting the need for expended sampling and further evidence.

  7. Nuclear magnetic resonance based metabolomics and liver diseases: Recent advances and future clinical applications.

    Science.gov (United States)

    Amathieu, Roland; Triba, Mohamed Nawfal; Goossens, Corentine; Bouchemal, Nadia; Nahon, Pierre; Savarin, Philippe; Le Moyec, Laurence

    2016-01-01

    Metabolomics is defined as the quantitative measurement of the dynamic multiparametric metabolic response of living systems to pathophysiological stimuli or genetic modification. It is an "omics" technique that is situated downstream of genomics, transcriptomics and proteomics. Metabolomics is recognized as a promising technique in the field of systems biology for the evaluation of global metabolic changes. During the last decade, metabolomics approaches have become widely used in the study of liver diseases for the detection of early biomarkers and altered metabolic pathways. It is a powerful technique to improve our pathophysiological knowledge of various liver diseases. It can be a useful tool to help clinicians in the diagnostic process especially to distinguish malignant and non-malignant liver disease as well as to determine the etiology or severity of the liver disease. It can also assess therapeutic response or predict drug induced liver injury. Nevertheless, the usefulness of metabolomics is often not understood by clinicians, especially the concept of metabolomics profiling or fingerprinting. In the present work, after a concise description of the different techniques and processes used in metabolomics, we will review the main research on this subject by focusing specifically on in vitro proton nuclear magnetic resonance spectroscopy based metabolomics approaches in human studies. We will first consider the clinical point of view enlighten physicians on this new approach and emphasis its future use in clinical "routine".

  8. Likelihood-based association analysis for nuclear families and unrelated subjects with missing genotype data.

    Science.gov (United States)

    Dudbridge, Frank

    2008-01-01

    Missing data occur in genetic association studies for several reasons including missing family members and uncertain haplotype phase. Maximum likelihood is a commonly used approach to accommodate missing data, but it can be difficult to apply to family-based association studies, because of possible loss of robustness to confounding by population stratification. Here a novel likelihood for nuclear families is proposed, in which distinct sets of association parameters are used to model the parental genotypes and the offspring genotypes. This approach is robust to population structure when the data are complete, and has only minor loss of robustness when there are missing data. It also allows a novel conditioning step that gives valid analysis for multiple offspring in the presence of linkage. Unrelated subjects are included by regarding them as the children of two missing parents. Simulations and theory indicate similar operating characteristics to TRANSMIT, but with no bias with missing data in the presence of linkage. In comparison with FBAT and PCPH, the proposed model is slightly less robust to population structure but has greater power to detect strong effects. In comparison to APL and MITDT, the model is more robust to stratification and can accommodate sibships of any size. The methods are implemented for binary and continuous traits in software, UNPHASED, available from the author.

  9. Evaluation of Monticello Nuclear Power Plant, Environmental Impact Prediction, based on monitoring programs

    Energy Technology Data Exchange (ETDEWEB)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1976-11-01

    This report evaluates quantitatively the nonradiological environmental monitoring programs at Monticello Nuclear Generating Plant. The general objective of the study is to assess the effectiveness of monitoring programs in the measurement of environmental impacts. Specific objectives include the following: (1) Assess the validity of environmental impact predictions made in the Environmental Statement by analysis of nonradiological monitoring data; (2) evaluate the general adequacy of environmental monitoring programs for detecting impacts and their responsiveness to Technical Specifications objectives; (3) assess the adequacy of preoperational monitoring programs in providing a sufficient data base for evaluating operational impacts; (4) identify possible impacts that were not predicted in the environmental statement and identify monitoring activities that need to be added, modified or deleted; and (5) assist in identifying environmental impacts, monitoring methods, and measurement problems that need additional research before quantitative predictions can be attempted. Preoperational as well as operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the analytical methods used to measure ecological and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data were available.

  10. Ion track reconstruction in 3D using alumina-based fluorescent nuclear track detectors

    CERN Document Server

    Niklas, Martin; Akselrod, Mark S; Abollahi, Amir; Jäkel, Oliver; Greilich, Steffen

    2013-01-01

    Fluorescent nuclear track detectors (FNTDs) based on Al2O3:C,Mg single crystal combined with confocal microscopy provide 3D information on ion tracks with a resolution only limited by light diffraction. FNTDs are also ideal substrates to be coated with cells to engineer cell-fluorescent ion track hybrid detectors. This radiobiological tool enables a novel platform linking cell responses to physical dose deposition on a sub-cellular level in proton and heavy ion therapies. To achieve spatial correlation between single ion hits in the cell coating and its biological response the ion traversals have to be reconstructed in 3D using the depth information gained by the FNTD read-out. FNTDs were coated with a confluent human lung adenocarcinoma epithelial cell layer. Carbon ion irradiation of the hybrid detector was performed perpendicular and angular to the detector surface. In-situ imaging of the fluorescently labeled cell layer and the FNTD was performed in a sequential read-out. Making use of the trajectory info...

  11. Thymic pathologies in myasthenia gravis: a preoperative assessment of CAT scan and nuclear based imaging.

    Science.gov (United States)

    Jordan, Berit; Kellner, Juliane; Jordan, Karin; Bähre, Manfred; Behrmann, Curd; Zierz, Stephan

    2016-04-01

    Precise diagnostic work up of a suspected thymic pathology in patients with myasthenia gravis (MG) is very important for potential surgical implications and further disease course. In this study the diagnostic value of combined preoperative radiological (CAT scan) and nuclear based imaging (octreotide and thallium scintigraphy) in patients with MG was evaluated. Twenty four patients were included. Histopathology revealed thymoma in nine patients, thymic carcinoma (TC) in one patient, lymphofollicular hyperplasia in seven patients, and involuted thymus in another seven patients. Diagnostic sensitivity for detecting thymoma/TC was 80 % in CAT scan as well as in somatostatin scintigraphy; the combination of both procedures reached 90 %. However, the diagnostic specifity to exclude thymoma in CAT scan was 100 % and in octreotide scintigraphy 85.7 %. Semiquantitative octreotide uptake significantly correlated with histological grading of thymoma/TC (r = 0.764) and histological proliferation rate Ki67 (r = 0.894). Thallium scintigraphy was positive only in one out of four thymoma cases. In this study, somatostatin scintigraphy has been shown to be a useful additional diagnostic technique in detecting thymic malignancies in patients with MG. These results might be especially helpful in patients with late onset MG as these patients are in general no candidates for thymectomy.

  12. A Spartan 6 FPGA-based data acquisition system for dedicated imagers in nuclear medicine

    Science.gov (United States)

    Fysikopoulos, E.; Loudos, G.; Georgiou, M.; David, S.; Matsopoulos, G.

    2012-12-01

    We present the development of a four-channel low-cost hardware system for data acquisition, with application in dedicated nuclear medicine imagers. A 12 bit octal channel high-speed analogue to digital converter, with up to 65 Msps sampling rate, was used for the digitization of analogue signals. The digitized data are fed into a field programmable gate array (FPGA), which contains an interface to a bank of double data rate 2 (DDR2)-type memory. The FPGA processes the digitized data and stores the results into the DDR2. An ethernet link was used for data transmission to a personal computer. The embedded system was designed using Xilinx's embedded development kit (EDK) and was based on Xilinx's Microblaze soft-core processor. The system has been evaluated using two different discrete optical detector arrays (a position-sensitive photomultiplier tube and a silicon photomultiplier) with two different pixelated scintillator arrays (BGO, LSO:Ce). The energy resolution for both detectors was approximately 25%. A clear identification of all crystal elements was achieved in all cases. The data rate of the system with this implementation can reach 60 Mbits s-1. The results have shown that this FPGA data acquisition system is a compact and flexible solution for single-photon-detection applications. This paper was originally submitted for inclusion in the special feature on Imaging Systems and Techniques 2011.

  13. Nuclear Insurance Subsidies Cost from Post-Fukushima Accounting Based on Media Sources

    Directory of Open Access Journals (Sweden)

    John J. Laureto

    2016-12-01

    Full Text Available Quantification of nuclear liability insurance is difficult without arbitrary liability caps; however, post-mortem calculations can be used to calculate insurance costs. This study analyzes the Fukushima (Daiichi nuclear power plant disaster to quantify the cost per unit electricity ($/kWh of nuclear energy from the lifetime of the plant after accounting for the true cost of the liability needed to cover the damages from the nuclear disaster determined from news reports. These costs are then compared to the cost of electricity currently paid by Japanese consumers, and then are aggregated to determine the indirect subsidy for nuclear power providers in both Japan and the USA. The results show that the reported costs of the Fukushima nuclear disaster are $20–525 billion, which results in a real insurance cost from the lifetime of electricity produced at the plants between $0.22–5.78/kWh. These values are far higher than the current insurance costs by Japanese law of $0.01/kWh and even the total costs consumers pay for electricity. Although the spread in the input costs is large and the reported metrics are incomplete, the nuclear insurance subsidy is clearly substantial in Japan and in the USA. Ideally, energy sources should be economically sustainable without the need for a government insurance subsidy. For the electricity market to function effectively and efficiently in all other countries using nuclear power, the insurance costs should be reported accurately and included in nuclear electricity costs without arbitrary government liability caps.

  14. NKS - The Nordic region's cooperative network for addressing challenges in nuclear safety and emergency preparedness

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, K.G. [NKS/Technical University of Denmark (Denmark); Andgren, K. [NKS/Vattenfall R and D (Sweden); Leino, K. [NKS/Fortum Power and Heat Oy (Finland); Magnusson, S. [NKS/Icelandic Radiation Safety Authority (Iceland); Physant, F. [NKS/FRIT, Roskilde (Denmark)

    2014-07-01

    Based on the foundation of a common cultural and historical heritage and a long tradition of collaboration, NKS aims to facilitate a common Nordic view on nuclear and radiation safety. A common understanding of rules, practice and measures, and national differences in this context, is here an essential requirement. Problems can generally be tackled quicker, more efficiently, more consistently and at a lower cost through collaboration, bearing in mind that key competencies are not equally distributed in the different Nordic countries. For instance common Nordic challenges emerge in relation to nuclear installations, where nuclear power plants are in operation in Finland and Sweden, and research reactors have been operated in Denmark, Finland, Norway and Sweden. There is an obvious benefit in exchanging ideas and technologies in relation to plant operation, and since a number of reactors in different Nordic countries are under decommissioning, a collaborative benefit can also be realised in that context. Sweden also has a nuclear fuel production plant, and its collaboration with other Nordic nuclear installations can also be beneficial. Further, a number of large radiological installations are projected in Nordic areas (e.g., the MAX-LAB/MAX IV synchrotron radiation source and the European spallation source ESS), where Nordic organisations are collaborating in addressing, e.g., potential environmental implications. On the emergency preparedness side, the Fukushima accident in March 2011 was a reminder that large accidents at nuclear installations can lead to widespread radioactive contamination in the environment. In order to respond to nuclear or radiological emergencies, should they affect Nordic populations, it is necessary to maintain an operational emergency preparedness. By continuously improving detection, response and decision aiding tools while maintaining an informal collaborative network between relevant stakeholders in the Nordic countries (including

  15. Discrimination between nuclear explosions and earthquakes based on consideration of tectonic ambient shear stress values

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    On the basis of fracture mechanics earthquake rupture model, the relations between source parameters and t0, the value of tectonic ambient shear stress in the place where the earthquake occurs, have been derived. Thus, we can calculate a large number of values of tectonic ambient shear stress or values of background stress in the place where the earthquake occurs. If nuclear explosions are treated as earthquakes in the calculation, we find that t0 values of nuclear explosions have about 20 MPa, which is obviously higher than average t0 values of earthquakes with the same magnitude. This result can be used to discriminate nuclear explosions from earthquakes.

  16. Resolving the H 2 effect on radiation induced dissolution of UO 2-based spent nuclear fuel

    Science.gov (United States)

    Trummer, Martin; Jonsson, Mats

    2010-01-01

    In recent years, the impact of H2 on α-radiation induced dissolution of UO2-based spent nuclear fuel has been studied and debated extensively. Experimental results on the effect of H2 on the concentration of H2O2 during α-radiolysis have been shown to disagree with numerical simulations. For this reason, the reaction scheme used in simulations of aqueous radiation chemistry has sometimes been questioned. In this work, we have studied the impact of H2 on the H2O2 concentration in α-irradiated aqueous solution using numerical simulations. The effects of H2 pressure, α-dose rate and HCO3- concentration were investigated by performing systematic variations in these parameters. The simulations show that the discrepancy between the previously published experimental result and numerical simulations is due to the use of a homogeneous dose rate (the energy is assumed to be equally distributed in the whole volume). Taking the actual dose rate of the α-irradiated volume into account, the simulation is in perfect agreement with the experimental results. This shows that the H2 effect is strongly α-dose rate dependent, and proves the reliability of the reaction scheme used in the simulations. The simulations also show that H2 influences the H2O2 concentration under α-radiolysis. The magnitude of the effect depends on the dose rate and the H2 pressure as well as on the concentration of HCO 3-. The impact of the radiolytic H2 effect on the rate of α-radiation induced dissolution of spent nuclear fuel is discussed along with other (α- and γ-) radiation induced processes capable of reducing the concentration of uranium in solution. The radiolytic H2 effect is quantitatively compared to the previously presented noble metal catalyzed H2 effect. This comparison shows that the noble metal catalyzed H2 effect is far more efficient than the radiolytic H2 effect. Reduction of U(VI) in solution due to low dose rate γ-radiolysis in the presence of H2 is proposed to be the cause of

  17. Development of parallel GPU based algorithms for problems in nuclear area; Desenvolvimento de algoritmos paralelos baseados em GPU para solucao de problemas na area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Adino Americo Heimlich

    2009-07-01

    Graphics Processing Units (GPU) are high performance co-processors intended, originally, to improve the use and quality of computer graphics applications. Since researchers and practitioners realized the potential of using GPU for general purpose, their application has been extended to other fields out of computer graphics scope. The main objective of this work is to evaluate the impact of using GPU in two typical problems of Nuclear area. The neutron transport simulation using Monte Carlo method and solve heat equation in a bi-dimensional domain by finite differences method. To achieve this, we develop parallel algorithms for GPU and CPU in the two problems described above. The comparison showed that the GPU-based approach is faster than the CPU in a computer with two quad core processors, without precision loss. (author)

  18. Installation package for a solar heating system

    Science.gov (United States)

    1978-01-01

    Installation information is given for a solar heating system installed in Concho Indian School at El Reno, Oklahoma. This package includes a system Operation and Maintenance Manual, hardware brochures, schematics, system operating modes and drawings.

  19. Track structure based modelling of light ion radiation effects on nuclear and mitochondrial DNA

    Science.gov (United States)

    Schmitt, Elke; Ottolenghi, Andrea; Dingfelder, Michael; Friedland, Werner; Kundrat, Pavel; Baiocco, Giorgio

    2016-07-01

    Space radiation risk assessment is of great importance for manned spaceflights in order to estimate risks and to develop counter-measures to reduce them. Biophysical simulations with PARTRAC can help greatly to improve the understanding of initial biological response to ionizing radiation. Results from modelling radiation quality dependent DNA damage and repair mechanisms up to chromosomal aberrations (e.g. dicentrics) can be used to predict radiation effects depending on the kind of mixed radiation field exposure. Especially dicentric yields can serve as a biomarker for an increased risk due to radiation and hence as an indicator for the effectiveness of the used shielding. PARTRAC [1] is a multi-scale biophysical research MC code for track structure based initial DNA damage and damage response modelling. It integrates physics, radiochemistry, detailed nuclear DNA structure and molecular biology of DNA repair by NHEJ-pathway to assess radiation effects on cellular level [2]. Ongoing experiments with quasi-homogeneously distributed compared to sub-micrometre focused bunches of protons, lithium and carbon ions allow a separation of effects due to DNA damage complexity on nanometre scale from damage clustering on (sub-) micrometre scale [3, 4]. These data provide an unprecedented benchmark for the DNA damage response model in PARTRAC and help understand the mechanisms leading to cell killing and chromosomal aberrations (e.g. dicentrics) induction. A large part of space radiation is due to a mixed ion field of high energy protons and few heavier ions that can be only partly absorbed by the shielding. Radiation damage induced by low-energy ions significantly contributes to the high relative biological efficiency (RBE) of ion beams around Bragg peak regions. For slow light ions the physical cross section data basis in PARTRAC has been extended to investigate radiation quality effects in the Bragg peak region [5]. The resulting range and LET values agree with ICRU data

  20. Study of A Multi-criteria Evaluation Methodology for Nuclear Fuel Cycle System Based on Sustainability

    Institute of Scientific and Technical Information of China (English)

    Liu Jingquan; Hidekazu Yoshikawa; OuYang Jun; Zhou Yangping

    2006-01-01

    This paper presents a multi-criteria evaluation methodology for nuclear fuel cycle options in terms of energy sustainability. Starting from the general sustainability concept and the public acceptance questionnaire, a set of indicators reflecting specific criteria for the evaluation of nuclear fuel cycle options are defined.Particular attention is devoted to the resource utility efficiency, environmental effect, human health hazard and economic effect, which represent the different concerns of different stakeholders. This methodology also integrated a special mathematic processing approach, namely the Extentics Evaluation Method, which quantifies the human being subjective perception to provide the intuitionistic judgement and comparison for different options. The once-through option and reprocessing option of nuclear fuel cycle are examined by using the proposed methodology. The assessment process and result can give us some guidance in nuclear fuel cycle evaluation under the constraint of limited data.