WorldWideScience

Sample records for multiple nuclear processes

  1. Application of neural networks to multiple alarm processing and diagnosis in nuclear power plants

    International Nuclear Information System (INIS)

    Cheon, Se Woo; Chang Soon Heung; Chung, Hak Yeong

    1992-01-01

    This paper presents feasibility studies of multiple alarm processing and diagnosis using neural networks. The back-propagation neural network model is applied to the training of multiple alarm patterns for the identification of failure in a reactor coolant pump (RCP) system. The general mapping capability of the neural network enables to identify a fault easily. The case studies are performed with emphasis on the applicability of the neural network to pattern recognition problems. It is revealed that the neural network model can identify the cause of multiple alarms properly, even when untrained or sensor-failed alarm symptoms are given. It is also shown that multiple failures are easily identified using the symptoms of multiple alarms

  2. Multiple nuclear ADC controller

    Energy Technology Data Exchange (ETDEWEB)

    Lovett, A; Rapaport, M S [Center for Nuclear Research, Soreq (Israel)

    1980-12-01

    A controller for an on-line three parameter coincidence and multispectra scaling system has been developed. It has been designed to control, event-by-event, the outputs of three nuclear analog-to-digital converters used at the SOLIS facility. The system utilizes an HP minicomputer with a 32k-word core memory, a disc drive and magnetic tape units.

  3. High-multiplicity processes

    International Nuclear Information System (INIS)

    Shelkov, G.; Sisakyan, A.; Mandzhavidze, I.

    1999-01-01

    We wish to demonstrate that investigation of asymptotically high multiplicity (AHM) hadron reactions may solve, or at least clear up, a number of problems unsolvable by other ways. We would lean upon the idea: (i) the reactions final state entropy is proportional to multiplicity and, by this reason, just in the AHM domain one may expect the equilibrium final state and (ii) the AHM final state is cold because of the energy-momentum conservation laws. This means that the collective phenomena may become important in the AHM domain. The possibility of hard processes dominance is considered also

  4. Nuclear process heat

    Energy Technology Data Exchange (ETDEWEB)

    Schulten, R [Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany). Inst. fuer Reaktorentwicklung

    1976-05-01

    It is anticipated that the coupled utilization of coal and nuclear energy will achieve great importance in the future, the coal serving mainly as raw material and nuclear energy more as primary energy. Prerequisite for this development is the availability of high-temperature reactors, the state of development of which is described here. Raw materials for coupled use with nuclear process heat are petroleum, natural gas, coal, lignite, and water. Steam reformers heated by nuclear process heat, which are suitable for numerous processes, are expected to find wide application. The article describes several individual methods, all based on the transport of gas in pipelines, which could be utilized for the long distance transport of 'nuclear energy'.

  5. Multiple preequilibrium decay processes

    International Nuclear Information System (INIS)

    Blann, M.

    1987-11-01

    Several treatments of multiple preequilibrium decay are reviewed with emphasis on the exciton and hybrid models. We show the expected behavior of this decay mode as a function of incident nucleon energy. The algorithms used in the hybrid model treatment are reviewed, and comparisons are made between predictions of the hybrid model and a broad range of experimental results. 24 refs., 20 figs

  6. Application of process monitoring to anomaly detection in nuclear material processing systems via system-centric event interpretation of data from multiple sensors of varying reliability

    International Nuclear Information System (INIS)

    Garcia, Humberto E.; Simpson, Michael F.; Lin, Wen-Chiao; Carlson, Reed B.; Yoo, Tae-Sic

    2017-01-01

    Highlights: • Process monitoring can strengthen nuclear safeguards and material accountancy. • Assessment is conducted at a system-centric level to improve safeguards effectiveness. • Anomaly detection is improved by integrating process and operation relationships. • Decision making is benefited from using sensor and event sequence information. • Formal framework enables optimization of sensor and data processing resources. - Abstract: In this paper, we apply an advanced safeguards approach and associated methods for process monitoring to a hypothetical nuclear material processing system. The assessment regarding the state of the processing facility is conducted at a system-centric level formulated in a hybrid framework. This utilizes architecture for integrating both time- and event-driven data and analysis for decision making. While the time-driven layers of the proposed architecture encompass more traditional process monitoring methods based on time series data and analysis, the event-driven layers encompass operation monitoring methods based on discrete event data and analysis. By integrating process- and operation-related information and methodologies within a unified framework, the task of anomaly detection is greatly improved. This is because decision-making can benefit from not only known time-series relationships among measured signals but also from known event sequence relationships among generated events. This available knowledge at both time series and discrete event layers can then be effectively used to synthesize observation solutions that optimally balance sensor and data processing requirements. The application of the proposed approach is then implemented on an illustrative monitored system based on pyroprocessing and results are discussed.

  7. Selectivity in multiple quantum nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Warren, W.S.

    1980-11-01

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

  8. Selectivity in multiple quantum nuclear magnetic resonance

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-11-01

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

  9. The nuclear fission process

    International Nuclear Information System (INIS)

    Wagemans, C.

    1991-01-01

    Fifty years after its discovery, the nuclear fission phenomenon is of recurring interest. When its fundamental physics aspects are considered, fission is viewed in a very positive way, which is reflected in the great interest generated by the meetings and large conferences organized for the 50th anniversary of its discovery. From a purely scientific and practical point of view, a new book devoted to the (low energy) nuclear fission phenomenon was highly desirable considering the tremendous amount of new results obtained since the publication of the book Nuclear Fission by Vandenbosch and Huizenga in 1973 (Academic Press). These new results could be obtained thanks to the growth of technology, which enabled the construction of powerful new neutron sources, particle and heavy ion accelerators, and very performant data-acquisition and computer systems. The re-invention of the ionization chamber, the development of large fission fragment spectrometers and sophisticated multiparameter devices, and the production of exotic isotopes also contributed significantly to an improved understanding of nuclear fission. This book is written at a level to introduce graduate students to the exciting subject of nuclear fission. The very complete list of references following each chapter also makes the book very useful for scientists, especially nuclear physicists. The book has 12 chapters covering the fission barrier and the various processes leading to fission as well as the characteristics of the various fission reaction products. In order to guarantee adequate treatment of the very specialized research fields covered, several distinguished scientists actively involved in some of these fields were invited to contribute their expertise as authors or co-authors of the different chapters

  10. Nuclear waste processing

    International Nuclear Information System (INIS)

    Nienhuys, K.; Noordegraaf, D.

    1977-04-01

    This report is composed with a view to the discussions around the selection of a site in F.R.Germany near the Netherlands' border for a fuel reprocessing plant. Most of the scientific data available are placed side by side, especially those which are contradictory in order to promote better judgement of affairs before governmental decisions are made. The report comprises a brief introduction to nuclear power plants, fuel cycle, radioactive materials and their properties. Next the transportation of wastes from the nuclear power plants to the reprocessing plants is dealt with more extensively, including the processing and the effluents of as well as the experiences with operational reprocessing plants. The hazards from manipulation of radioactive materials accidents and theft are outlined in each case, followed by a problem discussion. The appendix illustrates the German concept of 'industrial park for after-treatment and disposal'

  11. Mechanisms of multiple production processes

    International Nuclear Information System (INIS)

    Dremin, I.M.

    1977-01-01

    Theoretical approaches to multiple production processes are discussed. A large number of models proceeds from the notion about common excited system produced by colliding hadrons. This class of models includes the hydrodynamical, statistical, thermodynamical and statistical bootstrap models. Sometimes the production process is due to excitation and decay of two colliding particles. The fragmentation bremsstrahlung and inelastic diffraction models belong to this group. The largest group of models describes the multiple production process as a result of formation of many excited centers. The typical example is the multiperipheral model. An interesting direction is given by the attempts to interrelate the mechanism of multiple production with internal structure of particles that is with their constituents (C-group)'-quarks, gluons, etc. Besides the models there are phenomenological (p group) attempts to connect different features of multiple production. Experimental data indicate the existence of leading and pionization particles thus giving an evidence for applications of different models. The data about increase of total and inclusive cross sections, the behaviour of the mean multiplicity and correlations at high energies provide a clue for further development of multiple production theory

  12. Processing of nuclear waste

    International Nuclear Information System (INIS)

    Hennelly, E.J.

    1981-01-01

    The processing of nuclear waste to transform the liquid waste from fuel reprocessing activities is well defined. Most solid waste forms, if they are cooled and contain diluted waste, are compatible with many permanent storage environments. The public acceptance of methods for disposal is being delayed in the US because of the alternatives studies of waste forms and repositories now under way that give the impression of indecision and difficulty for the disposal of HLW. Conservative programs that dilute and cool solid waste are under way in France and Sweden and demonstrate that a solution to the problem is available now. Research and development should be directed toward improving selected methods rather than seeking a best method, which at best, may always be illusory

  13. Mean associative multiplicities in deep inelastic processes

    International Nuclear Information System (INIS)

    Dzhaparidze, G.Sh.; Kiselev, A.V.; Petrov, V.A.

    1981-01-01

    The associative hadron multiplicities in deep inelastic and Drell--Yan processes are studied. In particular the mean multiplicities in different hard processes in QCD are found to be determined by the mean multiplicity in parton jet [ru

  14. Studies of nuclear processes

    International Nuclear Information System (INIS)

    Ludwig, E.J.

    1993-01-01

    Results for the period 1 Sep 92 through 31 Aug 93 are presented in nearly a hundred brief papers, some of which present new but preliminary data. Activities reported may be grouped as follows: Fundamental symmetries in the nucleus (parity-mixing measurements, time reversal invariance measurements, signatures of quantum chaos in nuclei), Internucleon reactions (neutron -- proton interactions, the neutron -- neutron scattering length, reactions between deuterons and very light nuclei), Dynamics of very light nuclei (measurements of D states of very light nuclei by transfer reactions, nuclear reactions between very light nuclei, radiative capture reactions with polarized sources), The many-nucleon problem (nuclear astrophysics, high-spin spectroscopy and superdeformation, the nuclear mean field: Dispersive relations and nucleon scattering, configuration mixing in 56 Co and 46 Sc using (d,α) reactions, radiative capture studies, high energy resolution resonance studies at 100--400 keV, nuclear data evaluation for A=3--20), Nuclear instruments and methods (FN tandem accelerator operation, KN accelerator operation and maintenance, atomic beam polarized ion source, development of techniques for determining the concentration of SF 6 in the accelerator insulating gas mixture, production of beams and targets, detector systems, updating of TeX, Psprint, and associated programs on the VAX cluster), and Educational Activities

  15. Processing multidimensional nuclear physics data

    Energy Technology Data Exchange (ETDEWEB)

    Becker, J. [Lawrence Livermore National Lab., CA (United States)

    1994-11-15

    Modern Ge detector arrays for gamma-ray spectroscopy are producing data sets unprecedented in size and event multiplicity. Gammasphere, the DOE sponsored array, has the following characteristics: (1) High granularity (110 detectors); (2) High efficiency (10%); and (3) Precision energy measurements (Delta EE = 0.2%). Characteristics of detector line shape, the data set, and the standard practice in the nuclear physics community to the nuclear gamma-ray cascades from the 4096 times 4096 times 4096 data cube will be discussed.

  16. Modeling nuclear processes by Simulink

    Energy Technology Data Exchange (ETDEWEB)

    Rashid, Nahrul Khair Alang Md, E-mail: nahrul@iium.edu.my [Faculty of Engineering, International Islamic University Malaysia, Jalan Gombak, Selangor (Malaysia)

    2015-04-29

    Modelling and simulation are essential parts in the study of dynamic systems behaviours. In nuclear engineering, modelling and simulation are important to assess the expected results of an experiment before the actual experiment is conducted or in the design of nuclear facilities. In education, modelling can give insight into the dynamic of systems and processes. Most nuclear processes can be described by ordinary or partial differential equations. Efforts expended to solve the equations using analytical or numerical solutions consume time and distract attention from the objectives of modelling itself. This paper presents the use of Simulink, a MATLAB toolbox software that is widely used in control engineering, as a modelling platform for the study of nuclear processes including nuclear reactor behaviours. Starting from the describing equations, Simulink models for heat transfer, radionuclide decay process, delayed neutrons effect, reactor point kinetic equations with delayed neutron groups, and the effect of temperature feedback are used as examples.

  17. Modeling nuclear processes by Simulink

    International Nuclear Information System (INIS)

    Rashid, Nahrul Khair Alang Md

    2015-01-01

    Modelling and simulation are essential parts in the study of dynamic systems behaviours. In nuclear engineering, modelling and simulation are important to assess the expected results of an experiment before the actual experiment is conducted or in the design of nuclear facilities. In education, modelling can give insight into the dynamic of systems and processes. Most nuclear processes can be described by ordinary or partial differential equations. Efforts expended to solve the equations using analytical or numerical solutions consume time and distract attention from the objectives of modelling itself. This paper presents the use of Simulink, a MATLAB toolbox software that is widely used in control engineering, as a modelling platform for the study of nuclear processes including nuclear reactor behaviours. Starting from the describing equations, Simulink models for heat transfer, radionuclide decay process, delayed neutrons effect, reactor point kinetic equations with delayed neutron groups, and the effect of temperature feedback are used as examples

  18. Multiple phosphorylation sites at the C-terminus regulate nuclear import of HCMV DNA polymerase processivity factor ppUL44

    International Nuclear Information System (INIS)

    Alvisi, Gualtiero; Marin, Oriano; Pari, Gregory; Mancini, Manuela; Avanzi, Simone; Loregian, Arianna; Jans, David A.; Ripalti, Alessandro

    2011-01-01

    The processivity factor of human cytomegalovirus DNA polymerase, phosphoprotein ppUL44, is essential for viral replication. During viral infection ppUL44 is phosphorylated by the viral kinase pUL97, but neither the target residues on ppUL44 nor the effect of phosphorylation on ppUL44's activity are known. We report here that ppUL44 is phosphorylated when transiently expressed in mammalian cells and coimmunoprecipitates with cellular kinases. Of three potential phosphorylation sites (S413, S415, S418) located upstream of ppUL44's nuclear localization signal (NLS) and one (T427) within the NLS itself, protein kinase CK2 (CK2) specifically phosphorylates S413, to trigger a cascade of phosphorylation of S418 and S415 by CK1 and CK2, respectively. Negative charge at the CK2/CK1 target serine residues facilitates optimal nuclear accumulation of ppUL44, whereas negative charge on T427, a potential cyclin-dependent 1 phosphorylation site, strongly decreases nuclear accumulation. Thus, nuclear transport of ppUL44 is finely tuned during viral infection through complex phosphorylation events.

  19. Nuclear magnetic resonance relaxation in multiple sclerosis

    DEFF Research Database (Denmark)

    Larsson, H B; Barker, G J; MacKay, A

    1998-01-01

    OBJECTIVES: The theory of relaxation processes and their measurements are described. An overview is presented of the literature on relaxation time measurements in the normal and the developing brain, in experimental diseases in animals, and in patients with multiple sclerosis. RESULTS...... AND CONCLUSION: Relaxation time measurements provide insight into development of multiple sclerosis plaques, especially the occurrence of oedema, demyelination, and gliosis. There is also evidence that normal appearing white matter in patients with multiple sclerosis is affected. What is now needed are fast...

  20. Nuclear process heat

    International Nuclear Information System (INIS)

    Barnert, H.; Hohn, H.; Schad, M.; Schwarz, D.; Singh, J.

    1993-01-01

    In a system for the application of high temperature heat from the HTR one must distinguish between the current generation and the use of process heat. In this respect it is important that the current can be generated by dual purpose power plants. The process heat is used as sensible heat, vaporisation heat and as chemical energy at the chemical conversion for the conversion of raw materials, the refinement of fossil primary energy carriers and finally circuit processes for the fission of water. These processes supply the market for heat, fuels, motor fuels and basic materials. Fifteen examples of HTR heat processes from various projects and programmes are presented in form of energy balances, however in a rather short way. (orig./DG) [de

  1. Multistep processes in nuclear reactions

    International Nuclear Information System (INIS)

    Hodgson, P.E.

    1988-01-01

    The theories of nuclear reactions are reviewed with particular attention to the recent work on multistep processes. The evidence for compound nucleus and direct interaction reactions is described together with the results of comparisons between theories and experimental data. These theories have now proved inadequate, and there is evidence for multistep processes that take place after the initial direct stage but long before the attainment of the statistical equilibrium characteristic of compound nucleus processes. The theories of these reactions are described and it is shown how they can account for the experimental data and thus give a comprehensive understanding of nuclear reactions. (author)

  2. Mean associated multiplicities in deep inelastic processes

    International Nuclear Information System (INIS)

    Dzhaparidze, G.Sh.; Kiselev, A.V.; Petrov, V.A.

    1982-01-01

    A formula is derived for the mean hadron multiplicity in the target fragmentation range of deep inelastic scattering processes. It is shown that in the high-x region the ratio of the mean multiplicities in the current fragmentation region and in the target fragmentation region tends to unity at high energies. The mean multiplicity for the Drell-Yan process is considered

  3. Random processes in nuclear reactors

    CERN Document Server

    Williams, M M R

    1974-01-01

    Random Processes in Nuclear Reactors describes the problems that a nuclear engineer may meet which involve random fluctuations and sets out in detail how they may be interpreted in terms of various models of the reactor system. Chapters set out to discuss topics on the origins of random processes and sources; the general technique to zero-power problems and bring out the basic effect of fission, and fluctuations in the lifetime of neutrons, on the measured response; the interpretation of power reactor noise; and associated problems connected with mechanical, hydraulic and thermal noise sources

  4. Multiple microprocessor based nuclear reactor power monitor

    International Nuclear Information System (INIS)

    Lewis, P.S.; Ethridge, C.D.

    1979-01-01

    The reactor power monitor is a portable multiple-microprocessor controlled data acquisition device being built for the International Atomic Energy Association. Its function is to measure and record the hourly integrated operating thermal power level of a nuclear reactor for the purpose of detecting unannounced plutonium production. The monitor consists of a 3 He proportional neutron detector, a write-only cassette tape drive and control electronics based on two INTEL 8748 microprocessors. The reactor power monitor operates from house power supplied by the plant operator, but has eight hours of battery backup to cover power interruptions. Both the hourly power levels and any line power interruptions are recorded on tape and in memory. Intermediate dumps from the memory to a data terminal or strip chart recorder can be performed without interrupting data collection

  5. Very high multiplicity hadron processes

    International Nuclear Information System (INIS)

    Mandzhavidze, I.; Sisakyan, A.

    2000-01-01

    The paper contains a description of a first attempt to understand the extremely inelastic high energy hadron collisions, when the multiplicity of produced hadrons considerably exceeds its mean value. Problems with existing model predictions are discussed. The real-time finite-temperature S-matrix theory is built to have a possibility to find model-free predictions. This allows one to include the statistical effects into consideration and build the phenomenology. The questions to experiment are formulated at the very end of the paper

  6. Cumulative effect in multiple production processes on nuclei

    International Nuclear Information System (INIS)

    Golubyatnikova, E.S.; Shmonin, V.L.; Kalinkin, B.N.

    1989-01-01

    It is shown that the cumulative effect is a natural result of the process of hadron multiple production in nuclear reactions. Interpretation is made of the universality of slopes of inclusive spectra and other characteristics of cumulative hadrons. The character of information from such reactions is discussed, which could be helpful in studying the mechanism of multiparticle production. 27 refs.; 4 figs

  7. Mean associated multiplicities in deep inelastic processes

    International Nuclear Information System (INIS)

    Dzhaparidze, G.S.; Kiselev, A.V.; Petrov, V.A.

    1982-01-01

    A formula is derived for the mean multiplicity of hadrons in the target-fragmentation region in the process of deep inelastic scattering. It is shown that in the region of large x the ratio of the mean multiplicities in the current- and target-fragmentation regions tends to unity at high energies. The mean multiplicity in the Drell-Yan process is also discussed

  8. Nuclear energy and process heating

    Energy Technology Data Exchange (ETDEWEB)

    Kozier, K.S

    1999-10-01

    Nuclear energy generated in fission reactors is a versatile commodity that can, in principle, satisfy any and all of mankind's energy needs through direct or indirect means. In addition to its dominant current use for electricity generation and, to a lesser degree, marine propulsion, nuclear energy can and has been used for process heat applications, such as space heating, industrial process heating and seawater desalination. Moreover, a wide variety of reactor designs has been employed to this end in a range of countries. From this spectrum of experience, two design approaches emerge for nuclear process heating (NPH): extracting a portion of the thermal energy from a nuclear power plant (NPP) (i.e., creating a combined heat and power, or CHP, plant) and transporting it to the user, or deploying dedicated nuclear heating plants (NHPs) in generally closer proximity to the thermal load. While the former approach is the basis for much of the current NPH experience, considerable recent interest exists for the latter, typically involving small, innovative reactor plants with enhanced and passive safety features. The high emphasis on inherent nuclear safety characteristics in these reactor designs reflects the need to avoid any requirement for evacuation of the public in the event of an accident, and the desire for sustained operation and investment protection at minimum cost. Since roughly 67% of mankind's primary energy usage is not in the form of electricity, a vast potential market for NPH systems exists, particularly at the low-to-moderate end-use temperatures required for residential space heating and several industrial applications. Although only About 0.5% of global nuclear energy production is presently used for NPH applications, an expanded role in the 21st century seems inevitable, in part, as a measure to reduce greenhouse gas emissions and improve air quality. While the technical aspects of many NPH applications are considered to be well proven, a

  9. Nuclear energy and process heating

    International Nuclear Information System (INIS)

    Kozier, K.S.

    1999-10-01

    Nuclear energy generated in fission reactors is a versatile commodity that can, in principle, satisfy any and all of mankind's energy needs through direct or indirect means. In addition to its dominant current use for electricity generation and, to a lesser degree, marine propulsion, nuclear energy can and has been used for process heat applications, such as space heating, industrial process heating and seawater desalination. Moreover, a wide variety of reactor designs has been employed to this end in a range of countries. From this spectrum of experience, two design approaches emerge for nuclear process heating (NPH): extracting a portion of the thermal energy from a nuclear power plant (NPP) (i.e., creating a combined heat and power, or CHP, plant) and transporting it to the user, or deploying dedicated nuclear heating plants (NHPs) in generally closer proximity to the thermal load. While the former approach is the basis for much of the current NPH experience, considerable recent interest exists for the latter, typically involving small, innovative reactor plants with enhanced and passive safety features. The high emphasis on inherent nuclear safety characteristics in these reactor designs reflects the need to avoid any requirement for evacuation of the public in the event of an accident, and the desire for sustained operation and investment protection at minimum cost. Since roughly 67% of mankind's primary energy usage is not in the form of electricity, a vast potential market for NPH systems exists, particularly at the low-to-moderate end-use temperatures required for residential space heating and several industrial applications. Although only About 0.5% of global nuclear energy production is presently used for NPH applications, an expanded role in the 21st century seems inevitable, in part, as a measure to reduce greenhouse gas emissions and improve air quality. While the technical aspects of many NPH applications are considered to be well proven, a determined

  10. Process industry properties in nuclear industry

    International Nuclear Information System (INIS)

    Zheng Hualing

    2005-01-01

    In this article the writer has described the definition of process industry, expounded the fact classifying nuclear industry as process industry, compared the differences between process industry and discrete industry, analysed process industry properties in nuclear industry and their important impact, and proposed enhancing research work on regularity of process industry in nuclear industry. (authors)

  11. Fragmentation processes in nuclear reactions

    International Nuclear Information System (INIS)

    Legrain, R.

    1984-08-01

    Projectile and nuclear fragmentation are defined and processes referred to are recalled. The two different aspects of fragmentation are considered but the emphasis is also put on heavy ion induced reactions. The preliminary results of an experiment performed at GANIL to study peripheral heavy ions induced reactions at intermediate energy are presented. The results of this experiment will illustrate the characteristics of projectile fragmentation and this will also give the opportunity to study projectile fragmentation in the transition region. Then nuclear fragmentation is considered which is associated with more central collisions in the case of heavy ion induced reactions. This aspect of fragmentation is also ilustrated with two heavy ion experiments in which fragments emitted at large angle have been observed

  12. Management of the process of nuclear transport

    International Nuclear Information System (INIS)

    Requejo, P.

    2015-01-01

    Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

  13. Parallel processing in nuclear applications

    International Nuclear Information System (INIS)

    Muniz, Francisco Junqueira

    1995-01-01

    This paper summarizes some investigations on effective and scalable dynamic load-balancing mechanisms suitable for distributed-memory (loosely-coupled) MIMD systems. The selected implementation environment is composed of T800 transputers programed in the occam and C languages and an automatic routing package communication software mechanism (the virtual channel router). Tasks were generated, at execution time, using a multiple-spawning mechanism based on a set of remote procedure calls primitives. The objective is to improve maximum resource utilization. In particular, the investigation described here facilitate portability of the user application, since it concentrates on system-level load balancing mechanisms. The load-balancing mechanisms studies are also suitable for systems that can vary in size, concentrating on methods with potential for scalability. Two possible application examples, chosen from the nuclear area, where distributed-memory MIMD machines can be utilized, are mentioned. (author). 24 refs., 1 fig

  14. Membrane processes in nuclear technologies

    International Nuclear Information System (INIS)

    Zakrzewska-Trznadel, G.

    2006-01-01

    The treatment of radioactive wastes is necessary taking into account the potential hazard of radioactive substances to human health and surrounding environment. The choice of appropriate technology depends on capital and operational costs, wastes amount and their characteristics, appointed targets of the process, e.g. the values of decontamination factors and volume reduction coefficients. The conventional technologies applied for radioactive waste processing, such as precipitation coupled with sedimentation, ion exchange and evaporation have many drawbacks. These include high energy consumption and formation of secondary wastes, e.g. the sludge from sediment tanks, spent ion exchange adsorbents and regeneration solutions. There are also many limitations of such processes, i.e. foaming and drop entrainment in evaporators, loses of solvents and production of secondary wastes in solvent extraction or bed clogging in ion exchange columns. Membrane processes as the newest achievement of the process engineering can successfully supersede many non-effective, out-of-date methods. But in some instances they can also complement these methods whilst improving the parameters of effluents and purification economy. This monograph presents own research data on the application of recent achievements in the area of membrane processes for solving selected problems in nuclear technology. Relatively big space was devoted to the use of membrane processing of low and intermediate radioactive liquid wastes because of numerous applications of these processes in nuclear centres over the world and also because of the interests of the author that was reflected by her recent research projects and activity. This work presents a review on the membrane methods recently introduced into the nuclear technology against the background of the other, commonly applied separation techniques, with indications of the possibilities and prospects for their further developments. Particular attention was paid

  15. Fragmentation processes in nuclear reactions

    International Nuclear Information System (INIS)

    Baur, G.; Roesel, F.; Trautmann, D.; Shyam, R.

    1983-10-01

    Fragmentation processes in nuclear collisions are reviewed. The main emphasis is put on light ion breakup at nonrelativistic energies. The post- and prior-form DWBA theories are discussed. The post-form DWBA, appropriate for the ''spectator breakup'' describes elastic as well as inelastic breakup modes. This theory can also account for the stripping to unbound states. The theoretical models are compared to typical experimental results to illustrate the various possible mechanisms. It is discussed, how breakup reactions can be used to study high-lying single particle strength in the continuum; how it can yield information about momentum distributions of fragments in the nucleus. (orig.)

  16. Nuclear winter: Global consequences of multiple nuclear explosions

    International Nuclear Information System (INIS)

    Turco, R.P.; Toon, O.B.; Ackerman, T.P.; Pollack, J.B.; Sagan, C.

    1984-01-01

    Concern has been raised over the short- and long-term consequences of the dust, smoke, radioactivity, and toxic vapors that would be generated by a nuclear war. The discovery that dense clouds of soil particles may have played a major role in past mass extinctions of life on Earth has encouraged the reconsideration of nuclear war effects. These developments have led the authors to calculate, using new data and improved models, the potential global environmental effects of dust and smoke clouds (henceforth referred to as nuclear dust and smoke) generated in a nuclear war. They neglect the short-term effects of blast, fire, and radiation. Most of the world's population could probably survive the initial nuclear exchange and would inherit the postwar environment. Accordingly, the longer-term and global-scale aftereffects of nuclear war might prove to be as important as the immediate consequences of the war

  17. Evaluation and processing of nuclear data

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1981-01-01

    The role a nuclear data evaluator plays in obtaining evaluated nuclear data, needed for applications, from measured nuclear data is surveyed. Specific evaluation objectives, problems, and procedures are discussed. The use of nuclear systematics to complement nuclear experiment and theory is described. Using the Evaluated Nuclear Data File (ENDF) as an example the formatting, checking, and processing of nuclear data is discussed as well as the testing of evaluated nuclear data in the calculation of integral benchmark experiments. Other important topics such as the Probability Table Method and interrelation between differential and integral data are also discussed. (author)

  18. Evaluation and processing of nuclear data

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1980-01-01

    The role a nuclear data evaluator plays in obtaining evaluated nuclear data, needed for applications, from measured nuclear data is surveyed. Specific evaluation objectives, problems, and procedures are discussed. The use of nuclear systematics to complement nuclear experiment and theory is described. With the Evaluated Nuclear Data File (ENDF) as an example, the formatting, checking, and processing of nuclear data are discussed as well as the testing of evaluated nuclear data in the calculation of integral benchmark experiments. Other important topics such as the Probability Table Method and interrelation between differential and integral data are also discussed. 25 figures

  19. Multiple photon infrared processes in polyatomic molecules

    International Nuclear Information System (INIS)

    Harrison, R.G.; Butcher, S.R.

    1980-01-01

    This paper reviews current understanding of the process of multiple photon excitation and dissociation of polyatomic molecules, whereby in the presence of an intense infrared laser field a molecule may absorb upwards of 30 photons. The application of this process to new photochemistry and in particular laser isotope separation is also discussed. (author)

  20. Nuclear processing during star formation

    International Nuclear Information System (INIS)

    Newman, M.J.

    1978-01-01

    A preliminary survey was conducted of the thermonuclear energy release expected during star formation. The destruction of primordial deuterium provides substantial amounts of energy at surprisingly low temperatures, and must be considered in any meaningful treatment of star formation carried to stages in which the internal temperature exceeds a few hundred thousand degrees. Significant energy generation from consumption of initial lithium requires higher temperatures, of the order of a few million degrees. Depletion of primordial beryllium and boron may never provide an important energy source. The approach to equilibrium of the carbon--nitrogen cycle is dominant at temperatures approaching those characteristic of the central regions of main sequence stars. The present calculation should serve as a useful guide in choosing those nuclear processes to be included in a more detailed study. 8 figures, 2 tables

  1. Binaural Processing of Multiple Sound Sources

    Science.gov (United States)

    2016-08-18

    AFRL-AFOSR-VA-TR-2016-0298 Binaural Processing of Multiple Sound Sources William Yost ARIZONA STATE UNIVERSITY 660 S MILL AVE STE 312 TEMPE, AZ 85281...18-08-2016 2. REPORT TYPE Final Performance 3. DATES COVERED (From - To) 15 Jul 2012 to 14 Jul 2016 4. TITLE AND SUBTITLE Binaural Processing of...three topics cited above are entirely within the scope of the AFOSR grant. 15. SUBJECT TERMS Binaural hearing, Sound Localization, Interaural signal

  2. Nuclear fuel cycle, nuclear fuel makes the rounds: choosing a closed fuel cycle, nuclear fuel cycle processes, front-end of the fuel cycle: from crude ore to enriched uranium, back-end of the fuel cycle: the second life of nuclear fuel, and tomorrow: multiple recycling while generating increasingly less waste

    International Nuclear Information System (INIS)

    Philippon, Patrick

    2016-01-01

    France has opted for a policy of processing and recycling spent fuel. This option has already been deployed commercially since the 1990's, but will reach its full potential with the fourth generation. The CEA developed the processes in use today, and is pursuing research to improve, extend, and adapt these technologies to tomorrow's challenges. France has opted for a 'closed cycle' to recycle the reusable materials in spent fuel (uranium and plutonium) and optimise ultimate waste management. France has opted for a 'closed' nuclear fuel cycle. Spent fuel is processed to recover the reusable materials: uranium and plutonium. The remaining components (fission products and minor actinides) are the ultimate waste. This info-graphic shows the main steps in the fuel cycle currently implemented commercially in France. From the mine to the reactor, a vast industrial system ensures the conversion of uranium contained in the ore to obtain uranium oxide (UOX) fuel pellets. Selective extraction, purification, enrichment - key scientific and technical challenges for the teams in the Nuclear Energy Division (DEN). The back-end stages of the fuel cycle for recycling the reusable materials in spent fuel and conditioning the final waste-forms have reached maturity. CEA teams are pursuing their research in support of industry to optimise these processes. Multi-recycle plutonium, make even better use of uranium resources and, over the longer term, explore the possibility of transmuting the most highly radioactive waste: these are the challenges facing future nuclear systems. (authors)

  3. Metabonomics for detection of nuclear materials processing.

    Energy Technology Data Exchange (ETDEWEB)

    Alam, Todd Michael; Luxon, Bruce A. (University Texas Medical Branch); Neerathilingam, Muniasamy (University Texas Medical Branch); Ansari, S. (University Texas Medical Branch); Volk, David (University Texas Medical Branch); Sarkar, S. (University Texas Medical Branch); Alam, Mary Kathleen

    2010-08-01

    Tracking nuclear materials production and processing, particularly covert operations, is a key national security concern, given that nuclear materials processing can be a signature of nuclear weapons activities by US adversaries. Covert trafficking can also result in homeland security threats, most notably allowing terrorists to assemble devices such as dirty bombs. Existing methods depend on isotope analysis and do not necessarily detect chronic low-level exposure. In this project, indigenous organisms such as plants, small mammals, and bacteria are utilized as living sensors for the presence of chemicals used in nuclear materials processing. Such 'metabolic fingerprinting' (or 'metabonomics') employs nuclear magnetic resonance (NMR) spectroscopy to assess alterations in organismal metabolism provoked by the environmental presence of nuclear materials processing, for example the tributyl phosphate employed in the processing of spent reactor fuel rods to extract and purify uranium and plutonium for weaponization.

  4. Metabonomics for detection of nuclear materials processing

    International Nuclear Information System (INIS)

    Alam, Todd Michael; Luxon, Bruce A.; Neerathilingam, Muniasamy; Ansari, S.; Volk, David; Sarkar, S.; Alam, Mary Kathleen

    2010-01-01

    Tracking nuclear materials production and processing, particularly covert operations, is a key national security concern, given that nuclear materials processing can be a signature of nuclear weapons activities by US adversaries. Covert trafficking can also result in homeland security threats, most notably allowing terrorists to assemble devices such as dirty bombs. Existing methods depend on isotope analysis and do not necessarily detect chronic low-level exposure. In this project, indigenous organisms such as plants, small mammals, and bacteria are utilized as living sensors for the presence of chemicals used in nuclear materials processing. Such 'metabolic fingerprinting' (or 'metabonomics') employs nuclear magnetic resonance (NMR) spectroscopy to assess alterations in organismal metabolism provoked by the environmental presence of nuclear materials processing, for example the tributyl phosphate employed in the processing of spent reactor fuel rods to extract and purify uranium and plutonium for weaponization.

  5. Multiple scattering processes: inverse and direct

    International Nuclear Information System (INIS)

    Kagiwada, H.H.; Kalaba, R.; Ueno, S.

    1975-01-01

    The purpose of the work is to formulate inverse problems in radiative transfer, to introduce the functions b and h as parameters of internal intensity in homogeneous slabs, and to derive initial value problems to replace the more traditional boundary value problems and integral equations of multiple scattering with high computational efficiency. The discussion covers multiple scattering processes in a one-dimensional medium; isotropic scattering in homogeneous slabs illuminated by parallel rays of radiation; the theory of functions b and h in homogeneous slabs illuminated by isotropic sources of radiation either at the top or at the bottom; inverse and direct problems of multiple scattering in slabs including internal sources; multiple scattering in inhomogeneous media, with particular reference to inverse problems for estimation of layers and total thickness of inhomogeneous slabs and to multiple scattering problems with Lambert's law and specular reflectors underlying slabs; and anisotropic scattering with reduction of the number of relevant arguments through axially symmetric fields and expansion in Legendre functions. Gaussian quadrature data for a seven point formula, a FORTRAN program for computing the functions b and h, and tables of these functions supplement the text

  6. Phase transitions in multiplicative competitive processes

    International Nuclear Information System (INIS)

    Shimazaki, Hideaki; Niebur, Ernst

    2005-01-01

    We introduce a discrete multiplicative process as a generic model of competition. Players with different abilities successively join the game and compete for finite resources. Emergence of dominant players and evolutionary development occur as a phase transition. The competitive dynamics underlying this transition is understood from a formal analogy to statistical mechanics. The theory is applicable to bacterial competition, predicting novel population dynamics near criticality

  7. Nuclear Winter: Global Consequences of Multiple Nuclear Explosions

    Science.gov (United States)

    Turco, R. P.; Toon, O. B.; Ackerman, T. P.; Pollack, J. B.; Sagan, Carl

    1983-12-01

    The potential global atmospheric and climatic consequences of nuclear war are investigated using models previously developed to study the effects of volcanic eruptions. Although the results are necessarily imprecise, due to a wide range of possible scenarios and uncertainty in physical parameters, the most probable first-order effects are serious. Significant hemispherical attenuation of the solar radiation flux and subfreezing land temperatures may be caused by fine dust raised in high-yield nuclear surface bursts and by smoke from city and forest fires ignited by airbursts of all yields. For many simulated exchanges of several thousand megatons, in which dust and smoke are generated and encircle the earth within 1 to 2 weeks, average light levels can be reduced to a few percent of ambient and land temperatures can reach -15 degrees to -25 degrees C. The yield threshold for major optical and climatic consequences may be very low: only about 100 megatons detonated over major urban centers can create average hemispheric smoke optical depths greater than 2 for weeks and, even in summer, subfreezing land temperatures for months. In a 5000-megaton war, at northern mid-latitude sites remote from targets, radioactive fallout on time scales of days to weeks can lead to chronic mean doses of up to 50 rads from external whole-body gamma-ray exposure, with a likely equal or greater internal dose from biologically active radionuclides. Large horizontal and vertical temperature gradients caused by absorption of sunlight in smoke and dust clouds may greatly accelerate transport of particles and radioactivity from the Northern Hemisphere to the Southern Hemisphere. When combined with the prompt destruction from nuclear blast, fires, and fallout and the later enhancement of solar ultraviolet radiation due to ozone depletion, long-term exposure to cold, dark, and radioactivity could pose a serious threat to human survivors and to other species.

  8. Video image processing for nuclear safeguards

    International Nuclear Information System (INIS)

    Rodriguez, C.A.; Howell, J.A.; Menlove, H.O.; Brislawn, C.M.; Bradley, J.N.; Chare, P.; Gorten, J.

    1995-01-01

    The field of nuclear safeguards has received increasing amounts of public attention since the events of the Iraq-UN conflict over Kuwait, the dismantlement of the former Soviet Union, and more recently, the North Korean resistance to nuclear facility inspections by the International Atomic Energy Agency (IAEA). The role of nuclear safeguards in these and other events relating to the world's nuclear material inventory is to assure safekeeping of these materials and to verify the inventory and use of nuclear materials as reported by states that have signed the nuclear Nonproliferation Treaty throughout the world. Nuclear safeguards are measures prescribed by domestic and international regulatory bodies such as DOE, NRC, IAEA, and EURATOM and implemented by the nuclear facility or the regulatory body. These measures include destructive and non destructive analysis of product materials/process by-products for materials control and accountancy purposes, physical protection for domestic safeguards, and containment and surveillance for international safeguards

  9. Oil shales and the nuclear process heat

    International Nuclear Information System (INIS)

    Scarpinella, C.A.

    1974-01-01

    Two of the primary energy sources most dited as alternatives to the traditional fossil fuels are oil shales and nuclear energy. Several proposed processes for the extraction and utilization of oil and gas from shale are given. Possible efficient ways in which nuclear heat may be used in these processes are discussed [pt

  10. Method for processing spent nuclear reactor fuel

    International Nuclear Information System (INIS)

    Levenson, M.; Zebroski, E.L.

    1981-01-01

    A method and apparatus are claimed for processing spent nuclear reactor fuel wherein plutonium is continuously contaminated with radioactive fission products and diluted with uranium. Plutonium of sufficient purity to fabricate nuclear weapons cannot be produced by the process or in the disclosed reprocessing plant. Diversion of plutonium is prevented by radiation hazards and ease of detection

  11. Research on neutron source multiplication method in nuclear critical safety

    International Nuclear Information System (INIS)

    Zhu Qingfu; Shi Yongqian; Hu Dingsheng

    2005-01-01

    The paper concerns in the neutron source multiplication method research in nuclear critical safety. Based on the neutron diffusion equation with external neutron source the effective sub-critical multiplication factor k s is deduced, and k s is different to the effective neutron multiplication factor k eff in the case of sub-critical system with external neutron source. The verification experiment on the sub-critical system indicates that the parameter measured with neutron source multiplication method is k s , and k s is related to the external neutron source position in sub-critical system and external neutron source spectrum. The relation between k s and k eff and the effect of them on nuclear critical safety is discussed. (author)

  12. The enactment of the Nuclear Waste Policy Act of 1982: A multiple perspectives explanation

    International Nuclear Information System (INIS)

    Clary, B.B.

    1991-01-01

    The Nuclear Waste Policy Act (NWPA) is generally analyzed from the distinct perspective of any given actor involved in the nuclear waste policymaking process. Yet, these perspectives often rest on totally different models of decisionmaking. This article applies a multiple perspective explanation as developed by Allison (1971) and Linstone (1984) to the NWPA and explains policy outcomes by reference to three models of decisionmaking: rational actor, organizational processes and governmental politics. Commonalities and points of disjointure in the three models are highlighted and prospects for future nuclear waste disposal policy development are assessed using an integrated decisionmaking framework

  13. The probabilities of nuclear processes

    International Nuclear Information System (INIS)

    Sanchez del Rio, C.

    1972-01-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  14. Nuclear Data Processing for Reactor Physics Calculation

    International Nuclear Information System (INIS)

    Suwoto; Zuhair; Pandiangan, Tumpal

    2003-01-01

    Nuclear data processing for reactor physics calculation has been done. Raw nuclear data cross-sections on file ENDF should be prepared and processed before it used in neutronic calculation. The processing code system such as NJOY-PC code has been used from linearization of nuclear cross-sections data and background contribution of resonance parameter (MF2) using RECONR module (0K) with energy range from 10 -5 to 10 7 eV. Afterward, the neutron cross-sections data should be processed and broadened to desire temperature (i.e. 293K) by using BROADR module. The Grouper and Therma modules will be applied for multi-groups calculation which suitable for WIMS/D4 (69 groups) and thermalization of nuclear constants. The final stage of processing nuclear cross-sections is updating WIMS/D4 library. The WIMSR module in NJOY-PC and WILLIE code will be applied in this stage. The evaluated nuclear data file, especially for 1 H 1 isotope, was taken from JENDL-3.2 and ENDF/B-VI for preliminary study. The results of nuclear data processing 1 H 1 shows that the old-WIMS (WIMS-lama) library have much discrepancies comparing with JENDL-3.2 or ENDF/B-VI files, especially in energy around 5 keV

  15. The licensing processes influence on nuclear market

    International Nuclear Information System (INIS)

    Locatelli, Giorgio; Mancini, Mauro; Sainati, Tristano; Sallinen, Liisa

    2011-01-01

    The paper deals with the licensing nuclear power plants; it focuses primarily on the licensing process implications into the international nuclear market. Nowadays there are twenty-six countries that are planning to build new nuclear facilities, and thirty-seven where nuclear reactors are proposed; on the other hand, there are mainly ten international reactor vendors. At international level, there are few vendors that have sufficient resources, capabilities and experience to carry out the design and delivering of a nuclear power plant in the international market; On the other hand, the licensing processes are strictly dependent on national law frameworks, and on the nuclear policies. The paper proposes a comparison of six licensing processes (the ones established in Finland, France, Italy, South Korea, USA and UK), and analyzes its main features and implications; the IAEA licensing process is taken as reference point. The objective of the paper is to propose a systemic approach for considering the licensing procedures. The framework proposed enables facilitating the licensing management and inferring the main features of licensing contexts. The paper concludes with a forecast of the nuclear licensing context, especially with respect to the fourth generation of nuclear reactors. (author)

  16. NJOY nuclear data processing system: user's manual

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Barrett, R.J.; Muir, D.W.; Boicourt, R.M.

    1978-12-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections for neutron and photon transport calculations from ENDF/B-IV and -V evaluated nuclear data. This user's manual provides a concise description of the code, input instructions, sample problems, and installation instructions. 1 figure, 3 tables

  17. Alarm-Processing in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Otazo, J; Fernandez, R

    2000-01-01

    Information overload due to the activation of a great number of alarms in a short time is a common problem for the operator in the control room of a industrial plant, mainly in complex process like the nuclear power plants.The problem is the conventional conception of the alarm system, that defines each alarm like a separated and independent entity of the global situation of the plant.A direct consequence is the generation of multiple alarms during a significative disturbance in the process, being most of them redundant and irrelevant to the actual process state wich involves an extra load to the operator, who wastes time in acting selecting the important alarms of the group that appears or lead to a an erroneous action.The present work first describes the techniques developed in the last years to attack the avalanche of alarms problem.Later we present our approach to alarm-processing: an expert system as alarm-filter.Our objective is collect in the system the state of the art in the development of advanced alarm systems, offering an improvement of the information flow to the operators through the suppression of nonsignificant alarms and a structured visualization of the process state.Such support is important during a disturbance for the identification of plant state, diagnosis, consequence prediction and corrective actions.The system is arranged in three stages: alarm-generation, alarm-filter and alarm-presentation.The alarm-generation uses conventional techniques or receives them from an external system.The alarm-filter uses suppression techniques based on: irrelevance analysis with the operation mode and the state of components, causal reasoning and static importance analysis.The alarm presentation is made through a structured way using a priority scheme with three level.The knowledge representation of each alarm is based on frames and a graph of alarms for global knowledge, where the connections between nodes represent causal and irrelevance relations

  18. Image processing technology for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Beom; Kim, Woong Ki; Park, Soon Young

    1993-05-01

    Digital image processing technique is being actively studied since microprocessors and semiconductor memory devices have been developed in 1960's. Now image processing board for personal computer as well as image processing system for workstation is developed and widely applied to medical science, military, remote inspection, and nuclear industry. Image processing technology which provides computer system with vision ability not only recognizes nonobvious information but processes large information and therefore this technique is applied to various fields like remote measurement, object recognition and decision in adverse environment, and analysis of X-ray penetration image in nuclear facilities. In this report, various applications of image processing to nuclear facilities are examined, and image processing techniques are also analysed with the view of proposing the ideas for future applications. (Author)

  19. The cause multiplicity and the multiple cause style of adverse events in Japanese nuclear power plants

    International Nuclear Information System (INIS)

    Miyazaki, Takamasa

    2008-01-01

    An adverse event in a nuclear power plant occurs due to either one cause or multiple causes. To consider ways of preventing adverse events, it is useful to clarify whether events are caused by single or multiple causes. In this study, the multiple causes is expressed using the cause multiplicity and the multiple cause style. Classified causes of adverse events in Japanese nuclear power plants were analyzed, with the following results: the cause multiplicity of serious adverse events is higher than that of minor adverse events, and the multiple cause style can be expressed by combining two styles: series type and parallel type. Also, for a multiple cause event, a new method of displaying the event is presented as a cause-chain chart where the cause items are arranged in a sequential way and are connected considering the mutual relations among the causes. This new display method shows the whole flow of issues concerning the event more simply than the conventional display method of the chain of phenomena, and would be useful for considering the terminating point of the chain of causes. (author)

  20. Process information systems in nuclear reprocessing

    International Nuclear Information System (INIS)

    Jaeschke, A.; Keller, H.; Orth, H.

    1987-01-01

    On a production management level, a process information system in a nuclear reprocessing plant (NRP) has to fulfill conventional operating functions and functions for nuclear material surveillance (safeguards). Based on today's state of the art of on-line process control technology, the progress in hardware and software technology allows to introduce more process-specific intelligence into process information systems. Exemplified by an expert-system-aided laboratory management system as component of a NRP process information system, the paper demonstrates that these technologies can be applied already. (DG) [de

  1. Developments in quantum information processing by nuclear ...

    Indian Academy of Sciences (India)

    qubits, the 2n energy levels of the spin-system can be treated as an n-qubit system. ... Quantum information processing; qubit; nuclear magnetic resonance quantum comput- ing. ..... The equilibrium spectrum has theoretical intensities in the ra-.

  2. High temperature nuclear process heat systems for chemical processes

    International Nuclear Information System (INIS)

    Jiacoletti, R.J.

    1976-01-01

    The development planning and status of the very high temperature gas cooled reactor as a source of industrial process heat is presented. The dwindling domestic reserves of petroleum and natural gas dictate major increases in the utilization of coal and nuclear sources to meet the national energy demand. The nuclear process heat system offers a unique combination of the two that is environmentally and economically attractive and technically sound. Conceptual studies of several energy-intensive processes coupled to a nuclear heat source are presented

  3. Nuclear process steam for industry

    International Nuclear Information System (INIS)

    Seddon, W.A.

    1981-11-01

    A joint industrial survey funded by the Bruce County Council, the Ontario Energy Corporation and Atomic Energy of Canada Limited was carried out with the cooperation of Ontario Hydro and the Ontario Ministry of Industry and Tourism. Its objective was to identify and assess the future needs and interest of energy-intensive industries in an Industrial Energy Park adjacent to the Bruce Nuclear Power Development. The Energy Park would capitalize on the infrastructure of the existing CANDU reactors and Ontario Hydro's proven and unique capability to produce steam, as well as electricity, at a cost currently about half that from a comparable coal-fired station. Four industries with an integrated steam demand of some 1 x 10 6 lb/h were found to be prepared to consider seriously the use of nuclear steam. Their combined plants would involve a capital investment of over $200 million and provide jobs for 350-400 people. The high costs of transportation and the lack of docking facilities were considered to be the major drawbacks of the Bruce location. An indication of steam prices would be required for an over-all economic assessment

  4. Automated processing of nuclear materials accounting data

    International Nuclear Information System (INIS)

    Straka, J.; Pacak, P.; Moravec, J.

    1980-01-01

    An automated system was developed of nuclear materials accounting in Czechoslovakia. The system allows automating data processing including data storage. It comprises keeping records of inventories and material balance. In designing the system, the aim of the IAEA was taken into consideration, ie., building a unified information system interconnected with state-run systems of accounting and checking nuclear materials in the signatory countries of the non-proliferation treaty. The nuclear materials accounting programs were written in PL-1 and were tested at an EC 1040 computer at UJV Rez where also the routine data processing takes place. (B.S.)

  5. Process for producing nuclear reactor fuel oxides

    International Nuclear Information System (INIS)

    Goenrich, H.; Druckenbrodt, W.G.

    1981-01-01

    The waste gases of the calcination process furnace in the AVC or AV/PuC process (manufacture of nuclear reactor fuel dioxides) are returned to the furnace in a closed circuit. The NH 3 produced replaces the hydrogen which would otherwise be required for reduction in this process. (orig.) [de

  6. On Markov processes in the hadron-nuclear and nuclear-nuclear collisions at superhigh energies

    International Nuclear Information System (INIS)

    Lebedeva, A.A.; Rus'kin, V.I.

    2001-01-01

    In the article the possibility of the Markov processes use as simulation method for mean characteristics of hadron-nuclear and nucleus-nuclear collisions at superhigh energies is discussed. The simple (hadron-nuclear collisions) and non-simple (nucleus-nuclear collisions) non-uniform Markov process of output constant spectrum and absorption in a nucleon's nucleus-target with rapidity y are considered. The expression allowing to simulate the different collision modes were obtained

  7. Robot development for nuclear material processing

    International Nuclear Information System (INIS)

    Pedrotti, L.R.; Armantrout, G.A.; Allen, D.C.; Sievers, R.H. Sr.

    1991-07-01

    The Department of Energy is seeking to modernize its special nuclear material (SNM) production facilities and concurrently reduce radiation exposures and process and incidental radioactive waste generated. As part of this program, Lawrence Livermore National Laboratory (LLNL) lead team is developing and adapting generic and specific applications of commercial robotic technologies to SNM pyrochemical processing and other operations. A working gantry robot within a sealed processing glove box and a telerobot control test bed are manifestations of this effort. This paper describes the development challenges and progress in adapting processing, robotic, and nuclear safety technologies to the application. 3 figs

  8. Multiple scattering in the nuclear rearrangement reactions at medium energy

    International Nuclear Information System (INIS)

    Tekou, A.

    1980-09-01

    It is shown that the multiple scattering mechanism is very important in the transfer of the large momenta involved in the nuclear rearrangement reactions at medium energy. In contrast to the usual belief, the reaction cross-section is not very sensitive to the high momenta components of the nuclear wave function. The multiple scattering mechanism is especially important in 4 He(p,d) 3 He reaction around 800 MeV. Here the collisions involving two nucleons of the target nucleus are dominant. The triple collisions contribution is also important. The four collision contribution is negligible in the forward direction and sizeable at large angles. Thus, using the K.M.T. approach in DWBA calculations, the second order term of the optical potential must be included. So, is it not well established that the second term of the K.M.T. optical potential is important for the proton elastic scattering on light nuclei. (author)

  9. Process instrumentation for nuclear power station

    International Nuclear Information System (INIS)

    Yanai, Katsuya; Shinohara, Katsuhiko

    1978-01-01

    Nuclear power stations are the large scale compound system composed of many process systems. Accordingly, for the safe and high reliability operation of the plants, it is necessary to grasp the conditions of respective processes exactly and control the operation correctly. For this purpose, the process instrumentation undertakes the important function to monitor the plant operation. Hitachi Ltd. has exerted ceaseless efforts since long before to establish the basic technology for the process instrumentation in nuclear power stations, to develop and improve hardwares of high reliability, and to establish the quality control system. As for the features of the process instrumentation in nuclear power stations, the enormous quantity of measurement, the diversity of measured variables, the remote measurement and monitoring method, and the ensuring of high reliability are enumerated. Also the hardwares must withstand earthquakes, loss of coolant accidents, radiations, leaks and fires. Hitachi Unitrol Sigma Series is the measurement system which is suitable to the general process instrumentation in nuclear power stations, and satisfies sufficiently the basic requirements described above. It has various features as the nuclear energy system, such as high reliability by the use of ICs, the methods of calculation and transmission considering signal linkage, loop controller system and small size. HIACS-1000 Series is the analog controller of high reliability for water control. (Kako, I.)

  10. Processing of nuclear data - demonstrations

    International Nuclear Information System (INIS)

    Panini, G.C.

    1995-01-01

    Experimental data are not suitable for direct processing by computer codes. Data must be compiled in order to be compared, normalized, amended; gaps should be filled, differential data supplied. Evaluated data are given in a consistent computer readable format so as to facilitate the checking, the plotting, the comparison with the experimental source of the data. Processing codes have been developed for producing working libraries from the different sources. EXFOR is a complementary and essential tool for evaluators. It consists of a collection of experimental data in computer readable format. (R.P.)

  11. Hybrid models for the simulation of microstructural evolution influenced by coupled, multiple physical processes

    Energy Technology Data Exchange (ETDEWEB)

    Tikare, Veena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hernandez-Rivera, Efrain [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Madison, Jonathan D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Holm, Elizabeth Ann [Carnegie Mellon Univ., Pittsburgh, PA (United States); Patterson, Burton R. [Univ. of Florida, Gainesville, FL (United States). Dept. of Materials Science and Engineering; Homer, Eric R. [Brigham Young Univ., Provo, UT (United States). Dept. of Mechanical Engineering

    2013-09-01

    Most materials microstructural evolution processes progress with multiple processes occurring simultaneously. In this work, we have concentrated on the processes that are active in nuclear materials, in particular, nuclear fuels. These processes are coarsening, nucleation, differential diffusion, phase transformation, radiation-induced defect formation and swelling, often with temperature gradients present. All these couple and contribute to evolution that is unique to nuclear fuels and materials. Hybrid model that combines elements from the Potts Monte Carlo, phase-field models and others have been developed to address these multiple physical processes. These models are described and applied to several processes in this report. An important feature of the models developed are that they are coded as applications within SPPARKS, a Sandiadeveloped framework for simulation at the mesoscale of microstructural evolution processes by kinetic Monte Carlo methods. This makes these codes readily accessible and adaptable for future applications.

  12. Remote nuclear green pellet processing system

    International Nuclear Information System (INIS)

    Cellier, Francis.

    1980-01-01

    An automated system for manufacturing nuclear fuel pellets for use in nuclear fuel elements of nuclear power reactors is described. The system comprises process components arranged vertically but not directly under each other within a single enclosure. The vertical-lateral arrangement provides for gravity flow of the product from one component to the next and for removal of each component without interference with the other components. The single enclosure eliminates time consuming transfer between separate enclosures of each component while providing three-sided access to the component through glove ports. (auth)

  13. Radial pattern of nuclear decay processes

    International Nuclear Information System (INIS)

    Iskra, W.; Mueller, M.; Rotter, I.; Technische Univ. Dresden

    1994-05-01

    At high level density of nuclear states, a separation of different time scales is observed (trapping effect). We calculate the radial profile of partial widths in the framework of the continuum shell model for some 1 - resonances with 2p-2h nuclear structure in 16 O as a function of the coupling strength to the continuum. A correlation between the lifetime of a nuclear state and the radial profile of the corresponding decay process is observed. We conclude from our numerical results that the trapping effect creates structures in space and time characterized by a small radial extension and a short lifetime. (orig.)

  14. Efficient Processing of Multiple DTW Queries in Time Series Databases

    DEFF Research Database (Denmark)

    Kremer, Hardy; Günnemann, Stephan; Ivanescu, Anca-Maria

    2011-01-01

    . In many of today’s applications, however, large numbers of queries arise at any given time. Existing DTW techniques do not process multiple DTW queries simultaneously, a serious limitation which slows down overall processing. In this paper, we propose an efficient processing approach for multiple DTW...... for multiple DTW queries....

  15. NEA, Nuclear law and information processing

    International Nuclear Information System (INIS)

    Reyners, P.

    1977-01-01

    NEA has for many years now been collating information on, and analysing, laws and regulations on the peaceful uses of nuclear energy, and this work has resulted in a series of publications. However, as seen by the multiplication of computer-based legal information centres, both at national and international level, conventional information systems are no longer adequate to deal with the increasing volume of information and with users' needs. In view of the particular aspects of nuclear law and of its own availabilities, NEA has endeavoured to make the best possible use of existing structures by opting for participation in the IAEA International Nuclear Information System rather than by creating a specialised centre. Before becoming operational, the arrangements concluded between NEA and IAEA required that the INIS rules be altered somewhat to take account of the specific problems raised by treatment of legal literature and also to improve the quality of information provided to users. (auth.) [fr

  16. An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

    International Nuclear Information System (INIS)

    Warren, C.C.

    2010-01-01

    Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

  17. An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

    Energy Technology Data Exchange (ETDEWEB)

    Warren, C.C. [Nuclear Power Plants Operation Department, Slovenske Elektrarne, a.s., Mlynske nivy 47, 821 09 Bratislava (Slovakia)

    2010-07-01

    Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

  18. Exclusive hadronic and nuclear processes in QCD

    International Nuclear Information System (INIS)

    Brodsky, S.J.

    1985-12-01

    Hadronic and nuclear processes are covered, in which all final particles are measured at large invariant masses compared with each other, i.e., large momentum transfer exclusive reactions. Hadronic wave functions in QCD and QCD sum rule constraints on hadron wave functions are discussed. The question of the range of applicability of the factorization formula and perturbation theory for exclusive processes is considered. Some consequences of quark and gluon degrees of freedom in nuclei are discussed which are outside the usual domain of traditional nuclear physics. 44 refs., 7 figs

  19. Multiple paternity in reptiles: patterns and processes.

    Science.gov (United States)

    Uller, Tobias; Olsson, Mats

    2008-06-01

    The evolution of female promiscuity poses an intriguing problem as benefits of mating with multiple males often have to arise via indirect, genetic, effects. Studies on birds have documented that multiple paternity is common in natural populations but strong evidence for selection via female benefits is lacking. In an attempt to evaluate the evidence more broadly, we review studies of multiple paternity in natural populations of all major groups of nonavian reptiles. Multiple paternity has been documented in all species investigated so far and commonly exists in over 50% of clutches, with particularly high levels in snakes and lizards. Marine turtles and lizards with prolonged pair-bonding have relatively low levels of multiple paternity but levels are nevertheless higher than in many vertebrates with parental care. There is no evidence that high levels of polyandry are driven by direct benefits to females and the evidence that multiple paternity arises from indirect genetic benefits is weak. Instead, we argue that the most parsimonious explanation for patterns of multiple paternity is that it represents the combined effect of mate-encounter frequency and conflict over mating rates between males and females driven by large male benefits and relatively small female costs, with only weak selection via indirect benefits. A crucial step for researchers is to move from correlative approaches to experimental tests of assumptions and predictions of theory under natural settings, using a combination of molecular techniques and behavioural observations.

  20. Gas processing at DOE nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jacox, J.

    1995-02-01

    The term {open_quotes}Gas Processing{close_quotes} has many possible meanings and understandings. In this paper, and panel, we will be using it to generally mean the treatment of gas by methods other than those common to HVAC and Nuclear Air Treatment. This is only a working guideline not a rigorous definition. Whether a rigorous definition is desirable, or even possible is a question for some other forum. Here we will be discussing the practical aspects of what {open_quotes}Gas Processing{close_quotes} includes and how existing Codes, Standards and industry experience can, and should, apply to DOE and NRC Licensed facilities. A major impediment to use of the best engineering and technology in many nuclear facilities is the administrative mandate that only systems and equipment that meet specified {open_quotes}nuclear{close_quotes} documents are permissible. This paper will highlight some of the limitations created by this approach.

  1. Reliability Analysis Multiple Redundancy Controller for Nuclear Safety Systems

    International Nuclear Information System (INIS)

    Son, Gwangseop; Kim, Donghoon; Son, Choulwoong

    2013-01-01

    This controller is configured for multiple modular redundancy (MMR) composed of dual modular redundancy (DMR) and triple modular redundancy (TMR). The architecture of MRC is briefly described, and the Markov model is developed. Based on the model, the reliability and Mean Time To Failure (MTTF) are analyzed. In this paper, the architecture of MRC for nuclear safety systems is described. The MRC is configured for multiple modular redundancy (MMR) composed of dual modular redundancy (DMR) and triple modular redundancy (TMR). Markov models for MRC architecture was developed, and then the reliability was analyzed by using the model. From the reliability analyses for the MRC, it is obtained that the failure rate of each module in the MRC should be less than 2 Χ 10 -4 /hour and the MTTF average increase rate depending on FCF increment, i. e. ΔMTTF/ΔFCF, is 4 months/0.1

  2. Processing of nuclear data for reactor applications

    International Nuclear Information System (INIS)

    Trkov, A.; Ravnik, M.

    1996-01-01

    A brief description is given of the processing and validation of nuclear data in connection with the TRX-1, TRX-2, BAPL-1 and BAPL-2 benchmarks of a/o thermal reactors and in connection with the JEF-1, JENDL-3 and WIMS libraries. Also, the validation of the WLUP results are briefly discussed. 8 refs, 5 tabs

  3. Chemical aspects of nuclear fuel fabrication processes

    Energy Technology Data Exchange (ETDEWEB)

    Naylor, A; Ellis, J F; Watson, R H

    1986-04-01

    Processes used by British Nuclear Fuels plc for the conversion of uranium ore concentrates to uranium metal and uranium hexafluoride, are reviewed. Means of converting the latter compound, after enrichment, to sintered UO/sub 2/ fuel bodies are also described. An overview is given of the associated chemical engineering technology.

  4. Multiple production of hadrons in deep inelastic processes

    International Nuclear Information System (INIS)

    Kiselev, A.V.; Petrov, V.A.

    1985-01-01

    Formulas are proposed for the description of the mean multiplicity of hadrons in deep inelastic processes. On the basis of the existing data, predictions are made for the behavior of the mean multiplicity at higher energies

  5. Advances in Nuclear Power Process Heat Applications

    International Nuclear Information System (INIS)

    2012-05-01

    Following an IAEA coordinated research project, this publication compiles the findings of research and development activities related to practical nuclear process heat applications. An overview of current progress on high temperature gas cooled reactors coupling schemes for different process heat applications, such as hydrogen production and desalination is included. The associated safety aspects are also highlighted. The summary report documents the results and conclusions of the project.

  6. New nuclear plant design and licensing process

    International Nuclear Information System (INIS)

    Luangdilok, W.

    1996-01-01

    This paper describes latest developments in the nuclear power reactor technology with emphasis on three areas: (1) the US technology of advanced passive light water reactors (AP600 and S BWR), (2) regulatory processes that certify their safety, and (3) current engineering concerns. The goal is to provide and insight of how the government's regulatory agency guarantees public safety by looking into how new passive safety features were designed and tested by vendors and how they were re-evaluated and retested by the US NRC. The paper then discusses the US 1989 nuclear licensing reform (10 CFR Part 52) whose objectives are to promote the standardization of nuclear power plants and provide for the early and definitive resolution of site and design issues before plants are built. The new licensing process avoids the unpredictability nd escalated construction cost under the old licensing process. Finally, the paper summarizes engineering concerns found in current light water reactors that may not go away in the new design. The concerns are related the material and water chemistry technology in dealing with corrosion problems in water-cooled nuclear reactor systems (PWRs and BWRs). These engineering concerns include core shroud cracking (BWRs), jet pump hold-down beam cracking (BWRs), steam generator tube stress corrosion cracking (PWR)

  7. Aggregation process, application to nuclear multifragmentation

    International Nuclear Information System (INIS)

    Garcia, Jean-Baptiste

    1995-01-01

    It is depicted an aggregation model (applied to nuclear multifragmentation) which I have elaborated and validated. This model contains an aggregation procedure, allowing one to determine the aggregation state of a given system. It takes into account spatial and kinetic nucleonic information, as well as in-medium effects. It is made of several energetic linkage criterions, all based on a single quantity: the energy of a system computed in its center of mass frame. This procedure has been applied to nuclear physics, assuming nucleus as a mix of two Fermi gas, interacting via the Yukawa potential (plus Coulomb in between protons) and obeying to a classical exclusion principle. The general trends of the model match with those of nuclear physics. Moreover, two comparisons between the model and nuclear multifragmentation experiments (ALADIN, then FOPI) exhibit nice agreements. The FOPI one, shows that fragments are bound to be formed at the beginning of the expansion phase (Au + Au at 150 MeV/nuc, for central collisions). This work ends with a study of the main ingredients included in the model. It reveals that in-medium effects, exclusion principle as well as the shape of the potential have a non negligible influence on the studied nuclear aggregation process. (author) [fr

  8. Modeling closed nuclear fuel cycles processes

    Energy Technology Data Exchange (ETDEWEB)

    Shmidt, O.V. [A.A. Bochvar All-Russian Scientific Research Institute for Inorganic Materials, Rogova, 5a street, Moscow, 123098 (Russian Federation); Makeeva, I.R. [Zababakhin All-Russian Scientific Research Institute of Technical Physics, Vasiliev street 13, Snezhinsk, Chelyabinsk region, 456770 (Russian Federation); Liventsov, S.N. [Tomsk Polytechnic University, Tomsk, Lenin Avenue, 30, 634050 (Russian Federation)

    2016-07-01

    Computer models of processes are necessary for determination of optimal operating conditions for closed nuclear fuel cycle (NFC) processes. Computer models can be quickly changed in accordance with new and fresh data from experimental research. 3 kinds of process simulation are necessary. First, the VIZART software package is a balance model development used for calculating the material flow in technological processes. VIZART involves taking into account of equipment capacity, transport lines and storage volumes. Secondly, it is necessary to simulate the physico-chemical processes that are involved in the closure of NFC. The third kind of simulation is the development of software that allows the optimization, diagnostics and control of the processes which implies real-time simulation of product flows on the whole plant or on separate lines of the plant. (A.C.)

  9. Heat pump augmentation of nuclear process heat

    International Nuclear Information System (INIS)

    Koutz, S.L.

    1986-01-01

    A system is described for increasing the temperature of a working fluid heated by a nuclear reactor. The system consists of: a high temperature gas cooled nuclear reactor having a core and a primary cooling loop through which a coolant is circulated so as to undergo an increase in temperature, a closed secondary loop having a working fluid therein, the cooling and secondary loops having cooperative association with an intermediate heat exchanger adapted to effect transfer of heat from the coolant to the working fluid as the working fluid passes through the intermediate heat exchanger, a heat pump connected in the secondary loop and including a turbine and a compressor through which the working fluid passes so that the working fluid undergoes an increase in temperature as it passes through the compressor, a process loop including a process chamber adapted to receive a process fluid therein, the process chamber being connected in circuit with the secondary loop so as to receive the working fluid from the compressor and transfer heat from the working fluid to the process fluid, a heat exchanger for heating the working fluid connected to the process loop for receiving heat therefrom and for transferring heat to the secondary loop prior to the working fluid passing through the compressor, the secondary loop being operative to pass the working fluid from the process chamber to the turbine so as to effect driving relation thereof, a steam generator operatively associated with the secondary loop so as to receive the working fluid from the turbine, and a steam loop having a feedwater supply and connected in circuit with the steam generator so that feedwater passing through the steam loop is heated by the steam generator, the steam loop being connected in circuit with the process chamber and adapted to pass steam to the process chamber with the process fluid

  10. Operation of a nuclear test gage at low multiplications

    International Nuclear Information System (INIS)

    Baumann, N.P.

    1977-01-01

    The Nuclear Test Gage (NTG) at the Savannah River Plant is a subcritical multiplying facility (low k) with H 2 O moderator and 2.54-cm-diameter fuel slugs of 5 wt percent 235 U in aluminum alloy at a 4.285-cm triangular pitch. The core of the facility is 61-cm long with a normal diameter of 27 cm. The NTG is used for quality control of reactor components, such as 235 U-Al fuel tubes, Li--Al target tubes, control and safety rods, and miscellaneous special irradiation elements. A component is tested by passing it through an axial test port 11.63 cm in diameter. The ion chamber response from the resultant change in neutron source multiplication is then compared with corresponding responses from known standards

  11. Gas processing in the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Kovach, J.L.

    1995-02-01

    This article is a brief overview of code requirements in the nuclear air cleaning arena. NRC standards, which employ the various ASME codes, are noted. It is also noted that DOE facilities do not fall under the purview of the NRC and that DOE facilities (especially fuel cycle facilities) typically have broader gas processing activities than for power reactors. The typical differences between DOE facilities` and power reactor facilities` gas processing needs are listed, as are DOE facility components not covered by the ASME AG-1 code.

  12. Adaptive multiple importance sampling for Gaussian processes

    Czech Academy of Sciences Publication Activity Database

    Xiong, X.; Šmídl, Václav; Filippone, M.

    2017-01-01

    Roč. 87, č. 8 (2017), s. 1644-1665 ISSN 0094-9655 R&D Projects: GA MŠk(CZ) 7F14287 Institutional support: RVO:67985556 Keywords : Gaussian Process * Bayesian estimation * Adaptive importance sampling Subject RIV: BB - Applied Statistics, Operational Research OBOR OECD: Statistics and probability Impact factor: 0.757, year: 2016 http://library.utia.cas.cz/separaty/2017/AS/smidl-0469804.pdf

  13. Nuclear and toxic waste recycling process

    International Nuclear Information System (INIS)

    Bottillo, T.V.

    1988-01-01

    This patent describes the process for the safe and convenient disposal of nuclear and/or toxic wastes which comprises the steps of (a) collecting nuclear and/or toxic wastes which pose a danger to health; (b) packaging the wastes within containers for the safe containment thereof to provide filled containers having a weight sufficient to sink into the molten lava present within an active volcano; and (c) depositing the filled containers directly into the molten lava present within a volcano containing same to cause the containers to sink therein end to be dissolved or consumed by the heat, whereby the contents thereof are consumed to become a part of the mass of molten lava present within the volcano

  14. Permit processes for nuclear power. International lessons

    International Nuclear Information System (INIS)

    Gaahlin, Emil; Nilsson, Isabelle; Pettersson, Maria; Soederholm, Patrik

    2010-01-01

    The overall objective of this report is to analyze and compare the legal permitting and planning process for (first and foremost) new nuclear power stations in a number of selected countries. In this way the report provides relevant knowledge that could form the basis for discussing the efficiency of various national licensing processes (include the Swedish one). The study builds heavily on the analysis of legal documents and regulations, and addresses both the formal requirements for licensing and territorial planning procedures as well as the issues of public participation and access to justice in the respective countries. In addition to this legal approach, however, we also adopt an investor's perspective on the legislation, i.e., an analysis of the legal rules can influence investment decisions in practice. Furthermore, the study relies largely on a synthesis of previous studies as well as interviews with researchers, electricity companies and government officials in Sweden and abroad. The countries that are compared include Sweden, Finland, France, Canada, Switzerland, Great Britain, USA and South Korea. These include those that currently invest in new nuclear power as well as those who have recently reformed their plant permitting processes. The analysis highlights important differences among the various countries, including issues such as the political influence on the licensing process, the allocation of political power between the national and local levels, means of interacting with regular citizens, and the overall transparency and predictability of the legislation. Some selected practical experiences of the current legislation are also presented. The report first provides a short background to the role and the status of nuclear power in the global energy system, and we then present a rather comprehensive comparison of the permitting processes in the above countries. Each country section comprises a short background, a presentation of the existing

  15. Fluorine disposal processes for nuclear applications

    Energy Technology Data Exchange (ETDEWEB)

    Netzer, W.D.

    1977-04-08

    A study was performed to determine the best method for disposing of waste fluorine in the effluent from a uranium oxide conversion facility. After reviewing the fluorine disposal literature and upon considering the nuclear safety constraints, it was determined that the two most promising processes were the fluidized alumina bed and the caustic scrubber. To obtain more design data for the latter process, a 3-stage, 5-in. I.D. spray tower was constructed and operated. This unit used a 10% potassium hydroxide solution at flows of 1.5 to 3 gpm and achieved a 90% fluorine efficiency at fluorine flowrates as high as 4 scfm. However, two toxic by-products, oxygen difluoride and nitroxy fluoride, were detected in the effluent gases. After considering the relative merits of both disposal processes, it is concluded that the fluidized bed is superior, especially if the contaminated waste material were salable.

  16. Fluorine disposal processes for nuclear applications

    International Nuclear Information System (INIS)

    Netzer, W.D.

    1977-01-01

    A study was performed to determine the best method for disposing of waste fluorine in the effluent from a uranium oxide conversion facility. After reviewing the fluorine disposal literature and upon considering the nuclear safety constraints, it was determined that the two most promising processes were the fluidized alumina bed and the caustic scrubber. To obtain more design data for the latter process, a 3-stage, 5-in. I.D. spray tower was constructed and operated. This unit used a 10% potassium hydroxide solution at flows of 1.5 to 3 gpm and achieved a 90% fluorine efficiency at fluorine flowrates as high as 4 scfm. However, two toxic by-products, oxygen difluoride and nitroxy fluoride, were detected in the effluent gases. After considering the relative merits of both disposal processes, it is concluded that the fluidized bed is superior, especially if the contaminated waste material were salable

  17. Supporting Multiple Cognitive Processing Styles Using Tailored Support Systems

    International Nuclear Information System (INIS)

    Tuan Q. Tran; Karen M. Feigh; Amy R. Pritchett

    2007-01-01

    According to theories of cognitive processing style or cognitive control mode, human performance is more effective when an individual's cognitive state (e.g., intuition/scramble vs. deliberate/strategic) matches his/her ecological constraints or context (e.g., utilize intuition to strive for a 'good-enough' response instead of deliberating for the 'best' response under high time pressure). Ill-mapping between cognitive state and ecological constraints are believed to lead to degraded task performance. Consequently, incorporating support systems which are designed to specifically address multiple cognitive and functional states e.g., high workload, stress, boredom, and initiate appropriate mitigation strategies (e.g., reduce information load) is essential to reduce plant risk. Utilizing the concept of Cognitive Control Models, this paper will discuss the importance of tailoring support systems to match an operator's cognitive state, and will further discuss the importance of these ecological constraints in selecting and implementing mitigation strategies for safe and effective system performance. An example from the nuclear power plant industry illustrating how a support system might be tailored to support different cognitive states is included

  18. Restoring solvent for nuclear separation processes

    International Nuclear Information System (INIS)

    Reif, D.J.

    1987-01-01

    Solvent extraction separation processes are used to recover usable nuclear materials from spent fuels. These processes involve the use of an extractant/diluent (solvent) for separation of the reusable actinides from unwanted fission products. The most widely used processes employ tributyl phosphate as an extractant diluted with a normal-paraffin hydrocarbon. During use, the solvent is altered due to hydrolysis and radiolysis, forming materials that influence product losses, product decontamination, and separation efficiencies. In most processes, the solvent is recycled after cleaning. Solvent cleaning generally involves scrubbing with a sodium carbonate solution. Studies at the Savannah River Laboratory have shown that carbonate washing, although removing residual solvent activity, does not remove more solvent-soluble binding ligands (formed by solvent degradation), which hold fission products in the solvent. Treatment of the solvent with a solid adsorbent after carbonate washing removes binding ligands and significantly improves recycled solvent performance. Laboratory work to establish the advantage of adsorbent cleaning and the development of a full-scale adsorption process is described. The application of this process for cleaning the first cycle solvent of a Savannah River Plant production process is discussed

  19. Prototype plant for nuclear process heat (PNP)

    International Nuclear Information System (INIS)

    Duerrfeld, R.; Kraut-Giesen, G.

    1982-01-01

    1. Goals: Verification of owner's interests during experimental and engineering phase of nuclear coal gasification. 2. Method: 2.1 Witnessing and evaluating of experimental results from running test facilities. 2.2 Influencing experimental program. 2.3 Participation in important meetings of PNP-project. 3. Results: From present point of view the realization of nuclear coal gasification with a nuclear high temperature reactor (HTR) in accordance with the present technical status as well as meeting the existing safety regulations seems to be feasable. R+D-work will be needed for affirmation of design. The gasification of hard coal basing on the allothermal principal has proved to be possible. The examination of the gasifier on a pilot scale is not yet done. The design work for the pilot plant should be started immediately, particularly keeping in mind the decision for erection of PNP in 1990. The calculation of production costs in comparison to autothermal gasification processes is promising better economics, if uncertainties of investment calculation are deemed to be neglectable. (orig.) [de

  20. Waste processing system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashinakagawa, Emiko; Tezuka, Fuminobu; Maesawa, Yukishige; Irie, Hiromitsu; Daibu, Etsuji.

    1996-01-01

    The present invention concerns a waste processing system of a nuclear power plant, which can reduce the volume of a large amount of plastics without burying them. Among burnable wastes and plastic wastes to be discarded in the power plant located on the sea side, the plastic wastes are heated and converted into oils, and the burnable wastes are burnt using the oils as a fuel. The system is based on the finding that the presence of Na 2 O, K 2 O contained in the wastes catalytically improves the efficiency of thermal decomposition in a heating atmosphere, in the method of heating plastics and converting them into oils. (T.M.)

  1. Evaluation of nonaqueous processes for nuclear materials

    International Nuclear Information System (INIS)

    Musgrave, B.C.; Grens, J.Z.; Knighton, J.B.; Coops, M.S.

    1983-12-01

    A working group was assigned the task of evaluating the status of nonaqueous processes for nuclear materials and the prospects for successful deployment of these technologies in the future. In the initial evaluation, the study was narrowed to the pyrochemical/pyrometallurgical processes closely related to the processes used for purification of plutonium and its conversion to metal. The status of the chemistry and process hardware were reviewed and the development needs in both chemistry and process equipment technology were evaluated. Finally, the requirements were established for successful deployment of this technology. The status of the technology was evaluated along three lines: (1) first the current applications were examined for completeness, (2) an attempt was made to construct closed-cycle flow sheets for several proposed applications, (3) and finally the status of technical development and future development needs for general applications were reviewed. By using these three evaluations, three different perspectives were constructed that together present a clear picture of how complete the technical development of these processes are

  2. Data processing systems for clinical nuclear medicine

    International Nuclear Information System (INIS)

    Winkler, C.; Knopp, R.

    1975-01-01

    The model studies on the above mentioned data processing demonstration systems have shown that the development of a modular process computer with an applicable operation system makes it possible to meet the special demands of any nuclear-medical clinical centre corresponding to its capacity and finances. The respective first draft of the compact system described was discussed by a major circle of competent specialists at the DP-meeting of the Rheinisch-Westfaelische Gesellschaft fuer Nuklearmedizin in 1974. The positive response which the draft was met with confirmes our opinion that in the future equipment of the nuclear-medical institutions with DP-systems the universal applicability of these systems in operation with several participants and the implementation of clinically tested user's software should have priority over all other things. The development of the compact system, which is being carried out with the help of the Federal Ministry for Research and Technology will be instrumental in creating the preconditions necessary. It will be fully available in 1977 and is even expected to be completed in its partial functions (such as camera scanning, renal clearance, evaluation of laboratory data) in 1976 already. (orig.) [de

  3. Nuclear fuel re-processing plant

    International Nuclear Information System (INIS)

    Sasaki, Yuko; Honda, Takashi; Shoji, Saburo; Kobayashi, Shiro; Furuya, Yasumasa

    1989-01-01

    In a nuclear fuel re-processing plant, high Si series stainless steels not always have sufficient corrosion resistance in a solution containing only nitric acid at medium or high concentration. Further, a method of blowing NOx gases may possibly promote the corrosion of equipment constituent materials remarkably. In view of the above, the corrosion promoting effect of nuclear fission products is suppressed without depositing corrosive metal ions as metals in the nitric acid solution. That is, a reducing atmosphere is formed by generating NOx by electrolytic reduction thereby preventing increase in the surface potential of stainless steels. Further, an anode is disposed in the nitric acid solution containing oxidative metal ions to establish an electrical conduction and separate them by way of partition membranes and a constant potential or constant current is applied while maintaining an ionic state so as not to deposit metals. Thus, equipments of re-processing facility can be protected from corrosion with no particular treatment for wastes as radioactive materials. (K.M.)

  4. Measuring Strategic Processing when Students Read Multiple Texts

    Science.gov (United States)

    Braten, Ivar; Stromso, Helge I.

    2011-01-01

    This study explored the dimensionality of multiple-text comprehension strategies in a sample of 216 Norwegian education undergraduates who read seven separate texts on a science topic and immediately afterwards responded to a self-report inventory focusing on strategic multiple-text processing in that specific task context. Two dimensions were…

  5. Management of the process of nuclear transport; Gestion del proceso de transporte nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Requejo, P.

    2015-07-01

    Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

  6. Water treatment process for nuclear reactors

    International Nuclear Information System (INIS)

    Marwan, M.A.; Khattab, M.S.; Hanna, A.N.

    1993-01-01

    Water treatment for purification is very important in reactor cooling systems as well as in many industrial applications. Since impurities in water are main source of problems, it is necessary to achieve and maintain high purity of water before utilization in reactor cooling systems. The present work investigates water treatment process for nuclear reactor utilization. Analysis of outwater chemistry proved that demineralizing process is an appropriate method. Extensive experiments were conducted to determine economical concentration of the regenerants to obtain the optimum quantity of pure water which reached to 15 cubic-meter instead of 10 cubic-meter per regeneration. Running cost is consequently decreased by about 30%. Output water chemistry agrees with the recommended specifications for reactor utilization. The radionuclides produced in the primary cooling water due to reactor operation are determined. It is found that 70% of radioactive contaminants are retained by purification through resin of reactor filter. Decontamination factor and filter efficiency are also determined

  7. Water treatment process for nuclear reactors

    International Nuclear Information System (INIS)

    Marwan, M.A.; Khattab, M.S.; Hanna, A.N.

    1992-01-01

    Water treatment for purification is very important in reactor cooling systems as well as in many industrial applications. Since impurities in water are main source of problems, it is necessary to achieve and maintain high purity of water before utilization in reactor cooling systems. The present work investigate water treatment process for nuclear reactor utilization. Analysis of output water chemistry proved that demineralizing process is an appropriate method. Extensive experiments were conducted to determine economical concentration of the regenerates to obtain the optimum quantity of pure water which reached to 15 cubic meter instead of 10 cubic-meter per regeneration. Running cost is consequently decreased by about 30 %. output water chemistry agree with the recommended specifications for reactor utilization. The radionuclides produced in the primary cooling water due to reactor operation are determined. It is found that 70% of radioactive contaminants are retained by purification through resin of reactor filter. Decontamination factor and filter efficiency are also determined.5 fig., 3 tab

  8. Optimizing Sparse Matrix-Multiple Vectors Multiplication for Nuclear Configuration Interaction Calculations

    Energy Technology Data Exchange (ETDEWEB)

    Aktulga, Hasan Metin [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Buluc, Aydin [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Williams, Samuel [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Yang, Chao [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2014-08-14

    Obtaining highly accurate predictions on the properties of light atomic nuclei using the configuration interaction (CI) approach requires computing a few extremal Eigen pairs of the many-body nuclear Hamiltonian matrix. In the Many-body Fermion Dynamics for nuclei (MFDn) code, a block Eigen solver is used for this purpose. Due to the large size of the sparse matrices involved, a significant fraction of the time spent on the Eigen value computations is associated with the multiplication of a sparse matrix (and the transpose of that matrix) with multiple vectors (SpMM and SpMM-T). Existing implementations of SpMM and SpMM-T significantly underperform expectations. Thus, in this paper, we present and analyze optimized implementations of SpMM and SpMM-T. We base our implementation on the compressed sparse blocks (CSB) matrix format and target systems with multi-core architectures. We develop a performance model that allows us to understand and estimate the performance characteristics of our SpMM kernel implementations, and demonstrate the efficiency of our implementation on a series of real-world matrices extracted from MFDn. In particular, we obtain 3-4 speedup on the requisite operations over good implementations based on the commonly used compressed sparse row (CSR) matrix format. The improvements in the SpMM kernel suggest we may attain roughly a 40% speed up in the overall execution time of the block Eigen solver used in MFDn.

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

    CERN Document Server

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

    1987-01-01

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

  10. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R., E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas. Programa de Pos-Graduacao em Energia e Engenharia da Energia

    2015-07-01

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  11. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    International Nuclear Information System (INIS)

    Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R.

    2015-01-01

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  12. High-energy expansion for nuclear multiple scattering

    International Nuclear Information System (INIS)

    Wallace, S.J.

    1975-01-01

    The Watson multiple scattering series is expanded to develop the Glauber approximation plus systematic corrections arising from three (1) deviations from eikonal propagation between scatterings, (2) Fermi motion of struck nucleons, and (3) the kinematic transformation which relates the many-body scattering operators of the Watson series to the physical two-body scattering amplitude. Operators which express effects ignored at the outset to obtain the Glauber approximation are subsequently reintroduced via perturbation expansions. Hence a particular set of approximations is developed which renders the sum of the Watson series to the Glauber form in the center of mass system, and an expansion is carried out to find leading order corrections to that summation. Although their physical origins are quite distinct, the eikonal, Fermi motion, and kinematic corrections produce strikingly similar contributions to the scattering amplitude. It is shown that there is substantial cancellation between their effects and hence the Glauber approximation is more accurate than the individual approximations used in its derivation. It is shown that the leading corrections produce effects of order (2kR/subc/) -1 relative to the double scattering term in the uncorrected Glauber amplitude, hk being momentum and R/subc/ the nuclear char []e radius. The leading order corrections are found to be small enough to validate quatitative analyses of experimental data for many intermediate to high energy cases and for scattering angles not limited to the very forward region. In a Gaussian model, the leading corrections to the Glauber amplitude are given as convenient analytic expressions

  13. Steam process cogeneration using nuclear energy

    International Nuclear Information System (INIS)

    Alonso, G.; Ramirez, R.

    2010-10-01

    Use of energy in a sustainable manner is to make processes more efficient. Oil industry requires of electricity and steam for refinery and petrochemical processes, nuclear energy can be a clean energy alternative. Cogeneration is an option to be assessed by Mexico to provide additional value to electricity generation. Mexico is a country with oil resources that requires process heat for gasoline production among other things. With the concern about the climate change and sustain ability policies it is adequate to use cogeneration as a way to optimize energy resources. Currently there is a national program that considers cogeneration for several Mexican refineries, and the first choices are combined cycle plants and thermo power plants using residual oil. This is long term program. The pebble bed modular reactor (PBMR) is a next generation reactors that works with very high temperatures that can be used to produce steam process along with electricity, in this work two different couplings are assessed for the PBMR reactor to produce steam process, the two couplings are compared for using in the Mexican refineries and some conclusions are given. (Author)

  14. Optical Multiple Access Network (OMAN) for advanced processing satellite applications

    Science.gov (United States)

    Mendez, Antonio J.; Gagliardi, Robert M.; Park, Eugene; Ivancic, William D.; Sherman, Bradley D.

    1991-01-01

    An OMAN breadboard for exploring advanced processing satellite circuit switch applications is introduced. Network architecture, hardware trade offs, and multiple user interference issues are presented. The breadboard test set up and experimental results are discussed.

  15. The Arabidopsis gene DIG6 encodes a large 60S subunit nuclear export GTPase 1 that is involved in ribosome biogenesis and affects multiple auxin-regulated development processes

    KAUST Repository

    Zhao, Huayan

    2015-08-13

    The circularly permuted GTPase large subunit GTPase 1 (LSG1) is involved in the maturation step of the 60S ribosome and is essential for cell viability in yeast. Here, an Arabidopsis mutant dig6 (drought inhibited growth of lateral roots) was isolated. The mutant exhibited multiple auxin-related phenotypes, which included reduced lateral root number, altered leaf veins, and shorter roots. Genetic mapping combined with next-generation DNA sequencing identified that the mutation occurred in AtLSG1-2. This gene was highly expressed in regions of auxin accumulation. Ribosome profiling revealed that a loss of function of AtLSG1-2 led to decreased levels of monosomes, further demonstrating its role in ribosome biogenesis. Quantitative proteomics showed that the expression of certain proteins involved in ribosome biogenesis was differentially regulated, indicating that ribosome biogenesis processes were impaired in the mutant. Further investigations showed that an AtLSG1-2 deficiency caused the alteration of auxin distribution, response, and transport in plants. It is concluded that AtLSG1-2 is integral to ribosome biogenesis, consequently affecting auxin homeostasis and plant development.

  16. The Arabidopsis gene DIG6 encodes a large 60S subunit nuclear export GTPase 1 that is involved in ribosome biogenesis and affects multiple auxin-regulated development processes

    KAUST Repository

    Zhao, Huayan; Lü , Shiyou; Li, Ruixi; Chen, Tao; Zhang, Huoming; Cui, Peng; Ding, Feng; Liu, Pei; Wang, Guangchao; Xia, Yiji; Running, Mark P.; Xiong, Liming

    2015-01-01

    The circularly permuted GTPase large subunit GTPase 1 (LSG1) is involved in the maturation step of the 60S ribosome and is essential for cell viability in yeast. Here, an Arabidopsis mutant dig6 (drought inhibited growth of lateral roots) was isolated. The mutant exhibited multiple auxin-related phenotypes, which included reduced lateral root number, altered leaf veins, and shorter roots. Genetic mapping combined with next-generation DNA sequencing identified that the mutation occurred in AtLSG1-2. This gene was highly expressed in regions of auxin accumulation. Ribosome profiling revealed that a loss of function of AtLSG1-2 led to decreased levels of monosomes, further demonstrating its role in ribosome biogenesis. Quantitative proteomics showed that the expression of certain proteins involved in ribosome biogenesis was differentially regulated, indicating that ribosome biogenesis processes were impaired in the mutant. Further investigations showed that an AtLSG1-2 deficiency caused the alteration of auxin distribution, response, and transport in plants. It is concluded that AtLSG1-2 is integral to ribosome biogenesis, consequently affecting auxin homeostasis and plant development.

  17. The multiple applications of the nuclear techniques in Argentina

    International Nuclear Information System (INIS)

    Manzini, Alberto C.

    2001-01-01

    A review is given of the use of nuclear technology in Argentina, especially in the field of the production of radioisotopes and radiopharmaceuticals, nuclear medicine, and industrial applications. The applications of ionizing radiation are also reviewed

  18. Average multiplications in deep inelastic processes and their interpretation

    International Nuclear Information System (INIS)

    Kiselev, A.V.; Petrov, V.A.

    1983-01-01

    Inclusive production of hadrons in deep inelastic proceseseus is considered. It is shown that at high energies the jet evolution in deep inelastic processes is mainly of nonperturbative character. With the increase of a final hadron state energy the leading contribution to an average multiplicity comes from a parton subprocess due to production of massive quark and gluon jets and their further fragmentation as diquark contribution becomes less and less essential. The ratio of the total average multiplicity in deep inelastic processes to the average multiplicity in e + e - -annihilation at high energies tends to unity

  19. Digital signal processing application in nuclear spectroscopy

    Directory of Open Access Journals (Sweden)

    O. V. Zeynalova

    2009-06-01

    Full Text Available Digital signal processing algorithms for nuclear particle spectroscopy are described along with a digital pile-up elimination method applicable to equidistantly sampled detector signals pre-processed by a charge-sensitive preamplifier. The signal processing algorithms provided as recursive one- or multi-step procedures which can be easily programmed using modern computer programming languages. The influence of the number of bits of the sampling analogue-to-digital converter to the final signal-to-noise ratio of the spectrometer considered. Algorithms for a digital shaping-filter amplifier, for a digital pile-up elimination scheme and for ballistic deficit correction were investigated using a high purity germanium detector. The pile-up elimination method was originally developed for fission fragment spectroscopy using a Frisch-grid back-to-back double ionisation chamber and was mainly intended for pile-up elimination in case of high alpha-radioactivity of the fissile target. The developed pile-up elimination method affects only the electronic noise generated by the preamplifier. Therefore, the influence of the pile-up elimination scheme on the final resolution of the spectrometer investigated in terms of the distance between piled-up pulses. The efficiency of developed algorithms compared with other signal processing schemes published in literature.

  20. Letting the people speak: the public consultation process for nuclear power in Alberta and Saskatchewan

    International Nuclear Information System (INIS)

    Bratt, D.

    2010-01-01

    This paper compares the Alberta and Saskatchewan governments' public consultation process for the introduction of nuclear power in their provinces. While the goal was the same - to gauge public reaction on a continuous policy issue - the design of their respective consultation process was quite different. The paper analyzes the techniques of public consultation in the nuclear sector, especially the use of public hearings and multiple consultative tools. Finally, it assesses the impact that public consultation has on government decision-making. (author)

  1. Research on process management of nuclear power technological innovation

    International Nuclear Information System (INIS)

    Yang Hua; Zhou Yu

    2005-01-01

    Different from the other technological innovation processes, the technological innovation process of nuclear power engineering project is influenced deeply by the extensive environmental factors, the technological innovation of nuclear power engineering project needs to make an effort to reduce environmental uncertainty. This paper had described the mechanism of connection technological innovation process of nuclear power engineering project with environmental factors, and issued a feasible method based on model of bargaining to incorporate technological innovation process management of nuclear power engineering project with environmental factors. This method has realistic meanings to guide the technological innovation of nuclear power engineering project. (authors)

  2. Role of ion chromatograph in nuclear fuel fabrication process at Nuclear Fuel Complex

    International Nuclear Information System (INIS)

    Balaji Rao, Y.; Prasada Rao, G.; Prahlad, B.; Saibaba, N.

    2012-01-01

    The present paper discusses the different applications of ion chromatography followed in nuclear fuel fabrication process at Nuclear Fuel Complex. Some more applications of IC for characterization of nuclear materials and which are at different stages of method development at Control Laboratory, Nuclear Fuel Complex are also highlighted

  3. Pyrochemical processing of DOE spent nuclear fuel

    International Nuclear Information System (INIS)

    Laidler, J.J.

    1995-01-01

    A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or open-quotes pyroprocessing,close quotes provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (>99.9%) separation of transuranics. The resultant waste forms from the pyroprocess, are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and avoid the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory

  4. Quantum information processing and nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Cummins, H.K.

    2001-01-01

    Quantum computers are information processing devices which operate by and exploit the laws of quantum mechanics, potentially allowing them to solve problems which are intractable using classical computers. This dissertation considers the practical issues involved in one of the more successful implementations to date, nuclear magnetic resonance (NMR). Techniques for dealing with systematic errors are presented, and a quantum protocol is implemented. Chapter 1 is a brief introduction to quantum computation. The physical basis of its efficiency and issues involved in its implementation are discussed. NMR quantum information processing is reviewed in more detail in Chapter 2. Chapter 3 considers some of the errors that may be introduced in the process of implementing an algorithm, and high-level ways of reducing the impact of these errors by using composite rotations. Novel general expressions for stabilising composite rotations are presented in Chapter 4 and a new class of composite rotations, tailored composite rotations, presented in Chapter 5. Chapter 6 describes some of the advantages and pitfalls of combining composite rotations. Experimental evaluations of the composite rotations are given in each case. An actual implementation of a quantum information protocol, approximate quantum cloning, is presented in Chapter 7. The dissertation ends with appendices which contain expansions of some equations and detailed calculations of certain composite rotation results, as well as spectrometer pulse sequence programs. (author)

  5. The multiple applications of the nuclear techniques in Argentina; Las multiples aplicaciones de la tecnologia nuclear en Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Manzini, Alberto C [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Programa de Radioisotopos y Aplicaciones

    2001-07-01

    A review is given of the use of nuclear technology in Argentina, especially in the field of the production of radioisotopes and radiopharmaceuticals, nuclear medicine, and industrial applications. The applications of ionizing radiation are also reviewed.

  6. Aligning business processes and IT of multiple collaborating organisations

    NARCIS (Netherlands)

    Kassahun, Ayalew

    2017-01-01

    When multiple organisations want to collaborate with one another they have to integrate their business processes. This requires aligning the collaborative business processes and the underlying IT (Information Technology). Realizing the required alignment is, however, not trivial and is the

  7. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens, E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas

    2015-07-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  8. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    International Nuclear Information System (INIS)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens

    2015-01-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  9. Process and representation in multiple-cue judgment

    OpenAIRE

    Olsson, Anna-Carin

    2002-01-01

    This thesis investigates the cognitive processes and representations underlying human judgment in a multiple-cue judgment task. Several recent models assume that people have several qualitatively distinct and competing levels of knowledge representations (Ashby, Alfonso-Reese, Turken, & Waldron, 1998; Erickson & Kruschke, 1998; Nosofsky, Palmeri, & McKinley, 1994; Sloman, 1996). The most successful cognitive models in categorization and multiple-cue judgment are, respectively, exe...

  10. Comparison of risk assessment methodologies for nuclear power and nuclear fuels processing plants

    International Nuclear Information System (INIS)

    Durant, W.S.; Walker, D.H.

    1986-08-01

    The utilization of nuclear fission for the generation of electric power or other purposes has as its by-product radioactive fission products. These radioactive fission products represent a potential hazard different in nature from that associated with other process operations or other methods of electrical power generation. As a result the electrical power stations and the facilities designed to process the irradiated fuel to recover the still useful fuel and the products of the irradiation are designed with multiple physical barriers to contain the radioactive fission products in the event that an accident were to occur. In recent years, a disciplined approach has evolved for developing detailed models of a facility and its processes. These models can be used to assess the response for the facility to upset or accident events. The approach is based on an ordered application of available data employing fault tree/event tree methodologies. Data and/or engineering judgment are applied in a probabilisitc framework so the approach has been called Probabilistic Risk Assessment (PRA). The approach has been applied to nuclear electric generating facilities and to nuclear fuel processing facilities to assess the potential for release of fission product and transuranium element radionuclides (the hazard) and the resulting risks. The application of the methodology to the electrical generating facilities and to the fuel processing facilities has evolved somewhat differently because of differences in the facilities, availability of failure rate data, and expected outputs. This paper summarizes the two approaches and the differences in them compares the risk results from the existing studies

  11. Multiple electron processes of He and Ne by proton impact

    Science.gov (United States)

    Terekhin, Pavel Nikolaevich; Montenegro, Pablo; Quinto, Michele; Monti, Juan; Fojon, Omar; Rivarola, Roberto

    2016-05-01

    A detailed investigation of multiple electron processes (single and multiple ionization, single capture, transfer-ionization) of He and Ne is presented for proton impact at intermediate and high collision energies. Exclusive absolute cross sections for these processes have been obtained by calculation of transition probabilities in the independent electron and independent event models as a function of impact parameter in the framework of the continuum distorted wave-eikonal initial state theory. A binomial analysis is employed to calculate exclusive probabilities. The comparison with available theoretical and experimental results shows that exclusive probabilities are needed for a reliable description of the experimental data. The developed approach can be used for obtaining the input database for modeling multiple electron processes of charged particles passing through the matter.

  12. Efficient Adoption and Assessment of Multiple Process Improvement Reference Models

    Directory of Open Access Journals (Sweden)

    Simona Jeners

    2013-06-01

    Full Text Available A variety of reference models such as CMMI, COBIT or ITIL support IT organizations to improve their processes. These process improvement reference models (IRMs cover different domains such as IT development, IT Services or IT Governance but also share some similarities. As there are organizations that address multiple domains and need to coordinate their processes in their improvement we present MoSaIC, an approach to support organizations to efficiently adopt and conform to multiple IRMs. Our solution realizes a semantic integration of IRMs based on common meta-models. The resulting IRM integration model enables organizations to efficiently implement and asses multiple IRMs and to benefit from synergy effects.

  13. A practicable signal processing algorithm for industrial nuclear instrument

    International Nuclear Information System (INIS)

    Tang Yaogeng; Gao Song; Yang Wujiao

    2006-01-01

    In order to reduce the statistical error and to improve dynamic performances of the industrial nuclear instrument, a practicable method of nuclear measurement signal processing is developed according to industrial nuclear measurement features. The algorithm designed is implemented with a single-chip microcomputer. The results of application in (radiation level gauge has proved the effectiveness of this method). (authors)

  14. Basic processes in nuclear forensics and analytical plan

    International Nuclear Information System (INIS)

    Venugopal, V.

    2016-01-01

    Nuclear forensics is the analysis of nuclear materials recovered from either the capture of unused materials, or from the radioactive debris following a nuclear explosion and can contribute significantly to the identification of the sources of the materials and the industrial processes used to obtain them. In the case of an explosion, nuclear forensics can also reconstruct key features of the nuclear device. Nuclear forensic analysis works best in conjunction with other law enforcement, radiological protection dosimetry, traditional forensics, and intelligence work to provide the basis for attributing the materials and/or nuclear device to its originators. Nuclear forensics is a piece of the overall attribution process, not a stand-alone activity

  15. Study of rare nuclear processes with CUORE

    Science.gov (United States)

    Alduino, C.; Alfonso, K.; Avignone, F. T.; Azzolini, O.; Bari, G.; Bellini, F.; Benato, G.; Bersani, A.; Biassoni, M.; Branca, A.; Brofferio, C.; Bucci, C.; Camacho, A.; Caminata, A.; Canonica, L.; Cao, X. G.; Capelli, S.; Cappelli, L.; Cardani, L.; Carniti, P.; Casali, N.; Cassina, L.; Chiesa, D.; Chott, N.; Clemenza, M.; Copello, S.; Cosmelli, C.; Cremonesi, O.; Creswick, R. J.; Cushman, J. S.; D’Addabbo, A.; D’Aguanno, D.; Dafinei, I.; Davis, C. J.; Dell’Oro, S.; Deninno, M. M.; di Domizio, S.; di Vacri, M. L.; Dompè, V.; Drobizhev, A.; Fang, D. Q.; Faverzani, M.; Ferri, E.; Ferroni, F.; Fiorini, E.; Franceschi, M. A.; Freedman, S. J.; Fujikawa, B. K.; Giachero, A.; Gironi, L.; Giuliani, A.; Gladstone, L.; Gorla, P.; Gotti, C.; Gutierrez, T. D.; Han, K.; Heeger, K. M.; Hennings-Yeomans, R.; Huang, H. Z.; Keppel, G.; Kolomensky, Yu. G.; Leder, A.; Ligi, C.; Lim, K. E.; Ma, Y. G.; Marini, L.; Martinez, M.; Maruyama, R. H.; Mei, Y.; Moggi, N.; Morganti, S.; Nagorny, S. S.; Napolitano, T.; Nastasi, M.; Nones, C.; Norman, E. B.; Novati, V.; Nucciotti, A.; Nutini, I.; O’Donnell, T.; Ouellet, J. L.; Pagliarone, C. E.; Pallavicini, M.; Palmieri, V.; Pattavina, L.; Pavan, M.; Pessina, G.; Pira, C.; Pirro, S.; Pozzi, S.; Previtali, E.; Reindl, F.; Rosenfeld, C.; Rusconi, C.; Sakai, M.; Sangiorgio, S.; Santone, D.; Schmidt, B.; Schmidt, J.; Scielzo, N. D.; Singh, V.; Sisti, M.; Taffarello, L.; Terranova, F.; Tomei, C.; Vignati, M.; Wagaarachchi, S. L.; Wang, B. S.; Wang, H. W.; Welliver, B.; Wilson, J.; Wilson, K.; Winslow, L. A.; Wise, T.; Zanotti, L.; Zhang, G. Q.; Zimmermann, S.; Zucchelli, S.

    2018-03-01

    TeO2 bolometers have been used for many years to search for neutrinoless double beta decay in 130Te. CUORE, a tonne-scale TeO2 detector array, recently published the most sensitive limit on the half-life, T1/20ν > 1.5 × 1025 yr, which corresponds to an upper bound of 140-400 meV on the effective Majorana mass of the neutrino. While it makes CUORE a world-leading experiment looking for neutrinoless double beta decay, it is not the only study that CUORE will contribute to in the field of nuclear and particle physics. As already done over the years with many small-scale experiments, CUORE will investigate both rare decays (such as the two-neutrino double beta decay of 130Te and the hypothesized electron capture in 123Te), and rare processes (e.g. dark matter and axion interactions). This paper describes some of the achievements of past experiments that used TeO2 bolometers, and perspectives for CUORE.

  16. Some aspects of the nuclear fission process

    International Nuclear Information System (INIS)

    Netter, F.

    1961-01-01

    In the following report one can find first a short general view on the present situation of our knowledge concerning the nuclear fission process, namely on the nucleus going through the saddle-point. Then there are some aspects connected with the excitation energy of the fissioning nucleus. The measurements made at Saclay on the fast neutron fission cross-section of U 233 , U 235 , Pu 239 , U 238 are described at the beginning of this work. It appears that for U 233 there is some characteristic shape modulation of the cross-section curve, in relation with the collective excited state of the deformed nucleus at the saddle-point. Good evidence of this is also given by the study of the relative fission rate with emission of long-range particles; it appears also that this ternary fission rate does not change substantially for neutron between thermal energy and 2 MeV, but that is very lower for the compound nucleus U 239 than for even-even compound nuclei. At the end there are some experiments on the strong 4,5 MeV gamma-ray originated by slow neutron absorption in U 235 . Time-of-flight device is used to establish that this 4,5 MeV gamma-ray seems mostly connected with radiative capture. (author) [fr

  17. Nuclear data for neutron emission in the fission process

    International Nuclear Information System (INIS)

    Ganesan, S.

    1991-11-01

    This document contains the proceedings of the IAEA Consultants' Meeting on Nuclear Data for Neutron Emission in the Fission Process, Vienna, 22 - 24 October 1990. Included are the conclusions and recommendations reached at the meeting and the papers presented by the meeting participants. These papers provide a review of the status of experimental and theoretical data on neutron emission in spontaneous and neutron induced fission with reference to the data needs for reactor applications oriented towards actinide burner studies. The specific topics covered are the following: experimental measurements and theoretical predictions and evaluations of fission neutron energy spectra, average prompt fission neutron multiplicity, correlation in neutron emission from complementary fragments, neutron emission during acceleration of fission fragments, statistical properties of neutron rich nuclei by study of emission spectra of neutrons from the excited fission fragments, integral qualification of nu-bar for the major fissile isotopes, nu-bar total of 239 Pu and 235 U, and related problems. Refs figs and tabs

  18. Efficient multitasking: parallel versus serial processing of multiple tasks.

    Science.gov (United States)

    Fischer, Rico; Plessow, Franziska

    2015-01-01

    In the context of performance optimizations in multitasking, a central debate has unfolded in multitasking research around whether cognitive processes related to different tasks proceed only sequentially (one at a time), or can operate in parallel (simultaneously). This review features a discussion of theoretical considerations and empirical evidence regarding parallel versus serial task processing in multitasking. In addition, we highlight how methodological differences and theoretical conceptions determine the extent to which parallel processing in multitasking can be detected, to guide their employment in future research. Parallel and serial processing of multiple tasks are not mutually exclusive. Therefore, questions focusing exclusively on either task-processing mode are too simplified. We review empirical evidence and demonstrate that shifting between more parallel and more serial task processing critically depends on the conditions under which multiple tasks are performed. We conclude that efficient multitasking is reflected by the ability of individuals to adjust multitasking performance to environmental demands by flexibly shifting between different processing strategies of multiple task-component scheduling.

  19. Used nuclear fuel separations process simulation and testing

    International Nuclear Information System (INIS)

    Pereira, C.; Krebs, J.F.; Copple, J.M.; Frey, K.E.; Maggos, L.E.; Figueroa, J.; Willit, J.L.; Papadias, D.D.

    2013-01-01

    Recent efforts in separations process simulation at Argonne have expanded from the traditional focus on solvent extraction flowsheet design in order to capture process dynamics and to simulate other components, processing and systems of a used nuclear fuel reprocessing plant. For example, the Argonne Model for Universal Solvent Extraction (AMUSE) code has been enhanced to make it both more portable and more readily extensible. Moving away from a spreadsheet environment makes the addition of new species and processes simpler for the expert user, which should enable more rapid implementation of chemical models that simulate evolving processes. The dyAMUSE (dynamic AMUSE) version allows the simulation of transient behavior across an extractor. Electrochemical separations have now been modeled using spreadsheet codes that simulate the electrochemical recycle of fast reactor fuel. The user can follow the evolution of the salt, products, and waste compositions in the electro-refiner, cathode processors, and drawdown as a function of fuel batches treated. To further expand capabilities in integrating multiple unit operations, a platform for linking mathematical models representing the different operations that comprise a reprocessing facility was adapted to enable systems-level analysis and optimization of facility functions. (authors)

  20. Used nuclear fuel separations process simulation and testing

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, C.; Krebs, J.F.; Copple, J.M.; Frey, K.E.; Maggos, L.E.; Figueroa, J.; Willit, J.L.; Papadias, D.D. [Argonne National Laboratory: 9700 South Cass Avenue, Argonne, IL 60439 (United States)

    2013-07-01

    Recent efforts in separations process simulation at Argonne have expanded from the traditional focus on solvent extraction flowsheet design in order to capture process dynamics and to simulate other components, processing and systems of a used nuclear fuel reprocessing plant. For example, the Argonne Model for Universal Solvent Extraction (AMUSE) code has been enhanced to make it both more portable and more readily extensible. Moving away from a spreadsheet environment makes the addition of new species and processes simpler for the expert user, which should enable more rapid implementation of chemical models that simulate evolving processes. The dyAMUSE (dynamic AMUSE) version allows the simulation of transient behavior across an extractor. Electrochemical separations have now been modeled using spreadsheet codes that simulate the electrochemical recycle of fast reactor fuel. The user can follow the evolution of the salt, products, and waste compositions in the electro-refiner, cathode processors, and drawdown as a function of fuel batches treated. To further expand capabilities in integrating multiple unit operations, a platform for linking mathematical models representing the different operations that comprise a reprocessing facility was adapted to enable systems-level analysis and optimization of facility functions. (authors)

  1. The probabilities of nuclear processes; Probabilidades de los procesos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez del Rio, C

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  2. Multiple k Nearest Neighbor Query Processing in Spatial Network Databases

    DEFF Research Database (Denmark)

    Xuegang, Huang; Jensen, Christian Søndergaard; Saltenis, Simonas

    2006-01-01

    This paper concerns the efficient processing of multiple k nearest neighbor queries in a road-network setting. The assumed setting covers a range of scenarios such as the one where a large population of mobile service users that are constrained to a road network issue nearest-neighbor queries...... for points of interest that are accessible via the road network. Given multiple k nearest neighbor queries, the paper proposes progressive techniques that selectively cache query results in main memory and subsequently reuse these for query processing. The paper initially proposes techniques for the case...... where an upper bound on k is known a priori and then extends the techniques to the case where this is not so. Based on empirical studies with real-world data, the paper offers insight into the circumstances under which the different proposed techniques can be used with advantage for multiple k nearest...

  3. Multiple-predators-based capture process on complex networks

    International Nuclear Information System (INIS)

    Sharafat, Rajput Ramiz; Pu Cunlai; Li Jie; Chen Rongbin; Xu Zhongqi

    2017-01-01

    The predator/prey (capture) problem is a prototype of many network-related applications. We study the capture process on complex networks by considering multiple predators from multiple sources. In our model, some lions start from multiple sources simultaneously to capture the lamb by biased random walks, which are controlled with a free parameter α . We derive the distribution of the lamb’s lifetime and the expected lifetime 〈 T 〉. Through simulation, we find that the expected lifetime drops substantially with the increasing number of lions. Moreover, we study how the underlying topological structure affects the capture process, and obtain that locating on small-degree nodes is better than on large-degree nodes to prolong the lifetime of the lamb. The dense or homogeneous network structures are against the survival of the lamb. We also discuss how to improve the capture efficiency in our model. (paper)

  4. Multiple-electron processes in fast ion-atom collisions

    International Nuclear Information System (INIS)

    Schlachter, A.S.

    1989-03-01

    Research in atomic physics at the Lawrence Berkeley Laboratory Super-HILAC and Bevalac accelerators on multiple-electron processes in fast ion-atom collisions is described. Experiments have studied various aspects of the charge-transfer, ionization, and excitation processes. Examples of processes in which electron correlation plays a role are resonant transfer and excitation and Auger-electron emission. Processes in which electron behavior can generally be described as uncorrelated include ionization and charge transfer in high-energy ion-atom collisions. A variety of experiments and results for energies from 1 MeV/u to 420 MeV/u are presented. 20 refs., 15 figs

  5. Multiple multichannel spectra acquisition and processing system with intelligent interface

    International Nuclear Information System (INIS)

    Chen Ying; Wei Yixiang; Qu Jianshi; Zheng Futang; Xu Shengkui; Xie Yuanming; Qu Xing; Ji Weitong; Qiu Xuehua

    1986-01-01

    A Multiple multichannel spectra acquisition and processing system with intelligent interface is described. Sixteen spectra measured with various lengths, channel widths, back biases and acquisition times can be identified and collected by the intelligent interface simultaneously while the connected computer is doing data processing. The execution time for the Ge(Li) gamma-ray spectrum analysis software on IBM PC-XT is about 55 seconds

  6. Considerations about the licensing process of special nuclear industrial facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2015-07-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  7. Considerations about the licensing process of special nuclear industrial facilities

    International Nuclear Information System (INIS)

    Talarico, M.A.; Melo, P.F. Frutuoso e

    2015-01-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  8. Multiple nucleon transfer in damped nuclear collisions. [Lectures, mass charge, and linear and angular momentum transport

    Energy Technology Data Exchange (ETDEWEB)

    Randrup, J.

    1979-07-01

    This lecture discusses a theory for the transport of mass, charge, linear, and angular momentum and energy in damped nuclear collisions, as induced by multiple transfer of individual nucleons. 11 references.

  9. Nuclear shapes: from earliest ideas to multiple shape coexisting structures

    International Nuclear Information System (INIS)

    Heyde, K; Wood, J L

    2016-01-01

    The concept of the atomic nucleus being characterized by an intrinsic property such as shape came as a result of high precision hyperfine studies in the field of atomic physics, which indicated a non-spherical nuclear charge distribution. Herein, we describe the various steps taken through ingenious experimentation and bold theoretical suggestions that mapped the way for later work in the early 50s by Aage Bohr, Ben Mottelson and James Rainwater. We lay out a long and winding road that marked, in the period of 50s to 70s, the way shell-model and collective-model concepts were reconciled. A rapid increase in both accelerator and detection methods (70s towards the early 2000s) opened new vistas into nuclear shapes, and their coexistence, in various regions of the nuclear mass table. Next, we outline a possible unified view of nuclear shapes: emphasizing decisive steps taken as well as questions remaining, next to the theoretical efforts that could result in an emerging understanding of nuclear shapes, building on the nucleus considered as a strongly interacting system of nucleons as the microscopic starting point. (invited comment)

  10. Process of public attitudes toward nuclear power generation

    International Nuclear Information System (INIS)

    Shimooka, Hiroshi

    1993-01-01

    The Japanese public attitudes toward nuclear power generation had become negative year by year. After the Chernobyl accident, a percentage of the unfavorable respondent toward nuclear power generation has dramatically increased, and a new type of anti-nuclear movement has been observed. On the basis of our public opinion polls, the reason for this increase was found to be primarily decrease of sense of usefulness rather than increase of sense of nueasiness about nuclear safety. Particularly, social factors (change of life style, progress of civilian consciousness, credibility of the existing institutional system etc.) have influence on the attitude of either pro or anti-nuclear. Based on the above observation, we have inferred that process of the public attitudes has two flows arising from the above social factors, one is the usefulness and the other is the easiness about nuclear safety, and have formulated a model representing the process of public attitudes toward nuclear power. (author)

  11. Gasification of coal making use of nuclear processing heat

    International Nuclear Information System (INIS)

    Schilling, H.D.; Bonn, B.; Krauss, U.

    1981-01-01

    In the chapter 'Gasification of coal making use of nuclear processing heat', the steam gasification of brown coal and bituminous coal, the hydrogenating gasification of brown coal including nuclear process heat either by steam cracking methane in the steam reformer or by preheating the gasifying agent, as well as the hydrogenating gasification of bituminous coal are described. (HS) [de

  12. Some problems of neutron source multiplication method for site measurement technology in nuclear critical safety

    International Nuclear Information System (INIS)

    Shi Yongqian; Zhu Qingfu; Hu Dingsheng; He Tao; Yao Shigui; Lin Shenghuo

    2004-01-01

    The paper gives experiment theory and experiment method of neutron source multiplication method for site measurement technology in the nuclear critical safety. The measured parameter by source multiplication method actually is a sub-critical with source neutron effective multiplication factor k s , but not the neutron effective multiplication factor k eff . The experiment research has been done on the uranium solution nuclear critical safety experiment assembly. The k s of different sub-criticality is measured by neutron source multiplication experiment method, and k eff of different sub-criticality, the reactivity coefficient of unit solution level, is first measured by period method, and then multiplied by difference of critical solution level and sub-critical solution level and obtained the reactivity of sub-critical solution level. The k eff finally can be extracted from reactivity formula. The effect on the nuclear critical safety and different between k eff and k s are discussed

  13. Multifractal detrended fluctuation analysis of analog random multiplicative processes

    Energy Technology Data Exchange (ETDEWEB)

    Silva, L.B.M.; Vermelho, M.V.D. [Instituto de Fisica, Universidade Federal de Alagoas, Maceio - AL, 57072-970 (Brazil); Lyra, M.L. [Instituto de Fisica, Universidade Federal de Alagoas, Maceio - AL, 57072-970 (Brazil)], E-mail: marcelo@if.ufal.br; Viswanathan, G.M. [Instituto de Fisica, Universidade Federal de Alagoas, Maceio - AL, 57072-970 (Brazil)

    2009-09-15

    We investigate non-Gaussian statistical properties of stationary stochastic signals generated by an analog circuit that simulates a random multiplicative process with weak additive noise. The random noises are originated by thermal shot noise and avalanche processes, while the multiplicative process is generated by a fully analog circuit. The resulting signal describes stochastic time series of current interest in several areas such as turbulence, finance, biology and environment, which exhibit power-law distributions. Specifically, we study the correlation properties of the signal by employing a detrended fluctuation analysis and explore its multifractal nature. The singularity spectrum is obtained and analyzed as a function of the control circuit parameter that tunes the asymptotic power-law form of the probability distribution function.

  14. Multiple production of hadrons in deep-inelastic processes

    International Nuclear Information System (INIS)

    Kiselev, A.V.; Petrov, V.A.

    1984-01-01

    A formula to describe an average hadron multiplicity on deep-inelastic processes has been proposed. On the basis of available experimental data predictions are made about the behaviour of average multiplicity at higher energies. The W-dependence of obserVed in experiments at present remains invariable up to energies W approximately 20-25 GeV. At W> or approXimately 25 GeV there will begin a rapid ibcrease of , which is analogous to the increase, observed for sub(esup(+)esup(-)) and is of the same nature

  15. Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico

    International Nuclear Information System (INIS)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A.

    2015-09-01

    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)

  16. Observation of laser multiple filamentation process and multiple electron beams acceleration in a laser wakefield accelerator

    International Nuclear Information System (INIS)

    Li, Wentao; Liu, Jiansheng; Wang, Wentao; Chen, Qiang; Zhang, Hui; Tian, Ye; Zhang, Zhijun; Qi, Rong; Wang, Cheng; Leng, Yuxin; Li, Ruxin; Xu, Zhizhan

    2013-01-01

    The multiple filaments formation process in the laser wakefield accelerator (LWFA) was observed by imaging the transmitted laser beam after propagating in the plasma of different density. During propagation, the laser first self-focused into a single filament. After that, it began to defocus with energy spreading in the transverse direction. Two filaments then formed from it and began to propagate independently, moving away from each other. We have also demonstrated that the laser multiple filamentation would lead to the multiple electron beams acceleration in the LWFA via ionization-induced injection scheme. Besides, its influences on the accelerated electron beams were also analyzed both in the single-stage LWFA and cascaded LWFA

  17. Managing the high level waste nuclear regulatory commission licensing process

    International Nuclear Information System (INIS)

    Baskin, K.P.

    1992-01-01

    This paper reports that the process for obtaining Nuclear Regulatory Commission permits for the high level waste storage facility is basically the same process commercial nuclear power plants followed to obtain construction permits and operating licenses for their facilities. Therefore, the experience from licensing commercial reactors can be applied to the high level waste facility. Proper management of the licensing process will be the key to the successful project. The management of the licensing process was categorized into four areas as follows: responsibility, organization, communication and documentation. Drawing on experience from nuclear power plant licensing and basic management principles, the management requirement for successfully accomplishing the project goals are discussed

  18. Diffusion processes in nuclear waste glasses

    International Nuclear Information System (INIS)

    Serruys, Y.; Limoge, Y.; Brebec, G.

    1992-01-01

    Problems concerning the containment of nuclear wastes are presented. Different materials which have been considered for this purpose are briefly reviewed and we see why glass is one of the favorite candidates. It is focussed on what is known about diffusion in 'simple enough' glasses. After a recall concerning the structure and possible defects, the main results on diffusion in 'simple' glasses are given and it is shown what these results involve for the mechanisms of diffusion. The diffusion models are presented which can account for transport in random media: percolation and random walk models. Specific phenomena for the nuclear waste glasses are considered: the effect of irradiation on diffusion and leaching (i.e. corrosion by water). Finally diffusion data in nuclear waste glasses are presented. (author). 199 refs., 6 figs., 1 tab

  19. Electron pumping of the ground state of 21Ne. Transfers and multiple diffusion processes

    International Nuclear Information System (INIS)

    Stoeckel, F.; Lombardi, M.

    1978-01-01

    The electron-pumping process of the ground state of 21 Ne has been studied. It is demonstrated how in a neon cell at a pressure of 10 -4 to 10 -2 torr, a high frequency discharge can create a nuclear spin alignment in the fundamental level (I=3/2) when the excited levels are themselves aligned. The nuclear alignment is observed by monitoring the change of the linear polarization of several optical transitions during the magnetic resonance of the fundamental level. Various transfers of the alignments are investigated and a detailed study of the influence of the multiple diffusion is carried out. The multiple diffusion produces a depolarization and a relaxation of the nuclear spin. A theoretical calculation has been made for a two-level system with a J=1 radiative level and a J=0 ground state. Experimentally a relaxation time of the nuclear alignment varying from 37 ms to 240 ms is observed when the neon pressure decreases from 10 -2 to 10 -4 torr [fr

  20. Multiple particle production processes in the ''light'' of quantum optics

    International Nuclear Information System (INIS)

    Friedlander, E.M.

    1990-09-01

    Ever since the observation that high-energy ''nuclear active'' cosmic-ray particles create bunches of penetrating particles upon hitting targets, a controversy has raged about whether these secondaries are created in a ''single act'' or whether many hadrons are just the result of an intra-nuclear cascade, yielding one meson in every step. I cannot escape the impression that: the latter kind of model appeals naturally as a consequence of an innate bio-morphism in our way of thinking and that in one guise or another it has tenaciously survived to this day, also for hadron-hadron collisions, via multi-peripheral models to the modern parton shower approach. Indeed, from the very beginning of theoretical consideration of multiparticle production, the possibility of many particles arising from a single ''hot'' system has been explored, with many fruitful results, not the least of which are the s 1/4 dependence of the mean produced particle multiplicity and the ''thermal'' shape of the P T spectra. An important consequence of the thermodynamical-hydrodynamical models is that particle emission is treated in analogy to black-body radiation, implying for the secondaries a set of specific Quantum-Statistical properties, very similar to those observed in quantum optics. From here on I shall try to review a number of implications and applications of this QS analogy in the study of multiplicity distributions of the produced secondaries. I will touch only in passing another very important topic of this class, the Bose-Einstein two-particle correlations

  1. Nuclear pre-mRNA processing in plants

    Energy Technology Data Exchange (ETDEWEB)

    Reddy, A.S.N. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Biology and Program in Molecular Plant Biology; Golovkin, M. (eds.) [Thomas Jefferson Univ., Philadelphia, PA (United States). Dept. of Microbiology

    2008-07-01

    This volume of CTMI, entitled Nuclear premRNA Processing in Plants, with 16 chapters from leading scientists in this area, summarizes recent advances in nuclear pre-mRNA processing and its role in plant growth and development. It provides researchers in the field, as well as those in related areas, with an up-to-date and comprehensive, yet concise, overview of the current status and future potential of this research in understanding plant biology. The first four chapters focus on spliceosome composition, genome-wide alternative splicing, and splice site requirements for U1 and U12 introns using computational and empirical approaches. Analysis of sequenced plant genomes has revealed that 80% of all protein-coding nuclear genes contain one or more introns. The lack of an in vitro plant splicing system has made it difficult to identify general and plant-specific components of splicing machinery in plants. The next three chapters focus on serine/arginine-rich (SR) proteins, a family of highly conserved proteins, which are known to play key roles in constitutive and regulated splicing of pre-mRNA and other aspects of RNA metabolism in metazoans. These proteins engage both in RNA binding and protein.protein interactions and function as splicing regulators at multiple stages of spliceosome assembly. This family of proteins has expanded considerably in plants with several plant-specific SR proteins. Several serendipitous discoveries made using forward genetics are indicating that RNA metabolism (alternative splicing, alternative polyadenylation, mRNA transport) plays an important role in many aspects of plant growth and development and in plant responses to biotic and abiotic stresses. The next seven chapters focus on these aspects of RNA metabolism. The plant hormone abscisic acid (ABA) regulates a number of physiological processes during plant growth and development. The next chapter or A.B. Rose discusses the ways introns affect gene expression both positively and

  2. Nuclear pre-mRNA processing in plants

    International Nuclear Information System (INIS)

    Reddy, A.S.N.; Golovkin, M.

    2008-01-01

    This volume of CTMI, entitled Nuclear premRNA Processing in Plants, with 16 chapters from leading scientists in this area, summarizes recent advances in nuclear pre-mRNA processing and its role in plant growth and development. It provides researchers in the field, as well as those in related areas, with an up-to-date and comprehensive, yet concise, overview of the current status and future potential of this research in understanding plant biology. The first four chapters focus on spliceosome composition, genome-wide alternative splicing, and splice site requirements for U1 and U12 introns using computational and empirical approaches. Analysis of sequenced plant genomes has revealed that 80% of all protein-coding nuclear genes contain one or more introns. The lack of an in vitro plant splicing system has made it difficult to identify general and plant-specific components of splicing machinery in plants. The next three chapters focus on serine/arginine-rich (SR) proteins, a family of highly conserved proteins, which are known to play key roles in constitutive and regulated splicing of pre-mRNA and other aspects of RNA metabolism in metazoans. These proteins engage both in RNA binding and protein.protein interactions and function as splicing regulators at multiple stages of spliceosome assembly. This family of proteins has expanded considerably in plants with several plant-specific SR proteins. Several serendipitous discoveries made using forward genetics are indicating that RNA metabolism (alternative splicing, alternative polyadenylation, mRNA transport) plays an important role in many aspects of plant growth and development and in plant responses to biotic and abiotic stresses. The next seven chapters focus on these aspects of RNA metabolism. The plant hormone abscisic acid (ABA) regulates a number of physiological processes during plant growth and development. The next chapter or A.B. Rose discusses the ways introns affect gene expression both positively and

  3. Multiple uses for an old ibm-pc 486 in nuclear medicine using open source software

    International Nuclear Information System (INIS)

    Anselmi, C.E.; Anselmi, O.E.

    2002-01-01

    Multiple uses for an old ibm-pc 486 in nuclear medicine using open source software. Aim: To use a low budget platform to: 1 - send patient's images from processing workstation to the nuclear medicine information system; 2 - backup data files from acquisition in DICOM format in cd-rom; 3 - move data across different hospitals allowing remote processing and reading of studies. Both nuclear medicine systems in the two hospitals are Siemens Icon workstations. Material and methods: The computer used is an ibm-pc 486, which sells for about US dollar 70. The operating system installed is Red Hat Linux 6.2. The sending of the patient's images to the information system is performed through AppleTalk and Samba. The backup of acquisition files is performed by the communication from the workstation through DICOM to the Storage Class Provider (Office Dicom Toolkit) running in the 486, and the files are later burned on cd-rom. A similar configuration is present in another hospital, with minor differences in processor type. Data from any of the hospitals can be sent to the other one through the remote synchronization performed by Rsync. The connection between both Linux computers is encrypted through Secure Shell (open SSH). All software installed in the 486 was downloaded from the internet at no cost. No software was installed in the workstations. Results: The whole system is recognized transparently by the workstation's system as a local storage disk, such as the acquisition cameras or the other workstations. The transfer of images from the workstation to the information system or to a remote hospital is done the same way as copying data from the acquisition cameras in the vendor's software. When transferring large files across hospitals, the synchronization may take 1 to 3 minutes through broad band internet. The backup in DICOM format in cd-rom allows review of patient data in any computer equipped with a DICOM viewing software, as well as the re-processing of that

  4. Smoke production from multiple nuclear explosions in nonurban areas

    International Nuclear Information System (INIS)

    Small, R.D.; Bush, B.W.

    1985-01-01

    The amount of smoke that may be produced by wildland or rural fires as a consequence of a large-scale nuclear exchange is estimated. The calculation is based on a compilation of rural military facilities, identified from a wide variety of unclassified sources, together with data on their geographic positions, surrounding vegetation (fuel), and weather conditions. The ignition area (corrected for fuel moisture) and the amount of fire spread are used to calculate the smoke production. The results show a substantially lower estimated smoke production (from wildland fires) than in earlier nuclear winter studies. The amount varies seasonally and at its peak is less by an order of magnitude than the estimated threshold level necessary for a major attenuation of solar radiation. 32 references, 6 figures, 2 tables

  5. Multiple external hazards compound level 3 PSA methods research of nuclear power plant

    Science.gov (United States)

    Wang, Handing; Liang, Xiaoyu; Zhang, Xiaoming; Yang, Jianfeng; Liu, Weidong; Lei, Dina

    2017-01-01

    2011 Fukushima nuclear power plant severe accident was caused by both earthquake and tsunami, which results in large amount of radioactive nuclides release. That accident has caused the radioactive contamination on the surrounding environment. Although this accident probability is extremely small, once such an accident happens that is likely to release a lot of radioactive materials into the environment, and cause radiation contamination. Therefore, studying accidents consequences is important and essential to improve nuclear power plant design and management. Level 3 PSA methods of nuclear power plant can be used to analyze radiological consequences, and quantify risk to the public health effects around nuclear power plants. Based on multiple external hazards compound level 3 PSA methods studies of nuclear power plant, and the description of the multiple external hazards compound level 3 PSA technology roadmap and important technical elements, as well as taking a coastal nuclear power plant as the reference site, we analyzed the impact of off-site consequences of nuclear power plant severe accidents caused by multiple external hazards. At last we discussed the impact of off-site consequences probabilistic risk studies and its applications under multiple external hazards compound conditions, and explained feasibility and reasonableness of emergency plans implementation.

  6. Long-term worldwide effects of multiple nuclear weapons detonations

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The NAS report, issued in 1975 shocked the scientific community by suggesting that detonation of a fraction of the world's nuclear arsenal (10 4 megatons) could produce a major, 30-70%, reduction in stratospheric ozone, lasting a year or more. The consequences of such a reduction in the natural barrier to solar ultraviolet radiation include the potential extinction of mammalian life. The summary section of the 1975 report is reprinted here

  7. On the sequentiality of the multiple Coulomb-excitation process

    International Nuclear Information System (INIS)

    Dannhaeuser, G.; Boer, J. de

    1978-01-01

    This paper describes the results of 'computer experiments' illustrating the meaning of a new concept called 'sequentiality'. This concept applies to processes in which the excitation of a given state is mainly accomplished by a large multiple of steps, and it deals with the question as to what extent a transition close to the ground state occurs before one between the highest excited states. (orig.) [de

  8. System and process for pulsed multiple reaction monitoring

    Science.gov (United States)

    Belov, Mikhail E

    2013-05-17

    A new pulsed multiple reaction monitoring process and system are disclosed that uses a pulsed ion injection mode for use in conjunction with triple-quadrupole instruments. The pulsed injection mode approach reduces background ion noise at the detector, increases amplitude of the ion signal, and includes a unity duty cycle that provides a significant sensitivity increase for reliable quantitation of proteins/peptides present at attomole levels in highly complex biological mixtures.

  9. Determination of action zone in the nuclear / radiology handling process

    International Nuclear Information System (INIS)

    Ade Awalludin

    2013-01-01

    Assessment has been conducted on determination of action zone in nuclear or radiological emergency. The assessment is taken into account radiological risk level in nuclear or radiological emergency management process outside nuclear installation. Managing of nuclear emergency is same as that one of other emergency by adding the principles of radiation protection. This study aims to provide guidance in making of safety and security perimeter outside the nuclear installation for first responders during nuclear/radiological emergency based on dose rate, contamination level or distance from the scene. Separation of working zone is important for first responder safety that works in radiological environment in the event of nuclear or radiation emergency without violating their standard operating procedure. Value limit of safety and security perimeter has been made according to the conditions in Indonesia and considering the applicability in practical. (author)

  10. Nuclear Receptors and Multiple Endocrine Neoplasia type 1 (MEN1)

    NARCIS (Netherlands)

    Dreijerink, K.M.A.

    2009-01-01

    Multiple Endocrine Neoplasia type 1 (MEN1) is an inherited syndrome that is characterized by the occurrence of tumours of the parathyroid glands, gastroenteropancreatic tumours, pitui-tary gland adenomas, as well as adrenal adenomas and neuro-endocrine tumours, often at a young age. MEN1 tumours can

  11. Kinematics of high-energy nuclear processes

    International Nuclear Information System (INIS)

    Sanchez del Rio, C.

    1972-01-01

    This report is the first draft of one of the chapters of a book being prepared under the title:Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  12. Kinematics of low-energy nuclear processes

    International Nuclear Information System (INIS)

    Sanchez del Rio, C.

    1972-01-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  13. Programs for low-energy nuclear physics data processing

    International Nuclear Information System (INIS)

    Antuf'ev, Yu.P.; Dejneko, A.S.; Ekhichev, O.I.; Kuz'menko, V.A.; Mashkarov, Yu.G.; Nemashkalo, B.A.; Skakun, E.A.; Storizhko, V.E.; Shlyakhov, N.A.

    1978-01-01

    Purpose of six computer programs developed in KhPTI of AN USSR for the processing of the experimental data on low energy nuclear physics ia friendly described. The programs are written in Algol-60 language. They are applied to some types of nuclear reactions and permit to process differential cross sections and γ spectra, to compute statistical tensors and excitation functions as well as to analyze some processes by means of theoretical models

  14. Pedagogical Affordances of Multiple External Representations in Scientific Processes

    Science.gov (United States)

    Wu, Hsin-Kai; Puntambekar, Sadhana

    2012-12-01

    Multiple external representations (MERs) have been widely used in science teaching and learning. Theories such as dual coding theory and cognitive flexibility theory have been developed to explain why the use of MERs is beneficial to learning, but they do not provide much information on pedagogical issues such as how and in what conditions MERs could be introduced and used to support students' engagement in scientific processes and develop competent scientific practices (e.g., asking questions, planning investigations, and analyzing data). Additionally, little is understood about complex interactions among scientific processes and affordances of MERs. Therefore, this article focuses on pedagogical affordances of MERs in learning environments that engage students in various scientific processes. By reviewing literature in science education and cognitive psychology and integrating multiple perspectives, this article aims at exploring (1) how MERs can be integrated with science processes due to their different affordances, and (2) how student learning with MERs can be scaffolded, especially in a classroom situation. We argue that pairing representations and scientific processes in a principled way based on the affordances of the representations and the goals of the activities is a powerful way to use MERs in science education. Finally, we outline types of scaffolding that could help effective use of MERs including dynamic linking, model progression, support in instructional materials, teacher support, and active engagement.

  15. Development of processes for the utilization of Brazilian coal using nuclear process heat and/or nuclear process steam

    International Nuclear Information System (INIS)

    Bamert, H.; Niessen, H.F.; Walbeck, M.; Wasrzik, U.; Mueller, R.; Schiffers, U.; Strauss, W.

    1980-01-01

    Status of the project: End of the project definition phase and preparation of the planned conceptual phase. Objective of the project: Development of processes for the utilization of nuclear process heat and/or nuclear process steam for the gasification of coal with high ash content, in particular coal from Brazil. Results: With the data of Brazilian coal of high ash content (mine Leao/ 43% ash in the mine-mouth quality, 20% ash after preparation) there have been worked out proposals for the mine planning and for a number of processes. On the basis of these proposals and under consideration of the main data specified by the Brazilian working group there have been choosen two processes and worked out in a conceptual design: 1) pressurized water reactor + LURGI-pressure gasifier/hydrogasification for the production of SNG and 2) high temperature reactor steam gasification for the production of town gas. The economic evaluation showed that the two processes are not substantially different in their cost efficiency and they are economical on a long-term basis. For more specific design work there has been planned the implementation of an experimental programme using the semi-technical plants 'hydrogasification' in Wesseling and 'steam gasification' in Essen as the conceptual phase. (orig.) [de

  16. Risk assessment for nuclear processes at the Savannah River Site

    International Nuclear Information System (INIS)

    Durant, W.S.

    1992-01-01

    The Savannah River Site, one of the US Department of Energy's nuclear materials processing facilities, has for many years conducted risk-based safety analyses for the nuclear processes conducted at the facilities. This approach has allowed comparisons of risks to established criteria for acceptability. When the risk-based program was begun, it was evident that its success would depend upon having a compilation of data that was site specific. The decision was made to create a data bank of undesirable events that had occurred at the site's nuclear fuel reprocessing facilities. From this modest beginning, five data banks have been created for nuclear fuel reprocessing, waste management, nuclear fuel fabrication, tritium operations, and the Savannah River Technology Center. In addition to the primary purpose of providing a sound basis for risk-based safety analyses, these highly versatile data banks are routinely used for equipment breakdown histories, incident investigations, design studies, project justifications, reliability studies, process problem solving, training, and audits

  17. Primary processes initiated by nuclear transformations in solids

    International Nuclear Information System (INIS)

    Sano, Hirotoshi

    1975-01-01

    Primary processes of hot atom production initiated by nuclear transformation were discussed from past studies using Moessbauer spectroscopy. Many insulators (dielectric substances) showed various effect, such as abnormaly oxdized condition, following nuclear disintegration within the time duration of the life of Moessbauer nuclear excited state. Supposing these hot atom processes belonged to radiochemical processes, radiochemical characteristics of a certain chemical substance could be clarified by placing Moessbauer nuclide in the neighbourhood of the chemical substance to be studied. Chemical effects of disintegrated atom in the first and second composition, chemical substances produced in the surroundings of disintegrated atom, and environmental disturbance of disintegrated atom were studied and discussed. (Tsukamoto, Y.)

  18. Synergistic energy conversion process using nuclear energy and fossil fuels

    International Nuclear Information System (INIS)

    Hori, Masao

    2007-01-01

    Because primary energies such as fossil fuels, nuclear energy and renewable energy are limited in quantity of supply, it is necessary to use available energies effectively for the increase of energy demand that is inevitable this century while keeping environment in good condition. For this purpose, an efficient synergistic energy conversion process using nuclear energy and fossil fuels together converted to energy carriers such are electricity, hydrogen, and synthetic fuels seems to be effective. Synergistic energy conversion processes containing nuclear energy were surveyed and effects of these processes on resource saving and the CO 2 emission reduction were discussed. (T.T.)

  19. Scaling of charged particle multiplicity distributions in relativistic nuclear collisions

    International Nuclear Information System (INIS)

    Ahamd, N.; Hushnud; Azmi, M.D.; Zafar, M.; Irfan, M.; Khan, M.M.; Tufail, A.

    2011-01-01

    Validity of KNO scaling in hadron-hadron and hadron-nucleus collisions has been tested by several workers. Multiplicity distributions for p-emulsion interactions are found to be consistent with the KNO scaling hypothesis for pp collisions. The applicability of the scaling law was extended to FNAL energies by earlier workers. Slattery has shown that KNO scaling hypothesis is in fine agreement with the data for pp interactions over a wide range of incident energies. An attempt, is, therefore, made to examine the scaling hypothesis using multiplicity distributions of particles produced in 3.7A GeV/c 16 O-, 4.5A GeV/c and 14.5A GeV/c 28 Si - nucleus interactions

  20. Mean multiplicity of secondary particles in hadron-nuclear interactions

    International Nuclear Information System (INIS)

    Alaverdyan, G.B.; Pak, A.S.

    1980-01-01

    The mean multiplicity of secondary particles in hA interactions is examined in the framework of the multiplex scattering theory. The dependence of the secondary particle multiplicity coefficient Rsub(6)=anti nsub(hA)/anti nsub(hN) (where anti nsub(hA) and anti nsub(hN) are mean multiplicities of secondary relativistic particles in hA and hN interactions, respectively) on the energy and type of incident particles and atomic number of a target nucleus is analysed. It is shown that predictions of the leading particle cascade model are in satisfactory agreement with the experimental data if the uncertainties of the inelasticity in hN interactions are taken into account. The value Rsub(A) weakly depends both on the incident particle energy and the form of parametrization anti nsub(hN)(E). Allowance of energy losses fluctuation of leading particle results in the Rsub(A) value decrease. From the model of leading particles it does not follow that Rsub(a) strictly depends on the type of incident particles at the fixed value of mean number of collisions. But quantitative values of Rsub(A) for different types of particles and at one value of anti ν, (i.e. at properly chosen value) coincide. The value of Rsub(A) is profoundly dependent on the values of inelasticity factor in hN interactions

  1. Kinetic description of nuclear photoabsorption process

    International Nuclear Information System (INIS)

    Ferreira Filho, L.G.

    1986-01-01

    A phenomenological model for small amplitude nuclear vibrations is presented. The model separates explicitly the collective degree of freedom and considers its interaction with unspecified intrinsic degrees of freedom. The nuclear response function was calculated, including quantum correlation effects up to second order in the coupling potential, and compared with the usual harmonic approximation for the density fluctuation. The coupling between the two systems is treated with a phenomenological ansatz. The parameters are adjusted so as to reproduce the experimental total photoabsorption cross section for two nuclei ( 208 Pb, 238 U). It is shown that the inclusion of correlations may strongly alter the form of this curve as compared to the usual Iorentz curve. In the semiclassical limit the effective dynamics of the collective degree of freedom is shown to obey a Fokker-Planck equation. (Author) [pt

  2. High temperature heat exchange: nuclear process heat applications

    International Nuclear Information System (INIS)

    Vrable, D.L.

    1980-09-01

    The unique element of the HTGR system is the high-temperature operation and the need for heat exchanger equipment to transfer nuclear heat from the reactor to the process application. This paper discusses the potential applications of the HTGR in both synthetic fuel production and nuclear steel making and presents the design considerations for the high-temperature heat exchanger equipment

  3. Processing of LLRW arising from AECL nuclear research centres

    International Nuclear Information System (INIS)

    Buckley, L.P.; Le, V.T.; Beamer, N.V.; Brown, W.P.; Helbrecht, R.A.

    1988-11-01

    Operation of nuclear research reactors and laboratories results in the generation of a wide variety of solid and liquid radioactive wastes. This paper describes practical experience with processing of low-level radioactive wastes at two major nuclear research centres in Canada

  4. Use of multiple radiographic techniques for nuclear shielding development

    Energy Technology Data Exchange (ETDEWEB)

    Day, S., E-mail: dayse@mcmaster.ca [McMaster Univ., McMaster Nuclear Reactor, Hamilton, Ontario (Canada)

    2016-01-15

    The McMaster Nuclear Reactor (MNR) is a medium-sized research reactor located on the campus of McMaster University in Hamilton, Ontario. The largest nuclear reactor on a Canadian university campus, MNR is an open-pool, light water research reactor, Equipped with both in-core and ex-core irradiation facilities, MNR serves research, education, and industrial needs while producing radioisotopes for medical applications. Presently the University is preparing for the installation of a positron beam line facility at one of the MNR beam ports. One of five such facilities worldwide, the McMaster Intense Positron Beam Facility (MIPBF) will provide orders of magnitude more positrons than a standard bench-top arrangement, making possible experiments not previously feasible. Funded by the Canadian Foundation for Innovation and the Ontario Research Foundation, the MIPBF project is a collaborative effort between positron groups at McMaster, Western, and York universities and researchers and staff at MNR, The project has involved design and fabrication of both the positron production and transport system and custom biological shielding. The MIPBF shielding fabrication is scheduled to be complete by fall 2015 followed shortly by installation and commissioning testing at MNR. Positron beam availability is planned for later in 2016. Applications include defect characterization and surface analysis of advanced engineering materials and fundamental science experiments on antimatter properties, The MIPBF will be the latest addition to the extensive array of materials-related facilities at McMaster University. (author)

  5. Use of multiple radiographic techniques for nuclear shielding development

    International Nuclear Information System (INIS)

    Day, S.

    2016-01-01

    The McMaster Nuclear Reactor (MNR) is a medium-sized research reactor located on the campus of McMaster University in Hamilton, Ontario. The largest nuclear reactor on a Canadian university campus, MNR is an open-pool, light water research reactor, Equipped with both in-core and ex-core irradiation facilities, MNR serves research, education, and industrial needs while producing radioisotopes for medical applications. Presently the University is preparing for the installation of a positron beam line facility at one of the MNR beam ports. One of five such facilities worldwide, the McMaster Intense Positron Beam Facility (MIPBF) will provide orders of magnitude more positrons than a standard bench-top arrangement, making possible experiments not previously feasible. Funded by the Canadian Foundation for Innovation and the Ontario Research Foundation, the MIPBF project is a collaborative effort between positron groups at McMaster, Western, and York universities and researchers and staff at MNR, The project has involved design and fabrication of both the positron production and transport system and custom biological shielding. The MIPBF shielding fabrication is scheduled to be complete by fall 2015 followed shortly by installation and commissioning testing at MNR. Positron beam availability is planned for later in 2016. Applications include defect characterization and surface analysis of advanced engineering materials and fundamental science experiments on antimatter properties, The MIPBF will be the latest addition to the extensive array of materials-related facilities at McMaster University. (author)

  6. Public involvement in decision making process in nuclear field

    International Nuclear Information System (INIS)

    Constantin, M.; Diaconu, D.

    2009-01-01

    Decision Making Process (DMP) in nuclear field is influenced by multiple factors such as: complex technical aspects, diversity of stakeholders, long term risks, psychological stresses, societal attitudes, etc. General public is sometimes considered as the only one of stakeholders, the involvement of the public being seen as a factor to obtain the acceptance in the late phase of DMP. Generally it is assessed by public consultation on the environment impact studies and by approval of the sitting through the local authorities decision. Modern society uses methods to involve public from the beginning of DMP. The paper shows a general view of the methods and tools used in Europe for public involvement in DMP. The process of construction of a continuous democratic dialog inside of Romanian Stakeholder Group (RSG) in the frame of the FP6-COWAM2 and CIP projects is presented with a focusing of the barriers and factors of disturbing the trust and collaboration between stakeholders. The influence on the public acceptance is also discussed. (authors)

  7. Studies of Fluctuation Processes in Nuclear Collisions

    Energy Technology Data Exchange (ETDEWEB)

    Ayik, Sakir [Tennessee Technological Univ., Cookeville, TN (United States). Dept. of Physics

    2016-04-14

    The standard one-body transport approaches have been extensively applied to investigate heavy-ion collision dynamics at low and intermediate energies. At low energies the approach is the mean-field description of the time-dependent Hartree-Fock (TDHF) theory. At intermediate energies the approach is extended by including a collision term, and its application has been carried out mostly in the semi-classical framework of the Boltzmann-Uhling-Uhlenbeck (BUU) model. The standard transport models provide a good understanding of the average properties of the collision dynamics in terms of the effective interactions in both low and intermediate energies. However, the standard models are inadequate for describing the fluctuation dynamics of collective motion at low energies and disassembling of the nuclear system into fragments at intermediate energies resulting from the growth of density fluctuations in the spinodal region. Our tasks have been to improve the standard transport approaches by incorporating fluctuation mechanisms into the description. There are mainly two different mechanisms for fluctuations: (i) Collisional fluctuations generated by binary nucleon collisions, which provide the dominant mechanism at intermediate energies, and (ii) One-body mechanism or mean-field fluctuations, which is the dominant mechanism at low energies. In the first part of our project, the PI extended the standard transport model at intermediate energies by incorporating collisional mechanism according to the “Generalized Langevin Description” of Mori formalism. The PI and his collaborators carried out a number of applications for describing dynamical mechanism of nuclear multi fragmentations, and nuclear collective response in the semi-classical framework of the approach, which is known as the Boltzmann-Langevin model. In the second part of the project, we considered dynamical description at low energies. Because of the effective Pauli blocking, the collisional dissipation and

  8. The NJOY nuclear data processing system: The MICROR module

    International Nuclear Information System (INIS)

    Mathews, D.R.; Stepanek, J.; Pelloni, S.; Higgs, C.E.

    1984-12-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing pointwise and multigroup neutron and photon cross sections and related nuclear parameters from ENDF/B-IV and V evaluated nuclear data. The MICROR overlay is a reformatting module that produces cross sections library files for the MICROX, MICROX-2 and MICROBURN postprocessor codes. Using the data on the pointwise and groupwise NJOY tapes, MICROR produces the tapes containing basic nuclear data, FDTAPE, GAR and GGTAPE used by two-region spectrum codes MICROX and MICROX-2 and by two-region spectrum burn-up code MICROBURN. (author)

  9. Brazing process in nuclear fuel element fabrication

    International Nuclear Information System (INIS)

    Katam, K.; Sudarsono

    1982-01-01

    The purpose of the brazing process is to join the spacers and pads of fuel pins, so that the process is meant as a soldering technique and not only as a hardening or reinforcing process such as in common brazing purposes. There are some preliminary processes before executing the brazing process such as: materials preparation, sand blasting, brazing metal coating tack welding the spacers and pads on the fuel cladding. The metal brazing used is beryllium in strip form which will be evaporated in vacuum condition to coat the spacers and pads. The beryllium vapor and dust is very hazardous to the workers, so all the line process of brazing needs specials safety protection and equipment to protect the workers and the processing area. Coating process temperature is 2470 deg C with a vacuum pressure of 10 -5 mmHg. Brazing process temperature process is 1060 deg C with a vacuum pressure of 10 -6 mmHg. The brazing process with beryllium coating probably will give metallurgical structural change in the fuel cladding metal at the locations of spacers and pads. The quality of brazing is highly influenced by and is depending on the chemical composition of the metal and the brazing metal, materials preparations, temperature, vacuum pressure, time of coating and brazing process. The quality control of brazing could be performed with methods of visuality geometry, radiography and metallography. (author)

  10. Algorithms of image processing in nuclear medicine

    International Nuclear Information System (INIS)

    Oliveira, V.A.

    1990-01-01

    The problem of image restoration from noisy measurements as encountered in Nuclear Medicine is considered. A new approach for treating the measurements wherein they are represented by a spatial noncausal interaction model prior to maximum entropy restoration is given. This model describes the statistical dependence among the image values and their neighbourhood. The particular application of the algorithms presented here relates to gamma ray imaging systems, and is aimed at improving the resolution-noise suppression product. Results for actual gamma camera data are presented and compared with more conventional techniques. (author)

  11. Organizational processes and nuclear power plant safety

    International Nuclear Information System (INIS)

    Landy, F.J.; Jacobs, R.R.; Mathieu, J.

    1991-01-01

    The paper describes the effects organizational factors have on the risk associated with the operation of nuclear power plants. The described research project addresses three methods for identifying the organizational factors that impact safety. The first method consists of an elaborate theory-based protocol dealing with decision making procedures, interdepartmental coordination of activities, and communications. The second, known as goals/means/measures protocol, deals with identifying safey related goals. The third method is known as behaviorally anchored rating scale development. The paper discusses the importance of the convergence of these three methods to identify organizational factors essential to reactor safety

  12. Development process and achievements of China nuclear agricultural sciences

    International Nuclear Information System (INIS)

    Wen Xianfang

    2009-01-01

    This paper outlines the creation of our nuclear agricultural sciences and the development process as well as the main results for agricultural applications of nuclear technology. Nuclear agricultural sciences in China began in 1956, after 50 years of development, the collaborative research network, the academic exchange network, and the international exchange network have been formatted. These three networks comprehensively have promoted the formation and development of China nuclear agricultural sciences. Remarkable results have been achieved in the fields of radiation mutation breeding, space mutation breeding, isotope tracer technique application in agriculture, agricultural products storage and preservation of irradiation processing, irradiation sterile insect technique, low-doses of radiation to stimulate output. In addition, the concept of suggestions on the future development of China nuclear agricultural sciences, as well as the priorities of research fields are put forward. (authors)

  13. Three essential management processes of nuclear power plant operators

    International Nuclear Information System (INIS)

    Qi Tunfeng

    2010-01-01

    The paper takes the operation and management of Qinshan NPP Phase II as an example, focusing on the implementation of the essential process from the following three aspects the NPP production organization, training, examination and authorization for safety-related personnel, and financing budge management. A better understanding and implementation of the essential process will enable nuclear power plants to effectively control the nuclear safety from the most fundamental managerial level. (author)

  14. Process Information System - Nuclear Power Plant Krsko

    International Nuclear Information System (INIS)

    Mandic, D.; Barbic, B.; Linke, B.; Colak, I.

    1998-01-01

    Original NEK design was using several Process Computer Systems (PCS) for both process control and process supervision. PCS were built by different manufacturers around different hardware and software platforms. Operational experience and new regulatory requirements imposed new technical and functional requirements on the PCS. Requirements such as: - Acquisition of new signals from the technological processes and environment - Implementation of new application programs - Significant improvement of MMI (Man Machine Interface) - Process data transfer to other than Main Control Room (MCR) locations - Process data archiving and capability to retrieve same data for future analysis were impossible to be implemented within old systems. In order to satisfy new requirements, NEK has decided to build new Process Information System (PIS). During the design and construction of the PIS Project Phase I, in addition to the main foreign contractor, there was significant participation of local architect engineering and construction companies. This paper presents experience of NEK and local partners. (author)

  15. [Information processing speed and influential factors in multiple sclerosis].

    Science.gov (United States)

    Zhang, M L; Xu, E H; Dong, H Q; Zhang, J W

    2016-04-19

    To study the information processing speed and the influential factors in multiple sclerosis (MS) patients. A total of 36 patients with relapsing-remitting MS (RRMS), 21 patients with secondary progressive MS (SPMS), and 50 healthy control subjects from Xuanwu Hospital of Capital Medical University between April 2010 and April 2012 were included into this cross-sectional study.Neuropsychological tests was conducted after the disease had been stable for 8 weeks, including information processing speed, memory, executive functions, language and visual perception.Correlation between information processing speed and depression, fatigue, Expanded Disability Status Scale (EDSS) were studied. (1)MS patient groups demonstrated cognitive deficits compared to healthy controls.The Symbol Digit Modalities Test (SDMT) (control group 57±12; RRMS group 46±17; SPMS group 35±10, Pinformation processing (Pinformation processing speed, verbal memory and executive functioning are seen in MS patients, especially in SPMS subtype, while visual-spatial function is relatively reserved.Age, white matter change scales, EDSS scores, depression are negatively associated with information processing speed.

  16. Guideline validation in multiple trauma care through business process modeling.

    Science.gov (United States)

    Stausberg, Jürgen; Bilir, Hüseyin; Waydhas, Christian; Ruchholtz, Steffen

    2003-07-01

    Clinical guidelines can improve the quality of care in multiple trauma. In our Department of Trauma Surgery a specific guideline is available paper-based as a set of flowcharts. This format is appropriate for the use by experienced physicians but insufficient for electronic support of learning, workflow and process optimization. A formal and logically consistent version represented with a standardized meta-model is necessary for automatic processing. In our project we transferred the paper-based into an electronic format and analyzed the structure with respect to formal errors. Several errors were detected in seven error categories. The errors were corrected to reach a formally and logically consistent process model. In a second step the clinical content of the guideline was revised interactively using a process-modeling tool. Our study reveals that guideline development should be assisted by process modeling tools, which check the content in comparison to a meta-model. The meta-model itself could support the domain experts in formulating their knowledge systematically. To assure sustainability of guideline development a representation independent of specific applications or specific provider is necessary. Then, clinical guidelines could be used for eLearning, process optimization and workflow management additionally.

  17. Implications of QCD for soft hadronic and nuclear processes

    International Nuclear Information System (INIS)

    Hwa, R.C.

    1981-01-01

    Physical implications of QCD for strong forces in soft processes are discussed. Topics include long-range force, Van der Waals force, nuclear force, hadron and quark structures. In the absence of a reliable calculational scheme, phenomenological models have been built that incorporate QCD ideas as far as possible. In the framework of those models calculations have been made that provide an understanding of the soft processes in terms of quarks and gluons. We review recent work on nuclear potential, form factors at low Q 2 , pion decay constant, inclusive distribution of low p/sub T/, and radiation length of fast quark in nuclear matter

  18. Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

    International Nuclear Information System (INIS)

    Wittenbrock, N.G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

  19. PNRA Process for Utilizing Experience Feedback for Enhancing Nuclear Safety

    International Nuclear Information System (INIS)

    Shah, Z.H.

    2016-01-01

    One of the elements essential for any organization to become a learning organization is to learn from its own and others experience. The importance of utilizing experience feedback for enhancing operational safety is highlighted in nuclear industry again and again and this has resulted in establishment of several national and international forums. In addition, IAEA action plan on nuclear safety issued after Fukushima accident further highlighted the importance of experience sharing among nuclear community to enhance global nuclear safety regime. PNRA utilizes operating experience feedback gathered through different sources in order to improve its regulatory processes. During the review of licensing submissions, special emphasis is given to utilize the lessons learnt from experience feedback relating to nuclear industry within and outside the country. This emphasis has gradually resulted in various safety improvements in the facilities and processes. Accordingly, PNRA has developed a systematic process of evaluation of international operating experience feedback with the aim to create safety conscious approach. This process includes collecting information from different international forums such as IAEA, regulatory bodies of other countries and useful feedback of past accidents followed by its screening, evaluation and suggesting recommendations both for PNRA and its licensees. As a result of this process, several improvements concerning regulatory inspection plans of PNRA as well as in regulatory decision making and operational practices of licensees have been highlighted. This paper will present PNRA approach for utilizing experience feedback in its regulatory processes for enhancing / improving nuclear safety. (author)

  20. Nuclear reactor plant for production process heat

    International Nuclear Information System (INIS)

    Weber, M.

    1979-01-01

    The high temperature reactor is suitable as a heat source for carrying out endothermal chemical processes. A heat exchanger is required for separating the reactor coolant gases and the process medium. The heat of the reactor is transferred at a temperature lower than the process temperature to a secondary gas and is compressed to give the required temperature. The compression energy is obtained from the same reactor. (RW) [de

  1. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z., E-mail: jonatasfmata@yahoo.com.br, E-mail: vasconv@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  2. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    International Nuclear Information System (INIS)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z.

    2015-01-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  3. Determination of nuclear friction in strongly damped reactions from prescission neutron multiplicities

    International Nuclear Information System (INIS)

    Wilczynski, J.; Siwek-Wilczynska, K.; Wilschut, H.W.

    1996-01-01

    Nonfusion, fissionlike reactions in collisions of four heavy systems (well below the fusion extra-push energy threshold), for which Hinde and co-workers had measured the prescission neutron multiplicities, have been analyzed in terms of the deterministic dynamic model of Feldmeier coupled to a time-dependent statistical cascade calculation. In order to reproduce the measured prescission multiplicities and the observed (nearly symmetric) mass divisions, the energy dissipation must be dramatically changed with regard to the standard one-body dissipation: In the entrance channel, in the process of forming a composite system, the energy dissipation has to be reduced to at least half of the one-body dissipation strength (k s in ≤0.5), and in the exit channel (from a mononucleus shape to scission) it must be increased by a factor ranging for the studied reactions from k s out =4 to k s out =12. These results are compared with the temperature dependence of the friction coefficient, recently deduced by Hofman, Back, and Paul from data on the prescission giant dipole resonance emission in fusion-fission reactions. The combined picture of the temperature dependence of the friction coefficient, for both fusion-fission and nonfusion reactions, may indicate the onset of strong two-body dissipation already at a nuclear temperature of about 2 MeV. copyright 1996 The American Physical Society

  4. Tyrosine Residues Regulate Multiple Nuclear Functions of P54nrb.

    Science.gov (United States)

    Lee, Ahn R; Hung, Wayne; Xie, Ning; Liu, Liangliang; He, Leye; Dong, Xuesen

    2017-04-01

    The non-POU-domain-containing octamer binding protein (NONO; also known as p54nrb) has various nuclear functions ranging from transcription, RNA splicing, DNA synthesis and repair. Although tyrosine phosphorylation has been proposed to account for the multi-functional properties of p54nrb, direct evidence on p54nrb as a phosphotyrosine protein remains unclear. To investigate the tyrosine phosphorylation status of p54nrb, we performed site-directed mutagenesis on the five tyrosine residues of p54nrb, replacing the tyrosine residues with phenylalanine or alanine, and immunoblotted for tyrosine phosphorylation. We then preceded with luciferase reporter assays, RNA splicing minigene assays, co-immunoprecipitation, and confocal microscopy to study the function of p54nrb tyrosine residues on transcription, RNA splicing, protein-protein interaction, and cellular localization. We found that p54nrb was not phosphorylated at tyrosine residues. Rather, it has non-specific binding affinity to anti-phosphotyrosine antibodies. However, replacement of tyrosine with phenylalanine altered p54nrb activities in transcription co-repression and RNA splicing in gene context-dependent fashions by means of differential regulation of p54nrb protein association with its interacting partners and co-regulators of transcription and splicing. These results demonstrate that tyrosine residues, regardless of phosphorylation status, are important for p54nrb function. J. Cell. Physiol. 232: 852-861, 2017. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  5. Behavioral training promotes multiple adaptive processes following acute hearing loss.

    Science.gov (United States)

    Keating, Peter; Rosenior-Patten, Onayomi; Dahmen, Johannes C; Bell, Olivia; King, Andrew J

    2016-03-23

    The brain possesses a remarkable capacity to compensate for changes in inputs resulting from a range of sensory impairments. Developmental studies of sound localization have shown that adaptation to asymmetric hearing loss can be achieved either by reinterpreting altered spatial cues or by relying more on those cues that remain intact. Adaptation to monaural deprivation in adulthood is also possible, but appears to lack such flexibility. Here we show, however, that appropriate behavioral training enables monaurally-deprived adult humans to exploit both of these adaptive processes. Moreover, cortical recordings in ferrets reared with asymmetric hearing loss suggest that these forms of plasticity have distinct neural substrates. An ability to adapt to asymmetric hearing loss using multiple adaptive processes is therefore shared by different species and may persist throughout the lifespan. This highlights the fundamental flexibility of neural systems, and may also point toward novel therapeutic strategies for treating sensory disorders.

  6. Studies of fluctuation processes in nuclear collisions

    International Nuclear Information System (INIS)

    Ayik, S.

    1991-02-01

    This report summarizes the progress on grant No. DE-FG05-89ER40530 during the period April 15, 1990 to February 15, 1991. Our studies of heavy-ion collisions in the framework of ''a stochastic one-body transport model'' has progress in several directions. We developed a method for obtaining approximate numerical solutions of the transport-equation in semi-classical limit, i.e., Boltzmann-Langevin equation, and tested the method in realistic cases of heavy-ion collisions at energies below 100 MeV per nucleon. Some results of the numerical simulations for a head-on collision of 12 C + 12 C system is included in this report. Work has also continued on studying the stochastic one-body transport model in a quantal representation, which provides a microscopic basis for a consistent description of dissipation and fluctuation properties of large amplitude collective nuclear motion. The previous derivation of the stochastic one-body transport model was presented within the density matrix formalisam. We generalized this treatment and proposed an alternative derivation of the model by employing the Green's function approach within the real-time path formalism of Keldish. One manuscript has been submitted to Nucl. Phys. A for publication. Two other manuscripts are in preparation for publication. Several seminars and contributed talks were presented at various meeting

  7. Nuclear medicine imaging and data processing

    International Nuclear Information System (INIS)

    Bell, P.R.; Dillon, R.S.

    1978-01-01

    The Oak Ridge Imaging System (ORIS) is a software operating system structure around the Digital Equipment Corporation's PDP-8 minicomputer which provides a complete range of image manipulation procedures. Through its modular design it remains open-ended for easy expansion to meet future needs. Already included in the system are image access routines for use with the rectilinear scanner or gamma camera (both static and flow studies); display hardware design and corresponding software; archival storage provisions; and, most important, many image processing techniques. The image processing capabilities include image defect removal, smoothing, nonlinear bounding, preparation of functional images, and transaxial emission tomography reconstruction from a limited number of views

  8. High temperature reactor and application to nuclear process heat

    Energy Technology Data Exchange (ETDEWEB)

    Schulten, R; Kugeler, K [Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)

    1976-01-01

    The principle of high temperature nuclear process heat is explained and the main applications (hydrogasification of coal, nuclear chemical heat pipe, direct reduction of iron ore, coal gasification by steam and water splitting) are described in more detail. The motivation for the introduction of nuclear process heat to the market, questions of cost, of raw material resources and environmental aspects are the next point of discussion. The new technological questions of the nuclear reactor and the status of development are described, especially information about the fuel elements, the hot gas ducts, the contamination and some design considerations are added. Furthermore the status of development of helium heated steam reformers, the main results of the work until now and the further activities in this field are explained.

  9. Handbook on process and chemistry on nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Atsuyuki [Tokyo Univ., Tokyo (Japan); Asakura, Toshihide; Adachi, Takeo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; and others

    2001-12-01

    'Wet-type' nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of 'wet-type' reprocessing, because it contributes to establish and develop fuel reprocessing process and nuclear fuel cycle treating high burn-up UO{sub 2} fuel and spent MOX fuel, and to utilize 'wet-type' reprocessing technology much widely. This handbook summarizes the fundamental data on process and chemistry, which was collected and examined by 'Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing', from FY 1993 until FY 2000. (author)

  10. Handbook on process and chemistry on nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Suzuki, Atsuyuki; Asakura, Toshihide; Adachi, Takeo

    2001-12-01

    'Wet-type' nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of 'wet-type' reprocessing, because it contributes to establish and develop fuel reprocessing process and nuclear fuel cycle treating high burn-up UO 2 fuel and spent MOX fuel, and to utilize 'wet-type' reprocessing technology much widely. This handbook summarizes the fundamental data on process and chemistry, which was collected and examined by 'Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing', from FY 1993 until FY 2000. (author)

  11. Handbook on process and chemistry on nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Atsuyuki (ed.) [Tokyo Univ., Tokyo (Japan); Asakura, Toshihide; Adachi, Takeo (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-12-01

    'Wet-type' nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of 'wet-type' reprocessing, because it contributes to establish and develop fuel reprocessing process and nuclear fuel cycle treating high burn-up UO{sub 2} fuel and spent MOX fuel, and to utilize 'wet-type' reprocessing technology much widely. This handbook summarizes the fundamental data on process and chemistry, which was collected and examined by 'Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing', from FY 1993 until FY 2000. (author)

  12. Nuclear power plant personnel training process management system

    International Nuclear Information System (INIS)

    Arjona Vazquez, Orison; Venegas Bernal, Maria del Carmen; Armeteros Lopez, Ana L.

    1996-01-01

    The system in charge the management of the training process personnel from a nuclear power plant was designed taking into account all the requirements stated in the training guide for nuclear power plant personnel and their evaluation, which were prepared by the IAEA in 1995 in order to implement the SAT in the training programs for nuclear plant personnel. In the preparations of formats and elements that shape the system, account has been taken of the views expressed in such a guide, in some other bibliography that was consulted, and in the authors own opinion mainly with regard to those issues which the guide does not go deeper into

  13. Advances in chemical engineering in nuclear and process industries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

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

  14. Nuclear pulse signal processing techniques based on blind deconvolution method

    International Nuclear Information System (INIS)

    Hong Pengfei; Yang Lei; Qi Zhong; Meng Xiangting; Fu Yanyan; Li Dongcang

    2012-01-01

    This article presents a method of measurement and analysis of nuclear pulse signal, the FPGA to control high-speed ADC measurement of nuclear radiation signals and control the high-speed transmission status of the USB to make it work on the Slave FIFO mode, using the LabVIEW online data processing and display, using the blind deconvolution method to remove the accumulation of signal acquisition, and to restore the nuclear pulse signal with a transmission speed, real-time measurements show that the advantages. (authors)

  15. Advances in chemical engineering in nuclear and process industries

    International Nuclear Information System (INIS)

    1994-06-01

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

  16. Inelastic diffraction nuclear processes with redistribution of particles

    International Nuclear Information System (INIS)

    Sitenko, A.G.; Goryachij, V.V.; Peresypkin, V.V.

    1979-01-01

    The inelastic nuclear processes at high energies with redistribution of particles are described within the framework of the diffraction approach. The capture processes (p,d) and (p,p'n) generated by the high energy nucleon collision with nuclei are considered. The angular distribution of 4 He(p,d) 3 He reaction is calculated and compared with experimental data

  17. The NJOY nuclear data processing system Version 91

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Muir, D.W.

    1994-10-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing pointwise and multigroup cross sections and related quantities from elevated nuclear data in the ENDF format, including the latest US library, ENDF/B-VI. The NJOY code can work with neutrons, photons, and charged particles, and it can produce libraries for a wide variety of particle transport and reactor analysis codes

  18. Nuclear data processing using a database management system

    International Nuclear Information System (INIS)

    Castilla, V.; Gonzalez, L.

    1991-01-01

    A database management system that permits the design of relational models was used to create an integrated database with experimental and evaluated nuclear data.A system that reduces the time and cost of processing was created for computers type EC or compatibles.A set of programs for the conversion from nuclear calculated data output format to EXFOR format was developed.A dictionary to perform a retrospective search in the ENDF database was created too

  19. The NJOY Nuclear Data Processing System, Version 2016

    Energy Technology Data Exchange (ETDEWEB)

    Macfarlane, Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Muir, Douglas W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Boicourt, R. M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kahler, III, Albert Comstock [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Conlin, Jeremy Lloyd [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-01-09

    The NJOY Nuclear Data Processing System, version 2016, is a comprehensive computer code package for producing pointwise and multigroup cross sections and related quantities from evaluated nuclear data in the ENDF-4 through ENDF-6 legacy card-image formats. NJOY works with evaluated files for incident neutrons, photons, and charged particles, producing libraries for a wide variety of particle transport and reactor analysis codes.

  20. Scour process caused by multiple subvertical non-crossing jets

    Directory of Open Access Journals (Sweden)

    Stefano Pagliara

    2017-01-01

    Full Text Available The scour process induced by plunging jets is an important topic for hydraulic engineers. In recent decades, several researchers have developed new strategies and methodologies to control the scour morphology, including different jet arrangements and structures located in the stilling basin. It has been found that multiple jets can cause less scouring than single plunging jets. Based on this evidence, this study aimed to investigate the equilibrium morphology caused by multiple non-crossing jets. A dedicated laboratory model was built and experimental tests were carried out under different combinations of jet inclination angles, by varying the tailwater level and the virtual crossing point location, which was set below the original channel bed level. It was experimentally shown that the equilibrium scour morphology depends on the jet discharge, the differences in non-crossing jet inclination angles, the downstream water level, and the distance of the virtual crossing point from the original channel bed level. In particular, the last parameter was found to be one of the most influential parameters, because of the resulting flow patterns inside the water body. Furthermore, the analysis of experimental evidence allowed for a complete and detailed classification of the scour hole typologies. Three different scour typologies were distinguished and classified. Finally, based on previous studies, two novel relationships have been proposed to predict both the maximum scour depth and length within a large range of hydraulic and geometric parameters.

  1. Coolant processing device for nuclear reactor

    International Nuclear Information System (INIS)

    Kizawa, Hideo; Funakoshi, Toshio; Izumoji, Yoshiaki

    1981-01-01

    Purpose: To reduce an entire facility cost by concentrating and isolating tritium accumulated in coolants, removing the tritium out of the system, and returning hydrogen gas generated at a reactor accident to a recombiner in a closed loop by the switching of a valve. Constitution: Coolant from a reactor cooling system processed by a chemical volume control system facility (CVCS) and coolant drain from various devices processed by a liquid waste disposing system facility (LWDS) are fed to a tritium isolating facility, in which they are isolated into concentrated tritium water and dilute tritium water. The concentrated tritium water is removed out of the system and stored. The dilute tritium water is reused as supply water for coolant. If an accident occurs to cause hydrogen to be generated, a closed loop is formed between the containment vessel and the recombiner, the hydrogen is recombined with oxygen in the air of the closed loop to be thus returned to water. (Kamimura, M.)

  2. Simulation of neutron multiplicity measurements using Geant4. Open source software for nuclear arms control

    Energy Technology Data Exchange (ETDEWEB)

    Kuett, Moritz

    2016-07-07

    Nuclear arms control, including nuclear safeguards and verification technologies for nuclear disarmament typically use software as part of many different technological applications. This thesis proposes to use three open source criteria for such software, allowing users and developers to have free access to a program, have access to the full source code and be able to publish modifications for the program. This proposition is presented and analyzed in detail, together with the description of the development of ''Open Neutron Multiplicity Simulation'', an open source software tool to simulate neutron multiplicity measurements. The description includes physical background of the method, details of the developed program and a comprehensive set of validation calculations.

  3. Multiple pass and multiple layer friction stir welding and material enhancement processes

    Science.gov (United States)

    Feng, Zhili [Knoxville, TN; David, Stan A [Knoxville, TN; Frederick, David Alan [Harriman, TN

    2010-07-27

    Processes for friction stir welding, typically for comparatively thick plate materials using multiple passes and multiple layers of a friction stir welding tool. In some embodiments a first portion of a fabrication preform and a second portion of the fabrication preform are placed adjacent to each other to form a joint, and there may be a groove adjacent the joint. The joint is welded and then, where a groove exists, a filler may be disposed in the groove, and the seams between the filler and the first and second portions of the fabrication preform may be friction stir welded. In some embodiments two portions of a fabrication preform are abutted to form a joint, where the joint may, for example, be a lap joint, a bevel joint or a butt joint. In some embodiments a plurality of passes of a friction stir welding tool may be used, with some passes welding from one side of a fabrication preform and other passes welding from the other side of the fabrication preform.

  4. Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant

    International Nuclear Information System (INIS)

    Chan, Yea-Kuang; Tsai, Yu-Ching

    2017-01-01

    The objective of this study is to develop a turbine cycle model using the multiple regression approach to estimate the turbine-generator output for the Chinshan Nuclear Power Plant (NPP). The plant operating data was verified using a linear regression model with a corresponding 95% confidence interval for the operating data. In this study, the key parameters were selected as inputs for the multiple regression based turbine cycle model. The proposed model was used to estimate the turbine-generator output. The effectiveness of the proposed turbine cycle model was demonstrated by using plant operating data obtained from the Chinshan NPP Unit 2. The results show that this multiple regression based turbine cycle model can be used to accurately estimate the turbine-generator output. In addition, this study also provides an alternative approach with simple and easy features to evaluate the thermal performance for nuclear power plants.

  5. Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Chan, Yea-Kuang; Tsai, Yu-Ching [Institute of Nuclear Energy Research, Taoyuan City, Taiwan (China). Nuclear Engineering Division

    2017-03-15

    The objective of this study is to develop a turbine cycle model using the multiple regression approach to estimate the turbine-generator output for the Chinshan Nuclear Power Plant (NPP). The plant operating data was verified using a linear regression model with a corresponding 95% confidence interval for the operating data. In this study, the key parameters were selected as inputs for the multiple regression based turbine cycle model. The proposed model was used to estimate the turbine-generator output. The effectiveness of the proposed turbine cycle model was demonstrated by using plant operating data obtained from the Chinshan NPP Unit 2. The results show that this multiple regression based turbine cycle model can be used to accurately estimate the turbine-generator output. In addition, this study also provides an alternative approach with simple and easy features to evaluate the thermal performance for nuclear power plants.

  6. Facing the challenge of nuclear mass tort processing

    International Nuclear Information System (INIS)

    Pelzer, Norbert

    2017-01-01

    A great majority of states do not issue any specific legislation on nuclear mass tort litigations. They apparently build on general traditional practice as most probably already tried and tested in other areas. Some states defer the decision on the way to deal with mass tort claims to the time of the nuclear incident. They insert into their nuclear liability laws respective 'reminders' that contain an invitation or a demand to the legislator to take appropriate steps if and when necessary. Finally, there are a number of states that enacted elaborate regimes on how to react to, and organise, compensation of mass damages after a catastrophic nuclear incident. Among those states are in particular major nuclear states like Canada, India, Japan and the US. They developed compensation schemes where claims for compensation of nuclear damage shall be dealt with by fora that are not regular courts. In some of those states, the fora are exclusively competent without a right to appeal their decisions, while in other states the fora act in parallel or in complement to courts. So the international scenario appears to be somewhat confusing. Of course, sovereign states are free to organise claims processing, including nuclear mass claims processing, as they deem fit. The discretion of states is, however, limited by obligations under public international law. With regard to the victims of nuclear incidents, states are particularly bound by obligations under the 1948 Universal Declaration of Human Rights and other relevant instruments they may be a party to. National nuclear mass claim processing has in particular to comply with the obligation to guarantee 'a fair and public hearing by an independent and impartial tribunal'. With regard to possible international obligations vis-a-vis other states, it has to be taken into account that major nuclear incidents, as a rule, have transboundary detrimental effects. There is always a potential impact on territories

  7. Secondary process for securing emergency cooling in nuclear facilities

    International Nuclear Information System (INIS)

    Bachl, H.

    1975-01-01

    An auxiliary process for securing the emergency cooling of nuclear power plants is described which is characterized in that a two-material heat power auxiliary process is connected at the cold end of the cooling circuit to a main heat power process to obtain mechanical energy from thermal, which in normal operation works as a cold-absorption process, but with failure of the main process changes to a heat power process with full evaporation and subsequent superheating of the two-materials mixture. (RW/LH) [de

  8. Multipurpose nuclear process heat for energy supply in Brazil

    International Nuclear Information System (INIS)

    Hansen, U.; Inden, P.; Oesterwind, D.; Hukai, R.Y.; Pessine, R.T.; Pieroni, R.R.; Visoni, E.

    1978-11-01

    The industrialized nations require 75% of the energy as heat and it is likely that developing countries in the course of industrialization will show a comparable energy consumption structure. The High Temperature Reactor (HTR) allows the utilization of nuclear energy at high temperatures as process heat. In the Federal Republic of Germany (FRG) the development in the relevant technical areas is well advanced and warrants investigation as a matter for transfer to Brazil. In Brazil nuclear process heat finds possible applications in steel making, shale oil extraction, petroleum refining, and in the more distant future coal gasification with distribution networks. Based on growth forecasts for these industries a theoretical potential market of 38-53 GW (th) can be identified. At present nuclear process heat is marginally more expensive than conventional fossil technologies but the anticipated development is expected to add an economic incentive to the emerging necessity of providing a sound energy base in the developing countries. (author)

  9. Nuclear reactor application for high temperature power industrial processes

    International Nuclear Information System (INIS)

    Dollezhal', N.A.; Zaicho, N.D.; Alexeev, A.M.; Baturov, B.B.; Karyakin, Yu.I.; Nazarov, E.K.; Ponomarev-Stepnoj, N.N.; Protzenko, A.M.; Chernyaev, V.A.

    1977-01-01

    This report gives the results of considerations on industrial heat and technology processes (in chemistry, steelmaking, etc.) from the point of view of possible ways, technical conditions and nuclear safety requirements for the use of high temperature reactors in these processes. Possible variants of energy-technological diagrams of nuclear-steelmaking, methane steam-reforming reaction and other processes, taking into account the specific character of nuclear fuel are also given. Technical possibilities and economic conditions of the usage of different types of high temperature reactors (gas cooled reactors and reactors which have other means of transport of nuclear heat) in heat processes are examined. The report has an analysis of the problem, that arises with the application of nuclear reactors in energy-technological plants and an evaluation of solutions of this problem. There is a reason to suppose that we will benefit from the use of high temperature reactors in comparison with the production based on high quality fossil fuel [ru

  10. Technical and economic benefits of nuclear techniques in ore processing

    International Nuclear Information System (INIS)

    1989-08-01

    This report is the outcome of an Advisory Group Meeting organized by the Agency and hosted by the Institute of Physics and Nuclear Techniques, the Academy of Mining and Metallurgy in Krakow, Poland. The purpose of the meeting was to assess the technical and economic benefits of applying nuclear techniques in ore processing industry. Nucleonic control systems and nuclear on-line analytical techniques as well as radioisotope tracer tests and their applications in metallic ore-processing, coal production, and cement fabrication were discussed. This report contains a summary and the presentations dealing with nuclear techniques for process control made at this meeting. Using a number of case-histories as examples, it illustrates technical and economic benefits obtainable by the installation of nuclear process control instrumentation. It is expected to be useful for everybody dealing with ore and coal production, but especially for administrative personnel and engineers who plan and implement national development programmes related to mineral resources. Refs, figs and tabs

  11. Applicability of vector processing to large-scale nuclear codes

    International Nuclear Information System (INIS)

    Ishiguro, Misako; Harada, Hiroo; Matsuura, Toshihiko; Okuda, Motoi; Ohta, Fumio; Umeya, Makoto.

    1982-03-01

    To meet the growing trend of computational requirements in JAERI, introduction of a high-speed computer with vector processing faculty (a vector processor) is desirable in the near future. To make effective use of a vector processor, appropriate optimization of nuclear codes to pipelined-vector architecture is vital, which will pose new problems concerning code development and maintenance. In this report, vector processing efficiency is assessed with respect to large-scale nuclear codes by examining the following items: 1) The present feature of computational load in JAERI is analyzed by compiling the computer utilization statistics. 2) Vector processing efficiency is estimated for the ten heavily-used nuclear codes by analyzing their dynamic behaviors run on a scalar machine. 3) Vector processing efficiency is measured for the other five nuclear codes by using the current vector processors, FACOM 230-75 APU and CRAY-1. 4) Effectiveness of applying a high-speed vector processor to nuclear codes is evaluated by taking account of the characteristics in JAERI jobs. Problems of vector processors are also discussed from the view points of code performance and ease of use. (author)

  12. Pyroelectrochemical process for reprocessing irradiated nuclear fuels

    International Nuclear Information System (INIS)

    Brambilla, G.; Sartorelli, A.

    1982-01-01

    A pyroelectrochemical process for reprocessing irradiated fast reactor mixed oxide or carbide fuels is described. The fuel is dissolved in a bath of molten alkali metal sulfates. The Pu(SO 4 ) 2 formed in the bath is thermally decomposed, leaving crystalline PuO 2 on the bottom of the reaction vessel. Electrodes are then introduced into the bath, and UO 2 is deposited on the cathode. Alternatively, both UO 2 and PuO 2 may be electrodeposited. The molten salts, after decontamination by precipitating the fission products dissolved in the bath by introducing basic agents such as oxides, carbonates, or hydroxides, may be recycled. Since it is not possible to remove cesium from the molten salt bath, periodic disposal and partial renewal with fresh salts is necessary. The melted salts that contain the fission products are conditioned for disposal by embedding them in a metallic matrix

  13. Evidence for simultaneous syntactic processing of multiple words during reading.

    Directory of Open Access Journals (Sweden)

    Joshua Snell

    Full Text Available A hotly debated issue in reading research concerns the extent to which readers process parafoveal words, and how parafoveal information might influence foveal word recognition. We investigated syntactic word processing both in sentence reading and in reading isolated foveal words when these were flanked by parafoveal words. In Experiment 1 we found a syntactic parafoveal preview benefit in sentence reading, meaning that fixation durations on target words were decreased when there was a syntactically congruent preview word at the target location (n during the fixation on the pre-target (n-1. In Experiment 2 we used a flanker paradigm in which participants had to classify foveal target words as either noun or verb, when those targets were flanked by syntactically congruent or incongruent words (stimulus on-time 170 ms. Lower response times and error rates in the congruent condition suggested that higher-order (syntactic information can be integrated across foveal and parafoveal words. Although higher-order parafoveal-on-foveal effects have been elusive in sentence reading, results from our flanker paradigm show that the reading system can extract higher-order information from multiple words in a single glance. We propose a model of reading to account for the present findings.

  14. Galvanic cell for processing of used nuclear fuel

    Science.gov (United States)

    Garcia-Diaz, Brenda L.; Martinez-Rodriguez, Michael J.; Gray, Joshua R.; Olson, Luke C.

    2017-02-07

    A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO.sub.2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.

  15. Electrochemical fluorination for processing of used nuclear fuel

    Science.gov (United States)

    Garcia-Diaz, Brenda L.; Martinez-Rodriguez, Michael J.; Gray, Joshua R.; Olson, Luke C.

    2016-07-05

    A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO.sub.2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.

  16. Simultaneous processing of information on multiple errors in visuomotor learning.

    Science.gov (United States)

    Kasuga, Shoko; Hirashima, Masaya; Nozaki, Daichi

    2013-01-01

    The proper association between planned and executed movements is crucial for motor learning because the discrepancies between them drive such learning. Our study explored how this association was determined when a single action caused the movements of multiple visual objects. Participants reached toward a target by moving a cursor, which represented the right hand's position. Once every five to six normal trials, we interleaved either of two kinds of visual perturbation trials: rotation of the cursor by a certain amount (±15°, ±30°, and ±45°) around the starting position (single-cursor condition) or rotation of two cursors by different angles (+15° and -45°, 0° and 30°, etc.) that were presented simultaneously (double-cursor condition). We evaluated the aftereffects of each condition in the subsequent trial. The error sensitivity (ratio of the aftereffect to the imposed visual rotation) in the single-cursor trials decayed with the amount of rotation, indicating that the motor learning system relied to a greater extent on smaller errors. In the double-cursor trials, we obtained a coefficient that represented the degree to which each of the visual rotations contributed to the aftereffects based on the assumption that the observed aftereffects were a result of the weighted summation of the influences of the imposed visual rotations. The decaying pattern according to the amount of rotation was maintained in the coefficient of each imposed visual rotation in the double-cursor trials, but the value was reduced to approximately 40% of the corresponding error sensitivity in the single-cursor trials. We also found a further reduction of the coefficients when three distinct cursors were presented (e.g., -15°, 15°, and 30°). These results indicated that the motor learning system utilized multiple sources of visual error information simultaneously to correct subsequent movement and that a certain averaging mechanism might be at work in the utilization process.

  17. Multiplicative point process as a model of trading activity

    Science.gov (United States)

    Gontis, V.; Kaulakys, B.

    2004-11-01

    Signals consisting of a sequence of pulses show that inherent origin of the 1/ f noise is a Brownian fluctuation of the average interevent time between subsequent pulses of the pulse sequence. In this paper, we generalize the model of interevent time to reproduce a variety of self-affine time series exhibiting power spectral density S( f) scaling as a power of the frequency f. Furthermore, we analyze the relation between the power-law correlations and the origin of the power-law probability distribution of the signal intensity. We introduce a stochastic multiplicative model for the time intervals between point events and analyze the statistical properties of the signal analytically and numerically. Such model system exhibits power-law spectral density S( f)∼1/ fβ for various values of β, including β= {1}/{2}, 1 and {3}/{2}. Explicit expressions for the power spectra in the low-frequency limit and for the distribution density of the interevent time are obtained. The counting statistics of the events is analyzed analytically and numerically, as well. The specific interest of our analysis is related with the financial markets, where long-range correlations of price fluctuations largely depend on the number of transactions. We analyze the spectral density and counting statistics of the number of transactions. The model reproduces spectral properties of the real markets and explains the mechanism of power-law distribution of trading activity. The study provides evidence that the statistical properties of the financial markets are enclosed in the statistics of the time interval between trades. A multiplicative point process serves as a consistent model generating this statistics.

  18. Fuel production from coal by the Mobil Oil process using nuclear high-temperature process heat

    International Nuclear Information System (INIS)

    Hoffmann, G.

    1982-01-01

    Two processes for the production of liquid hydrocarbons are presented: Direct conversion of coal into fuel (coal hydrogenation) and indirect conversion of coal into fuel (syngas production, methanol synthesis, Mobil Oil process). Both processes have several variants in which nuclear process heat may be used; in most cases, the nuclear heat is introduced in the gas production stage. The following gas production processes are compared: LURGI coal gasification process; steam reformer methanation, with and without coal hydrogasification and steam gasification of coal. (orig./EF) [de

  19. NMTC/JAM, Simulates High Energy Nuclear Reactions and Nuclear-Meson Transport Processes

    International Nuclear Information System (INIS)

    Furihata, Shiori

    2002-01-01

    1 - Description of program or function: NMTC/JAM is an upgraded version of the code system NMTC/JAERI97. NMTC/JAERI97 simulates high energy nuclear reactions and nucleon-meson transport processes. It implements an intra-nuclear cascade model taking account of the in-medium nuclear effects and the pre-equilibrium calculation model based on the exciton one. For treating the nucleon transport process, the nucleon-nucleus cross sections are revised to those derived by the systematics of Pearlstein. Moreover, the level density parameter derived by Ignatyuk is included as a new option for particle evaporation calculation. A geometry package based on the Combinatorial Geometry with multi-array system and the importance sampling technique is implemented in the code. Tally function is also employed for obtaining such physical quantities as neutron energy spectra, heat deposition and nuclide yield without editing a history file. The code can simulate both the primary spallation reaction and the secondary particle transport in the intermediate energy region from 20 MeV to 3.5 GeV by the use of the Monte Carlo technique. The code has been employed in combination with the neutron-photon transport codes available to the energy region below 20 MeV for neutronics calculation of accelerator-based subcritical reactors, analyses of thick target spallation experimented and so on. 2 - Methods: High energy nuclear reactions induced by incident high energy protons, neutrons and pions are simulated with the Monte Carlo Method by the intra-nuclear nucleon-nucleon reaction probabilities based on an intra-nuclear nucleon cascade model followed by the particle evaporation including high energy fission process. Jet-Aa Microscopic transport model (JAM) is employed to simulate high energy nuclear reactions in the energy range of GeV. All reaction channels are taken into account in the JAM calculation. An intra-nuclear cascade model (ISOBAR code) taking account of the in-medium nuclear effects

  20. Resonance internal conversion as a way of accelerating nuclear processes

    International Nuclear Information System (INIS)

    Karpeshin, F.F.

    2006-01-01

    Theory of resonance conversion is presented. Being a natural extension of the traditional internal conversion into the subthreshold area, resonance conversion in a number of cases strongly affects the nuclear processes. Moreover, concentrating the transition strength on the narrow bands corresponding to the spectral atomic lines, it offers a unique tool capable of accelerating nuclear decay rates. Furthermore, along with the conventional nonradiative process of nuclear excitation through NEET and its reverse, TEEN, resonance conversion offers an appropriate mathematics for consideration of a number of cross-invariant processes involving both nuclei and electrons: excitation and deexcitation of the nuclei by hyperfine magnetic field, nuclear spin mixing, hyperfine interaction and magnetic anomalies in the atomic spectra, collisional nuclear excitation via ionization of the shells in the muon decay in the orbit, etc. The mechanisms of the optical pumping of the isomers are also considered, as well as triggering their energy in the resonance field of a laser. The effect is especially high in the hydrogen-like heavy ions due to practical absence of any damping of the resonance. The theory is also generalized to the case of the discrete Auger transitions [ru

  1. Remote operated systems for the management of nuclear processes

    International Nuclear Information System (INIS)

    Popa, I.

    1997-01-01

    The paper shortly presents the remote techniques and systems used regularly for the management of nuclear processes according to the variability and complexity of human operations and to the degree of automation. The paper contains a synthesis of the evolution of remote operating systems and advances the model of an adaptive and self-adaptive expert-robot equipment which is a very complex equipment used for integrated management of nuclear processes. Due to the complexity and variability of the technological operations and environment conditions, none of the techniques and systems presented in the paper do satisfy completely the management of the nuclear technologies as a whole. They must be utilized selectively according to the nature of the actual characteristics of the nuclear process. The expert and expert-robot systems offer a series of advantages among which one can mention: the continuity of the high quality expert's reports, easy extension, the explanation of the decision in detail, the elimination of the routine, the diagnosis of some equipment and process state, forecast of the future behaviour of equipment, processes, market, environment, etc., the multiplying of sources of information, pertinent comparison, the increasing of the performance of the user in general. The expert and expert-robot systems maintain some important drawbacks as: the possibility of taking wrong decision, the difficulty of using information from other expert systems similar to this one at present and not in the least, the high prices. (author)

  2. Use of data processing tools in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Petrasch, P.; Lukacs, G.

    1995-01-01

    With the present level of electronic data processing technology, no project of the scale of nuclear reactor decommissioning could be carried out without the use of data processing systems. On the contrary, a reactor decommissioning project requires essential support not only for the technical but also the economic side through the use of proper data processing programs, and not only general applications in the area of personal computers such as MS-EXCEL or MS Project, but also special data processing systems designed for the reactor decommissioning tasks. Various data processing supports are required depending upon the progress of a reactor decommissioning project. (orig./DG) [de

  3. Concerning permission of change in nuclear fuel processing business of Japan Nuclear Fuel Co. , Ltd

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    In response to an inquiry on the title issue received on Jun. 17, 1988, the Nuclear Safety Commission made a study and submitted the findings to the Prime Minister on Jul. 21, 1988. The study was intended to determine the conformity of the permission to the applicable criteria specified in laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The proposed modification plan included changes in the facilities in the No.1 processing building and changes in processing methods which were required to perform processing of blanket fuel assemblies for fast breeder reactor. It also included changes in the facilities in the No.2 building which were required to improve the processes. The safety study covered the anti-earthquake performance, fire/explosion prevention, criticality control, containment performance, radioactive waste disposal, and other major safety issues. Other investigations included exposure dose evaluation and accident analysis. Study results were examined on the basis of the Basic Guidelines for Nuclear Fuel Facilities Safety Review and the Uranium Processing Safety Review Guidelines. It was concluded that the modifications would not have adverse effect on the safety of the facilities. (Nogami, K.).

  4. Concerning permission of change in nuclear fuel processing business of Japan Nuclear Fuel Co., Ltd

    International Nuclear Information System (INIS)

    1988-01-01

    In response to an inquiry on the title issue received on Jun. 17, 1988, the Nuclear Safety Commission made a study and submitted the findings to the Prime Minister on Jul. 21, 1988. The study was intended to determine the conformity of the permission to the applicable criteria specified in laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The proposed modification plan included changes in the facilities in the No.1 processing building and changes in processing methods which were required to perform processing of blanket fuel assemblies for fast breeder reactor. It also included changes in the facilities in the No.2 building which were required to improve the processes. The safety study covered the anti-earthquake performance, fire/explosion prevention, criticality control, containment performance, radioactive waste disposal, and other major safety issues. Other investigations included exposure dose evaluation and accident analysis. Study results were examined on the basis of the Basic Guidelines for Nuclear Fuel Facilities Safety Review and the Uranium Processing Safety Review Guidelines. It was concluded that the modifications would not have adverse effect on the safety of the facilities. (Nogami, K.)

  5. Systems integration processes for space nuclear electric propulsion systems

    International Nuclear Information System (INIS)

    Olsen, C.S.; Rice, J.W.; Stanley, M.L.

    1991-01-01

    The various components and subsystems that comprise a nuclear electric propulsion system should be developed and integrated so that each functions ideally and so that each is properly integrated with the other components and subsystems in the optimum way. This paper discusses how processes similar to those used in the development and intergration of the subsystems that comprise the Multimegawatt Space Nuclear Power System concepts can be and are being efficiently and effectively utilized for these purposes. The processes discussed include the development of functional and operational requirements at the system and subsystem level; the assessment of individual nuclear power supply and thruster concepts and their associated technologies; the conduct of systems integration efforts including the evaluation of the mission benefits for each system; the identification and resolution of concepts development, technology development, and systems integration feasibility issues; subsystem, system, and technology development and integration; and ground and flight subsystem and integrated system testing

  6. Maintenance of process instrumentation in nuclear power plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2006-01-01

    The resurgence of the nuclear power industry at a time when the nuclear plant I and C workforce is diminishing due to aging and retirements has been the motivation for writing this book. This book compiles 30 years of practical knowledge gained by the author and his staff in testing the I and C systems of nuclear power plants around the world. It focuses on process temperature and pressure sensors and the verification of these sensors' calibration and response time. In spite of great advances in electronics, computers, and measurement technologies, important process parameters such as temperature and pressure are still measured with conventional sensing techniques found in RTDs, thermocouples, and conventional pressure and differential pressure sensors. Furthermore, no improved technology providing comparable performance is currently on the horizon. Therefore, it is important to understand how these sensors function and the testing techniques for verifying their performance. This book is intended to help provide this understanding. (orig.)

  7. Public hearing process for nuclear power plants. Seminar report

    International Nuclear Information System (INIS)

    1979-02-01

    On June 26 and 27, 1978, the Nuclear Regulatory Commission conducted a seminar on the public hearing process for nuclear power plants. The seminar was intended to examine current practices regarding the conduct of public hearings and how these practices related to the statutory intent, to assess whether existing procedures are being followed, and to explore whether administrative or legal changes are warranted. The seminar format allowed exchanges of views among participants in the hearing process and was attended by members of the public, the General Accounting Office, Congressional staffs, NRC, and the nuclear industry. The report contains panel reports on scheduling of public hearings, procedures for Board notification, selection and training of panel members, hearing procedures, and Board functions

  8. Gasification of coal using nuclear process heat. Chapter D

    International Nuclear Information System (INIS)

    Schilling, H.-D.; Bonn, B.; Krauss, U.

    1979-01-01

    In the light of the high price of coal and the enormous advances made recently in nuclear engineering, the possibility of using heat from high-temperature nuclear reactors for gasification processes was discussed as early as the 1960s. The advantages of this technology are summarized. A joint programme of development work is described, in which the Nuclear Research Centre at Juelich is aiming to develop a high-temperature reactor which will supply process heat at as high a temperature as possible, while other organizations are working on the hydrogasification of lignites and hard coals, and steam gasification. Experiments are at present being carried out on a semi-technical scale, and no operational data for large-scale plants are available as yet. (author)

  9. Decommissioning Licensing Process of Nuclear Installations in Spain

    International Nuclear Information System (INIS)

    Correa Sainz, Cristina

    2016-01-01

    The Enresa experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandellos I and Jose Cabrera NPPs. The Vandellos I gas-graphite reactor was decommissioned in about five years (from 1998 to 2003) to what is known as level 2. In February 2010, the decommissioning of Jose Cabrera power plant has been initiated and it is scheduled to be finished by 2018. The decommissioning of a nuclear power plant is a complex administrative process, the procedure for changing from operation to decommissioning is established in the Spanish law. This paper summarizes the legal framework defining the strategies, the main activities and the basic roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the Licensing documents required to obtain the decommissioning authorization and the Enresa point of view, as licensee, on the licensing decommissioning process. (author)

  10. Chemical process measurements in PWR-type nuclear power plants

    International Nuclear Information System (INIS)

    Glaeser, E.

    1978-01-01

    In order to achieve high levels of availability of nuclear power plants equipped with pressurized water reactors, strict standards have to be applied to the purity of coolant and of other media. Chemical process measurements can meet these requirements only if programmes are established giving maximum information with minimum expenditure and if these programmes are realized with effective analytical methods. Analysis programmes known from literature are proved for their usefulness, and hints are given for establishing rational programmes. Analytical techniques are compared with each other taking into consideration both methods which have already been introduced into nuclear power plant practice and methods not yet generally used in practice, such as atomic absorption spectrophotometry, gas chromatography, etc. Finally, based on the state of the art of chemical process measurements in nuclear power plants, the trends of future development are pointed out. (author)

  11. The importance of environmental education in the process of nuclear and environmental licensing of nuclear facilities

    International Nuclear Information System (INIS)

    Araujo, Jefferson Borges; Ribeiro, Katia Maria Bruno

    2009-01-01

    Today, there is a thread with regard to the global environment. To reduce the environmental impact due to spending supplies to meet the basic needs of the global population. Can be considered as the power of these needs and in this context, the environmental impact occurs by the use of fossil fuels and loss of land for use of water resources. To minimize these impacts, governments are establishing appropriate laws towards the use of renewable energy. However it appears that there is still a great distance between the established law and implementation in practice. In this context nuclear energy is an attractive option, both economic and environmental. The facilities that are somehow associated with nuclear power plants are classified as radioactive or nuclear. These facilities are subject to two licensing procedures: Environmental (by IBAMA) and Nuclear (by CNEN). Nuclear installations such as nuclear power plants Angra 1 and 2, deposits and tailings facilities of the nuclear fuel cycle in Rezende that are more the attention of the population. As part of these processes are reports of analysis of safety and environmental impacts and socio-economic (EIA/RIMA RFAS), which are available to the public and then discussed at public hearings, where there is the opportunity for questions on these reports. These questions are mainly related with the social-environmental and economic due to construction and operation of these facilities. This work is a research, discussing the law, identifying the difficulties in the licensing process and presents a discussion on the importance of environmental education at all school levels, for adult audiences and is a connection between the environmental education and process of environmental licensing and nuclear, showing how the popular consciousness more informed can better discuss issues associated with these licenses, understand the advantages and disadvantages and obtain benefits. (author)

  12. Maintenance of process instrumentation in nuclear power plants

    CERN Document Server

    Hashemian, H M

    2006-01-01

    Compiles 30 years of practical knowledge gained by the author and his staff in testing the I and C systems of nuclear power plants around the world. This book focuses on process temperature and pressure sensors and the verification of these sensors' calibration and response time.

  13. Processing of spent nuclear fuel from light water reactors

    International Nuclear Information System (INIS)

    Sraier, V.

    1978-11-01

    A comprehensive review is given of the reprocessing of spent nuclear fuel from LWR's (covering references up to No. 18 (1977) of INIS inclusively). Particular attention is devoted to waste processing, safety, and reprocessing plants. In the addendum, the present status is shown on the example of KEWA, the projected large German fuel reprocessing plant. (author)

  14. Process considerations for hot pressing ceramic nuclear waste forms

    International Nuclear Information System (INIS)

    Wilson, C.N.; Brite, D.W.

    1981-01-01

    Spray calcined simulated ceramic nuclear waste powders were hot pressed in graphite, nickel-lined graphite and ZrO 2 -lined Al 2 O 3 dies. Densification, initial off-gas, waste element retention and pellet-die interactions were evaluated. Indicated process considerations and limitations are discussed. 15 figures

  15. Optimal design of nuclear mechanical dampers with analytical hierarchy process

    International Nuclear Information System (INIS)

    Zou Yuehua; Wen Bo; Xu Hongxiang; Qin Yonglie

    2000-01-01

    An optimal design with analytical hierarchy process on nuclear mechanical dampers manufactured by authors' university was described. By using fuzzy judgement matrix the coincidence was automatically satisfied without the need of coincidence test. The results obtained by this method have been put into the production practices

  16. Pseudo-color processing in nuclear medical image

    International Nuclear Information System (INIS)

    Wang Zhiqian; Jin Yongjie

    1992-01-01

    The application of pseudo-color technology in nuclear medical image processing is discussed. It includes selection of the number of pseudo-colors, method of realizing pseudo-color transformation, function of pseudo-color transformation and operation on the function

  17. Process for automatic filling of nuclear fuel rod cans

    International Nuclear Information System (INIS)

    Bezold, H.

    1977-01-01

    A drying section is inserted in the production line for the automation of the filling process for fuel rods with nuclear fuel pellets. The pellets are taken in a drum magazine to a drying furnace and then pushed out one after the other into the can to be filled. (TK) [de

  18. Mathematic filters and digital processing in nuclear medicine

    International Nuclear Information System (INIS)

    Dimentein, R.

    1992-01-01

    The mathematic filters used in nuclear medicine were evaluated. Tomographic processing of a Jaszczak phantom, using separately Hanning, Butterworth and Wiener filters were presented. For each type of filter were made simulation, where the cut frequency and extenuation grade values were changed. (C.G.C.)

  19. Study on process of laser cladded nuclear valve parts

    International Nuclear Information System (INIS)

    Zhang Chunliang

    2000-01-01

    The microstructure and performances of the Co-base alloy coatings that are formed by laser cladding, plasma spurt welding and arc surfacing on the nuclear valve-sealing surface have been studied and compared. The combination costs of laser cladding, plasma spurt welding and arc, surfacing have been analyzed and compared. The results showed that the laser cladding processing has the advantages of high efficiency, low energy cost, a little machining allowance, high rate of finished products and low combination cost, compared with plasma spurt welding processing and arc surfacing processing. The laser cladding technology can improve the qualities of nuclear valve parts and increase their service life. Therefore, the laser cladding processing is a new technology with developing potential

  20. National need for utilizing nuclear energy for process heat generation

    International Nuclear Information System (INIS)

    Gambill, W.R.; Kasten, P.R.

    1984-01-01

    Nuclear reactors are potential sources for generating process heat, and their applications for such use economically competitive. They help satisfy national needs by helping conserve and extend oil and natural gas resources, thus reducing energy imports and easing future international energy concerns. Several reactor types can be utilized for generating nuclear process heat; those considered here are light water reactors (LWRs), heavy water reactors (HWRs), gas-cooled reactors (GCRs), and liquid metal reactors (LMRs). LWRs and HWRs can generate process heat up to 280 0 C, LMRs up to 540 0 C, and GCRs up to 950 0 C. Based on the studies considered here, the estimated process heat markets and the associated energy markets which would be supplied by the various reactor types are summarized

  1. The Multiple-Patient Simulation Toolkit: Purpose, Process, and Pilot.

    Science.gov (United States)

    Beroz, Sabrina; Sullivan, Nancy; Kramasz, Vanessa; Morgan, Patricia

    Educating nursing students to safely care for multiple patients has become an important but challenging focus for nurse educators. New graduate nurses are expected to manage care for multiple patients in a complex and multifaceted health care system. With patient safety as a priority, multiple-patient assignments are necessary in order for nursing students to learn how to effectively prioritize and delegate care. The purpose of this project was the construction of an adaptable and flexible template for the development of multiple-patient simulations. Through utilization, the template moved to a toolkit adding an operational guide, sample-populated template, and bibliography.

  2. Dynamics of process at the final stage of nuclear fission

    International Nuclear Information System (INIS)

    Koljari, I.G.; Mavlitov, N.D.

    2005-01-01

    Numerous experimental data show, that the final stage of nuclear fission near to a scission point plays an essential role at formation of characteristics of fission products. At the description of a final stage of fission there is a number of problems: Definition of the form of the nuclear near the scission point and definition forms of a fission fragments; The account of dynamic processes in compound nuclear directly before of fission. The condition of the quasistatic al adiabatic process - dS/dt=0 - is applied in a point of transition from the uniform compound nuclei to several forms for definition of generalized coordinates and speeds. Calculation of dependence of post neutrons from nuclear mass of fission fragments for reactions is α+ 83 Bi 209 → 85 At 213 (E lab = 45 MeV); α+ 92 U 242 → 94 Pu 242 (E lab = 45 MeV); 8 O 18 + 79 Au 197 → 97 Fr 215 (E lab = 159 MeV). System of equations, which describes behaviour of system in a point of nuclear fission-transition from the uniform form to system of a two (and, probably more) fission fragments is given. The system of the equations allows in a fission point to define the generalized coordinates, and the generalized speeds for each of the generalized coordinates of collective deformation variables

  3. Screen-based process control in nuclear plants

    International Nuclear Information System (INIS)

    Hinz, W.; Arnoldt, C.; Hessler, C.

    1993-01-01

    Requirements, development and conceptual design of a screen-based control room for nuclear power plants are outlined. The control room consists of three or four equally equipped operator workstations comprising screens for process information and manual process control. A plant overview will assist the coordination among the operators. A safety classified backup system (safety control area) is provided to cover postulated failures of the control means. Some aspects of ergonomical validation and of future development trends are discussed. (orig.) [de

  4. A novel digital pulse processing architecture for nuclear instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    Moline, Yoann; Thevenin, Mathieu; Corre, Gwenole [CEA, LIST - Laboratoire Capteurs et Architectures electroniques, F-91191 Gif-sur-Yvette, (France); Paindavoine, Michel [CNRS, Universite de Bourgogne - Laboratoire d' Etude de l' Apprentissage et du Developpement, 21000 DIJON, (France)

    2015-07-01

    The field of nuclear instrumentation covers a wide range of applications, including counting, spectrometry, pulse shape discrimination and multi-channel coincidence. These applications are the topic of many researches, new algorithms and implementations are constantly proposed thanks to advances in digital signal processing. However, these improvements are not yet implemented in instrumentation devices. This is especially true for neutron-gamma discrimination applications which traditionally use charge comparison method while literature proposes other algorithms based on frequency domain or wavelet theory which show better performances. Another example is pileups which are generally rejected while pileup correction algorithms also exist. These processes are traditionally performed offline due to two issues. The first is the Poissonian characteristic of the signal, composed of random arrival pulses which requires to current architectures to work in data flow. The second is the real-time requirement, which implies losing pulses when the pulse rate is too high. Despite the possibility of treating the pulses independently from each other, current architectures paralyze the acquisition of the signal during the processing of a pulse. This loss is called dead-time. These two issues have led current architectures to use dedicated solutions based on re-configurable components like Field Programmable Gate Arrays (FPGAs) to overcome the need of performance necessary to deal with dead-time. However, dedicated hardware algorithm implementations on re-configurable technologies are complex and time-consuming. For all these reasons, a programmable Digital pulse Processing (DPP) architecture in a high level language such as Cor C++ which can reduce dead-time would be worthwhile for nuclear instrumentation. This would reduce prototyping and test duration by reducing the level of hardware expertise to implement new algorithms. However, today's programmable solutions do not meet

  5. A novel digital pulse processing architecture for nuclear instrumentation

    International Nuclear Information System (INIS)

    Moline, Yoann; Thevenin, Mathieu; Corre, Gwenole; Paindavoine, Michel

    2015-01-01

    The field of nuclear instrumentation covers a wide range of applications, including counting, spectrometry, pulse shape discrimination and multi-channel coincidence. These applications are the topic of many researches, new algorithms and implementations are constantly proposed thanks to advances in digital signal processing. However, these improvements are not yet implemented in instrumentation devices. This is especially true for neutron-gamma discrimination applications which traditionally use charge comparison method while literature proposes other algorithms based on frequency domain or wavelet theory which show better performances. Another example is pileups which are generally rejected while pileup correction algorithms also exist. These processes are traditionally performed offline due to two issues. The first is the Poissonian characteristic of the signal, composed of random arrival pulses which requires to current architectures to work in data flow. The second is the real-time requirement, which implies losing pulses when the pulse rate is too high. Despite the possibility of treating the pulses independently from each other, current architectures paralyze the acquisition of the signal during the processing of a pulse. This loss is called dead-time. These two issues have led current architectures to use dedicated solutions based on re-configurable components like Field Programmable Gate Arrays (FPGAs) to overcome the need of performance necessary to deal with dead-time. However, dedicated hardware algorithm implementations on re-configurable technologies are complex and time-consuming. For all these reasons, a programmable Digital pulse Processing (DPP) architecture in a high level language such as Cor C++ which can reduce dead-time would be worthwhile for nuclear instrumentation. This would reduce prototyping and test duration by reducing the level of hardware expertise to implement new algorithms. However, today's programmable solutions do not meet

  6. Alarm processing system using AI techniques for nuclear power plant

    International Nuclear Information System (INIS)

    Yang, Joon On; Chang, Soon Heung

    1990-01-01

    An alarm processing system (APS) has been developed using artificial intelligence (AI) techniques. The alarms of nuclear power plants (NPP's) are classified into the generalized and special alarms. The generalized alarms are also classified into the global and local alarms. For each type of alarms, the specific processing rules are applied to filter and suppress unnecessary and potentially misleading alarms. The local processing are based on 'model-based reasoning.' The global and special alarms are processed by using the general cause-consequence check rules. The priorities of alarms are determined according to the plant state and the consistencies between them

  7. AI-based alarm processing for a nuclear power plant

    International Nuclear Information System (INIS)

    Na, N.J.; Kim, I.S.; Hwang, I.K.; Lee, D.Y.; Ham, C.S.

    1996-01-01

    A real-time expert system is implemented using artificial intelligence and object-oriented technology for alarm processing and presentation in a nuclear power plant. The knowledge base is constructed based on some schemes to process and display alarms to the plant operators. The activated alarms are dynamically prioritized by the reasoning rules, and then, presented on the process mimic overview and by some other means. To demonstrate the proposed system, the alarm processing and presentation is carried out in a simulated environment of the TMI-2 accident

  8. Sensitivity studies for the main r process: nuclear masses

    Directory of Open Access Journals (Sweden)

    A. Aprahamian

    2014-02-01

    Full Text Available The site of the rapid neutron capture process (r process is one of the open challenges in all of physics today. The r process is thought to be responsible for the creation of more than half of all elements beyond iron. The scientific challenges to understanding the origin of the heavy elements beyond iron lie in both the uncertainties associated with astrophysical conditions that are needed to allow an r process to occur and a vast lack of knowledge about the properties of nuclei far from stability. One way is to disentangle the nuclear and astrophysical components of the question. On the nuclear physics side, there is great global competition to access and measure the most exotic nuclei that existing facilities can reach, while simultaneously building new, more powerful accelerators to make even more exotic nuclei. On the astrophysics side, various astrophysical scenarios for the production of the heaviest elements have been proposed but open questions remain. This paper reports on a sensitivity study of the r process to determine the most crucial nuclear masses to measure using an r-process simulation code, several mass models (FRDM, Duflo-Zuker, and HFB-21, and three potential astrophysical scenarios.

  9. U.S. Nuclear Regulatory Commission Process for Risk-Informing the Nuclear Waste Arena

    International Nuclear Information System (INIS)

    Leslie, B. W.

    2003-01-01

    The U.S. Nuclear Regulatory Commission (NRC) is increasing the use of risk insights and information in its regulation of nuclear materials and waste. The objective of this risk-informed regulatory effort is to improve the effectiveness and efficiency of the agency, while maintaining or increasing its focus on safety. The agency's Office of Nuclear Material Safety and Safeguards (NMSS) proposed a five-step process to carry out a framework for increasing the use of risk information and insights in its regulation of nuclear materials and waste. The office is carrying out the five-step process to risk-inform the nuclear materials and waste arenas. NMSS's actions included forming a Risk Task Group and the use of case studies to test and complete screening criteria for identifying candidate regulatory applications amenable for risk-informing. Other actions included involving stakeholders through enhanced public participation, developing safety goals for materials and waste regulatory applications, and establishing a risk training program for staff. Through the case studies, NRC staff found the draft screening criteria to be effective in deciding regulatory areas that may be amenable to an increased use of risk insights. NRC staff also found that risk information may have the potential to reduce regulatory burden and improve staff's efficiency in making decisions, while maintaining safety. Finally, staff found that it would be possible to develop safety goals for the nuclear materials and waste arenas

  10. Mass estimation of loose parts in nuclear power plant based on multiple regression

    International Nuclear Information System (INIS)

    He, Yuanfeng; Cao, Yanlong; Yang, Jiangxin; Gan, Chunbiao

    2012-01-01

    According to the application of the Hilbert–Huang transform to the non-stationary signal and the relation between the mass of loose parts in nuclear power plant and corresponding frequency content, a new method for loose part mass estimation based on the marginal Hilbert–Huang spectrum (MHS) and multiple regression is proposed in this paper. The frequency spectrum of a loose part in a nuclear power plant can be expressed by the MHS. The multiple regression model that is constructed by the MHS feature of the impact signals for mass estimation is used to predict the unknown masses of a loose part. A simulated experiment verified that the method is feasible and the errors of the results are acceptable. (paper)

  11. Measurement of the nuclear multiplicity ratio for Ks0 hadronization at CLAS

    Science.gov (United States)

    Daniel, A.; Hicks, K.; Brooks, W. K.; Hakobyan, H.; Adhikari, K. P.; Adikaram, D.; Aghasyan, M.; Amarian, M.; Anghinolfi, M.; Avakian, H.; Baghdasaryan, H.; Battaglieri, M.; Batourine, V.; Bedlinskiy, I.; Bennett, R. P.; Biselli, A. S.; Bookwalter, C.; Briscoe, W. J.; Burkert, V. D.; Carman, D. S.; Casey, L.; Celentano, A.; Chandavar, S.; Cole, P. L.; Contalbrigo, M.; Crede, V.; D'Angelo, A.; Dashyan, N.; De Vita, R.; De Sanctis, E.; Deur, A.; Dey, B.; Dickson, R.; Djalali, C.; Dodge, G. E.; Doughty, D.; Egiyan, H.; El Fassi, L.; Elouadrhiri, L.; Eugenio, P.; Fedotov, G.; Fegan, S.; Gabrielyan, M. Y.; Gevorgyan, N.; Gilfoyle, G. P.; Giovanetti, K. L.; Girod, F. X.; Goetz, J. T.; Gohn, W.; Golovatch, E.; Gothe, R. W.; Griffioen, K. A.; Guidal, M.; Guo, L.; Hanretty, C.; Heddle, D.; Holtrop, M.; Hyde, C. E.; Ilieva, Y.; Ireland, D. G.; Ishkhanov, B. S.; Isupov, E. L.; Jawalkar, S. S.; Jo, H. S.; Joo, K.; Kalantarians, N.; Keller, D.; Khandaker, M.; Khetarpal, P.; Kim, A.; Kim, W.; Klein, A.; Klein, F. J.; Kubarovsky, V.; Kuleshov, S. V.; Kuznetsov, V.; Lu, H. Y.; MacGregor, I. J. D.; Mao, Y.; Markov, N.; Mayer, M.; McAndrew, J.; McKinnon, B.; Meyer, C. A.; Mineeva, T.; Mirazita, M.; Mokeev, V.; Moutarde, H.; Munevar, E.; Nadel-Turonski, P.; Ni, A.; Niccolai, S.; Niculescu, G.; Niculescu, I.; Osipenko, M.; Ostrovidov, A. I.; Paolone, M.; Pappalardo, L.; Paremuzyan, R.; Park, K.; Park, S.; Pasyuk, E.; Anefalos Pereira, S.; Phelps, E.; Pisano, S.; Pogorelko, O.; Pozdniakov, S.; Price, J. W.; Procureur, S.; Protopopescu, D.; Raue, B. A.; Ricco, G.; Rimal, D.; Ripani, M.; Rosner, G.; Rossi, P.; Sabatié, F.; Saini, M. S.; Salgado, C.; Schott, D.; Schumacher, R. A.; Seraydaryan, H.; Sharabian, Y. G.; Smith, G. D.; Sober, D. I.; Sokhan, D.; Stepanyan, S. S.; Stepanyan, S.; Strauch, S.; Taiuti, M.; Tang, W.; Taylor, C. E.; Tkachenko, S.; Ungaro, M.; Vernarsky, B.; Vineyard, M. F.; Voskanyan, H.; Voutier, E.; Watts, D. P.; Weinstein, L. B.; Weygand, D. P.; Wood, M. H.; Zana, L.; Zachariou, N.; Zhao, B.; Zhao, Z. W.

    2011-11-01

    The influence of cold nuclear matter on lepto-production of hadrons in semi-inclusive deep inelastic scattering is measured using the CLAS detector in Hall B at Jefferson Lab and a 5.014 GeV electron beam. We report the Ks0 multiplicity ratios for targets of C, Fe, and Pb relative to deuterium as a function of the fractional virtual photon energy z transferred to the Ks0 and the transverse momentum squared pT2 of the Ks0. We find that the multiplicity ratios for Ks0 are reduced in the nuclear medium at high z and low pT2, with a trend for the Ks0 transverse momentum to be broadened in the nucleus for large pT2.

  12. Pyrolytic electrochemical process for the reprocessing of irradiated nuclear fuels

    International Nuclear Information System (INIS)

    Brambilla, G.; Sartorelli, A.

    1980-01-01

    The reprocessing is aimed at synthetic UO 2 -PuO 2 mixed oxides, UC-PuC mixed carbides and at oxides and carbides of U, Pu and Th from fast nuclear reactors. The nuclear fuel is dissolved in a salt melting bath. The conversion of the Pu(SO 4 ) 2 is done thermally and that of UO 2 is done electrolytically. The molten salts are returned to the input of the process and the fission products and the molten salts are conditioned. (DG) [de

  13. Nuclear pulse signal processing technique based on blind deconvolution method

    International Nuclear Information System (INIS)

    Hong Pengfei; Yang Lei; Fu Tingyan; Qi Zhong; Li Dongcang; Ren Zhongguo

    2012-01-01

    In this paper, we present a method for measurement and analysis of nuclear pulse signal, with which pile-up signal is removed, the signal baseline is restored, and the original signal is obtained. The data acquisition system includes FPGA, ADC and USB. The FPGA controls the high-speed ADC to sample the signal of nuclear radiation, and the USB makes the ADC work on the Slave FIFO mode to implement high-speed transmission status. Using the LabVIEW, it accomplishes online data processing of the blind deconvolution algorithm and data display. The simulation and experimental results demonstrate advantages of the method. (authors)

  14. Method for treating a nuclear process off-gas stream

    International Nuclear Information System (INIS)

    Pence, D.T.; Chou, C.-C.

    1981-01-01

    A method is described for selectively removing and recovering the noble gas and other gaseous components typically emitted during nuclear process operations. The method is useful for treating dissolver off-gas effluents released during reprocessing of spent nuclear fuels to permit radioactive contaminant recovery prior to releasing the remaining off-gases to the atmosphere. The method involves a sequence of adsorption and desorption steps which are specified. Particular reference is made to the separation of xenon and krypton from the off-gas stream, and to the use of silver-exchanged mordenite as the adsorbent. (U.K.)

  15. Radioactive waste processing method for a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, Y; Kuriyama, O

    1976-06-04

    Object is to subject radioactive liquid waste in a nuclear power plant to reverse permeation process after which it is vaporized and concentrated thereby decreasing the quantity of foam to be used to achieve effective concentration of the liquid waste. Liquid waste containing a radioactive material produced from a nuclear power plant is first applied with pressure in excess of osmotic pressure by a reverse permeation device and is separated into clean water and concentrated liquid by semi-permeable membrane. Next, the thus reverse-permeated and concentrated waste is fed to an evaporator which control foaming by the foam and then further reconcentrated for purification of the liquid waste.

  16. Interim guidelines for protecting fire-fighting personnel from multiple hazards at nuclear plant sites

    International Nuclear Information System (INIS)

    Klein, A.R.; Bloom, C.W.

    1989-07-01

    This report provides interim guidelines for reducing the impact to fire fighting and other supporting emergency response personnel from the multiple hazards of radiation, heat stress, and trauma when fighting a fire in a United States commercial nuclear power plant. Interim guidelines are provided for fire brigade composition, training, equipment, procedures, strategies, heat stress and trauma. In addition, task definitions are provided to evaluate and further enhance the interim guidelines over the long term. 19 refs

  17. Thermionic nuclear reactor with internal heat distribution and multiple duct cooling

    Science.gov (United States)

    Fisher, C.R.; Perry, L.W. Jr.

    1975-11-01

    A Thermionic Nuclear Reactor is described having multiple ribbon-like coolant ducts passing through the core, intertwined among the thermionic fuel elements to provide independent cooling paths. Heat pipes are disposed in the core between and adjacent to the thermionic fuel elements and the ribbon ducting, for the purpose of more uniformly distributing the heat of fission among the thermionic fuel elements and the ducts.

  18. Uranium mining, processing and nuclear energy - opportunities for Australia?

    International Nuclear Information System (INIS)

    2006-12-01

    On 6 June 2006, the Prime Minister announced the appointment of a taskforce to undertake an objective, scientific and comprehensive review of uranium mining, value-added processing and the contribution of nuclear energy in Australia in the longer term. This is known as the Review of Uranium Mining Processing and Nuclear Energy in Australia, referred to in this report as the Review. The Prime Minister asked the Review to report by the end of 2006. A draft report was released for public comment on 21 November 2006 and was also reviewed by an expert panel chaired by the Chief Scientist (see Appendix F). The Review is grateful for comments provided on the draft report by members of the public. The report has been modified in the light of those comments. In response to its initial call for public comment in August 2006 the Review received over 230 submissions from interested parties. It also conducted a wide range of consultations with organisations and individuals in Australia and overseas, and commissioned specialist studies on various aspects of the nuclear industry. Participating in the nuclear fuel cycle is a difficult issue for many Australians and can elicit strong views. This report is intended to provide a factual base and an analytical framework to encourage informed community discussion. Australia's demand for electricity will more than double before 2050. Over this period, more than two-thirds of existing electricity generation will need to be substantially upgraded or replaced and new capacity added. The additional capacity will need to be near-zero greenhouse gas emitting technology if Australia is just to keep greenhouse gas emissions at today's levels. Many countries confront similar circumstances and have therefore considered the use of nuclear power for some of the following reasons: the relative cost competitiveness of nuclear power versus the alternatives; security of supply and independence from fossil fuel energy imports; diversity of domestic

  19. Nuclear Material Processing at the Savannah River Site

    International Nuclear Information System (INIS)

    Severynse, T.F.

    1998-07-01

    Plutonium production for national defense began at Savannah River in the mid-1950s, following construction of production reactors and separations facilities. Following the successful completion of its production mission, the site's nuclear material processing facilities continue to operate to perform stabilization of excess materials and potentially support the disposition of these materials. A number of restoration and productivity improvement projects implemented in the 1980s, totaling nearly a billion dollars, have resulted in these facilities representing the most modern and only remaining operating large-scale processing facilities in the DOE Complex. Together with the Site's extensive nuclear infrastructure, and integrated waste management system, SRS is the only DOE site with the capability and mission of ongoing processing operations

  20. Designing new nuclear chemical processing plants for safeguards accountability

    International Nuclear Information System (INIS)

    Sprouse, K.M.

    1987-01-01

    New nuclear chemical processing plants will be required to develop material accountability control limits from measurement error propagation analysis rather than historical inventory difference data as performed in the past. In order for measurement error propagation methods to be viable alternatives, process designers must ensure that two nondimensional accountability parameters are maintained below 0.1. These parameters are ratios between the material holdup increase and the variance in inventory difference measurement uncertainty. Measurement uncertainty data for use in error propagation analysis is generally available in the open literature or readily derived from instrument calibration data. However, nuclear material holdup data has not been adequately developed for use in the material accountability design process. Long duration development testing on isolated unit operations is required to generate this necessary information

  1. The r-process nucleosynthesis: Nuclear physics challenges

    Energy Technology Data Exchange (ETDEWEB)

    Goriely, S. [Institut d' Astronomie et d' Astrophysique, Universite Libre de Bruxelles Campus de la Plaine, CP 226, 1050 Brussels (Belgium)

    2012-10-20

    About half of the nuclei heavier than iron observed in nature are produced by the socalled rapid neutron capture process, or r-process, of nucleosynthesis. The identification of the astrophysics site and the specific conditions in which the r-process takes place remains, however, one of the still-unsolved mysteries of modern astrophysics. Another underlying difficulty associated with our understanding of the r-process concerns the uncertainties in the predictions of nuclear properties for the few thousands exotic neutron-rich nuclei involved and for which essentially no experimental data exist. The present contribution emphasizes some important future challenges faced by nuclear physics in this problem, particularly in the determination of the nuclear structure properties of exotic neutron-rich nuclei as well as their radiative neutron capture rates and their fission probabilities. These quantities are particularly relevant to determine the composition of the matter resulting from the r-process. Their impact on the r-abundance distribution resulting from the decompression of neutron star matter is discussed.

  2. DUPIC nuclear fuel manufacturing and process technology development

    International Nuclear Information System (INIS)

    Yang, Myung Seung; Park, J. J.; Lee, J. W.

    2000-05-01

    In this study, DUPIC fuel fabrication technology and the active fuel laboratory were developed for the study of spent nuclear fuel. A new nuclear fuel using highly radioactive nuclear materials can be studied at the active fuel laboratory. Detailed DUPIC fuel fabrication process flow was developed considering the manufacturing flow, quality control process and material accountability. The equipment layout of about twenty DUPIC equipment at IMEF M6 hot cell was established for the minimization of the contamination during DUPIC processes. The characteristics of the SIMFUEL powder and pellets was studied in terms of milling conditions. The characteristics of DUPIC powder and pellet was studied by using 1 kg of spent PWR fuel at PIEF nr.9405 hot cell. The results were used as reference process conditions for following DUPIC fuel fabrication at IMEF M6. Based on the reference fabrication process conditions, the main DUPIC pellet fabrication campaign has been started at IMEF M6 using 2 kg of spent PWR fuel since 2000 January. As of March 2000, about thirty DUPIC pellets were successfully fabricated

  3. DUPIC nuclear fuel manufacturing and process technology development

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Myung Seung; Park, J. J.; Lee, J. W. [and others

    2000-05-01

    In this study, DUPIC fuel fabrication technology and the active fuel laboratory were developed for the study of spent nuclear fuel. A new nuclear fuel using highly radioactive nuclear materials can be studied at the active fuel laboratory. Detailed DUPIC fuel fabrication process flow was developed considering the manufacturing flow, quality control process and material accountability. The equipment layout of about twenty DUPIC equipment at IMEF M6 hot cell was established for the minimization of the contamination during DUPIC processes. The characteristics of the SIMFUEL powder and pellets was studied in terms of milling conditions. The characteristics of DUPIC powder and pellet was studied by using 1 kg of spent PWR fuel at PIEF nr.9405 hot cell. The results were used as reference process conditions for following DUPIC fuel fabrication at IMEF M6. Based on the reference fabrication process conditions, the main DUPIC pellet fabrication campaign has been started at IMEF M6 using 2 kg of spent PWR fuel since 2000 January. As of March 2000, about thirty DUPIC pellets were successfully fabricated.

  4. CEQ regulations called peril to nuclear licensing process

    International Nuclear Information System (INIS)

    O'Neill, J.V.

    1979-01-01

    Court challenges are expected over regulations of the Council on Environmental Quality (CEQ) that were designed to improve nuclear-licensing decisions, but that have actually changed the meanings of National Environmental Policy Act (NEPA) regulations. The legal implications of these changes could, unless resolved, make the licensing process for nuclear facilities even more uncertain. Agency comments are thought to be critical, although the CEQ has declined to release them, and some question the Council's legality. The Nuclear Regulatory Commission faults the CEQ regulations for revising existing law, being inconsistent with the responsibilities of an independent regulatory body, and extending the CEQ's authority beyond the role assigned by NEPA and the President's Executive Order

  5. Proximal processes of children with profound multiple disabilities

    OpenAIRE

    Wilder, Jenny

    2008-01-01

    In this thesis four empirical studies dealt with children with profound multiple disabilities and their parents with regard to: (a) how parents perceived interaction with their children (b) how observed child/parent interaction was linked to behavior style of the children as perceived by the parents (c) how parents of children with profound multiple disabilities perceived child/parent interaction and behavior style of their children in comparison to parents to children without disabilities ma...

  6. Spectrophotometry with optical fibers applied to nuclear product processing

    International Nuclear Information System (INIS)

    Boisde, G.; Perez, J.J.; Velluet, M.T.; Jeunhomme, L.B.

    1988-01-01

    Absorption spectrophotometry is widely used in laboratories for composition analysis and quality control of chemical processes. Using optical fibers for transmitting the light between the instrument and the process line allows to improve the safety and productivity of chemical processes, thanks to real time measurements. Such applications have been developed since 1975 in CEA for the monitoring of nuclear products. This has led to the development of fibers, measurement cells, and optical feedthrough sustaining high radiation doses, of fiber/spectrophotometer couplers, and finally of a photodiode array spectrophotometer optimized for being used together with optical fibers [fr

  7. Theoretical studies of multistep processes. Isospin effects in nuclear scattering, and meson and baryon interactions in nuclear physics. Progress report

    International Nuclear Information System (INIS)

    Madsen, V.A.; Landau, R.H.

    1985-12-01

    Research on microscopic optical potentials, multistep processes, neutron-proton differences in nuclear vibrations, and exact calculations of Coulomb plus nuclear bound states of exotic systems is reported. 21 refs

  8. Control and data processing systems in UK nuclear power plant and nuclear facilities

    International Nuclear Information System (INIS)

    Baldwin, J.A.; Wall, D.N.

    1997-01-01

    This note identifies some of the data processing and control systems in UK nuclear power plant, with emphasis on direct digital control systems and sequence control. A brief indication is also given of some of the associated research activities on control systems and software. (author). 2 figs

  9. Control and data processing systems in UK nuclear power plant and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Baldwin, J A; Wall, D N [AEA Technology, Winfrith, Dorchester (United Kingdom)

    1997-07-01

    This note identifies some of the data processing and control systems in UK nuclear power plant, with emphasis on direct digital control systems and sequence control. A brief indication is also given of some of the associated research activities on control systems and software. (author). 2 figs.

  10. Covariant description of dynamical processes in relativistic nuclear matter

    International Nuclear Information System (INIS)

    Celenza, L.S.; Pantziris, A.; Shakin, C.M.

    1992-01-01

    We report results of covariant calculations of density-dependent polarization processes in relativistic nuclear matter. We consider the polarization induced by those mesons that play an important role in the boson-exchange model of nuclear forces (σ,π,ρ,ω). After obtaining the polarization operators, we construct the propagators for these mesons. The covariant nature of the calculation greatly clarifies the structure of the polarization operators and associated Green's functions. (In addition to the meson momentum, these quantities depend upon another four-vector, η μ , that describes the uniform motion of the medium.) In the case of the pion, we show that the same results are obtained for pseudovector or pseudoscalar coupling to the nucleon, if the associated Lagrangians are related by chiral transformations. Of particular interest are the extremely large values found for the polarization operators of the omega and sigma mesons. It is also found that the coupling of the sigma and omega fields through the polarization process is also extremely large. (Because of these results one cannot usefully consider the sigma and omega fields as independent degrees of freedom in nuclear matter.) We describe methods for reorganizing the calculation of ring diagrams in which we group those diagrams that exhibit strong cancellations. We also comment on the implication of our results for nuclear structure studies

  11. Towards A Unified HFE Process For The Nuclear Industry

    Energy Technology Data Exchange (ETDEWEB)

    Jacques Hugo

    2012-07-01

    As nuclear power utilities embark on projects to upgrade and modernize power plants, they are likely to discover that traditional engineering methods do not typically make provision for the integration of human considerations. In addition, human factors professionals will find that traditional human performance methods such as function allocation, task analysis, human reliability analysis and human-machine interface design do not scale well to the complexity of a large-scale nuclear power upgrade project. Up-to-date human factors engineering processes, methods, techniques and tools are required to perform these kinds of analyses. This need is recognized widely in industry and an important part of the Department of Energy’s Light Water Reactor Sustainability Program deals with identifying potential impacts of emerging technologies on human performance and the technical bases needed to address them. However, so far no formal initiative has been launched to deal with the lack of integrated processes. Although human factors integration frameworks do exist in industries such as aviation or defense, no formal integrated human factors process exists in the nuclear industry. As a first step towards creating such a process, a “unified human factors engineering process” is proposed as a framework within which engineering organizations, human factors practitioners and regulatory bodies can ensure that human factors requirements are embedded in engineering activities throughout the upgrade project life cycle.

  12. Electrosleeve process for in-situ nuclear steam generator repair

    International Nuclear Information System (INIS)

    Renaud, E.; Brennenstuhl, A.M.; Stewart, D.R.; Gonzalez, F.

    2000-01-01

    Degradation of steam generator tubing by localized corrosion is a widespread problem in the nuclear industry that can lead to costly forced outages, unit derating, steam generator replacement or even the permanent shutdown of a reactor. In response to the onset of steam generator degradation at Ontario Power Generation's Pickering Nuclear Generating Station (PNGS) Unit 5, and the determined unsuitability of conventional repair methods (mechanically expanded or welded sleeves) for Alloy 400, an alternative repair technology was developed. Electrosleeve is a non-intrusive, low-temperature process that involves the electrodeposition of a nanocrystalline nickel microalloy forming a continuously bonded, structural layer over the internal diameter of the degraded region. This technology is designed to provide a long-term pressure boundary repair, fully restoring the structural integrity of the damaged region to its original state. This paper describes the Electrosleeve process for steam generator tubing repair and the unique properties of the advanced sleeve material. The successful installation of fourteen Electrosleeves that have been in service for more than six years in Alloy 400 tubing at the Pickering-S CANDU unit, and the more recent (Nov. 99) extension of the technology to Alloy 600 by the installation of 57 sleeves in a U.S. pressurized water reactor (PWR) at Callaway, is presented. The Electrosleeve process has been granted a conditional license by the U.S. Nuclear Regulatory Commission (NRC). In Canada, the process of licensing Electrosleeve with the CNSC / TSSA has begun. (author)

  13. Once-through hybrid sulfur process for nuclear hydrogen production

    International Nuclear Information System (INIS)

    Jeong, Y. H.

    2008-01-01

    Increasing concern about the global climate change spurs the development of low- or zero-carbon energy system. Nuclear hydrogen production by water electrolysis would be the one of the short-term solutions, but low efficiency and high production cost (high energy consumption) is the technical hurdle to be removed. In this paper the once-through sulfur process composed of the desulfurization and the water electrolysis systems is proposed. Electrode potential for the conventional water electrolysis (∼2.0 V) can be reduced significantly by the anode depolarization using sulfur dioxide: down to 0.6 V depending on the current density This depolarized electrolysis is the electrolysis step of the hybrid sulfur process originally proposed by the Westinghouse. However; recycling of sulfur dioxide requires a high temperature heat source and thus put another technical hurdle on the way to nuclear hydrogen production: the development of high temperature nuclear reactors and corresponding sulfuric acid decomposition system. By the once-through use of sulfur dioxide rather than the closed recycle, the hurdle can be removed. For the sulfur feed, the desulfurization system is integrated into the water electrolysis system. Fossil fuels include a few percent of sulfur by weight. During the refinement or energy conversion, most of the sulfur should be separated The separated sulfur can be fed to the water electrolysis system and the final product would be hydrogen and sulfuric acid, which is number one chemical in the world by volume. Lowered electrode potential and additional byproduct, the sulfuric acid, can provide economically affordable hydrogen. In this study, the once-through hybrid sulfur process for hydrogen production was proposed and the process was optimized considering energy consumption in electrolysis and sulfuric acid concentration. Economic feasibility of the proposed process was also discussed. Based on currently available experimental data for the electrode

  14. Nuclear effects in the Drell-Yan process.

    Energy Technology Data Exchange (ETDEWEB)

    Raufeisen, J. (Jorg)

    2002-01-01

    In the target rest frame and at high energies, Drell-Yan (DY) dilepton production looks like bremsstrahlung of massive photons, rather than parton annihilation. The projectile quark is decomposed into a series of Fock states. Configurations with fixed transverse separations in impact parameter space are interaction eigenstates for p p scattering. The DY cross section can then be expressed in terms of the same color dipole cross section as DIS. We compare calculations in this dipole approach with E772 data and with next-to-leading order parton model calculations. This approach is especially suitable to describe nuclear effects, since it allows one to apply Glauber multiple scattering theory. We go beyond the Glauber eikonal approximation by taking into account transitions between states, which would be eigenstates for a proton target. We calculate nuclear shadowing at large Feynman-x{sub F} for DY in proton-nucleus collisions and compare to E772 data. Nuclear effects on the transverse momentum distribution are also investigated.

  15. A full scope nuclear power plant simulator for multiple reactor types with virtual control panels

    International Nuclear Information System (INIS)

    Yonezawa, Hisanori; Ueda, Hiroki; Kato, Takahisa

    2017-01-01

    This paper summarizes a full scope nuclear power plant simulator for multiple reactor types with virtual control panels which Toshiba developed and delivered. After the Fukushima DAIICHI nuclear power plants accident, it is required that all the people who are engaged in the design, manufacturing, operation, maintenance, management and regulation for the nuclear power plant should learn the wide and deep knowledge about the nuclear power plant design including the severe accident. For this purpose, the training with a full scope simulator is one of the most suitable ways. However the existing full scope simulators which are consist of the control panels replica of the referenced plants are costly and they are hard to remodel to fit to the real plant of the latest condition. That's why Toshiba developed and delivered the new concept simulator system which covers multiple referenced plants even though they have different design like BWR and PWR. The control panels of the simulator are made by combining 69 large Liquid Crystal Display (LCD) panels with touch screen instead of a control panel replica of referenced plant. The screen size of the each panel is 42 inches and 3 displays are arranged in tandem for one unit and 23 units are connected together. Each panel displays switches, indicators, recorders and lamps with the Computer Graphics (CG) and trainees operate them with touch operations. The simulator includes a BWR and a PWR simulator model, which enable trainees to learn the wide and deep knowledge about the nuclear power plant of BWR and PWR reactor types. (author)

  16. Progress on China nuclear data processing code system

    Science.gov (United States)

    Liu, Ping; Wu, Xiaofei; Ge, Zhigang; Li, Songyang; Wu, Haicheng; Wen, Lili; Wang, Wenming; Zhang, Huanyu

    2017-09-01

    China is developing the nuclear data processing code Ruler, which can be used for producing multi-group cross sections and related quantities from evaluated nuclear data in the ENDF format [1]. The Ruler includes modules for reconstructing cross sections in all energy range, generating Doppler-broadened cross sections for given temperature, producing effective self-shielded cross sections in unresolved energy range, calculating scattering cross sections in thermal energy range, generating group cross sections and matrices, preparing WIMS-D format data files for the reactor physics code WIMS-D [2]. Programming language of the Ruler is Fortran-90. The Ruler is tested for 32-bit computers with Windows-XP and Linux operating systems. The verification of Ruler has been performed by comparison with calculation results obtained by the NJOY99 [3] processing code. The validation of Ruler has been performed by using WIMSD5B code.

  17. Potential industrial market for process heat from nuclear reactors

    International Nuclear Information System (INIS)

    Barnes, R.W.

    1976-07-01

    A specific segment of industrial process heat use has been examined in detail to identify individual plant locations throughout the United states where nuclear generated steam may be a viable alternative. Five major industries have been studied: paper, chemicals, petroleum, rubber, and primary metals. For these industries, representing 75 percent of the total industrial steam consumption, the individual plant locations within the U.S. using steam in large quantities have been located and characterized as to fuel requirements

  18. Simulation of land mine detection processes using nuclear techniques

    International Nuclear Information System (INIS)

    Aziz, M.

    2005-01-01

    A computer models were designed to study the processes of land mine detection using nuclear technique. Parameters that affect the detection were analyzed . Mines of different masses at different depths in the soil are considered using two types of sources , 252 C f and 14 MeV neutron source. The capability to differentiate between mines and other objects such as concrete , iron , wood , Aluminum ,water and polyethylene were analyzed and studied

  19. Nuclear structure in cold rearrangement processes in fission and fusion

    Energy Technology Data Exchange (ETDEWEB)

    Armbruster, P.

    1998-11-01

    In fission and fusion of heavy nuclei large numbers of nucleons are rearranged at a scale of excitation energy very small compared to the binding energy of the nuclei. The energies involved are less than 40 MeV at nuclear temperatures below 1.5 MeV. The shapes of the configurations in the rearrangement of a binary system into a monosystem in fusion, or vice versa in fission, change their elongations by as much as 8 fm, the radius of the monosystem. The dynamics of the reactions macroscopically described by a potential energy surface, inertia parameters, dissipation, and a collision energy is strongly modified by the nuclear structure of the participating nuclei. Experiments showing nuclear structure effects in fusion and fission of the heaviest nuclei are reviewed. The reaction kinematics and the multitude of isotopes involved are investigated by detector techniques and by recoil spectrometers. The advancement of the latter allows to find very small reaction branches in the range of 10{sup -5} to 10{sup -10}. The experiments reveal nuclear structure effects in all stages of the rearrangement processes. These are discussed pointing to analogies in fusion and fission on the microscopic scale, notwithstanding that both processes macroscopically are irreversible. Heavy clusters, as 132Sn, 208Pb, nuclei with closed shell configurations N=82,126, Z=50,82 survive in large parts of the nuclear rearrangement. They determine the asymmetry in the mass distribution of low energy fission, and they allow to synthesise superheavy elements, until now up to element 112. Experiments on the cold rearrangement in fission and fusion are presented. Here, in the range of excitation energies below 12 MeV the phenomena are observed most convincingly. (orig.)

  20. Safety implications of computerized process control in nuclear power plants

    International Nuclear Information System (INIS)

    1991-02-01

    Modern nuclear power plants are making increasing use of computerized process control because of the number of potential benefits that accrue. This practice not only applies to new plants but also to those in operation. Here, the replacement of both conventional process control systems and outdated computerized systems is seen to be of benefit. Whilst this contribution is obviously of great importance to the viability of nuclear electricity generation, it must be recognized that there are major safety concerns in taking this route. However, there is the potential for enhancing the safety of nuclear power plants if the full power of microcomputers and the associated electronics is applied correctly through well designed, engineered, installed and maintained systems. It is essential that areas where safety can be improved be identified and that the pitfalls are clearly marked so that they can be avoided. The deliberations of this Technical Committee Meeting are a step on the road to this goal of improved safety through computerized process control. This report also contains the papers presented at the technical committee meeting by participants. A separate abstract was prepared for each of these 15 presentations. Refs, figs and tabs

  1. Identification and characterization of multiple conserved nuclear localization signals within adenovirus E1A

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, Kris S.; Cohen, Michael J.; Fonseca, Greg J.; Todorovic, Biljana; King, Cason R. [Department of Microbiology and Immunology, Western University, London Regional Cancer Program, London, ON, Canada N6A 4L6 (Canada); Yousef, Ahmed F. [Department of Chemical and Environmental Engineering, Masdar Institute, Abu Dhabi (United Arab Emirates); Zhang, Zhiying [College of Animal Science and Technologies, Northwest A and F University, Yangling, Shaanxi 712100 (China); Mymryk, Joe S., E-mail: jmymryk@uwo.ca [Department of Microbiology and Immunology, Western University, London Regional Cancer Program, London, ON, Canada N6A 4L6 (Canada); Department of Oncology, Western University, London Regional Cancer Program, London, ON, Canada N6A 4L6 (Canada)

    2014-04-15

    The human adenovirus 5 (HAdV-5) E1A protein has a well defined canonical nuclear localization signal (NLS) located at its C-terminus. We used a genetic assay in the yeast Saccharomyces cerevisiae to demonstrate that the canonical NLS is present and functional in the E1A proteins of each of the six HAdV species. This assay also detects a previously described non-canonical NLS within conserved region 3 and a novel active NLS within the N-terminal/conserved region 1 portion of HAdV-5 E1A. These activities were also present in the E1A proteins of each of the other five HAdV species. These results demonstrate that, despite substantial differences in primary sequence, HAdV E1A proteins are remarkably consistent in that they contain one canonical and two non-canonical NLSs. By utilizing independent mechanisms, these multiple NLSs ensure nuclear localization of E1A in the infected cell. - Highlights: • HAdV E1A uses multiple mechanisms for nuclear import. • We identified an additional non-canonical NLS in the N-terminal/CR1 portion of E1A. • The new NLS does not contact importin-alpha directly. • All NLSs are functionally conserved in the E1A proteins of all 6 HAdV species.

  2. Application of the parallel processing computer to a nuclear disaster prevention support system

    Energy Technology Data Exchange (ETDEWEB)

    Shigehiro, Nukatsuka; Osami, Watanabe [Mitsubishi Heavy Industries, LTD (Japan)

    2003-07-01

    At the time of nuclear emergency, it is important to identify the type and the cause of the accident. Besides with these, it is also important to provide adequate information for the emergency response organization to support decision making by predicting and evaluating the development of the event and the influence of the release of radioactivity for the environment. Recently, a new type of nuclear disaster prevention support system called MEASURES (Multiple Radiological Emergency Assistance System for Urgent Response) was developed which provides not only the current state of the nuclear power plant and the influence of the radioactivity for the environment, but also the future prediction of the accident development. In order to provide the accurate results of these analyses quickly, MEASURES utilizes various techniques, such as multiple nesting method which narrows down the calculation area gradually, and parallel processing computer for three dimensional analyses, such as air current distribution analysis. In this paper, the outline and the feature of MEASURES are presented, especially focused on the usage of parallel processing computer for the three dimensional air current distribution analysis. (authors)

  3. Application of the parallel processing computer to a nuclear disaster prevention support system

    International Nuclear Information System (INIS)

    Shigehiro, Nukatsuka; Osami, Watanabe

    2003-01-01

    At the time of nuclear emergency, it is important to identify the type and the cause of the accident. Besides with these, it is also important to provide adequate information for the emergency response organization to support decision making by predicting and evaluating the development of the event and the influence of the release of radioactivity for the environment. Recently, a new type of nuclear disaster prevention support system called MEASURES (Multiple Radiological Emergency Assistance System for Urgent Response) was developed which provides not only the current state of the nuclear power plant and the influence of the radioactivity for the environment, but also the future prediction of the accident development. In order to provide the accurate results of these analyses quickly, MEASURES utilizes various techniques, such as multiple nesting method which narrows down the calculation area gradually, and parallel processing computer for three dimensional analyses, such as air current distribution analysis. In this paper, the outline and the feature of MEASURES are presented, especially focused on the usage of parallel processing computer for the three dimensional air current distribution analysis. (authors)

  4. Pedagogical Affordances of Multiple External Representations in Scientific Processes

    Science.gov (United States)

    Wu, Hsin-Kai; Puntambekar, Sadhana

    2012-01-01

    Multiple external representations (MERs) have been widely used in science teaching and learning. Theories such as dual coding theory and cognitive flexibility theory have been developed to explain why the use of MERs is beneficial to learning, but they do not provide much information on pedagogical issues such as how and in what conditions MERs…

  5. Prescription-induced jump distributions in multiplicative Poisson processes.

    Science.gov (United States)

    Suweis, Samir; Porporato, Amilcare; Rinaldo, Andrea; Maritan, Amos

    2011-06-01

    Generalized Langevin equations (GLE) with multiplicative white Poisson noise pose the usual prescription dilemma leading to different evolution equations (master equations) for the probability distribution. Contrary to the case of multiplicative Gaussian white noise, the Stratonovich prescription does not correspond to the well-known midpoint (or any other intermediate) prescription. By introducing an inertial term in the GLE, we show that the Itô and Stratonovich prescriptions naturally arise depending on two time scales, one induced by the inertial term and the other determined by the jump event. We also show that, when the multiplicative noise is linear in the random variable, one prescription can be made equivalent to the other by a suitable transformation in the jump probability distribution. We apply these results to a recently proposed stochastic model describing the dynamics of primary soil salinization, in which the salt mass balance within the soil root zone requires the analysis of different prescriptions arising from the resulting stochastic differential equation forced by multiplicative white Poisson noise, the features of which are tailored to the characters of the daily precipitation. A method is finally suggested to infer the most appropriate prescription from the data.

  6. Prescription-induced jump distributions in multiplicative Poisson processes

    Science.gov (United States)

    Suweis, Samir; Porporato, Amilcare; Rinaldo, Andrea; Maritan, Amos

    2011-06-01

    Generalized Langevin equations (GLE) with multiplicative white Poisson noise pose the usual prescription dilemma leading to different evolution equations (master equations) for the probability distribution. Contrary to the case of multiplicative Gaussian white noise, the Stratonovich prescription does not correspond to the well-known midpoint (or any other intermediate) prescription. By introducing an inertial term in the GLE, we show that the Itô and Stratonovich prescriptions naturally arise depending on two time scales, one induced by the inertial term and the other determined by the jump event. We also show that, when the multiplicative noise is linear in the random variable, one prescription can be made equivalent to the other by a suitable transformation in the jump probability distribution. We apply these results to a recently proposed stochastic model describing the dynamics of primary soil salinization, in which the salt mass balance within the soil root zone requires the analysis of different prescriptions arising from the resulting stochastic differential equation forced by multiplicative white Poisson noise, the features of which are tailored to the characters of the daily precipitation. A method is finally suggested to infer the most appropriate prescription from the data.

  7. Automated system for processing nuclear emulsion data on nuclear-nuclear interactions for EMU-15 CERN experiment

    International Nuclear Information System (INIS)

    Aleksandrov, A.B.; Azarenkova, I.Yu.; Feinberg, E.L.; Goneharova, L.A.; Martynov, A.G.; Polukhina, N.G.; Starkov, N.I.

    2004-01-01

    The EMU-15 experiment has been performed at CERN by the LPI group with the aim of studying characteristics of high-density and high-temperature nuclear matter, in particular, for searching for manifestation of quark-gluon plasma. The main problem inherent in these investigations is a large amount of track measurements in nuclear emulsions. A very efficient Completely Automated Measuring Complex (Russian abbreviation sounds as P AVICOM ) for track-detector data processing in nuclear and high-energy particle physics is operating at the Lebedev Physical Institute. The PAVICOM provides essential improving the efficiency of experimental studies performed not only by the LPI group, but also by many Russian Institutes

  8. The regulatory process for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1990-01-01

    The objective of this publication is to provide general guidance to Member States for regulating the decommissioning of nuclear facilities within the established nuclear regulatory framework. The Guide should also be useful to those responsible for, or interested in, the decommissioning of nuclear facilities. The Guide describes in general terms the process to be used in regulating decommissioning and the considerations to be applied in the development of decommissioning regulations and guides. It also delineates the responsibilities of the regulatory body and the licensee in decommissioning. The provisions of this Guide are intended to apply to all facilities within the nuclear fuel cycle and larger industrial installations using long lived radionuclides. For smaller installations, however, less extensive planning and less complex regulatory control systems should be acceptable. The Guide deals primarily with decommissioning after planned shutdown. Most provisions, however, are also applicable to decommissioning after an abnormal event, once cleanup operations have been terminated. The decommissioning planning in this case must take account of the abnormal event. 28 refs, 1 fig

  9. Process for the fabrication of nuclear fuel oxide pellets

    International Nuclear Information System (INIS)

    Francois, Bernard; Paradis, Yves.

    1977-01-01

    Process for the fabrication of nuclear fuel oxide pellets of the type for which particles charged with an organic binder -selected from the group that includes polyvinyl alcohol, carboxymethyl cellulose, polyvinyl compounds and methyl cellulose- are prepared from a powder of such an oxide, for instance uranium dioxide. These particles are then compressed into pellets which are then sintered. Under this process the binder charged particles are prepared by stirring the powder with a gas, spraying on to the stirred powder a solution or a suspension in a liquid of this organic binder in order to obtain these particles and then drying the particles so obtained with this gas [fr

  10. Seismic PSA method for multiple nuclear power plants in a site

    Energy Technology Data Exchange (ETDEWEB)

    Hakata, Tadakuni [Nuclear Safety Commission, Tokyo (Japan)

    2007-07-15

    The maximum number of nuclear power plants in a site is eight and about 50% of power plants are built in sites with three or more plants in the world. Such nuclear sites have potential risks of simultaneous multiple plant damages especially at external events. Seismic probabilistic safety assessment method (Level-1 PSA) for multi-unit sites with up to 9 units has been developed. The models include Fault-tree linked Monte Carlo computation, taking into consideration multivariate correlations of components and systems from partial to complete, inside and across units. The models were programmed as a computer program CORAL reef. Sample analysis and sensitivity studies were performed to verify the models and algorithms and to understand some of risk insights and risk metrics, such as site core damage frequency (CDF per site-year) for multiple reactor plants. This study will contribute to realistic state of art seismic PSA, taking consideration of multiple reactor power plants, and to enhancement of seismic safety. (author)

  11. Centrality Dependence of Hadron Multiplicities in Nuclear Collisions in the Dual Parton Model

    CERN Document Server

    Capella, A

    2001-01-01

    We show that, even in purely soft processes, the hadronic multiplicity in nucleus-nucleus interactions contains a term that scales with the number of binary collisions. In the absence of shadowing corrections, this term dominates at mid rapidities and high energies. Shadowing corrections are calculated as a function of impact parameter and the centrality dependence of mid-rapidity multiplicities is determined. The multiplicity per participant increases with centrality with a rate that increases between SPS and RHIC energies, in agreement with experiment.

  12. Multiplicity distributions and multiplicity correlations in sequential, off-equilibrium fragmentation process

    International Nuclear Information System (INIS)

    Botet, R.

    1996-01-01

    A new kinetic fragmentation model, the Fragmentation - Inactivation -Binary (FIB) model is described where a dissipative process stops randomly the sequential, conservative and off-equilibrium fragmentation process. (K.A.)

  13. Processes of hydrogen production, coupled with nuclear reactors: Economic perspectives

    International Nuclear Information System (INIS)

    Werkoff, Francois; Avril, Sophie; Mansilla, Christine; Sigurvinsson, Jon

    2006-01-01

    Hydrogen production, using nuclear power is considered from a technic-economic (TE) point of view. Three different processes are examined: Alkaline electrolysis, High-temperature steam electrolysis (HTE) and the thermochemical Sulphur-Iodine (S/I) cycle. The three processes differ, in the sense that the first one is operational and both last ones are still at demonstration stages. For them, it is at present only possible to identify key points and limits of competitiveness. The cost of producing hydrogen by alkaline electrolysis is analysed. Three major contributions to the production costs are examined: the electricity consumption, the operation and maintenance expenditures and the depreciation capital expenditures. A technic-economic evaluation of hydrogen production by HTE coupled to a high-temperature reactor (HTR) is presented. Key points appear to be the electrolyser and the high temperature heat exchangers. The S/I thermochemical cycle is based on the decomposition and the re-composition of H 2 SO 4 and HI acids. The energy consumption and the recovery of iodine are key points of the S/I cycle. With the hypothesis that the hydrogen energy will progressively replace the fossil fuels, we give a first estimate of the numbers of nuclear reactors (EPR or HTR) that would be needed for a massive nuclear hydrogen production. (authors)

  14. Electrosleeve process for in-situ nuclear steam generator repair

    International Nuclear Information System (INIS)

    Barton, R.A.; Moran, T.E.; Renaud, E.

    1997-01-01

    Degradation of steam generator (SG) tubing by localized corrosion is a widespread problem in the nuclear industry that can lead to costly forced out-ages, unit de-rating, SG replacement or even the permanent shutdown of a reactor. In response to the onset of SG tubing degradation at Ontario Hydro's Pickering Nuclear Generating Station (PNGS) Unit 5, and the determined unsuitability of conventional repair methods (mechanically expanded or welded sleeves) for Alloy 400, an alternative repair technology was developed. Electrosleeve is a non-intrusive, low-temperature process that involves the electrodeposition of a nanocrystalline nickel microalloy forming a continuously bonded, structural layer over the internal diameter of the degraded region. This technology is designed to provide a long-term pressure boundary repair, fully restoring the structural integrity of the damaged region to its original state. This paper describes the Electrosleeve process for SG tubing repair and the unique properties of the advanced sleeve material. The successful installation of Electrosleeves that have been in service for more than three years in Alloy 400 SG tubing at the Pickering-5 CANDU unit, the more recent extension of the technology to Alloy 600 and its demonstration in a U.S. pressurized water reactor (PWR), is presented. A number of PWR operators have requested plant operating technical specification changes to permit Electrosleeve SG tube repair. Licensing of the Electrosleeve by the U.S. Nuclear Regulatory Commission (NRC) is expected imminently. (author)

  15. Multiplicity of nuclear receptor activation by PFOA and PFOS in primary human and rodent hepatocytes

    International Nuclear Information System (INIS)

    Bjork, J.A.; Butenhoff, J.L.; Wallace, K.B.

    2011-01-01

    Perfluorooctanoate (PFOA) and perfluorooctanesulfonate (PFOS) are surface active fluorochemicals that, due to their exceptional stability to degradation, are persistent in the environment. Both PFOA and PFOS are eliminated slowly in humans, with geometric mean serum elimination half-lives estimated at 3.5 and 4.8 years, respectively. The biological activity of PFOA and PFOS in rodents is attributed primarily to transactivation of the nuclear receptor peroxisome proliferator activated receptor alpha (PPARA), which is an important regulator of lipid and carbohydrate metabolism. However, there are significant species-specific differences in the response to PFOA and PFOS exposure; non-rodent species, including humans, are refractory to several but not all of these effects. Many of the metabolic effects have been attributed to the activation of PPARA; however, recent studies using PPARα knockout mice demonstrate residual PPARA-independent effects, some of which may involve the activation of alternate nuclear receptors, including NR1I2 (PXR), NR1I3 (CAR), NR1H3 (LXRA), and NR1H4 (FXR). The objective of this investigation was to characterize the activation of multiple nuclear receptors and modulation of metabolic pathways associated with exposure to PFOA and PFOS, and to compare and contrast the effects between rat and human primary liver cells using quantitative reverse transcription PCR (RT-qPCR). Our results demonstrate that multiple nuclear receptors participate in the metabolic response to PFOA and PFOS exposure resulting in a substantial shift from carbohydrate metabolism to fatty acid oxidation and hepatic triglyceride accumulation in rat liver cells. This shift in intermediary metabolism was more pronounced for PFOA than PFOS. Furthermore, while there is some similarity in the activation of metabolic pathways between rat and humans, particularly in PPARA regulated responses; the changes in primary human cells were more subtle and possibly reflect an adaptive

  16. Public perception process of nuclear power risk and some enlightenment to public education for nuclear power acceptance

    International Nuclear Information System (INIS)

    Yang Bo

    2013-01-01

    This paper, based on the international research literatures on perception of risks, designs a conceptual model of public perception of nuclear power risk. In this model, it is considered that the public perception of nuclear power risk is a dynamic, complicate and closed system and is a process from subjective perception to objective risk. Based on the features of the public perception of nuclear power risk and multi-faceted dimension influences as discussed, suggestions for the public education for nuclear power acceptance are given in five aspects with indication that the public education for nuclear power acceptance plays an important role in maintaining the public perception of nuclear power risk system. (author)

  17. Advanced Bayesian processing of clinical data in nuclear medicine

    International Nuclear Information System (INIS)

    Jirsa, L.

    1999-11-01

    The Bayesian methodology was applied with a view to improving the quality of thyroid gland disease treatment at a nuclear medicine department. The specific tasks included: formulation of the estimation tasks from the theoretical point of view; elaborating algorithms to estimate various physical, medical and dosimetric quantities used in radiodiagnosis and radiotherapy of thyroid gland diseases; testing their numerical precision; testing their numerical stability on a large set of clinical data; implementation of the algorithms at a level applicable in routine conditions of the nuclear medicine department and replace by them the data processing methods used there so far; exploring and testing the quality improvement of the estimates; and in dependence on the results, proposing hints where improvement of the data measurement methodology is necessary

  18. A multiple sampling time projection ionization chamber for nuclear fragment tracking and charge measurement

    International Nuclear Information System (INIS)

    Bauer, G.; Bieser, F.; Brady, F.P.; Chance, J.C.; Christie, W.F.; Gilkes, M.; Lindenstruth, V.; Lynen, U.; Mueller, W.F.J.; Romero, J.L.; Sann, H.; Tull, C.E.; Warren, P.

    1997-01-01

    A detector has been developed for the tracking and charge measurement of the projectile fragment nuclei produced in relativistic nuclear collisions. This device, MUSIC II, is a second generation Multiple Sampling Ionization Chamber (MUSIC), and employs the principles of ionization and time projection chambers. It provides unique charge determination for charges Z≥6, and excellent track position measurement. MUSIC II has been used most recently with the EOS (equation of state) TPC and other EOS collaboration detectors. Earlier it was used with other systems in experiments at the Heavy Ion Superconducting Spectrometer (HISS) facility at Lawrence Berkeley Laboratory and the ALADIN spectrometer at GSI. (orig.)

  19. Modern integrated environmental monitoring and processing systems for nuclear facilities

    International Nuclear Information System (INIS)

    Oprea, I.

    2000-01-01

    The continuous activity to survey and monitor releases and the current radiation levels in the vicinity of a nuclear object is essential for person and environment protection. Considering the vast amount of information and data needed to keep an updated overview of a situation both during the daily surveillance work and during accident situations, the need for an efficient monitoring and processing system is evident. The rapid development, both in computer technology and in telecommunications, the evolution of fast and accurate computer codes enabling the on-line calculations improve the quality of decision-making in complex situations and assure a high efficiency. The monitoring and processing systems are used both for environmental protection and for controlling nuclear power plant emergency and post-accident situations. Such a system can offer information to the radiation management systems in order to assess the consequences of nuclear accidents and to establish a basis for right decisions in civil defense. The integrated environmental monitoring systems have as main task to record, collect, process and transmit the radiation levels and weather data, incorporating a number of stationary or mobile radiation monitoring equipment, weather parameter measuring station, an information processing center and the communication network, all running under a real-time operating system.They provide the automatic data collection on-line and off-line, remote diagnostic, advanced presentation techniques, including a graphically oriented executive support, which has the ability to respond to an emergency by geographical representation of the hazard zones on the map. The systems are based on local intelligent measuring and transmission units, simultaneous processing and data presentation using a real-time operating system for personal computers and geographical information system (GIS). All information can be managed directly from the map by multilevel data retrieving and

  20. Radiation processing of biological tissues for nuclear disaster management

    International Nuclear Information System (INIS)

    Singh, Rita

    2012-01-01

    A number of surgical procedures require tissue substitutes to repair or replace damaged or diseased tissues. Biological tissues from human donor like bone, skin, amniotic membrane and other soft tissues can be used for repair or reconstruction of the injured part of the body. Tissues from human donor can be processed and banked for orthopaedic, spinal, trauma and other surgical procedures. Allograft tissues provide an excellent alternative to autografts. The use of allograft tissue avoids the donor site morbidity and reduces the operating time, expense and trauma associated with the acquisition of autografts. Further, allografts have the added advantage of being available in large quantities. This has led to a global increase in allogeneic transplantation and development of tissue banking. However, the risk of infectious disease transmission via tissue allografts is a major concern. Therefore, tissue allografts should be sterilized to make them safe for clinical use. Radiation processing has well appreciated technological advantages and is the most suitable method for sterilization of biological tissues. Radiation processed biological tissues can be provided by the tissue banks for the management of injuries due to a nuclear disaster. A nuclear detonation will result in a large number of casualties due to the heat, blast and radiation effects of the weapon. Skin dressings or skin substitutes like allograft skin, xenograft skin and amniotic membrane can be used for the treatment of thermal burns and radiation induced skin injuries. Bone grafts can be employed for repairing fracture defects, filling in destroyed regions of bone, management of open fractures and joint injuries. Radiation processed tissues have the potential to repair or reconstruct damaged tissues and can be of great assistance in the treatment of injuries due to the nuclear weapon. (author)

  1. Two-dimensional multiplicity fluctuation analysis of target residues in nuclear collisions

    International Nuclear Information System (INIS)

    Dong-Hai, Zhang; Yao-Jie, Niu; Li-Chun, Wang; Wen-Jun, Yan; Li-Juan, Gao; Ming-Xing, Li; Li-Ping, Wu; Hui-Ling, Li; Jun-Sheng, Li

    2010-01-01

    Multiplicity fluctuation of the target residues emitted in the interactions in a wide range of projectile energies from 500 A MeV to 60 A GeV is investigated in the framework of two-dimensional scaled factorial moment methodology. The evidence of non-statistical multiplicity fluctuation is found in 16 O–AgBr collisions at 60 A GeV, but not in 56 Fe–AgBr collisions at 500 A MeV, 84 Kr–AgBr collisions at 1.7 A GeV, 16 O–AgBr collisions at 3.7 A GeV and 197 Au–AgBr collisions at 10.7 A GeV. (nuclear physics)

  2. A stochastic model of multiple scattering of charged particles: process, transport equation and solutions

    International Nuclear Information System (INIS)

    Papiez, L.; Moskvin, V.; Tulovsky, V.

    2001-01-01

    The process of angular-spatial evolution of multiple scattering of charged particles can be described by a special case of Boltzmann integro-differential equation called Lewis equation. The underlying stochastic process for this evolution is the compound Poisson process on the surface of the unit sphere. The significant portion of events that constitute compound Poisson process that describes multiple scattering have diffusional character. This property allows to analyze the process of angular-spatial evolution of multiple scattering of charged particles as combination of soft and hard collision processes and compute appropriately its transition densities. These computations provide a method of the approximate solution to the Lewis equation. (orig.)

  3. Evidence for simultaneous syntactic processing of multiple words during reading

    NARCIS (Netherlands)

    Snell, Joshua; Meeter, Martijn; Grainger, Jonathan

    2017-01-01

    A hotly debated issue in reading research concerns the extent to which readers process parafoveal words, and how parafoveal information might influence foveal word recognition. We investigated syntactic word processing both in sentence reading and in reading isolated foveal words when these were

  4. Effect of multiplicative noise on stationary stochastic process

    Science.gov (United States)

    Kargovsky, A. V.; Chikishev, A. Yu.; Chichigina, O. A.

    2018-03-01

    An open system that can be analyzed using the Langevin equation with multiplicative noise is considered. The stationary state of the system results from a balance of deterministic damping and random pumping simulated as noise with controlled periodicity. The dependence of statistical moments of the variable that characterizes the system on parameters of the problem is studied. A nontrivial decrease in the mean value of the main variable with an increase in noise stochasticity is revealed. Applications of the results in several physical, chemical, biological, and technical problems of natural and humanitarian sciences are discussed.

  5. Newly Developed Software Application for Multiple Access Process Planning

    Directory of Open Access Journals (Sweden)

    Katarina Monkova

    2014-11-01

    Full Text Available The purchase of a complex system for computer aided process planning (CAPP can be expensive for little and some middle sized plants, sometimes an inaccessible investment, with a long recoupment period. According to this fact and the author's experience with Eastern European plants, they decided to design a new database application which is suitable for production, stock, and economic data holding as well as processing and exploitation within the manufacturing process. The application can also be used to process a plan according to the selected criteria, for technological documentation and NC program creation. It was based on the theory of a multivariant approach to computer aided plan generation. Its fundamental features, the internal mathematical structure and new code system of processed objects, were prepared by the authors. The verification of the designed information system in real practice has shown that it enables about 30% cost and production time reduction and decreases input material assortment variability.

  6. The Development of Advanced Processing and Analysis Algorithms for Improved Neutron Multiplicity Measurements

    International Nuclear Information System (INIS)

    Santi, P.; Favalli, A.; Hauck, D.; Henzl, V.; Henzlova, D.; Ianakiev, K.; Iliev, M.; Swinhoe, M.; Croft, S.; Worrall, L.

    2015-01-01

    One of the most distinctive and informative signatures of special nuclear materials is the emission of correlated neutrons from either spontaneous or induced fission. Because the emission of correlated neutrons is a unique and unmistakable signature of nuclear materials, the ability to effectively detect, process, and analyze these emissions will continue to play a vital role in the non-proliferation, safeguards, and security missions. While currently deployed neutron measurement techniques based on 3He proportional counter technology, such as neutron coincidence and multiplicity counters currently used by the International Atomic Energy Agency, have proven to be effective over the past several decades for a wide range of measurement needs, a number of technical and practical limitations exist in continuing to apply this technique to future measurement needs. In many cases, those limitations exist within the algorithms that are used to process and analyze the detected signals from these counters that were initially developed approximately 20 years ago based on the technology and computing power that was available at that time. Over the past three years, an effort has been undertaken to address the general shortcomings in these algorithms by developing new algorithms that are based on fundamental physics principles that should lead to the development of more sensitive neutron non-destructive assay instrumentation. Through this effort, a number of advancements have been made in correcting incoming data for electronic dead time, connecting the two main types of analysis techniques used to quantify the data (Shift register analysis and Feynman variance to mean analysis), and in the underlying physical model, known as the point model, that is used to interpret the data in terms of the characteristic properties of the item being measured. The current status of the testing and evaluation of these advancements in correlated neutron analysis techniques will be discussed

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

    International Nuclear Information System (INIS)

    Romine, D.T.

    1989-01-01

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

  8. Cogeneration using a nuclear reactor to generate process heat

    International Nuclear Information System (INIS)

    Alonso, Gustavo; Ramirez, Ramon

    2009-01-01

    Some of the new nuclear reactor technologies (Generation III+) are claiming the production of process heat as an additional value to electricity generation. These technologies are still under development and none of them has shown how this can be possible and what will be the penalty in electricity generation to have this additional product. The current study assess the likeliness of generate process heat from a Pebble Bed Modular Reactor to be used for a refinery showing different plant balance and alternatives to produce and use that process heat. An actual practical example is presented to demonstrate the cogeneration viability using the fact that the PBMR is a modular small reactor and also the challenges that this option has. (author)

  9. Nuclear information needs for the astrophysical s-process

    Energy Technology Data Exchange (ETDEWEB)

    Mathews, G.J.; Howard, W.M.; Takahashi, K.; Ward, R.A.

    1986-01-01

    The astrophysical s-process is a sequence of neutron-capture and beta-decay reactions on a slow time scale compared to beta-decay lifetimes near the line of stability. This detailed sequence of neutron capture, continuum and bound-state beta decay, positron decay, and electron-capture reactions that comprise the s-process has been studied for a broad range of astrophysical environments. The results are then compared with the solar-system abundancies of heavy elements to determine the range of physical conditions responsible for their nucleosynthesis. The nuclear data needs are extensive but have begun to be precise enough to allow for a consistent interpretation of the astrophysical site for the s-process.

  10. Nuclear information needs for the astrophysical s-process

    Energy Technology Data Exchange (ETDEWEB)

    Mathews, G.J.; Howard, W.M.; Takahashi, K.; Ward, R.A.

    1985-05-01

    The astrophysical s-process is a sequence of neutron-capture and beta-decay reactions on a slow time scale compared to beta-decay lifetimes near the line of stability. We systematically study this detailed sequence of neutron capture, continuum and bound-state beta decay, positron decay, and electron-capture reactions that comprise the s-process for a broad range of astrophysical environments. Our results are then compared with the solar-system abundances of heavy elements to determine the range of physical conditions responsible for their nucleosynthesis. The nuclear data needs are extensive but have begun to be precise enough to allow for a consistent interpretation of the astrophysical site for the s-process.

  11. Design and analysis of nuclear processes with the APROS

    International Nuclear Information System (INIS)

    Haenninen, M.; Puska, E.K.; Nystroem, P.

    1987-01-01

    APROS (Advanced Process Simulator) is the product being developed in the process simulators project of Imatran Voima Co. and Technical Research Centre of Finland. The aim is to design and construct an efficient and easy to use computer simulation system for process and automation system design, evaluation, analysis, testing and training purposes. As halfway of this project a working system exists with a large number of proven routines and models. However, a lot of development is still foreseen before the project will be finished. This article gives an overview of the APROS in general and of the nuclear features in particular. The calculational capabilities of the system are presented with the help of one example. (orig.)

  12. Radioanalytical Chemistry for Automated Nuclear Waste Process Monitoring

    International Nuclear Information System (INIS)

    Egorov, Oleg B.; Grate, Jay W.; DeVol, Timothy A.

    2004-01-01

    This research program is directed toward rapid, sensitive, and selective determination of beta and alpha-emitting radionuclides such as 99Tc, 90Sr, and trans-uranium (TRU) elements in low activity waste (LAW) processing streams. The overall technical approach is based on automated radiochemical measurement principles, which entails integration of sample treatment and separation chemistries and radiometric detection within a single functional analytical instrument. Nuclear waste process streams are particularly challenging for rapid analytical methods due to the complex, high-ionic-strength, caustic brine sample matrix, the presence of interfering radionuclides, and the variable and uncertain speciation of the radionuclides of interest. As a result, matrix modification, speciation control, and separation chemistries are required for use in automated process analyzers. Significant knowledge gaps exist relative to the design of chemistries for such analyzers so that radionuclides can be quantitatively and rapidly separated and analyzed in solutions derived from low-activity waste processing operations. This research is addressing these knowledge gaps in the area of separation science, nuclear detection, and analytical chemistry and instrumentation. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for sample matrix modification and analyte speciation control and chemistries for rapid and selective separation and preconcentration of target radionuclides from complex sample matrices. In addition, new approaches for quantification of alpha emitters in solution using solid-state diode detectors, as well as improved instrumentation and signal processing techniques for use with solid-state and scintillation detectors, will be developed. New knowledge of the performance of separation materials, matrix modification and speciation control chemistries, instrument configurations, and quantitative analytical approaches will

  13. Estimation methods for process holdup of special nuclear materials

    International Nuclear Information System (INIS)

    Pillay, K.K.S.; Picard, R.R.; Marshall, R.S.

    1984-06-01

    The US Nuclear Regulatory Commission sponsored a research study at the Los Alamos National Laboratory to explore the possibilities of developing statistical estimation methods for materials holdup at highly enriched uranium (HEU)-processing facilities. Attempts at using historical holdup data from processing facilities and selected holdup measurements at two operating facilities confirmed the need for high-quality data and reasonable control over process parameters in developing statistical models for holdup estimations. A major effort was therefore directed at conducting large-scale experiments to demonstrate the value of statistical estimation models from experimentally measured data of good quality. Using data from these experiments, we developed statistical models to estimate residual inventories of uranium in large process equipment and facilities. Some of the important findings of this investigation are the following: prediction models for the residual holdup of special nuclear material (SNM) can be developed from good-quality historical data on holdup; holdup data from several of the equipment used at HEU-processing facilities, such as air filters, ductwork, calciners, dissolvers, pumps, pipes, and pipe fittings, readily lend themselves to statistical modeling of holdup; holdup profiles of process equipment such as glove boxes, precipitators, and rotary drum filters can change with time; therefore, good estimation of residual inventories in these types of equipment requires several measurements at the time of inventory; although measurement of residual holdup of SNM in large facilities is a challenging task, reasonable estimates of the hidden inventories of holdup to meet the regulatory requirements can be accomplished through a combination of good measurements and the use of statistical models. 44 references, 62 figures, 43 tables

  14. Radioanalytical Chemistry for Automated Nuclear Waste Process Monitoring

    International Nuclear Information System (INIS)

    Egorov, Oleg B.; Grate, Jay W.; DeVol, Timothy A.

    2003-01-01

    This research program is directed toward rapid, sensitive, and selective determination of beta and alpha-emitting radionuclides such as 99Tc, 90Sr, and trans-uranium (TRU) elements in low activity waste (LAW) processing streams. The overall technical approach is based on automated radiochemical measurement principles. Nuclear waste process streams are particularly challenging for rapid analytical methods due to the complex, high- ionic-strength, caustic brine sample matrix, the presence of interfering radionuclides, and the variable and uncertain speciation of the radionuclides of interest. As a result, matrix modification, speciation control, and separation chemistries are required for use in automated process analyzers. Significant knowledge gaps exist relative to the design of chemistries for such analyzers so that radionuclides can be quantitatively and rapidly separated and analyzed in solutions derived from low-activity waste processing operations. This research is addressing these knowledge gaps in the area of separation science, nuclear detection, and analytical chemistry and instrumentation. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for sample matrix modification and analyte speciation control and chemistries for rapid and selective separation and preconcentration of target radionuclides from complex sample matrices. In addition, new approaches for quantification of alpha emitters in solution using solid state diode detectors, as well as improved instrumentation and signal processing techniques for use with solid-state and scintillation detectors, will be developed. New knowledge of the performance of separation materials, matrix modification and speciation control chemistries, instrument configurations, and quantitative analytical approaches will provide the basis for designing effective instrumentation for radioanalytical process monitoring. Specific analytical targets include 99 Tc, 90Sr and

  15. Scientific Opportunities to Reduce Risk in Nuclear Process Science

    International Nuclear Information System (INIS)

    Bredt, Paul R.; Felmy, Andrew R.; Gauglitz, Phillip A.; Hobbs, David T.; Krahn, Steve; Machara, N.; Mcilwain, Michael; Moyer, Bruce A.; Poloski, Adam P.; Subramanian, K.; Vienna, John D.; Wilmarth, B.

    2008-01-01

    Cleaning up the nation's nuclear weapons complex remains as one of the most technologically challenging and financially costly problems facing the U.S. Department of Energy (DOE). Safety, cost, and technological challenges have often delayed progress in retrieval, processing, and final disposition of high-level waste, spent nuclear fuel, and challenging materials. Some of the issues result from the difficulty and complexity of the technological issues; others have programmatic bases, such as contracting strategies that may provide undue focus on near-term, specific clean-up goals or difficulty in developing and maintaining stakeholder confidence in the proposed solutions. We propose that independent basic fundamental science research focused on the full cleanup life-cycle offers an opportunity to help address these challenges by providing (1) scientific insight into the fundamental mechanisms involved in currently selected processing and disposal options, (2) a rational path to the development of alternative technologies should the primary options fail, (3) confidence that models that predict long-term performance of different disposal options are based upon the best available science, (4) fundamental science discovery that enables transformational solutions to revolutionize the current baseline processes.

  16. Some computer applications and digital image processing in nuclear medicine

    International Nuclear Information System (INIS)

    Lowinger, T.

    1981-01-01

    Methods of digital image processing are applied to problems in nuclear medicine imaging. The symmetry properties of central nervous system lesions are exploited in an attempt to determine the three-dimensional radioisotope density distribution within the lesions. An algorithm developed by astronomers at the end of the 19th century to determine the distribution of matter in globular clusters is applied to tumors. This algorithm permits the emission-computed-tomographic reconstruction of spherical lesions from a single view. The three-dimensional radioisotope distribution derived by the application of the algorithm can be used to characterize the lesions. The applicability to nuclear medicine images of ten edge detection methods in general usage in digital image processing were evaluated. A general model of image formation by scintillation cameras is developed. The model assumes that objects to be imaged are composed of a finite set of points. The validity of the model has been verified by its ability to duplicate experimental results. Practical applications of this work involve quantitative assessment of the distribution of radipharmaceuticals under clinical situations and the study of image processing algorithms

  17. Liquid radwaste processing history at Fort Calhoun Nuclear Station

    International Nuclear Information System (INIS)

    Bilau, A.; Rutar, F.

    1989-01-01

    This report presents a historical perspective of liquid radwaste processing at the Fort Calhoun Unit 1 Nuclear Power Station, located in east central Nebraska. Of particular interest is the textual and graphical comparison of the operational implications of the various waste processing methods employed in the last ten years at the Fort Calhoun Station. Fort Calhoun's waste collection and processing systems are described in detail. These process systems include evaporation and solidification employing an in-plant drum solidification system. This solidification system was later replaced with vendor solidification services which solidified wastes in large liners. Ultimately, the plant converted its processing operation to ion exchange cleanup using ion selective media. The operational and economic impact of each of these process systems is discussed including overall costs, personnel exposure, capital expenditure requirements, burial volumes generated, maintenance and reliability assessments. Operational goals and performance criteria employed in the decision-making process for selection of the optimal technology are discussed, including the impact of various influent and effluent requirements

  18. Astrophysical r- and rp-processes, and radioactive nuclear beams

    International Nuclear Information System (INIS)

    Boyd, Richard N.

    1998-01-01

    The modern description of the r-process follows naturally from α-rich freezeout, thought to occur in the hot neutrino wind just beyond the nascent neutron star in a type II supernova. Initially, all pre-existing nuclei are reduced to α-particles and neutrons. As the environment cools, nuclei up to about mass 90 to 100 u are synthesized, in nuclear statistical equilibrium, in about 1 s. In the next few seconds, the remaining neutrons are captured to form the r-process progenitors, which then decay to the r-process nuclides. The rp-process occurs in a high-temperature H-rich environment. It is one of the processes that synthesize the p-process nuclei, the most neutron-poor nuclei in the periodic table. It is thought to occur during the explosion of a C-O white dwarf in a type Ia supernova or in a binary system during accretion onto a white dwarf or a neutron star. It appears to be capable of forming the p-nuclei up to about mass 90 u. Both processes pass through nuclei that are far from stability. Thus, their description requires the masses, half-lives, decay modes, and structure of these nuclei. The next generation of radioactive beam facilities promises to allow the study of many such nuclei. (author)

  19. The role of women in nuclear - attracting public participation in regulatory decision-making process

    Science.gov (United States)

    Mohamad Jais, Azlina; Hassan, Najwa

    2018-01-01

    Public participation is vital in demonstrating transparency and enhancing effectiveness of a nuclear regulatory process. As such, it is necessary for nuclear practitioners to involve the public in key nuclear delivery milestones. This paper specifically discusses challenges faced in attracting public participation throughout the nuclear regulatory decision-making process, and highlights the roles of women in nuclear (WiN) in initiating the said public discourse.

  20. Simultaneous energy harvesting and information processing in wireless multiple relays with multiple antennas

    Science.gov (United States)

    Albaaj, Azhar; Makki, S. Vahab A.; Alabkhat, Qassem; Zahedi, Abdulhamid

    2017-07-01

    Wireless networks suffer from battery discharging specially in cooperative communications when multiple relays have an important role but they are energy constrained. To overcome this problem, energy harvesting from radio frequency signals is applied to charge the node battery. These intermediate nodes have the ability to harvest energy from the source signal and use the energy harvested to transmit information to the destination. In fact, the node tries to harvest energy and then transmit the data to destination. Division of energy harvesting and data transmission can be done in two algorithms: time-switching-based relaying protocol and power-splitting-based relaying protocol. These two algorithms also can be applied in delay-limited and delay-tolerant transmission systems. The previous works have assumed a single relay for energy harvesting, but in this article, the proposed method is concentrated on improving the outage probability and throughput by using multiple antennas in each relay node instead of using single antenna. According to our simulation results, when using multi-antenna relays, ability of energy harvesting is increased and thus system performance will be improved to great extent. Maximum ratio combining scheme has been used when the destination chooses the best signal of relays and antennas satisfying the required signal-to-noise ratio.

  1. Process to separate transuranic elements from nuclear waste

    International Nuclear Information System (INIS)

    Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

    1989-01-01

    A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs

  2. Radiation processing program at the Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Khairul Zaman

    2007-01-01

    Radiation processing technology has been proven to enhance industrial efficiency and productivity, improve product quality and competitiveness. For many years, variety of radiation crosslinkable materials based on synthetic polymers have been studied at the Malaysian Nuclear Agency either in the form of thermoplastic resins, polymer blends or composites. At present, effort is focused towards developing new materials based on natural polymers such as natural rubber and rubber based products, palm oil and palm oil based products and polysaccharide. In this respect, the most challenging issues are to develop new materials/products that have commercial value and to bring the products from laboratory to market. (author)

  3. Process to separate transuranic elements from nuclear waste

    Science.gov (United States)

    Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

    1989-03-21

    A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

  4. Review of multigroup nuclear cross-section processing

    Energy Technology Data Exchange (ETDEWEB)

    Trubey, D.K.; Hendrickson, H.R. (comps.)

    1978-10-01

    These proceedings consist of 18 papers given at a seminar--workshop on ''Multigroup Nuclear Cross-Section Processing'' held at Oak Ridge, Tennessee, March 14--16, 1978. The papers describe various computer code systems and computing algorithms for producing multigroup neutron and gamma-ray cross sections from evaluated data, and experience with several reference data libraries. Separate abstracts were prepared for 13 of the papers. The remaining five have already been cited in ERA, and may be located by referring to the entry CONF-780334-- in the Report Number Index. (RWR)

  5. Synthesis of hydrocarbons using coal and nuclear process heat

    International Nuclear Information System (INIS)

    Eickhoff, H.G.; Kugeler, K.

    1975-01-01

    An analysis of the global petroleum resources and demand shows that the amount of mineral oil products is sufficient to meet the requirements of the next decades. The geographical resources, however, could lead to problems of distribution and foreign exchange. The production of hydrocarbons with coal as basis using high temperature nuclear process heat has advantages compared to the conventional techniques. Next to the conservation of reserve fossil primary energy carriers there are advantages as regards prices, which at high coal costs are especially pronounced. (orig.) [de

  6. NHI economic analysis of candidate nuclear hydrogen processes

    International Nuclear Information System (INIS)

    Allen, D.; Pickard, P.; Patterson, M.; Sink, C.

    2010-01-01

    The DOE Nuclear Hydrogen Initiative (NHI) is investigating candidate technologies for large scale hydrogen production using high temperature gas-cooled reactors (HTGR) in concert with the Next Generation Nuclear Plant (NGNP) programme. The candidate processes include high temperature thermochemical and high temperature electrolytic processes which are being investigated in a sequence of experimental and analytic studies to establish the most promising and cost effective means of hydrogen production with nuclear energy. Although these advanced processes are in an early development stage, it is important that the projected economic potential of these processes be evaluated to assist in the prioritisation of research activities, and ultimately in the selection of the most promising processes for demonstration and deployment. The projected cost of hydrogen produced is the most comprehensive metric in comparing candidate processes. Since these advanced processes are in the early stages of development and much of the technology is still unproven, the estimated production costs are also significantly uncertain. The programme approach has been to estimate the cost of hydrogen production from each process periodically, based on the best available data at that time, with the intent of increasing fidelity and reducing uncertainty as the research programme and system definition studies progress. These updated cost estimates establish comparative costs at that stage of development but are also used as inputs to the evaluation of research priorities, and identify the key cost and risk (uncertainty) drivers for each process. The economic methodology used to assess the candidate processes are based on the H2A ground rules and modelling tool (discounted cash flow) developed by the DOE Office of Energy Efficiency and Renewable Energy (EERE). The figure of merit output from the calculation is the necessary selling price for hydrogen in dollars per kilogram that satisfies the cost

  7. Prioritisation process for decommissioning of the Iraq former nuclear complex

    International Nuclear Information System (INIS)

    Jarjies, Adnan; Abbas, Mohammed; Fernandes, Horst M.; Coates, Roger

    2008-01-01

    There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive waste. The principal nuclear site is Al-Tuwaitha, the former nuclear research centre. Many of these sites suffered substantial physical damage during the Gulf Wars and have been subjected to subsequent looting. All require decommissioning in order to ensure both radiological and non-radiological safety. However, it is not possible to undertake the decommissioning of all sites and facilities at the same time. Therefore, a prioritization methodology has been developed in order to aid the decision-making process. The methodology comprises three principal stages of assessment: 1) a quantitative surrogate risk assessment, 2) a range of sensitivity analyses and 3) the inclusion of qualitative modifying factors. A group of five Tuwaitha facilities presented the highest evaluated risk, followed by a middle ranking grouping of Tuwaitha facilities and some other sites, with a relatively large number of lower risk facilities and sites comprising a third group. This initial risk-based order of priority is changed when modifying factors are taken into account. It is necessary to take account of Iraq's isolation from the international nuclear community over the last two decades and the lack of experienced personnel. Therefore it is appropriate to initiate decommissioning operations on selected low risk facilities at Tuwaitha in order to build capacity/experience and prepare for work to be carried out in more complex and potentially high hazard facilities. In addition it is appropriate to initiate some prudent precautionary actions relating to some of the higher risk facilities. (author)

  8. Streamline processing of discrete nuclear spectra by means of authoregularized iteration process (the KOLOBOK code)

    International Nuclear Information System (INIS)

    Gadzhokov, V.; Penev, I.; Aleksandrov, L.

    1979-01-01

    A brief description of the KOLOBOK computer code designed for streamline processing of discrete nuclear spectra with symmetric Gaussian shape of the single line on computers of the ES series, models 1020 and above, is given. The program solves the stream of discrete-spectrometry generated nonlinear problems by means of authoregularized iteration process. The Fortran-4 text of the code is reported in an Appendix

  9. Novel scaling of the multiplicity distributions in the sequential fragmentation process and in the percolation

    International Nuclear Information System (INIS)

    Botet, R.

    1996-01-01

    A novel scaling of the multiplicity distributions is found in the shattering phase of the sequential fragmentation process with inhibition. The same scaling law is shown to hold in the percolation process. (author)

  10. Associated multiplicity of γ-particles in processes of lepton pair production on nuclei

    International Nuclear Information System (INIS)

    Gevorkyan, S.R.; Gulkanyan, H.R.; Vartanyan, V.A.

    1986-01-01

    An expression has been obtained for mean multiplicity of g-particles accompanying the process of deep-inelastic lepton pair production on nuclei. The expression allows one to get information on structure peculiarities of leading hadron in this process

  11. Health physics self-assessment and the nuclear regulatory oversight process at a nuclear power plant

    International Nuclear Information System (INIS)

    Schofield, R.S.

    2003-01-01

    The U.S. Nuclear Regulatory Commission has developed improvements in their Nuclear Power Plant inspection, assessment and enforcement practices. The objective of these changes was to link regulatory action with power plant performance through a risk- informed process which is intended to enhance objectivity. One of the Strategic Performance Areas of focus by the U.S. NRC is radiation safety. Two cornerstones, Occupational Radiation Safety and Public Radiation Safety, make up this area. These cornerstones are being evaluated through U.S. NRC Performance Indicators (PI) and baseline site inspections. Key to the U.S. NRC's oversight program is the ability of the licensee to implement a self-assessment program which pro-actively identifies potential problems and develops improvements to enhance management's effectiveness. The Health Physics Self-Assessment Program at San Onofre Nuclear Generating Station (SONGS) identifies radiation protection-related weakness or negative trends. The intended end result is improved performance through rapid problem identification, timely evaluation, corrective action and follow-up effectiveness reviews. A review of the radiation protection oversight process and the SONGS Health Physics Self-Assessment Program will be presented. Lessons learned and management tools, which evaluate workforce and Health Physics (HP) staff performance to improve radiological practices, are discussed. (author)

  12. Determining of the nuclear composition of primary cosmic rays from the experimental distributions of multiple muons in atmospheric showers

    International Nuclear Information System (INIS)

    Beshtoev, Kh.M.

    1993-01-01

    Various approaches are discussed for determining the nuclear composition of the primary cosmic radiation from the distributions of multiple muons. Results are presented of calculations of the distributions of multiple muons for A 1 , A 4 , A 14 , A 26 , A 56 nuclei for an infinite plane and for the underground scintillation telescope of the Institute for Nuclear Research of the Academy of Sciences of Russia.The most suitable technique for determination of the primary nuclear composition of cosmic rays from the distribution of multiple muons is shown to be the approximate solution of a set of N equations, in which the respective coefficients of the contributions of various nuclei A i (i=1-N) to the primary composition serve as variables, while the remaining parts of these equations are the distributions of multiple muons obtained experimentally. 7 refs.; 2 tabs

  13. Digital image processing for radiography in nuclear power plants

    International Nuclear Information System (INIS)

    Heidt, H.; Rose, P.; Raabe, P.; Daum, W.

    1985-01-01

    With the help of digital processing of radiographic images from reactor-components it is possible to increase the security and objectiveness of the evaluation. Several examples of image processing procedures (contrast enhancement, density profiles, shading correction, digital filtering, superposition of images etc.) show the advantages for the visualization and evaluation of radiographs. Digital image processing can reduce some of the restrictions of radiography in nuclear power plants. In addition a higher degree of automation can be cost-saving and increase the quality of radiographic evaluation. The aim of the work performed was to to improve the readability of radiographs for the human observer. The main problem is lack of contrast and the presence of disturbing structures like weld seams. Digital image processing of film radiographs starts with the digitization of the image. Conventional systems use TV-cameras or scanners and provide a dynamic range of 1.5. to 3 density units, which are digitized to 256 grey levels. For the enhancement process it is necessary that the grey level range covers the density range of the important regions of the presented film. On the other hand the grey level coverage should not be wider than necessary to minimize the width of digitization steps. Poor digitization makes flaws and cracks invisible and spoils all further image processing

  14. Models for multiple relaxation processes in collagen fiber

    Indian Academy of Sciences (India)

    ... originate from stress strain induced changes in hydrogen bond network whereas the other seems to be more strongly coupled to salt like bridges and electrostatic interactions. Urea alters the activation energy for one relaxation step while pH and solvent dielectric constant alter the relaxation behavior one set of processes.

  15. Friction modeling on multiple scales for Deep drawing processes

    NARCIS (Netherlands)

    Karupannasamy, Dinesh Kumar

    2013-01-01

    A deep drawing process is one of the widely used manufacturing techniques in the automotive industry because of its capability to produce complex shapes with sheet material, often performed using lubricants to ease the forming. Finite Element Methods (FEM) are popularly used at the design stage to

  16. 75 FR 63725 - Nuclear Energy Institute; Consideration of Petition in the Rulemaking Process

    Science.gov (United States)

    2010-10-18

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Part 70 [Docket No. PRM-70-8; NRC-2009-0184] Nuclear Energy Institute; Consideration of Petition in the Rulemaking Process AGENCY: Nuclear Regulatory Commission. ACTION... Commission (NRC) will consider five of the issues raised in a petition submitted by the Nuclear Energy...

  17. Initial results from a multiple monoenergetic gamma radiography system for nuclear security

    Science.gov (United States)

    O'Day, Buckley E.; Hartwig, Zachary S.; Lanza, Richard C.; Danagoulian, Areg

    2016-10-01

    The detection of assembled nuclear devices and concealed special nuclear materials (SNM) such as plutonium or uranium in commercial cargo traffic is a major challenge in mitigating the threat of nuclear terrorism. Currently available radiographic and active interrogation systems use ∼1-10 MeV bremsstrahlung photon beams. Although simple to build and operate, bremsstrahlung-based systems deliver high radiation doses to the cargo and to potential stowaways. To eliminate problematic issues of high dose, we are developing a novel technique known as multiple monoenergetic gamma radiography (MMGR). MMGR uses ion-induced nuclear reactions to produce two monoenergetic gammas for dual-energy radiography. This allows us to image the areal density and effective atomic number (Zeff) of scanned cargo. We present initial results from the proof-of-concept experiment, which was conducted at the MIT Bates Research and Engineering Center. The purpose of the experiment was to assess the capabilities of MMGR to measure areal density and Zeff of container cargo mockups. The experiment used a 3.0 MeV radiofrequency quadrupole accelerator to create sources of 4.44 MeV and 15.11 MeV gammas from the 11B(d,nγ)12C reaction in a thick natural boron target; the gammas are detected by an array of NaI(Tl) detectors after transmission through cargo mockups . The measured fluxes of transmitted 4.44 MeV and 15.11 MeV gammas were used to assess the areal density and Zeff. Initial results show that MMGR is capable of discriminating the presence of high-Z materials concealed in up to 30 cm of iron shielding from low- and mid-Z materials present in the cargo mockup.

  18. Secondary resources processing in production of nuclear grade yellow cake

    International Nuclear Information System (INIS)

    Sivasubramanian, S.

    2009-01-01

    Full text: Recovering uranium in a cost competitive manner from sources other than the uranium ore is considered necessary from the point of view of meeting the strategic as well as the nuclear power programme need of the country. Globally, uranium is produced from ores which have more than 10 times uranium content compared to those available in India. Secondary sources of uranium are mostly defined by recycled uranium, from spent fuel of nuclear reactors, re-enriched depleted uranium tails, ex-military weapons grade uranium and stock piles for civilian use. Uranium production from secondary sources in India is largely dependent on processing of monazite, and to a smaller extent it is recovered from waste metallurgical slags generated by BARC and other private industries engaged in extracting niobium tantalum from the ores. The paper gives over view of the commercially successful processes of producing uranium from monazite and other secondary sources along with the details of setting up demonstration units for recovering uranium from wet phosphoric acid. The research and development work carried out to improve the cost economics of uranium production from monazite is also discussed as the total reported quantity of uranium associated with the monazite resources of the country is estimated at 30,000 tons of uranium metal (at the end of X Plan) compared to 75,000 ton of uranium in its primary ores

  19. Liquid radioactive waste processing improvement of PWR nuclear power plants

    International Nuclear Information System (INIS)

    Nery, Renata Wolter dos Reis; Martinez, Aquilino Senra; Monteiro, Jose Luiz Fontes

    2005-01-01

    The study evaluate an inorganic ion exchange to process the low level liquid radwaste of PWR nuclear plants, so that the level of the radioactivity in the effluents and the solid waste produced during the treatment of these liquid radwaste can be reduced. The work compares two types of ion exchange materials, a strong acid cation exchange resin, that is the material typically used to remove radionuclides from PWR nuclear plants wastes, and a mordenite zeolite. These exchange material were used to remove cesium from a synthetic effluent containing only this ion and another effluent containing cesium and cobalt. The breakthrough curves of the zeolite and resin using a fix bed reactor were compared. The results demonstrated that the zeolite is more efficient than the resin in removing cesium from a solution containing cesium and cobalt. The results also showed that a bed combining zeolite and resin can process more volume of an effluent containing cesium and cobalt than a bed resin alone. (author)

  20. MRI study of degenerative process in multiple system atrophy

    International Nuclear Information System (INIS)

    Yagishita, Toshiyuki; Kojima, Shigeyuki; Hirayama, Keizo

    1995-01-01

    The characteristic morphological changes of the brainstem and cerebellar regions of multiple system atrophy (MSA) were studied by MRI in varing subtypes, that is olivoponto cerebellar atrophy (OPCA: 23 cases), striatonigral degeneration (SND: 7 cases) and Shy-Drager's syndrome (SDS: 9 cases). OPCA was characterized by atrophy of the entire regions of the brainstem and the cerebellum. SND and SDS tended to show atrophy similar in type but lessin extent to OPCA. The common lesions in MSA were atrophy of the pontine base and cerebellum, and dilation of the fourth ventricle. Atrophy of the pontine base was more dominant in the inferior part than in the superior part, and cerebellar atrophy was more dominant in the superior part than in the inferior part, indicating that degeneration of the pontocerebellar pathway proceeds principally along fibers connecting the inferior part of the pons and the superior part of the cerebellum. Dilation of the fourth ventricle indicated atrophy of the middle cerebellar peduncle. In almost all the cases of OPCA and about a half the cases of SND and SDS, the pontine base and the middle cerebellar peduncle appeared as high signal intensity on T 2 weighted image and as low intensity on T 1 , suggesting degeneration and demyelination. In a few cases of OPCA, the dorsolateral part of the putamen were demonstrated as low signal intensity on T 2 weighted image. (author)

  1. MRI study of degenerative process in multiple system atrophy

    Energy Technology Data Exchange (ETDEWEB)

    Yagishita, Toshiyuki; Kojima, Shigeyuki; Hirayama, Keizo [Chiba Univ. (Japan). School of Medicine

    1995-02-01

    The characteristic morphological changes of the brainstem and cerebellar regions of multiple system atrophy (MSA) were studied by MRI in varing subtypes, that is olivoponto cerebellar atrophy (OPCA: 23 cases), striatonigral degeneration (SND: 7 cases) and Shy-Drager`s syndrome (SDS: 9 cases). OPCA was characterized by atrophy of the entire regions of the brainstem and the cerebellum. SND and SDS tended to show atrophy similar in type but lessin extent to OPCA. The common lesions in MSA were atrophy of the pontine base and cerebellum, and dilation of the fourth ventricle. Atrophy of the pontine base was more dominant in the inferior part than in the superior part, and cerebellar atrophy was more dominant in the superior part than in the inferior part, indicating that degeneration of the pontocerebellar pathway proceeds principally along fibers connecting the inferior part of the pons and the superior part of the cerebellum. Dilation of the fourth ventricle indicated atrophy of the middle cerebellar peduncle. In almost all the cases of OPCA and about a half the cases of SND and SDS, the pontine base and the middle cerebellar peduncle appeared as high signal intensity on T{sub 2} weighted image and as low intensity on T{sub 1}, suggesting degeneration and demyelination. In a few cases of OPCA, the dorsolateral part of the putamen were demonstrated as low signal intensity on T{sub 2} weighted image. (author).

  2. Steam gasification of coal, project prototype plant nuclear process heat

    International Nuclear Information System (INIS)

    Heek, K.H. van

    1982-05-01

    This report describes the tasks, which Bergbau-Forschung has carried out in the field of steam gasification of coal in cooperation with partners and contractors during the reference phase of the project. On the basis of the status achieved to date it can be stated, that the mode of operation of the gas-generator developed including the direct feeding of caking high volatile coal is technically feasible. Moreover through-put can be improved by 65% at minimum by using catalysts. On the whole industrial application of steam gasification - WKV - using nuclear process heat stays attractive compared with other gasification processes. Not only coal is conserved but also the costs of the gas manufactured are favourable. As confirmed by recent economic calculations these are 20 to 25% lower. (orig.) [de

  3. Processing glass-pyrochlore composites for nuclear waste encapsulation

    International Nuclear Information System (INIS)

    Pace, S.; Cannillo, V.; Wu, J.; Boccaccini, D.N.; Seglem, S.; Boccaccini, A.R.

    2005-01-01

    Glass matrix composites have been developed as alternative materials to immobilize nuclear solid waste, in particular actinides. These composites are made of soda borosilicate glass matrix, into which particles of lanthanum zirconate pyrochlore are encapsulated in concentrations of 30 vol.%. The fabrication process involves powder mixing followed by hot-pressing. At the relatively low processing temperature used (620 deg. C), the pyrochlore crystalline structure of the zirconate, which is relevant for containment of radioactive nuclei, remains unaltered. The microstructure of the composites exhibits a homogeneous distribution of isolated pyrochlore particles in the glass matrix and strong bonding at the matrix-particle interfaces. Hot-pressing was found to lead to high densification (95% th.d.) of the composite. The materials are characterized by relatively high elastic modulus, flexural strength, hardness and fracture toughness. A numerical approach using a microstructure-based finite element solver was used in order to investigate the mechanical properties of the composites

  4. Process for the fabrication of a nuclear fuel

    International Nuclear Information System (INIS)

    Hirose, Yasuo.

    1970-01-01

    Herein disclosed is a process for fabricating a nuclear fuel incorporating either uranium or plutonium. A pellet-like substrate consisting of a packed powder ceramic fuel such as uranium or plutonium is prepared with the horizontal surface of the body provided with a masking. Next, after impregnating the substrate voids with a solution consisting of a fissile material or mixture of fissile material and poison, the solvent is removed by a chemical deposition process which causes the impregnated material to migrate through capillary action toward the vicinity of the fuel body surface. Sintering and pyrolysis of the deposited material and masking are subsequently carried out to yield a fuel body having adjacent to its surface an intensely concentrated layer of either fissile material or a mixture of fissile material and poison. (Owens, K.J.)

  5. The role of nuclear inputs in r-process nucleosynthesis

    Energy Technology Data Exchange (ETDEWEB)

    Giuliani, Samuel Andrea; Arzhanov, Alexander; Friess, Stephen; Martinez-Pinedo, Gabriel; Moeller, Heiko; Sieverding, Andre; Wu, Meng-Ru [TU Darmstadt (Germany)

    2016-07-01

    We have studied the sensitivity of the r-process abundances produced in dynamical ejecta from neutron star mergers to different nuclear mass models. For each mass model, the resulting abundances are almost independent of the astrophysical conditions and reproduce the general features of the observed r-process abundance. We find that the second peak around A ∝ 130 is produced by the fission yields of the material that piles up in nuclei with A >or similar 250. We also find distinct differences in the predictions at and just above the third peak (A ∝ 195) for different mass models, due to different neutron separation energies at N = 130. Due to the crucial role that fission plays in r-process nucleosynthesis, we have computed the fission properties of superheavy nuclei using the BCPM energy density functional. We found that certain combinations of neutron and proton number lead to an enhanced stability against the spontaneous fission process, related with the existence of magic numbers in the superheavy region. However, the systematic of the fission properties is strongly affected by the choice of the collective degree of freedom when the fission path is obtained by minimizing the action integral. Finally, a comparison with other theoretical models and the consequences for r-process nucleosynthesis are discussed.

  6. Scientific Opportunities to Reduce Risk in Nuclear Process Science

    International Nuclear Information System (INIS)

    Bredt, Paul R.; Felmy, Andrew R.; Gauglitz, Phillip A.; Poloski, Adam P.; Vienna, John D.; Moyer, Bruce A.; Hobbs, David; Wilmarth, B.; Mcilwain, Michael; Subramanian, K.; Krahn, Steve; Machara, N.

    2009-01-01

    Cleaning up the nation's nuclear weapons complex remains as one of the most technologically challenging and financially costly problems facing the U.S. Department of Energy (DOE). Safety, cost, and technological challenges have often delayed progress in retrieval, processing, and final disposition of high-level waste, spent nuclear fuel, and challenging materials. Some of the issues result from the difficulty and complexity of the technological issues; others have programmatic bases, such as strategies that may provide undue focus on near-term goals or difficulty in developing and maintaining stakeholder confidence in the proposed solutions. We propose that independent basic fundamental science research, addressing the full cleanup life-cycle, offers an opportunity to help address these challenges by providing (1) scientific insight into the fundamental mechanisms involved in currently selected processing and disposal options, (2) a rational path to the development of alternative technologies should the primary options fail, (3) confidence that models that predict long-term performance of different disposal options are based upon the best available science, and (4) fundamental science discovery that enables transformational solutions to revolutionize the current baseline processes. Over the last 3 years, DOE's Office of Environmental Management (EM) has experienced a fundamental shift in philosophy. The mission focus of driving to closure has been replaced by one of enabling the long-term needs of DOE and the nation. Resolving new challenges, such as the disposition of DOE spent nuclear fuel, have been added to EM's responsibilities. In addition, the schedules for addressing several elements of the cleanup mission have been extended. As a result, EM's mission is no longer focused only on driving the current baselines to closure. Meeting the mission will require fundamental advances over at least a 30-year window if not longer as new challenges are added. The

  7. Multiple Monte Carlo Testing with Applications in Spatial Point Processes

    DEFF Research Database (Denmark)

    Mrkvička, Tomáš; Myllymäki, Mari; Hahn, Ute

    with a function as the test statistic, 3) several Monte Carlo tests with functions as test statistics. The rank test has correct (global) type I error in each case and it is accompanied with a p-value and with a graphical interpretation which shows which subtest or which distances of the used test function......(s) lead to the rejection at the prescribed significance level of the test. Examples of null hypothesis from point process and random set statistics are used to demonstrate the strength of the rank envelope test. The examples include goodness-of-fit test with several test functions, goodness-of-fit test...

  8. Graphical analysis of processes with multiple activation energies

    International Nuclear Information System (INIS)

    Lachter, J.; Bragg, R.H.; Close, E.

    1986-01-01

    The activation energies characterizing a kinetic process are derived from the slopes of the Arrhenius diagrams obtained by plotting rate constants versus reciprocal temperature. Those rate constants correspond to the shifts along the time axis needed to superpose the successive isotherms. A general method based on Chebyshev interpolation is proposed for the optimization of the superposition of the experimental data points. This method is applied to determine the activation energies of the graphitization kinetics of the interlayer spacings of pitch coke and pyrocarbon samples

  9. ARTIST process. A novel chemical process for treatment of spent nuclear fuel

    International Nuclear Information System (INIS)

    Tachimori, Shoichi

    2001-10-01

    A new chemical process, ARTIST process, is proposed for the treatment of spent nuclear fuel. The main concept of the ARTIST process is to recover and stock all actinides (Ans) as two groups, uranium (U) and a mixture of transuranics (TRU), to preserve their resource value and to dispose solely fission products (FPs). The process is composed of two main steps, an U exclusive isolation and a total recovery of TRU; which copes with the nuclear non-proliferation measures, and additionally of Pu separation process and soft N-donor process if requested, and optionally of processes for separation of long-lived FPs. These An products: U-product and TRU-product, are to be solidified by calcination and allowed to the interim stockpile for future utilization. These separations are achieved by use of amidic extractants in accord with the CHON principle. The technical feasibility of the ARTIST process was explained by the performance of both the branched alkyl monoamides in extracting U and suppressing the extraction of tetravalent Ans due to the steric effect and the diglycolic amide (TODGA) in thorough extraction of all TRU by tridentate fashion. When these TRU are requested to put into reactors, LWR or FBR, for power generation or the Accelerator - Driven System (ADS) for transmutation, Pu (Np) or Am-Cm (Np) are to be extracted from the TRU-product. (author)

  10. Digital signal processing algorithms for nuclear particle spectroscopy

    International Nuclear Information System (INIS)

    Zejnalova, O.; Zejnalov, Sh.; Hambsch, F.J.; Oberstedt, S.

    2007-01-01

    Digital signal processing algorithms for nuclear particle spectroscopy are described along with a digital pile-up elimination method applicable to equidistantly sampled detector signals pre-processed by a charge-sensitive preamplifier. The signal processing algorithms are provided as recursive one- or multi-step procedures which can be easily programmed using modern computer programming languages. The influence of the number of bits of the sampling analogue-to-digital converter on the final signal-to-noise ratio of the spectrometer is considered. Algorithms for a digital shaping-filter amplifier, for a digital pile-up elimination scheme and for ballistic deficit correction were investigated using a high purity germanium detector. The pile-up elimination method was originally developed for fission fragment spectroscopy using a Frisch-grid back-to-back double ionization chamber and was mainly intended for pile-up elimination in case of high alpha-radioactivity of the fissile target. The developed pile-up elimination method affects only the electronic noise generated by the preamplifier. Therefore the influence of the pile-up elimination scheme on the final resolution of the spectrometer is investigated in terms of the distance between pile-up pulses. The efficiency of the developed algorithms is compared with other signal processing schemes published in literature

  11. Sustained qualification process for full scope nuclear power plant simulators

    International Nuclear Information System (INIS)

    Pirson, J.; Stubbe, E.; Vanhoenacker, L.

    1994-01-01

    In the past decade, simulator training for all nuclear power plant operators has evolved into a vital requirement. To assure a correct training, the simulator qualification process is an important issue not only for the initial validation but also following major simulator updates, which are necessary during the lifetime of the simulator. In order to avoid degradation of the simulator validated software, the modifications have to be introduced according to a rigorous methodology and a practical requalification process has to be applied. Such methodology has to be enforced at every phase of the simulator construction or updating process from plant data package constitution, over simulator software development to simulator response qualification. The initial qualification and requalification process is based on the 3 levels identified by the ANSI/ANS 3-5 standard for steady-state, operational transients and accident conditions. For the initial certification of the full scope simulators in Belgium, a practical qualification methodology has been applied, which has been adapted into a set of non regression tests for the requalification after major simulator updates. (orig.) (4 refs., 3 figs.)

  12. Liquid radwaste process optimization at Catawba Nuclear Station

    International Nuclear Information System (INIS)

    Cauthen, B.E.; Taylor, J.C.

    1990-01-01

    Since commercial operation in 1985, Catawba Nuclear Station has experienced significant filtration problems with the radioactive liquid waste system. The performance of the filtration and ion exchange equipment has been significantly worse than other Duke Power stations. Full scale tests have been performed to investigate the causes and potential solutions to the waste processing difficulties. The initial waste stream characterization study revealed a large percentage of sub-micron particles. This information immediately suggested that the existing filtration equipment was not adequately sized to effectively process the waste stream. New technologies which would effectively enhance the performance of the processing system and reduce both operating and maintenance costs were researched. This included bag filters, depth filtration, custom designed ion exchange vessels and radionuclide specific ion exchange media. The subsequent full scale testing resulted in a processing scheme which resulted in extended filter life, over 100 percent increase in ion exchange bed life, 90 percent reduction in filter media costs and improved radionuclide removal. 4 refs., 4 figs., 1 tab

  13. Deep knowledge expert system for diagnosis of multiple-failure severe transients in nuclear power plant

    International Nuclear Information System (INIS)

    Martin, R.P.; Nassersharif, B.

    1987-01-01

    TAMUS (Transient Analysis of MUltiple-failure Simulations) is a prototype expert system which is the result of a project investigating and implementing event confidence-levels (used by reactor safety experts in reactor transient analysis) in the form of an expert system. Currently, TAMUS is designed to diagnose reactor transients by analyzing simulated sensor and plant thermal hydraulic information from a system simulation. TAMUS uses a knowledge base of existing emergency nuclear plant operating guidelines and detailed thermal-hydraulic calculating results correlated to confidence-levels. TAMUS can diagnose a number of reactor transients (for example, loss-of-coolant accidents, steam-generator-tube ruptures, loss-of-offsite power, etc.). Future work includes the expansion of the knowledge base and improvement of the deep-knowledge qualitative models

  14. Forward-backward multiplicity fluctuation and longitudinal harmonics in high-energy nuclear collisions

    Science.gov (United States)

    Jia, Jiangyong; Radhakrishnan, Sooraj; Zhou, Mingliang; Huo, Peng

    2016-12-01

    Forward-backward (FB) multiplicity fluctuation in high-energy nuclear collisions can be quantified by two-particle pseudo-rapidity correlation function and its expansion into Legendre polynomials. The corresponding coefficients represent different fluctuation modes in longitudinal direction. The leading term corresponds to the asymmetry of numbers of the participants from the two colliding nuclei. This method is tested in events generated from AMPT and HIJING model. The an signal are found to be strongly dampened in AMPT than in HIJIGN, due to weaker short-range correlaitons and final-state effects in AMPT. Two-particle correlation also reveals an intresting shallow minimum around Δη ≈ 0 in AMPT events, which is absent in HIJING results. The method opens a new avenue to elucidate the particle production mechanism and early time dynamics in heavy-ion collisions.

  15. Method for treating a nuclear process off-gas stream

    Science.gov (United States)

    Pence, Dallas T.; Chou, Chun-Chao

    1984-01-01

    Disclosed is a method for selectively removing and recovering the noble gas and other gaseous components typically emitted during nuclear process operations. The method is adaptable and useful for treating dissolver off-gas effluents released during reprocessing of spent nuclear fuels whereby to permit radioactive contaminant recovery prior to releasing the remaining off-gases to the atmosphere. Briefly, the method sequentially comprises treating the off-gas stream to preliminarily remove NO.sub.x, hydrogen and carbon-containing organic compounds, and semivolatile fission product metal oxide components therefrom; adsorbing iodine components on silver-exchanged mordenite; removing water vapor carried by said stream by means of a molecular sieve; selectively removing the carbon dioxide components of said off-gas stream by means of a molecular sieve; selectively removing xenon in gas phase by passing said stream through a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from oxygen by means of a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from the bulk nitrogen stream using a molecular sieve comprising silver-exchanged mordenite cooled to about -140.degree. to -160.degree. C.; concentrating the desorbed krypton upon a molecular sieve comprising silver-exchange mordenite cooled to about -140.degree. to -160.degree. C.; and further cryogenically concentrating, and the recovering for storage, the desorbed krypton.

  16. Property-process relationships in nuclear fuel fabrication

    International Nuclear Information System (INIS)

    Tikare, V.

    2015-01-01

    Nuclear fuels are fabricated using many different techniques as they come in a large variety of shapes and compositions. The design and composition of nuclear fuels are predominantly dictated by the engineering requirements necessary for their function in reactors of various designs. Other engineering properties requirements originate from safety and security concerns, and the easy of handling, storing, transporting and disposing of the radioactive materials. In this chapter, the more common of these fuels will be briefly reviewed and the methods used to fabricate them will be presented. The fuels considered in this paper are oxide fuels used in LWRs and FRs, metal fuels in FRs and particulate fuels used in HTGRs. Fabrication of alternative fuel forms and use of standard fuels in alternative reactors will be discussed briefly. The primary motivation to advance fuel fabrication is to improve performance, reduce cost, reduce waste or enhance safety and security of the fuels. To achieve optimal performance, developing models to advance fuel fabrication has to be done in concert with developing fuel performance models. The specific properties and microstructures necessary for improved fuel performance must be identified using fuel performance models, while fuel fabrication models that can determine processing variables to give the desired microstructure and materials properties must be developed. (author)

  17. Radiation processing program at the Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Khairul Zaman Hj. Mohd Dahlan

    2008-01-01

    Radiation processing technology has been proven to enhance industrial efficiency and productivity, improve product quality and competitiveness. For many years, varieties of radiation crosslinkable materials based on synthetic polymers have been studied at the Malaysian Nuclear Agency either in the form of thermoplastic resins, polymer blends or composites. At present, effort is focused towards developing new materials based on natural polymers such as natural rubber and rubber based products, palm oil and palm oil based products and polysaccharide. Hydrogel based on sago starch has been developed and commercialized for face mask. As for wound dressing application, sago hydrogel is still subjected to the clinical evaluation. Sago starch has also been modified for biodegradable products such as bio-film and bio-foam for packaging purposes. On the other hand palm oil based acrylate resins have been synthesized at the Nuclear Malaysia for pressure sensitive adhesive and printing ink applications. Meanwhile, natural rubber is used in a polymer blend and composites for automotive components. All of these products are at various stages of commercialization. (author)

  18. Method for treating a nuclear process off-gas stream

    International Nuclear Information System (INIS)

    Pence, D.T.; Chou, C.C.

    1984-01-01

    Disclosed is a method for selectively removing and recovering the noble gas and other gaseous components typically emitted during nuclear process operations. The method is adaptable and useful for treating dissolver off-gas effluents released during reprocessing of spent nuclear fuels whereby to permit radioactive contaminant recovery prior to releasing the remaining off-gases to the atmosphere. Briefly, the method sequentially comprises treating the off-gas stream to preliminarily remove NO /SUB x/ , hydrogen and carbon-containing organic compounds, and semivolatile fission product metal oxide components therefrom; adsorbing iodine components on silver-exchanged mordenite; removing water vapor carried by said stream by means of a molecular sieve; selectively removing the carbon dioxide components of said off-gas stream by means of a molecular sieve; selectively removing xenon in gas phase by passing said stream through a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from oxygen by means of a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from the bulk nitrogen stream using a molecular sieve comprising silver-exchanged mordenite cooled to about -140 0 to -160 0 C.; concentrating the desorbed krypton upon a molecular sieve comprising silver-exchange mordenite cooled to about -140 0 to -160 0 C.; and further cryogenically concentrating, and the recovering for storage, the desorbed krypton

  19. Multiplicative Process in Turbulent Velocity Statistics: A Simplified Analysis

    Science.gov (United States)

    Chillà, F.; Peinke, J.; Castaing, B.

    1996-04-01

    A lot of models in turbulence links the energy cascade process and intermittency, the characteristic of which being the shape evolution of the probability density functions (pdf) for longitudinal velocity increments. Using recent models and experimental results, we show that the flatness factor of these pdf gives a simple and direct estimate for what is called the deepness of the cascade. We analyse in this way the published data of a Direct Numerical Simulation and show that the deepness of the cascade presents the same Reynolds number dependence as in laboratory experiments. Plusieurs modèles de turbulence relient la cascade d'énergie et l'intermittence, caractérisée par l'évolution des densités de probabilité (pdf) des incréments longitudinaux de vitesse. Nous appuyant aussi bien sur des modèles récents que sur des résultats expérimentaux, nous montrons que la Curtosis de ces pdf permet une estimation simple et directe de la profondeur de la cascade. Cela nous permet de réanalyser les résultats publiés d'une simulation numérique et de montrer que la profondeur de la cascade y évolue de la même façon que pour les expériences de laboratoire en fonction du nombre de Reynolds.

  20. Multiple-scale stochastic processes: Decimation, averaging and beyond

    Energy Technology Data Exchange (ETDEWEB)

    Bo, Stefano, E-mail: stefano.bo@nordita.org [Nordita, KTH Royal Institute of Technology and Stockholm University, Roslagstullsbacken 23, SE-106 91 Stockholm (Sweden); Celani, Antonio [Quantitative Life Sciences, The Abdus Salam International Centre for Theoretical Physics (ICTP), Strada Costiera 11, I-34151 - Trieste (Italy)

    2017-02-07

    The recent experimental progresses in handling microscopic systems have allowed to probe them at levels where fluctuations are prominent, calling for stochastic modeling in a large number of physical, chemical and biological phenomena. This has provided fruitful applications for established stochastic methods and motivated further developments. These systems often involve processes taking place on widely separated time scales. For an efficient modeling one usually focuses on the slower degrees of freedom and it is of great importance to accurately eliminate the fast variables in a controlled fashion, carefully accounting for their net effect on the slower dynamics. This procedure in general requires to perform two different operations: decimation and coarse-graining. We introduce the asymptotic methods that form the basis of this procedure and discuss their application to a series of physical, biological and chemical examples. We then turn our attention to functionals of the stochastic trajectories such as residence times, counting statistics, fluxes, entropy production, etc. which have been increasingly studied in recent years. For such functionals, the elimination of the fast degrees of freedom can present additional difficulties and naive procedures can lead to blatantly inconsistent results. Homogenization techniques for functionals are less covered in the literature and we will pedagogically present them here, as natural extensions of the ones employed for the trajectories. We will also discuss recent applications of these techniques to the thermodynamics of small systems and their interpretation in terms of information-theoretic concepts.

  1. Acquisition and processing of multiple functional investigations in cardiology

    International Nuclear Information System (INIS)

    Baruthio, J.; Constantinesco, A.; Chavas, M.; Meyer, P.; Dumitresco, B.; Chambron, J.; Nikitine, S.; Voegtlin, R.

    1978-01-01

    This work is based on a acquisition and pretreating Service of data and signals resulting from several types of functional explorations in cardiology. This Service, through a specialised phone-line, is connected to the Medical Centre of Informatic where the different treatments and on occasion the recording of data are carried out. This functions according to the Real Time Executive System and the clinical results are send back to the investigation unit. The main types of cardiologic analysis as studied by the system are envisaged: measure in real time of the cardiac output and analysis of the radiocardiogram, measure and display of the thoracic potentials, spectral analysis of the vectorcardiogram, quantitative cineangiocardiography and analysis of intracardiac pressures. This system is particularly interesting in that it may treat several processes which could ask for a great capacity of storing and an important calculus power, see for instance the study of thoracic potentials. This type of analysis could not be envisaged financially with isolated calculators. The set of results obtained enables us to investigate thoroughly and precisely the cardiac performance [fr

  2. Nuclear medicine imaging of multiple myeloma, particularly in the relapsed setting

    Energy Technology Data Exchange (ETDEWEB)

    Waal, Esther G.M. de; Vellenga, Edo [University of Groningen, University Medical Center Groningen, Department of Hematology, PO Box 30001, Groningen (Netherlands); Glaudemans, Andor W.J.M. [University of Groningen, University Medical Center Groningen, Department of Nuclear Medicine and Molecular Imaging, Groningen (Netherlands); Schroeder, Carolien P. [University of Groningen, University Medical Center Groningen, Department of Medical Oncology, Groningen (Netherlands); Slart, Riemer H.J.A. [University of Groningen, University Medical Center Groningen, Department of Nuclear Medicine and Molecular Imaging, Groningen (Netherlands); University of Twente, Department of Biomedical Photonic Imaging, Enschede (Netherlands)

    2017-02-15

    Multiple myeloma (MM) is characterized by a monoclonal plasma cell population in the bone marrow. Lytic lesions occur in up to 90 % of patients. For many years, whole-body X-ray (WBX) was the method of choice for detecting skeleton abnormalities. However, the value of WBX in relapsing disease is limited because lesions persist post-treatment, which restricts the capacity to distinguish between old, inactive skeletal lesions and new, active ones. Therefore, alternative techniques are necessary to visualize disease activity. Modern imaging techniques such as magnetic resonance imaging, positron emission tomography and computed tomography offer superior detection of myeloma bone disease and extramedullary manifestations. In particular, the properties of nuclear imaging enable the identification of disease activity by directly targeting the specific cellular properties of malignant plasma cells. In this review, an overview is provided of the effectiveness of radiopharmaceuticals that target metabolism, surface receptors and angiogenesis. The available literature data for commonly used nuclear imaging tracers, the promising first results of new tracers, and our pilot work indicate that a number of these radiopharmaceutical applications can be used effectively for staging and response monitoring of relapsing MM patients. Moreover, some tracers can potentially be used for radio immunotherapy. (orig.)

  3. Economic analysis of multiple-module high temperature gas-cooled reactor (MHTR) nuclear power plants

    International Nuclear Information System (INIS)

    Liu Yu; Dong Yujie

    2011-01-01

    In recent years, as the increasing demand of energy all over the world, and the pressure on greenhouse emissions, there's a new opportunity for the development of nuclear energy. Modular High Temperature Gas-cooled Reactor (MHTR) received recognition for its inherent safety feature and high outlet temperature. Whether the Modular High Temperature Gas-cooled Reactor would be accepted extensively, its economy is a key point. In this paper, the methods of qualitative analysis and the method of quantitative analysis, the economic models designed by Economic Modeling Working Group (EMWG) of the Generation IV International Forum (GIF), as well as the HTR-PM's main technical features, are used to analyze the economy of the MHTR. A prediction is made on the basis of summarizing High Temperature Gas-cooled Reactor module characteristics, construction cost, total capital cost, fuel cost and operation and maintenance (O and M) cost and so on. In the following part, comparative analysis is taken measures to the economy and cost ratio of different designs, to explore the impacts of modularization and standardization on the construction of multiple-module reactor nuclear power plant. Meanwhile, the analysis is also adopted in the research of key factors such as the learning effect and yield to find out their impacts on the large scale development of MHTR. Furthermore, some reference would be provided to its wide application based on these analysis. (author)

  4. Iodine-129 in aquatic organisms near nuclear fuels processing plants

    International Nuclear Information System (INIS)

    Watson, D.G.

    1975-04-01

    Concentrations of 129 I in two aquatic habitats near nuclear fuel processing plants were highest in algae and crustaceans. These two forms may be useful in future monitoring of 129 I. There is some indication of an increase in atom ratios and specific activity in aquatic organisms over that in water and sediments. Additional measurements should be made to verify this conclusion. Efforts should continue to measure the possible long term build-up of 129 I in aquatic environments receiving effluents from fuels reprocessing plants. Even at very low rates of release to the environment, the long physical half-life of 129 I creates the potential for build-up of this nuclide to significant levels. (U.S.)

  5. Are current processes for nuclear emergency management in Europe adequate?

    Energy Technology Data Exchange (ETDEWEB)

    Carter, E; French, S [Manchester Business School, University of Manchester, Booth Street West, Manchester M15 6PB (United Kingdom)

    2006-12-15

    We describe the results of process mapping of nuclear emergency management procedures in four European countries. We find clear differences and explore these in relation to their suitability for building a shared understanding across the emergency management team of the evolving situation and a balanced appreciation of the uncertainties. Our findings indicate that there are some issues that cause concern in that the procedures may run smoothly and efficiently but they may also risk underestimating uncertainty or ignore key issues that have only been identified by a minority of experts or models. We are concerned that they do not facilitate the building of shared mental models that the literature such as that on highly reliable organisations has shown is important.

  6. A Computer- Based Digital Signal Processing for Nuclear Scintillator Detectors

    International Nuclear Information System (INIS)

    Ashour, M.A.; Abo Shosha, A.M.

    2000-01-01

    In this paper, a Digital Signal Processing (DSP) Computer-based system for the nuclear scintillation signals with exponential decay is presented. The main objective of this work is to identify the characteristics of the acquired signals smoothly, this can be done by transferring the signal environment from random signal domain to deterministic domain using digital manipulation techniques. The proposed system consists of two major parts. The first part is the high performance data acquisition system (DAQ) that depends on a multi-channel Logic Scope. Which is interfaced with the host computer through the General Purpose Interface Board (GPIB) Ver. IEEE 488.2. Also, a Graphical User Interface (GUI) has been designed for this purpose using the graphical programming facilities. The second of the system is the DSP software Algorithm which analyses, demonstrates, monitoring these data to obtain the main characteristics of the acquired signals; the amplitude, the pulse count, the pulse width, decay factor, and the arrival time

  7. Scientific Opportunities to Reduce Risk in Nuclear Process Science

    International Nuclear Information System (INIS)

    Bredt, P.R.; Felmy, A.R.; Gauglitz, P.A.; Poloski, A.P.; Vienna, J.D.; Moyer, B.A.; Hobbs, D.; Wilmarth, B.; McIlwain, M.; Subramanian, K.; Krahn, S.; Machara, N.

    2009-01-01

    Cleaning up the nation's nuclear weapons complex remains as one of the most technologically challenging and financially costly problems facing the U.S. Department of Energy (DOE). Safety, cost, and technological challenges have often delayed progress in retrieval, processing, and final disposition of high-level waste, spent nuclear fuel, and challenging materials. Some of the issues result from the difficulty and complexity of the technological issues; others have programmatic bases, such as strategies that may provide undue focus on near-term goals or difficulty in developing and maintaining stakeholder confidence in the proposed solutions. We propose that independent basic fundamental science research addressing the full cleanup life-cycle offers an opportunity to help address these challenges by providing 1) scientific insight into the fundamental mechanisms involved in currently selected processing and disposal options, 2) a rational path to the development of alternative technologies should the primary options fail, 3) confidence that models that predict long-term performance of different disposal options are based upon the best available science, and 4) fundamental science discovery that enables transformational solutions to revolutionize the current baseline processes. Over the last 3 years, DoE's Office of Environmental Management (EM) has experienced a fundamental shift in philosophy. The mission focus of driving to closure has been replaced by one of enabling the long-term needs of DOE and the nation. Resolving new challenges, such as the disposition of DOE spent nuclear fuel, have been added to EM's responsibilities. In addition, the schedules for addressing several elements of the cleanup mission have been extended. As a result, EM's mission is no longer focused only on driving the current baselines to closure. Meeting the mission will require fundamental advances over at least a 30-year window if not longer as new challenges are added. The overall

  8. Are current processes for nuclear emergency management in Europe adequate?

    International Nuclear Information System (INIS)

    Carter, E; French, S

    2006-01-01

    We describe the results of process mapping of nuclear emergency management procedures in four European countries. We find clear differences and explore these in relation to their suitability for building a shared understanding across the emergency management team of the evolving situation and a balanced appreciation of the uncertainties. Our findings indicate that there are some issues that cause concern in that the procedures may run smoothly and efficiently but they may also risk underestimating uncertainty or ignore key issues that have only been identified by a minority of experts or models. We are concerned that they do not facilitate the building of shared mental models that the literature such as that on highly reliable organisations has shown is important

  9. Nuclear reactor fuel cycle technology with pyroelectrochemical processes

    International Nuclear Information System (INIS)

    Skiba, O.V.; Maershin, A.A.; Bychkov, A.V.; Zhdanov, A.N.; Kislyj, V.A.; Vavilov, S.K.; Babikov, L.G.

    1999-01-01

    A group of dry technologies and processes of vibro-packing granulated fuel in combination with unique properties of vibro-packed FEs make it possible to implement a new comprehensive approach to the fuel cycle with plutonium fuel. Testing of a big number of FEs with vibro-packed U-Pu oxide fuel in the BOR-60 reactor, successful testing of experimental FSAs in the BN-600 rector, reliable operation of the experimental and research complex facilities allow to make the conclusion about a real possibility to develop a safe, economically beneficial U-Pu fuel cycle based on the technologies enumerated above and to use both reactor-grade and weapon-grade plutonium in nuclear reactors with a reliable control and accounting system [ru

  10. The Relationship between Multiple Intelligences with Preferred Science Teaching and Science Process Skills

    Directory of Open Access Journals (Sweden)

    Mohd Ali Samsudin

    2015-02-01

    Full Text Available This study was undertaken to identify the relationship between multiple intelligences with preferred science teaching and science process skills. The design of the study is a survey using three questionnaires reported in the literature: Multiple Intelligences Questionnaire, Preferred Science Teaching Questionnaire and Science Process Skills Questionnaire. The study selected 300 primary school students from five (5 primary schools in Penang, Malaysia. The findings showed a relationship between kinesthetic, logical-mathematical, visual-spatial and naturalistic intelligences with the preferred science teaching. In addition there was a correlation between kinesthetic and visual-spatial intelligences with science process skills, implying that multiple intelligences are related to science learning.

  11. Smith predictor-based multiple periodic disturbance compensation for long dead-time processes

    Science.gov (United States)

    Tan, Fang; Li, Han-Xiong; Shen, Ping

    2018-05-01

    Many disturbance rejection methods have been proposed for processes with dead-time, while these existing methods may not work well under multiple periodic disturbances. In this paper, a multiple periodic disturbance rejection is proposed under the Smith predictor configuration for processes with long dead-time. One feedback loop is added to compensate periodic disturbance while retaining the advantage of the Smith predictor. With information of the disturbance spectrum, the added feedback loop can remove multiple periodic disturbances effectively. The robust stability can be easily maintained through the rigorous analysis. Finally, simulation examples demonstrate the effectiveness and robustness of the proposed method for processes with long dead-time.

  12. The United States nuclear regulatory commission license renewal process

    International Nuclear Information System (INIS)

    Holian, B.E.

    2009-01-01

    The United States (U.S.) Nuclear Regulatory Commission (NRC) license renewal process establishes the technical and administrative requirements for the renewal of operating power plant licenses. Reactor ope-rating licenses were originally issued for 40 years and are allowed to be renewed. The review process for license renewal applications (L.R.A.) provides continued assurance that the level of safety provided by an applicant's current licensing basis is maintained for the period of extended operation. The license renewal review focuses on passive, long-lived structures and components of the plant that are subject to the effects of aging. The applicant must demonstrate that programs are in place to manage those aging effects. The review also verifies that analyses based on the current operating term have been evaluated and shown to be valid for the period of extended operation. The NRC has renewed the licenses for 52 reactors at 30 plant sites. Each applicant requested, and was granted, an extension of 20 years. Applications to renew the licenses of 20 additional reactors at 13 plant sites are under review. As license renewal is voluntary, the decision to seek license renewal and the timing of the application is made by the licensee. However, the NRC expects that, over time, essentially all U.S. operating reactors will request license renewal. In 2009, the U.S. has 4 plants that enter their 41. year of ope-ration. The U.S. Nuclear Industry has expressed interest in 'life beyond 60', that is, requesting approval of a second renewal period. U.S. regulations allow for subsequent license renewals. The NRC is working with the U.S. Department of Energy (DOE) on research related to light water reactor sustainability. (author)

  13. Diffusion processes in tumors: A nuclear medicine approach

    International Nuclear Information System (INIS)

    Amaya, Helman

    2016-01-01

    The number of counts used in nuclear medicine imaging techniques, only provides physical information about the desintegration of the nucleus present in the the radiotracer molecules that were uptaken in a particular anatomical region, but that information is not a real metabolic information. For this reason a mathematical method was used to find a correlation between number of counts and "1"8F-FDG mass concentration. This correlation allows a better interpretation of the results obtained in the study of diffusive processes in an agar phantom, and based on it, an image from the PETCETIX DICOM sample image set from OsiriX-viewer software was processed. PET-CT gradient magnitude and Laplacian images could show direct information on diffusive processes for radiopharmaceuticals that enter into the cells by simple diffusion. In the case of the radiopharmaceutical "1"8F-FDG is necessary to include pharmacokinetic models, to make a correct interpretation of the gradient magnitude and Laplacian of counts images.

  14. A survey of decontamination processes applicable to DOE nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

    1997-05-01

    The objective of this survey was to select an appropriate technology for in situ decontamination of equipment interiors as part of the decommissioning of U.S. Department of Energy nuclear facilities. This selection depends on knowledge of existing chemical decontamination methods. This report provides an up-to-date review of chemical decontamination methods. According to available information, aqueous systems are probably the most universally used method for decontaminating and cleaning metal surfaces. We have subdivided the technologies, on the basis of the types of chemical solvents, into acid, alkaline permanganate, highly oxidizing, peroxide, and miscellaneous systems. Two miscellaneous chemical decontamination methods (electrochemical processes and foam and gel systems) are also described. A concise technical description of various processes is given, and the report also outlines technical considerations in the choice of technologies, including decontamination effectiveness, waste handing, fields of application, and the advantages and limitations in application. On the basis of this survey, six processes were identified for further evaluation. 144 refs., 2 tabs.

  15. Digital Process Management Technology for Nuclear Power Plants

    International Nuclear Information System (INIS)

    You, Young M.; Suh, Kune Y.

    2009-01-01

    PHILOSOPHIA, Inc. and Seoul National University have utilized the cutting edge Digital Process Management (DPM) technology for the good of Nuclear Power Plant in recent days. This work represent the overall benefits and the use of this new flow of technology which come into the spotlight. Before realizing the three dimensional (3D) technologies and applying it to real mechanical manufactures and constructions, majority of planning and designing works need huge time and cost even if the process is before the real work. Especially, for a massive construction such as power plant and harbor, without computer-aided technology currently we cannot imagine the whole process can be established easily. Computer-aided Design (CAD) is now main and common technology for manufacturing or construction. This technology lead the other virtual reality 3D technologies into the job site. As a member of these new technologies, DPM is utilized in high-tech and huge scale manufacturing and construction for the benefits of time and cost

  16. Nuclear processes in deuterium/natural hydrogen-metal systems

    International Nuclear Information System (INIS)

    Zelensky, V.F.

    2013-01-01

    The survey presents the analysis of the phenomena taking place in deuterium - metal and natural hydrogen - metal systems under cold fusion experimental conditions. The cold fusion experiments have shown that the generation of heat and helium in the deuterium-metal system without emission of energetic gamma-quanta is the result of occurrence of a chain of chemical, physical and nuclear processes observed in the system, culminating in both the fusion of deuterium nuclei and the formation of a virtual, electron-modified excited 4He nucleus. The excitation energy of the helium nucleus is transferred to the matrix through emission of conversion electrons, and that, under appropriate conditions, provides a persistent synthesis of deuterium. The processes occurring in the deuterium/natural hydrogen - metal systems have come to be known as chemonuclear DD- and HD-fusion. The mechanism of stimulation of weak interaction reactions under chemonuclear deuterium fusion conditions by means of strong interaction reactions has been proposed. The results of numerous experiments discussed in the survey bear witness to the validity of chemonuclear fusion. From the facts discussed it is concluded that the chemonuclear deuterium fusion scenario as presented in this paper may serve as a basis for expansion of deeper research and development of this ecologically clean energy source. It is shown that the natural hydrogen-based system, containing 0.015% of deuterium, also has good prospects as an energy source. The chemonuclear fusion processes do not require going beyond the scope of traditional physics for their explanation

  17. Concentration processes under tubesheet sludge piles in nuclear steam generators

    International Nuclear Information System (INIS)

    Gonzalez, F.; Spekkens, P.

    1987-01-01

    The process by which bulk water solutes are concentrated under tubesheet sludge piles in nuclear steam generators was investigated in the laboratory under simulated CANDU operating conditions. Concentration rates were found to depend on the tube heat flux and pile depth, although beyond a critical depth the concentration efficiency decreased. This efficiency could be expressed by a concentration coefficient, and was found to depend also on the sludge pile porosity. Solute concentration profiles in the sludge pile suggested that the concentration mechanism in a high-porosity/permeability pile is characterized by boiling mainly near or at the tube surface, while in low-porosity piles, the change of phase may also become important in the body of the sludge pile. In all cases, the full depth of the pile was active to some extent in the concentration process. As long as the heat transfer under the pile was continued, the solute remained under the pile and slowly migrated toward the bottom. When the heat transfer was stopped, the solute diffused back into the bulk solution at a rate slower than that of the concentration process

  18. A survey of decontamination processes applicable to DOE nuclear facilities

    International Nuclear Information System (INIS)

    Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

    1997-05-01

    The objective of this survey was to select an appropriate technology for in situ decontamination of equipment interiors as part of the decommissioning of U.S. Department of Energy nuclear facilities. This selection depends on knowledge of existing chemical decontamination methods. This report provides an up-to-date review of chemical decontamination methods. According to available information, aqueous systems are probably the most universally used method for decontaminating and cleaning metal surfaces. We have subdivided the technologies, on the basis of the types of chemical solvents, into acid, alkaline permanganate, highly oxidizing, peroxide, and miscellaneous systems. Two miscellaneous chemical decontamination methods (electrochemical processes and foam and gel systems) are also described. A concise technical description of various processes is given, and the report also outlines technical considerations in the choice of technologies, including decontamination effectiveness, waste handing, fields of application, and the advantages and limitations in application. On the basis of this survey, six processes were identified for further evaluation. 144 refs., 2 tabs

  19. Diffusion processes in tumors: A nuclear medicine approach

    Energy Technology Data Exchange (ETDEWEB)

    Amaya, Helman, E-mail: haamayae@unal.edu.co [Grupo de Física Nuclear, Universidad Nacional de Colombia (Colombia)

    2016-07-07

    The number of counts used in nuclear medicine imaging techniques, only provides physical information about the desintegration of the nucleus present in the the radiotracer molecules that were uptaken in a particular anatomical region, but that information is not a real metabolic information. For this reason a mathematical method was used to find a correlation between number of counts and {sup 18}F-FDG mass concentration. This correlation allows a better interpretation of the results obtained in the study of diffusive processes in an agar phantom, and based on it, an image from the PETCETIX DICOM sample image set from OsiriX-viewer software was processed. PET-CT gradient magnitude and Laplacian images could show direct information on diffusive processes for radiopharmaceuticals that enter into the cells by simple diffusion. In the case of the radiopharmaceutical {sup 18}F-FDG is necessary to include pharmacokinetic models, to make a correct interpretation of the gradient magnitude and Laplacian of counts images.

  20. Decision process regarding nuclear generation: the Brazilian case

    International Nuclear Information System (INIS)

    Metri, Paulo

    2009-01-01

    Countries face a constant need to expand their electricity generation capacities. Electricity sources in a country and the respective generation technologies have different technical, economic, environmental, social and political characteristics. The evaluation criteria of the generating sources and their technologies must not be restricted to the supply of the increased demand at the lowest cost. Compliance with other public policies must be considered in the decision process of the expansion, for instance, maximize local acquisition and minimize foreign fuel purchase. Countries have different energy resources, as well as different levels of technology and development in their industrial parks. Brazil has many mineral reserves, besides the hydraulic potential, for supporting the expansion. The decision process in this sector, which includes nuclear energy as a sub-sector, requires analyzing and evaluating various information and data. In this stage, a quantitative model providing a first approach for the decision may be applied. The new institutional structure adopted in the sector during the 1990s and 2000s brought about new conditions into an already complex decision process. In such context of methodology complexity, political aspects gain relevance, becoming of increased importance. The political environment is described and the players are identified. One conclusion and a few recommendations are provided. (author)

  1. Nuclear magnetic resonance imaging in a case of facial myokymia with multiple sclerosis

    International Nuclear Information System (INIS)

    Kojima, Shigeyuki; Yagishita, Toshiyuki; Kita, Kohei; Hirayama, Keizo; Ikehira, Hiroo; Fukuda, Nobuo; Tateno, Yukio.

    1985-01-01

    A 59-year-old female of facial myokymia with multiple sclerosis was reported. In this case, facial myokymia appeared at the same time as the first attack of multiple sclerosis, in association with paroxysmal pain and desesthesia of the neck, painful tonic seizures of the right upper and lower extremities and cervical transverse myelopathy. The facial myokymia consisted of grossly visible, continuous, fine and worm-like movement, which often began in the area of the left orbicularis oculi and spread to the other facial muscles on one side. Electromyographic studies revealed grouping of motor units and continuous spontaneous rhythmic discharges in the left orbicularis oris suggesting facial myokymia, but there were no abnormalities on voluntary contraction. Sometimes doublet or multiplet patterns occurred while at other times the bursts were of single motor potential. The respective frequencies were 3-4/sec and 40-50/sec. There was no evidence of fibrillation. The facial myokymia disappeared after 4-8 weeks of administration of prednisolone and did not recur. In the remission stage after disappearance of the facial myokymia, nuclear magnetic resonance (NMR) imaging by the inversion recovery method demonstrated low intensity demyelinated plaque in the left lateral tegmentum of the inferior pons, which was responsible for the facial myokymia, but X-ray computed tomography revealed no pathological findings. The demyelinated plaque demonstrated by NMR imaging seemed to be located in the infranuclear area of the facial nerve nucleus and to involve the intramedurally root. (J.P.N.)

  2. Nuclear magnetic resonance imaging in a case of facial myokymia with multiple sclerosis

    Energy Technology Data Exchange (ETDEWEB)

    Kojima, Shigeyuki; Yagishita, Toshiyuki; Kita, Kohei; Hirayama, Keizo; Ikehira, Hiroo; Fukuda, Nobuo; Tateno, Yukio

    1985-06-01

    A 59-year-old female of facial myokymia with multiple sclerosis was reported. In this case, facial myokymia appeared at the same time as the first attack of multiple sclerosis, in association with paroxysmal pain and desesthesia of the neck, painful tonic seizures of the right upper and lower extremities and cervical transverse myelopathy. The facial myokymia consisted of grossly visible, continuous, fine and worm-like movement, which often began in the area of the left orbicularis oculi and spread to the other facial muscles on one side. Electromyographic studies revealed grouping of motor units and continuous spontaneous rhythmic discharges in the left orbicularis oris suggesting facial myokymia, but there were no abnormalities on voluntary contraction. Sometimes doublet or multiplet patterns occurred while at other times the bursts were of single motor potential. The respective frequencies were 3-4/sec and 40-50/sec. There was no evidence of fibrillation. The facial myokymia disappeared after 4-8 weeks of administration of prednisolone and did not recur. In the remission stage after disappearance of the facial myokymia, nuclear magnetic resonance (NMR) imaging by the inversion recovery method demonstrated low intensity demyelinated plaque in the left lateral segmentum of the inferior pons, which was responsible for the facial myokymia, but X-ray computed tomography revealed no pathological findings. The demyelinated plaque demonstrated by NMR imaging seemed to be located in the infranuclear area of the facial nerve nucleus and to involve the intramedurally root.

  3. Application of laser processing for disassembly of nuclear power plants

    Science.gov (United States)

    Baranov, Gennady A.; Zinchenko, A. V.; Arutyunyan, R. B.

    1998-12-01

    Provision of safety and drop of ecological risk at salvaging of nuclear submarines (NSM) of Russia Navy Forces represents one of the most actual problems of nowadays. It is necessary to remove from services of Russian Navy Forces 170 - 180 nuclear submarines by 2000. At salvaging of Russian Navy Forces NSM it should be necessary to cut out reactor compartments with more than 150 thousand tons of gross weight and to fragment terminal carcasses of submarines with gross weight of 2 million tons. Taking into account overall dimensions of salvaging objects and Euro-standard requirement on the sizes of carcass fragments, for salvaging of one NSM it is necessary to execute more than 10 km of cuts. Using of conventional methods of gas and plasma cutting of ship constructions and equipment polluted with radioactive oxides and bedding of insulation and paint and varnish materials causes contamination of working zones and environment by a mix of radioactive substances and highly toxic combustion products, nomenclature of which includes up to 50 names. Calculations carried out in the Institute of industrial and Marine Medicine have shown that salvage of just one NSM with using of gas and plasma cutting are accompanied by discharge into an environment of up to 11.5 kg of chromium oxides, up to 22.5 kg of manganese oxides, up to 97 kg of carbon oxides and up to 650 kg of nitrogen oxides. Fragmentation of such equipment by a method of directional explosion or hydraulic jet is problematic because of complexity of treated constructions and necessity to create special protective facilities, which will accumulate a bulk of radioactive and toxic discharges, as a consequence of the explosion and spreaded by shock waves and water deluges. In a number of new technological processes the cutting with using of high-power industrial lasers radiation stands out. As compared with other technological processes, laser cutting has many advantages determined by such unique properties of laser

  4. The Answering Process for Multiple-Choice Questions in Collaborative Learning: A Mathematical Learning Model Analysis

    Science.gov (United States)

    Nakamura, Yasuyuki; Nishi, Shinnosuke; Muramatsu, Yuta; Yasutake, Koichi; Yamakawa, Osamu; Tagawa, Takahiro

    2014-01-01

    In this paper, we introduce a mathematical model for collaborative learning and the answering process for multiple-choice questions. The collaborative learning model is inspired by the Ising spin model and the model for answering multiple-choice questions is based on their difficulty level. An intensive simulation study predicts the possibility of…

  5. 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

  6. Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process

    International Nuclear Information System (INIS)

    Johnson, E.R.; Best, R.E.

    2009-01-01

    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 of the

  7. Polyuridylylation and processing of transcripts from multiple gene minicircles in chloroplasts of the dinoflagellate Amphidinium carterae

    KAUST Repository

    Barbrook, Adrian C.; Dorrell, Richard G.; Burrows, Jennifer; Plenderleith, Lindsey J.; Nisbet, R. Ellen R.; Howe, Christopher J.

    2012-01-01

    -PCR to study transcription and transcript processing in the chloroplasts of Amphidinium carterae, a model peridinin-containing dinoflagellate. These organisms have a highly unusual chloroplast genome, with genes located on multiple small 'minicircle' elements

  8. Processing of foodstuffs as countermeasures following a nuclear accident

    International Nuclear Information System (INIS)

    Coulon, R.; Despres, A.; Diaz, A.; Soulatges, D.

    1989-01-01

    The processing of foodstuffs is one of the countermeasures which may be taken following a nuclear accident in order to reduce the contamination of the foodstuffs concerned. A consideration of the transfer of radioactivity during the processing or the preparation of food makes it possible to estimate the effectiveness of the countermeasure concerned, which is one essential criterion for its selection; the other is the cost of its application. In short, consideration must be given at the same time to both of these factors if a rational choice is to be made between the various potential options on an industrial scale. In addition to the countermeasures involving processing or culinary preparation of the foodstuffs concerned, they may also be destroyed, stored, used as feedingstuffs or decontaminated, and the crops may be buried, the feedingstuffs of animals changed, farmland frozen, etc. An expert system using the GOLDWORKS software should help to select the most appropriate countermeasure on the basis of its cost and effectiveness. Such a system would evaluate: - the effectiveness of each of the countermeasures likely to be selected (to be expressed in terms of dose); - the social cost of the dose avoided by their application; - the cost of the countermeasure itself. The last is estimated as thoroughly as possible by taking into account, inter alia, food processing, compensation to the producers, the costs of transport and storage or of destruction. This is followed by a proposed classification of the countermeasures according to their cost effectiveness. 17 radionuclides and 4 foodstuffs (milk, meat, green vegetables and cereals) are considered. Depending on the date of the accident concerned, the input data for themodel are produced from the concentrations measured in the foodstuffs or in the soil. In the latter case, dynamic transfer coefficients make it possible to evaluate the contamination of future harvests [fr

  9. Charged particle multiplicity distributions in e+e--annihilation processes in the LEP experiments

    International Nuclear Information System (INIS)

    Shlyapnikov, P.V.

    1992-01-01

    Results of studies of the charged particle multiplicity distributions in the process of e + e - -annihilation into hadrons obtained in experiments at LEP accelerator in CERN are reviewed. Universality in energy dependence of the average charged particle multiplicity in e + e - and p ± p collisions, evidence for KNO-scaling in e + e - data, structure in multiplicity distribution and its relation to the jet structure of events, average particle multiplicities or quark and gluon jets, 'clan' picture and other topics are discussed. 73 refs.; 20 figs.; 3 tabs

  10. The Relationship between Multiple Intelligences with Preferred Science Teaching and Science Process Skills

    OpenAIRE

    Mohd Ali Samsudin; Noor Hasyimah Haniza; Corrienna Abdul-Talib; Hayani Marlia Mhd Ibrahim

    2015-01-01

    This study was undertaken to identify the relationship between multiple intelligences with preferred science teaching and science process skills. The design of the study is a survey using three questionnaires reported in the literature: Multiple Intelligences Questionnaire, Preferred Science Teaching Questionnaire and Science Process Skills Questionnaire. The study selected 300 primary school students from five (5) primary schools in Penang, Malaysia. The findings showed a relationship betwee...

  11. Spent Nuclear Fuel (SNF) Project Design Verification and Validation Process

    International Nuclear Information System (INIS)

    OLGUIN, L.J.

    2000-01-01

    This document provides a description of design verification and validation activities implemented by the Spent Nuclear Fuel (SNF) Project. During the execution of early design verification, a management assessment (Bergman, 1999) and external assessments on configuration management (Augustenburg, 1999) and testing (Loscoe, 2000) were conducted and identified potential uncertainties in the verification process. This led the SNF Chief Engineer to implement corrective actions to improve process and design products. This included Design Verification Reports (DVRs) for each subproject, validation assessments for testing, and verification of the safety function of systems and components identified in the Safety Equipment List to ensure that the design outputs were compliant with the SNF Technical Requirements. Although some activities are still in progress, the results of the DVR and associated validation assessments indicate that Project requirements for design verification are being effectively implemented. These results have been documented in subproject-specific technical documents (Table 2). Identified punch-list items are being dispositioned by the Project. As these remaining items are closed, the technical reports (Table 2) will be revised and reissued to document the results of this work

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

    International Nuclear Information System (INIS)

    Murray, R.L.

    1988-01-01

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

  13. Nuclear renaissance or premature try?; Renacimiento nuclearo o aborto prematuro? Los multiples interrogantes de la opcion nuclear presagian su incierto futuro

    Energy Technology Data Exchange (ETDEWEB)

    Coderch, M

    2008-07-01

    After the economic failure of the 70's and not having been able to solve for decades its multiple problems, the nuclear industry was suffering a slow but inescapable agony. However, the need to reduce CO{sub 2} emissions and the likely arrival of the worldwide peak of oil production have infused new life to the nuclear option, and it has again become one of the main topics of discussion in the worldwide energy debate. But in this debate we tend to forget that the causes of the abrupt end of the first nuclear era have not disappeared, and that for this reason it may well be that we are lead to a repetition of the events that induced its first demise. The much talked nuclear renaissance is thus likely to end up as a premature miscarriage. (Author)

  14. Nuclear renaissance or premature try?; Renacimiento nuclearo o aborto prematuro? Los multiples interrogantes de la opcion nuclear presagian su incierto futuro

    Energy Technology Data Exchange (ETDEWEB)

    Coderch, M.

    2008-07-01

    After the economic failure of the 70's and not having been able to solve for decades its multiple problems, the nuclear industry was suffering a slow but inescapable agony. However, the need to reduce CO{sub 2} emissions and the likely arrival of the worldwide peak of oil production have infused new life to the nuclear option, and it has again become one of the main topics of discussion in the worldwide energy debate. But in this debate we tend to forget that the causes of the abrupt end of the first nuclear era have not disappeared, and that for this reason it may well be that we are lead to a repetition of the events that induced its first demise. The much talked nuclear renaissance is thus likely to end up as a premature miscarriage. (Author)

  15. Multiple-failure signal validation in nuclear power plants using artificial neural networks

    International Nuclear Information System (INIS)

    Fantoni, P.F.; Mazzola, A.

    1996-01-01

    The possibility of using a neural network to validate process signals during normal and abnormal plant conditions is explored. In boiling water reactor plants, signal validation is used to generate reliable thermal limits calculation and to supply reliable inputs to other computerized systems that support the operator during accident scenarios. The way that autoassociative neural networks can promptly detect faulty process signal measurements and produce a best estimate of the actual process values even in multifailure situations is shown. A method was developed to train the network for multiple sensor-failure detection, based on a random failure simulation algorithm. Noise was artificially added to the input to evaluate the network's ability to respond in a very low signal-to-noise ratio environment. Training and test data sets were simulated by the real-time transient simulator code APROS

  16. Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book II. Nuclear Chemistry, Process Technology, and Radioactive Waste Processing and Environment

    International Nuclear Information System (INIS)

    1996-06-01

    The proceeding contains papers presented on Scientific Meeting and Presentation on on Basic Research of Nuclear Science and Technology, held in Yogyakarta, 25-27 April 1995. This proceeding is second part of two books published for the meeting contains papers on nuclear chemistry, process technology, and radioactive waste management and environment. There are 62 papers indexed individually. (ID)

  17. Multiple nuclear dots and rim-like/membranous IgG isotypes in primary biliary cirrhosis.

    Science.gov (United States)

    Muratori, Paolo; Granito, Alessandro; Ferri, Silvia; Pappas, Georgios; Volta, Umberto; Menichella, Rita; Bianchi, Francesco B; Lenzi, Marco; Muratori, Luigi

    2009-03-01

    Anti nuclear (ANA) immunomorphological patterns such as multiple nuclear dots (MND) and rim-like/membranous (RL/M) are considered highly specific but little sensitive for primary biliary cirrhosis (PBC) diagnosis. To evaluate frequency and clinical significance of MND and RL/M in PBC patients when investigated at the level of immunoglobulin G isotypes. MND and RL/M pattern have been tested in 141 PBC sera and 230 pathological controls using HEp-2 cells as substrate and anti- total IgG and individual IgG subclasses (IgG1, IgG2, IgG3, IgG4) as specific antisera. One hundred and fourteen of 141 (80%) PBC patients had RL/M or MND pattern when IgG subclasses were used as revealing reagents (vs. 34% when anti total IgG were used, p < 0.0001). The prevalent isotype was IgG1 for RL/M, and IgG2 for MND pattern. None of controls was positive. No clinical differences in terms of severity and outcome of disease have been observed in PBC patients positive for MND and RL/M when investigated with IgG isotypes. The research for RL/M and MND pattern at level of IgG isotype determines a wide gain in terms of sensitivity without a loss of specificity. In Italian PBC patients MND and RL/M pattern did not seem to characterize any subgroup of patients with a poorer prognosis.

  18. NJOY nuclear data processing system. Volume IV. The ERRORR and COVR modules

    International Nuclear Information System (INIS)

    Muir, D.W.; MacFarlane, R.E.

    1985-12-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections and related nuclear parameters from ENDF/B evaluated nuclear data. This volume provides detailed descriptions of the NJOY modules ERRORR and COVR, which are concerned with the covariances (uncertainties and correlations) of multigroup cross sections and fission neutron yield (anti nu) values. 17 refs

  19. Two citizen task forces and the challenge of the evolving nuclear waste siting process

    International Nuclear Information System (INIS)

    Peelle, E.B.

    1990-01-01

    Siting any nuclear waste facility is problematic in today's climate of distrust toward nuclear agencies and fear of nuclear waste. This study compares and contrasts the siting and public participation processes as two citizen task forces dealt with their difficult responsibilities. 10 refs., 3 tabs

  20. Prototype plant for nuclear process heat (PNP), reference phase

    International Nuclear Information System (INIS)

    Fladerer, R.; Schrader, L.

    1982-07-01

    The coal gasification processes using nuclear process heat being developed within the framwork of the PNP project, have the advantages of saving feed coal, improving efficiency, reducing emissions, and stabilizing energy costs. One major gasification process is the hydrogasification of coal for producing SNG or gas mixture of carbon monoxide and hydrogen; this process can also be applied in a conventional route. The first steps to develop this process were planning, construction and operation of a semi-technical pilot plant for hydrogasification of coal in a fluidized bed having an input of 100 kg C/h. Before the completion of the development phase (reference phase) describing here, several components were tested on part of which no operational experience had so far been gained; these were the newly developed devices, e.g. the inclined tube for feeding coal into the fluidized bed, and the raw gas/hydrogenation gas heat exchanger for utilizing the waste heat of the raw gas leaving the gasifier. Concept optimizing of the thoroughly tested equipment parts led to an improved operational behaviour. Between 1976 and 1980, the semi-technical pilot plant was operated for about 19,400 hours under test conditions, more than 7,400 hours of which it has worked under gasification conditions. During this time approx. 1,100 metric tons of dry brown coal and more than 13 metric tons of hard coal were gasified. The longest coherent operational phase under gasification conditions was 748 hours in which 85.4 metric tons of dry brown coal were gasified. Carbon gasification rates up to 82% and methane contents in the dry raw gas (free of N 2 ) up to 48 vol.% were obtained. A detailed evaluation of the test results provided information of the results obtained previously. For the completion of the test - primarily of long-term tests - the operation of the semi-technical pilot plant for hydrogasification of coal is to be continued up to September 1982. (orig.) [de

  1. Permission of the alteration in nuclear fuel material processing business in the Kumatori Works of Nuclear Fuel Industries, Ltd. (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Prime Minister concerning the permission of the alteration in nuclear fuel material processing business in the Kumatori Works, Nuclear Fuel Industries Ltd., was presented. The technical capability of NFI and the safety of the business alteration were confirmed. The items of the safety examination concerning the alteration, made by the Committee on Examination of Nuclear Fuel Safety of NSC, are as follows: the aseismic design and fire prevention measures of the No.2 processing building and the No.3 waste storage building to be newly installed; criticality control concerning the No.2 processing building; the release control of gaseous and liquid wastes; the management of solid wastes; radiation control; the exposure dose of general public. (J.P.N.)

  2. Modeling risk assessment for nuclear processing plants with LAVA

    International Nuclear Information System (INIS)

    Smith, S.T.; Tisinger, R.M.

    1988-01-01

    Using the Los Alamos Vulnerability and Risk Assessment (LAVA) methodology, the authors developed a model for assessing risks associated with nuclear processing plants. LAVA is a three-part systematic approach to risk assessment. The first part is the mathematical methodology; the second is the general personal computer-based software engine; and the third is the application itself. The methodology provides a framework for creating applications for the software engine to operate upon; all application-specific information is data. Using LAVA, the authors build knowledge-based expert systems to assess risks in applications systems comprising a subject system and a safeguards system. The subject system model is sets of threats, assets, and undesirable outcomes. The safeguards system model is sets of safeguards functions for protecting the assets from the threats by preventing or ameliorating the undesirable outcomes, sets of safeguards subfunctions whose performance determine whether the function is adequate and complete, and sets of issues, appearing as interactive questionnaires, whose measures (in both monetary and linguistic terms) define both the weaknesses in the safeguards system and the potential costs of an undesirable outcome occurring

  3. Process and device for feeding a cutter of nuclear fuel

    International Nuclear Information System (INIS)

    Chaze, Gilbert; Cherel, Guy; Guilloteau, Rene; Tucoulat, Daniel.

    1975-01-01

    A process is described for feeding the cutter of a nuclear fuel tube bundle by means of a mobile magazine. The first operation consists in grabbing the bundle in the storage pool by means of handling gear incorporated in the cutter magazine and introducing the bundle right into the magazine. The second operation is to locate the position of the bundle and to do so a mobile reference plate, of which the relative positions in relation to the magazine and to the cutting section in the cutter are known, is placed near the end of the magazine that will enter into contact with the cutter, the bundle is then moved until its end enters into contact with the reference plate. The next operation consists in adjusting the position of the bundle by moving it out of the magazine by a given length as from the position of the bundle when it was in contact with the reference plate so as to separate the foot end of the bundle by a cut made right next to this foot end. In several successive operations to adjust the cutting positions, the bundle is fed forward in the cutter by a length equal to a tube section. All these operations are carried out without the bundle being separated from the single handling gear built into the magazine [fr

  4. Antinuclear antibodies giving the 'multiple nuclear dots' or the 'rim-like/membranous' patterns: diagnostic accuracy for primary biliary cirrhosis.

    Science.gov (United States)

    Granito, A; Muratori, P; Muratori, L; Pappas, G; Cassani, F; Worthington, J; Guidi, M; Ferri, S; DE Molo, C; Lenzi, M; Chapman, R W; Bianchi, F B

    2006-12-01

    Serum antinuclear antibodies giving the 'multiple nuclear dots' or the 'rim-like/membranous' patterns are frequently detected by indirect immunofluorescence on HEp-2 cells in patients with primary biliary cirrhosis. To assess the accuracy of multiple nuclear dot and rim-like/membranous antinuclear antibodies for the diagnosis of primary biliary cirrhosis. Sera from 4371 consecutive patients referred to our laboratory were analysed under code for antinuclear antibodies testing by indirect immunofluorescence on HEp-2 cells. Review of the clinical records of the 4371 patients allowed identification of 101 patients with antimitochondrial antibody-positive primary biliary cirrhosis and 22 with antimitochondrial antibody-negative variant. Multiple nuclear dot and/or rim-like/membranous patterns were found in 59 (1.3%) of the 4371 patients: 31 antimitochondrial antibody-positive primary biliary cirrhosis, 17 antimitochondrial antibody-negative primary biliary cirrhosis and 11 non-primary biliary cirrhosis. The specificity for primary biliary cirrhosis of both the antinuclear antibodies pattern was 99%. Positive predictive value and likelihood ratio for a positive test were 86% (95% CI: 72.7-94) and 221 (95% CI: 91.7-544) for multiple nuclear dot, 79% (95% CI: 62.2-90.1) and 132 (95% CI: 56.8-312.7) for rim-like/membranous, respectively. Multiple nuclear dot and rim-like/membranous antinuclear antibodies are rare findings. Their positivity strongly suggests the diagnosis of primary biliary cirrhosis, irrespective of antimitochondrial antibody status. The high specificity for primary biliary cirrhosis makes them a useful diagnostic tool especially in antimitochondrial antibody-negative patients.

  5. Multiple functions and essential roles of nuclear receptor coactivators of bHLH-PAS family.

    Science.gov (United States)

    Pecenova, L; Farkas, Robert

    2016-07-01

    Classical non-peptide hormones, such as steroids, retinoids, thyroid hormones, vitamin D3 and their derivatives including prostaglandins, benzoates, oxysterols, and bile acids, are collectively designated as small lipophilic ligands, acting via binding to the nuclear receptors (NRs). The NRs form a large superfamily of transcription factors that participate virtually in every key biological process. They control various aspects of animal development, fertility, gametogenesis, and numerous metabolic pathways, and can be misregulated in many types of cancers. Their enormous functional plasticity, as transcription factors, relates in part to NR-mediated interactions with plethora of coregulatory proteins upon ligand binding to their ligand binding domains (LBD), or following covalent modification. Here, we review some general views of a specific group of NR coregulators, so-called nuclear receptor coactivators (NRCs) or steroid receptor coactivators (SRCs) and highlight some of their unique functions/roles, which are less extensively mentioned and discussed in other reviews. We also try to pinpoint few neglected moments in the cooperative action of SRCs, which may also indicate their variable roles in the hormone-independent signaling pathways.

  6. Stochastic processes analysis in nuclear reactor using ARMA models

    International Nuclear Information System (INIS)

    Zavaljevski, N.

    1990-01-01

    The analysis of ARMA model derived from general stochastic state equations of nuclear reactor is given. The dependence of ARMA model parameters on the main physical characteristics of RB nuclear reactor in Vinca is presented. Preliminary identification results are presented, observed discrepancies between theory and experiment are explained and the possibilities of identification improvement are anticipated. (author)

  7. Multiple post-translational modifications in hepatocyte nuclear factor 4α

    International Nuclear Information System (INIS)

    Yokoyama, Atsushi; Katsura, Shogo; Ito, Ryo; Hashiba, Waka; Sekine, Hiroki; Fujiki, Ryoji; Kato, Shigeaki

    2011-01-01

    Highlights: → We performed comprehensive PTM analysis for HNF4α protein. → We identified 8 PTMs in HNF4α protein including newly identified PTMs. → Among them, we found acetylation at lysine 458 was one of the prime PTMs for HNF4α function. → Acetylation at lysine 458 was inhibitory for HNF4α transcription function. → This modification fluctuated in response to extracellular condition. -- Abstract: To investigate the role of post-translational modifications (PTMs) in the hepatocyte nuclear factor 4α (HNF4α)-mediated transcription, we took a comprehensive survey of PTMs in HNF4α protein by massspectrometry and identified totally 8 PTM sites including newly identified ubiquitilation and acetylation sites. To assess the impact of identified PTMs in HNF4α-function, we introduced point mutations at the identified PTM sites and, tested transcriptional activity of the HNF4α. Among the point-mutations, an acetylation site at lysine 458 was found significant in the HNF4α-mediated transcriptional control. An acetylation negative mutant at lysine 458 showed an increased transcriptional activity by about 2-fold, while an acetylation mimic mutant had a lowered transcriptional activation. Furthermore, this acetylation appeared to be fluctuated in response to extracellular nutrient conditions. Thus, by applying an comprehensive analysis of PTMs, multiple PTMs were newly identified in HNF4α and unexpected role of an HNF4α acetylation could be uncovered.

  8. Phylogenetic Relationships of Pseudorasbora, Pseudopungtungia, and Pungtungia (Teleostei; Cypriniformes; Gobioninae Inferred from Multiple Nuclear Gene Sequences

    Directory of Open Access Journals (Sweden)

    Keun-Yong Kim

    2013-01-01

    Full Text Available Gobionine species belonging to the genera Pseudorasbora, Pseudopungtungia, and Pungtungia (Teleostei; Cypriniformes; Cyprinidae have been heavily studied because of problems on taxonomy, threats of extinction, invasion, and human health. Nucleotide sequences of three nuclear genes, that is, recombination activating protein gene 1 (rag1, recombination activating gene 2 (rag2, and early growth response 1 gene (egr1, from Pseudorasbora, Pseudopungtungia, and Pungtungia species residing in China, Japan, and Korea, were analyzed to elucidate their intergeneric and interspecific phylogenetic relationships. In the phylogenetic tree inferred from their multiple gene sequences, Pseudorasbora, Pseudopungtungia and Pungtungia species ramified into three phylogenetically distinct clades; the “tenuicorpa” clade composed of Pseudopungtungia tenuicorpa, the “parva” clade composed of all Pseudorasbora species/subspecies, and the “herzi” clade composed of Pseudopungtungia nigra, and Pungtungia herzi. The genus Pseudorasbora was recovered as monophyletic, while the genus Pseudopungtungia was recovered as polyphyletic. Our phylogenetic result implies the unstable taxonomic status of the genus Pseudopungtungia.

  9. Multiple lead seal assembly for a liquid-metal-cooled fast-breeder nuclear reactor

    International Nuclear Information System (INIS)

    Hutter, E.; Pardini, J.A.

    1977-01-01

    A reusable multiple lead seal assembly provides leak-free passage of stainless-steel-clad instrument leads through the cover on the primary tank of a liquid-metal-cooled fast-breeder nuclear reactor. The seal isolates radioactive argon cover gas and sodium vapor within the primary tank from the exterior atmosphere and permits reuse of the assembly and the stainless-steel-clad instrument leads. Leads are placed in flutes in a seal body, and a seal shell is then placed around the seal body. Circumferential channels in the body and inner surface of the shell are contiguous and together form a conduit which intersects each of the flutes, placing them in communication with a port through the wall of the seal shell. Liquid silicone rubber sealant is injected into the flutes through the port and conduit; the sealant fills the space in the flutes not occupied by the leads themselves and dries to a rubbery hardness. A nut, threaded onto a portion of the seal body not covered by the seal shell, jacks the body out of the shell and shears the sealant without damage to the body, shell, or leads. The leads may then be removed from the body. The sheared sealant is cleaned from the body, leads, and shell and the assembly may then be reused with the same or different leads. 3 claims, 6 figures

  10. DTN and international cooperation of the Spanish Nuclear Sector in nuclear technology development processes

    International Nuclear Information System (INIS)

    Acero, M.

    1995-01-01

    The Spanish electrical utilities with interests in the Nuclear Sector-IBERDROLA, ENDESA,FUERZAS ELECTRICAS DE CATALU=A5A (FECSA), UNION ELECTRICA FENOSA S.A., COMPA=A5IA SEVILLANA DE ELECTRICIDAD S.A., AND HIDROELECTRICA DEL CANTABRICO S.A.-created on September 26, 1994 the ''Agrupacion Electrica para el Desarrollo Tecnologico Nuclear, A.I.E. (DTN)'' (Electrical Society for Nuclear technology Development A.I.E.) for the purpose of promoting and managing Nuclear Nechnology Development, and integrating and coordinating the efforts of the Nuclear Electrical Sector with industrial companies and other related institutions in spain and abroad. This mission is primarily accomplished by establinhing a common strategy for the Nuclear Electrical Sector in the different areas of responsibility of DTN, centralizing actions by implementing a clear and coherent policy, and ensuring the presence of the entire Electrical Sector in all those fora deemed to be strategic to the Nuclear Sector

  11. Modelling the Dynamics of Intracellular Processes as an Organisation of Multiple Agents

    NARCIS (Netherlands)

    Bosse, T.; Jonker, C.M.; Treur, J.; Armano, G.; Merelli, E.; Denzinger, J.; Martin, A.; Miles, S.; Tianfield, H.; Unland, R.

    2005-01-01

    This paper explores how the dynamics of complex biological processes can be modeled as an organisation of multiple agents. This modelling perspective identifies organisational structure occurring in complex decentralised processes and handles complexity of the analysis of the dynamics by structuring

  12. Description of multiple processes on the basis of triangulation in the velocity space

    International Nuclear Information System (INIS)

    Baldin, A.M.; Baldin, A.A.

    1986-01-01

    A method of the construction of polyhedrons in the relative four-velocity space is suggested which gives a complete description of multiple processes. A method of the consideration of a general case, when the total number of the relative velocity variables exceeds the number of the degrees of freedom, is also given. The account of the particular features of the polyhedrons due to the clusterization in the velocity space, as well as the account of the existence of intermediate asymptotics and the correlation depletion principle makes it possible to propose an algorithm for processing much larger bulk of experimental information on multiple processes as compared to the inclusive approach

  13. Presentation of the process External communications on the nuclear facilities operation of the Adjunct Head Office of Nuclear Safety of Comision Nacional de Seguridad Nuclear y Salvaguardias

    International Nuclear Information System (INIS)

    Espinosa V, J. M.

    2012-10-01

    The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in use of their attributions granted by the Regulation Law of the constitutional Art. 27 in nuclear matter began the development of the called process External communications on the nuclear facilities operation, with the purpose of negotiating the evaluation of the concerns related with the safety of the nuclear facilities received these of external people to the CNSNS. The process External communications on the nuclear facilities operation will allow to the public's members and the workers that carry out activities inside the mark regulator imposed by the CNSNS that report to this Commission their concerns related with safety for several means (for example, directly to the personnel of the assigned Office, official and public statements, phone communication, electronic mail, etc.) The present article presents the legal mark confers the CNSNS the attributions to develop the mentioned process and exposes the most important elements that compose it. The term External communication on the nuclear facilities operation is defined and also is described how these communications are received, evaluated and closed by the assigned Office. Of equal way the objectives that intents to reach this process are indicated. The intention of the mentioned process is to strengthen the actions that the CNSNS carries out in the execution of its functions to maintain the safety standards in the operation of the nuclear facilities in Mexico. (Author)

  14. Concerning permission of commercial processing of nuclear fuel substances at Rokkasho plant of Japan Nuclear Fuel Industries, Ltd

    International Nuclear Information System (INIS)

    1988-01-01

    The Nuclear Safety Commission on Dec. 19, 1987 directed the Nuclear Fuel Safety Expert Group to carry out a study on it, made deliberations after receiving a report from the Group on July 13, 1988, and submitted the findings to the Prime Minister on July 21. The study and deliberations were intended to determine the conformity of the permission to the applicable criteria specified in laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The investigation on the location covered the site conditions, meteorology, ground conditions, hydrology, seismic environments, and social environment. The investigations on the safety design addressed the anti-earthquake performance, fire/explosion prevention, criticality control, thermal stability, containment performance, safety against natural phenomena other than earthquake, radioactive waste management, and radiation control. Other investigations included exposure evaluation and accident analysis. It was concluded that the permission would not have adverse effects on the safety of the processing business. (Nogami, K.)

  15. Concerning permission of commercial processing of nuclear fuel substances at Rokkasho plant of Japan Nuclear Fuel Industries, Ltd

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    The Nuclear Safety Commission on Dec. 19, 1987 directed the Nuclear Fuel Safety Expert Group to carry out a study on it, made deliberations after receiving a report from the Group on July 13, 1988, and submitted the findings to the Prime Minister on July 21. The study and deliberations were intended to determine the conformity of the permission to the applicable criteria specified in laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The investigation on the location covered the site conditions, meteorology, ground conditions, hydrology, seismic environments, and social environment. The investigations on the safety design addressed the anti-earthquake performance, fire/explosion prevention, criticality control, thermal stability, containment performance, safety against natural phenomena other than earthquake, radioactive waste management, and radiation control. Other investigations included exposure evaluation and accident analysis. It was concluded that the permission would not have adverse effects on the safety of the processing business. (Nogami, K.).

  16. USNRC licensing process as related to nuclear criticality safety

    International Nuclear Information System (INIS)

    Ketzlach, N.

    1987-01-01

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

  17. Technology in the policy process - controlling nuclear power

    International Nuclear Information System (INIS)

    Collingridge, D.

    1983-01-01

    The discussion in this book is built around nuclear power. The technology of nuclear power is shown to have features which make it inflexible in the sense that, once built, it is difficult and expensive to control. If inflexible technology is to be avoided, it is crucially important to be able to identify this failing at an early stage in the technology's development, before it has acquired an immunity to political control. Again, this problem is approached through the example of nuclear power, in particular the breeder reactor. The breeder is shown to be even less flexible than today's nuclear technology, because it will have higher capital costs, be of greater capital intensity, longer lead time, larger unit size, and will require more infrastructure for its operation. If this is developed, the breeder will be even less open to political control than the nuclear plant of the present. To put it another way, its planning will be even more open to errors and whatever errors are made will be even more costly than for existing nuclear technology. It is therefore even less of a socially and economically acceptable technology than today's nuclear power. (author)

  18. Use of a tangential filtration unit for processing liquid waste from nuclear laundries

    International Nuclear Information System (INIS)

    Augustin, X.; Buzonniere, A. de; Barnier, H.

    1993-01-01

    Nuclear laundries produce large quantities of weakly contaminated effluents charged with insoluble and soluble products. In collaboration with CEA, TECHNICATOME has developed an ultrafiltration process for liquid waste from nuclear laundries, associated with prior in-solubilization of the radiochemical activity. This process 'seeded ultrafiltration' is based on the use of decloggable mineral filter media and combines very high separation efficiency with long membrane life. The efficiency of the tangential filtration unit which has been processing effluents from the Cadarache Nuclear Research Center (CEA-France) nuclear laundry since mid-1988, has been confirmed on several sites

  19. FRENDY: A new nuclear data processing system being developed at JAEA

    Science.gov (United States)

    Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio

    2017-09-01

    JAEA has provided an evaluated nuclear data library JENDL and nuclear application codes such as MARBLE, SRAC, MVP and PHITS. These domestic codes have been widely used in many universities and industrial companies in Japan. However, we sometimes find problems in imported processing systems and need to revise them when the new JENDL is released. To overcome such problems and immediately process the nuclear data when it is released, JAEA started developing a new nuclear data processing system, FRENDY in 2013. This paper describes the outline of the development of FRENDY and both its capabilities and performances by the analyses of criticality experiments. The verification results indicate that FRENDY properly generates ACE files.

  20. Theoretical studies of multistep processes, isospin effects in nuclear scattering, and meson and baryon interactions in nuclear physics: Annual progess report, 1 May 1988--30 April 1989

    International Nuclear Information System (INIS)

    Landau, R.H.; Madsen, V.A.

    1988-01-01

    A progress report is presented for DOE grant FG06-86ER40283 supporting theoretical studies in nuclear and particle physics at Oregon State University. The research was led by Professors Landau and Madsen, and carried out in collaboration with graduate students in Corvallis, and scientists at LLNL-Livermore, TRIUMF, KFA-Juelich, Purdue University, and Florida State University. The studies include meson-exchange-current effects, quark effects, and relativistic (Dirac) effects deduced from spin observables in p- 3 He scattering, atomic and nuclear Gamow states in momentum space of kaons and antiprotons, and charge-symmetry violation in pion scattering. Additional studies include microscopic optical potential calculations, multiple step processes, and differences in neutron and proton multipole matrix elements and transition densities in low lying collective states and in giant resonances. 13 refs

  1. The main chemical safety problems in main process of nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Song Fengli; Zhao Shangui; Liu Xinhua; Zhang Chunlong; Lu Dan; Liu Yuntao; Yang Xiaowei; Wang Shijun

    2014-01-01

    There are many chemical reactions in the aqueous process of nuclear fuel reprocessing. The reaction conditions and the products are different so that the chemical safety problems are different. In the paper the chemical reactions in the aqueous process of nuclear fuel reprocessing are described and the main chemical safety problems are analyzed. The reference is offered to the design and accident analysis of the nuclear fuel reprocessing plant. (authors)

  2. Single-copy nuclear genes place haustorial Hydnoraceae within piperales and reveal a cretaceous origin of multiple parasitic angiosperm lineages.

    Directory of Open Access Journals (Sweden)

    Julia Naumann

    Full Text Available Extreme haustorial parasites have long captured the interest of naturalists and scientists with their greatly reduced and highly specialized morphology. Along with the reduction or loss of photosynthesis, the plastid genome often decays as photosynthetic genes are released from selective constraint. This makes it challenging to use traditional plastid genes for parasitic plant phylogenetics, and has driven the search for alternative phylogenetic and molecular evolutionary markers. Thus, evolutionary studies, such as molecular clock-based age estimates, are not yet available for all parasitic lineages. In the present study, we extracted 14 nuclear single copy genes (nSCG from Illumina transcriptome data from one of the "strangest plants in the world", Hydnora visseri (Hydnoraceae. A ~15,000 character molecular dataset, based on all three genomic compartments, shows the utility of nSCG for reconstructing phylogenetic relationships in parasitic lineages. A relaxed molecular clock approach with the same multi-locus dataset, revealed an ancient age of ~91 MYA for Hydnoraceae. We then estimated the stem ages of all independently originated parasitic angiosperm lineages using a published dataset, which also revealed a Cretaceous origin for Balanophoraceae, Cynomoriaceae and Apodanthaceae. With the exception of Santalales, older parasite lineages tend to be more specialized with respect to trophic level and have lower species diversity. We thus propose the "temporal specialization hypothesis" (TSH implementing multiple independent specialization processes over time during parasitic angiosperm evolution.

  3. Role of nuclear medicine in pulmonary neoplastic processes

    International Nuclear Information System (INIS)

    Waxman, A.D.

    1986-01-01

    It has been demonstrated that the single most important factor in determining survival in patients with bronchogenic carcinoma is the extent of spread of metastasis from the primary lesion. This explains the extensive efforts in developing accurate staging tests for pulmonary tumors, both primary and metastatic, with special emphasis on the determination of pulmonary hilar and mediastinal spread of disease. Continued improvements in nuclear medicine instrumentation along with the development of tumor specific radiopharmaceuticals, as well as agents that have the capability of tracking tumor viability, have changed the orientation of scintigraphic techniques in the evaluation of pulmonary neoplastic processes. Gallium scintigraphy is no longer considered as a primary imaging modality in the staging of pulmonary tumors, and in most institutions has been replaced by computed tomography (CT) for this purpose. It has been demonstrated that gallium, relative to other imaging modalities, is a sensitive indicator of hilar spread of tumor. However, because of the normally high background activity within the sternum and spine, mediastinal abnormalities are poorly detected. Since most pulmonary tumors metastasize via regional nodes to the pulmonary hilum and then to the mediastinum, the high sensitivity for the detection of pulmonary hilar abnormalities and the high specificity for mediastinal lesion detection suggest that gallium scintigraphy is a valuable adjunctive test when used appropriately. Thallium 201 as a tumor agent is being studied by several institutions. Preliminary results indicate a high degree of sensitivity for the detection of pulmonary hilar and mediastinal lesions and there are early indications that thallium is a promising agent to evaluate tumor viability. 52 references

  4. Data acquisition and management system for a nuclear processes simulator

    International Nuclear Information System (INIS)

    Gonzalez M, J.A.; Santiago C, J.

    2003-01-01

    In the development of this work (Data acquisition and management system for a simulator of nuclear processes (SAMAD)), is important to mention the main modules that involve the operation of the same one. At the beginning it was necessary to contemplate the possible programming languages, as well as the compatibility and handling easiness among them. The used languages to be able to land the contemplated ideas are: C ++ , PHP, HTML, as well as the My SQL database manager. After this it was designed the database (DB), which contains the tables of each one of the components, this according to the enter file type of the RELAP5 code that will be use for each simulation, as well as, tables that will allow us to relate and to maintain the control of the information supplied to the DB. Once created the database is interacting with it through an application program based on PHP (Preprocessor). The application basically consists, in extracting the data from each one of the components to work in that moment, that is to say, to obtain the data of the enter file, as well as, to depurate the data, excluding comments. The preprocessor gives bigger easiness to place the data in the DB. Also, it was developed an graphic interface that allows to register variables to the DB, depending from the unfolding to visualize. Another application that has been implemented is the Data Collector that has as function, to obtain in a direct way the data of the display variables of the RELAP5 code, with the purpose of storing them in the DB, this will be carry out in real time and it was updated in a very small time period. (Author)

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

    International Nuclear Information System (INIS)

    Lee, Deok Joo; Hwang, Jooho

    2010-01-01

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

  6. Energy loss effect in high energy nuclear Drell-Yan process

    International Nuclear Information System (INIS)

    Duan, C.G.; Song, L.H.; Huo, L.J.; Li, G.L.

    2003-01-01

    The energy loss effect in nuclear matter, which is a nuclear effect apart from the nuclear effect on the parton distribution as in deep-inelastic scattering process, can be measured best by the nuclear dependence of the high energy nuclear Drell-Yan process. By means of the nuclear parton distribution studied only with lepton deep-inelastic scattering experimental data, the measured Drell-Yan production cross sections for 800 GeV proton incident on a variety of nuclear targets are analyzed within the Glauber framework which takes into account the energy loss of the beam proton. It is shown that the theoretical results with considering the energy loss effect are in good agreement with the FNAL E866 data. (orig.)

  7. Contribution to the optimization of the coupling of nuclear reactors to desalination processes

    International Nuclear Information System (INIS)

    Dardour, S.

    2007-04-01

    This work deals with modelling, simulation and optimization of the coupling between nuclear reactors (PWR, modular high temperature reactors) and desalination processes (multiple effect distillation, reverse osmosis). The reactors considered in this study are PWR (Pressurized Water Reactor) and GTMHR (Gas Turbine Modular Helium Reactor). The desalination processes retained are MED (Multi Effect Distillation) and SWRO (Sea Water Reverse Osmosis). A software tool: EXCELEES of thermodynamic modelling of coupled systems, based on the Engineering Algebraic Equation Solver has been developed. Models of energy conversion systems and of membrane desalination processes and distillation have been developed. Based on the first and second principles of thermodynamics, these models have allowed to determine the optimal running point of the coupled systems. The thermodynamic analysis has been completed by a first economic evaluation. Based on the use of the DEEP software of the IAEA, this evaluation has confirmed the interest to use these types of reactors for desalination. A modelling tool of thermal processes of desalination in dynamic condition has been developed too. This tool has been applied to the study of the dynamics of an existing plant and has given satisfying results. A first safety checking has been at last carried out. The transients able to jeopardize the integrated system have been identified. Several measures aiming at consolidate the safety have been proposed. (O.M.)

  8. Applications of genetic algorithms to optimization problems in the solvent extraction process for spent nuclear fuel

    International Nuclear Information System (INIS)

    Omori, Ryota, Sakakibara, Yasushi; Suzuki, Atsuyuki

    1997-01-01

    Applications of genetic algorithms (GAs) to optimization problems in the solvent extraction process for spent nuclear fuel are described. Genetic algorithms have been considered a promising tool for use in solving optimization problems in complicated and nonlinear systems because they require no derivatives of the objective function. In addition, they have the ability to treat a set of many possible solutions and consider multiple objectives simultaneously, so they can calculate many pareto optimal points on the trade-off curve between the competing objectives in a single iteration, which leads to small computing time. Genetic algorithms were applied to two optimization problems. First, process variables in the partitioning process were optimized using a weighted objective function. It was observed that the average fitness of a generation increased steadily as the generation proceeded and satisfactory solutions were obtained in all cases, which means that GAs are an appropriate method to obtain such an optimization. Secondly, GAs were applied to a multiobjective optimization problem in the co-decontamination process, and the trade-off curve between the loss of uranium and the solvent flow rate was successfully obtained. For both optimization problems, CPU time with the present method was estimated to be several tens of times smaller than with the random search method

  9. Human factor in the process of nuclear power development

    International Nuclear Information System (INIS)

    Enenkl, V.

    The building up of nuclear power requires the training not only of personnel but of the whole population as well. Professional workers in nuclear power facilities production and personnel operating the equipment of nuclear power plants must be on a high technical and managerial level. The important quality of such personnel is their reliability and responsibility. The human factor influences the level, quality and thereby also the service-life of the machines and equipment and their operation. The improvement of the quality of work in nuclear power production depends on upgrading the scientific and technical level of workers and personnel, their training, in-service education and the raising of the social standing. (B.H.)

  10. Corrosion process studies in a nuclear waste container

    International Nuclear Information System (INIS)

    Guasp, Ruben A.; Lanzani, Liliana A.; Coronel, Pascual; Bruzzoni, Pablo; Semino, Carlos J.

    1999-01-01

    Latest results on corrosion behavior studies on high activity nuclear waste container are reported. Corrosion evaluation on lead base alloys and modeling to predict carbon steel external container cover generalized corrosion, are the main issues of these studies. (author)

  11. Core power distribution measurement and data processing in Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    Zhang Hong

    1997-01-01

    For the first time in China, Daya Bay Nuclear Power Station applied the advanced technology of worldwide commercial pressurized reactors to the in-core detectors, the leading excore six-chamber instrumentation for precise axial power distribution, and the related data processing. Described in this article are the neutron flux measurement in Daya Bay Nuclear Power Station, and the detailed data processing

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

    CERN Document Server

    Murray, Raymond L

    1993-01-01

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

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

    CERN Document Server

    Murray, Raymond

    2001-01-01

    Nuclear Energy, Fifth Edition provides nuclear engineers, plant designers and radiation physicists with a comprehensive overview of nuclear energy and its uses, discusses potential problems and provides an outlook for the futureNew and important trends are discussed including probabilistic safety analysis (PSA), deregulation of the electric power industry to permit competition in the supply of electricity; improvements in performance characteristics of nuclear power plants, such as capacity factor, production costs, and safety factors; storage and disposal of all types of radioactive w

  14. Modification in fuel processing of Mitsubishi Nuclear Fuel's Tokai Works

    International Nuclear Information System (INIS)

    1976-01-01

    Results of the study by the Committee for Examination of Fuel Safety, reported to the AEC of Japan, are presented, concerning safety of the modifications of Tokai Works, Mitsubishi Nuclear Fuel Co., Ltd. Safety has been confirmed thereof. The modifications covered are the following: storage facility of nuclear fuel in increase, analytical facility in transfer, fuel assemblage equipment in addition, incineration facility of combustible solid wastes in installation, experimental facility of uranium recovery in installation, and warehouse in installation. (Mori, K.)

  15. Nuclear safety inspection in treatment process for SG heat exchange tubes deficiency of unit 1, TNPS

    International Nuclear Information System (INIS)

    Zhang Chunming; Song Chenxiu; Zhao Pengyu; Hou Wei

    2006-01-01

    This paper describes treatment process for SG heat exchange tubes deficiency of Unit 1, TNPS, nuclear safety inspection of Northern Regional Office during treatment process for deficiency and further inspection after deficiency had been treated. (authors)

  16. Availability analysis of safety grade multiple redundant controller used in advanced nuclear safety systems

    International Nuclear Information System (INIS)

    Son, Kwang Seop; Kim, Dong Hoon; Park, Gee Yong; Kang, Hyun Gook

    2018-01-01

    Highlights: •The multiple redundant controller, SPLC is configured as the combination of DMR and TMR architecture. •We construct the Markov model of SPLC using the concept of the system unavailability rate. •To satisfy the availability requirement of safety grade controller, the fault coverage factor (FCF) should be ≥0.8 and the MTTR of each module should be ≤100 h when FCF is 0.9. •The availability of SPLC is better than that of PLC having iTMR architecture however it is poorer than iTMR considering the off-line test and inspection on the assumption that MTTR of each module is ≤200 h. -- Abstract: We analyze the availability of the Safety Programmable Logic Controller (SPLC) having multiple redundant architectures. In the SPLC, input/output and processor module are configured as triple modular redundancy (TMR), and backplane bus, power and communication modules are configured as dual modular redundancy (DMR). The voting logics for redundant architectures are based on the forwarding error detection. It means that the receivers perform the voting logics based on the status information of transmitters. To analyze the availability of SPLC, we construct the Markov model and simplify the model adopting the system unavailability rate. The results show that the fault coverage factor should be ≥0.8 and Mean Time To Repair (MTTR) should be ≤100 h in order to satisfy the requirement that the availability of the safety grade PLC should be ≥0.995. Also we evaluate the availability of SPLC comparing to other PLCs such as simplex, processor DMR (pDMR) and independent TMR (iTMR) PLCs used in the existing nuclear safety systems. The availability of SPLC is higher than those of the simplex, pDMR but is lower than that of iTMR for one month which is the periodic off-line test and inspection. That’s why the number of redundant modules used in PLC is more dominant to increasing the availability than the number of fault masking methods such as voting logics used

  17. Nuclear spectrometry signal acquisition and processing system based on LabVIEW and C

    International Nuclear Information System (INIS)

    Chen Xiaojun; Fang Fang; Chen Mingchi; Jiang Zancheng; Wang Min

    2008-01-01

    The process of designing nuclear spectrometry signal acquisition and processing system based on virtual instrument technology is showed in this article. For the deficiency of LabVIEW in big data analyzing and processing, a method is presented in which C programmer is inserted and applied in signal smoothing, peak searching and area of the peak calculating. A complete nuclear spectrometry signal acquisition, processing and document management system is implemented. (authors)

  18. A data-driven multiplicative fault diagnosis approach for automation processes.

    Science.gov (United States)

    Hao, Haiyang; Zhang, Kai; Ding, Steven X; Chen, Zhiwen; Lei, Yaguo

    2014-09-01

    This paper presents a new data-driven method for diagnosing multiplicative key performance degradation in automation processes. Different from the well-established additive fault diagnosis approaches, the proposed method aims at identifying those low-level components which increase the variability of process variables and cause performance degradation. Based on process data, features of multiplicative fault are extracted. To identify the root cause, the impact of fault on each process variable is evaluated in the sense of contribution to performance degradation. Then, a numerical example is used to illustrate the functionalities of the method and Monte-Carlo simulation is performed to demonstrate the effectiveness from the statistical viewpoint. Finally, to show the practical applicability, a case study on the Tennessee Eastman process is presented. Copyright © 2013. Published by Elsevier Ltd.

  19. Luminous Infrared Galaxies. III. Multiple Merger, Extended Massive Star Formation, Galactic Wind, and Nuclear Inflow in NGC 3256

    Science.gov (United States)

    Lípari, S.; Díaz, R.; Taniguchi, Y.; Terlevich, R.; Dottori, H.; Carranza, G.

    2000-08-01

    -line ratios (N II/Hα, S II/Hα, S II/S II), and FWHM (Hα) maps for the central region (30''×30'' rmax~22''~4 kpc), with a spatial resolution of 1". In the central region (r~5-6 kpc) we detected that the nuclear starburst and the extended giant H II regions (in the spiral arms) have very similar properties, i.e., high metallicity and low-ionization spectra, with Teff=35,000 K, solar abundance, a range of Te~6000-7000 K, and Ne~100-1000 cm-3. The nuclear and extended outflow shows properties typical of galactic wind/shocks, associated with the nuclear starburst. We suggest that the interaction between dynamical effects, the galactic wind (outflow), low-energy cosmic rays, and the molecular+ionized gas (probably in the inflow phase) could be the possible mechanism that generate the ``similar extended properties in the massive star formation, at a scale of 5-6 kpc!'' We have also studied the presence of the close merger/interacting systems NGC 3256C (at ~150 kpc, ΔV=-100 km s-1) and the possible association between the NGC 3256 and 3263 groups of galaxies. In conclusion, these results suggest that NGC 3256 is the product of a multiple merger, which generated an extended massive star formation process with an associated galactic wind plus a nuclear inflow. Therefore, NGC 3256 is another example in which the relation between mergers and extreme starburst (and the powerful galactic wind, ``multiple'' Type II supernova explosions) play an important role in the evolution of galaxies (the hypothesis of Rieke et al., Joseph et al., Terlevich et al., Heckman et al., and Lípari et al.). Based on observations obtained at the Hubble Space Telescope (HST; Wide Field Planetary Camera 2 [WFPC2] and NICMOS) satellite; International Ultraviolet Explorer (IUE) satellite; European Southern Observatory (ESO, NTT); Chile, Cerro Tololo Inter-American Observatory (CTIO), Chile; Complejo Astronómico el Leoncito (CASLEO), Argentina; Estación Astrofísica de Bosque Alegre (BALEGRE), Argentina.

  20. Langevin equation with multiplicative white noise: Transformation of diffusion processes into the Wiener process in different prescriptions

    International Nuclear Information System (INIS)

    Kwok, Sau Fa

    2012-01-01

    A Langevin equation with multiplicative white noise and its corresponding Fokker–Planck equation are considered in this work. From the Fokker–Planck equation a transformation into the Wiener process is provided for different orders of prescription in discretization rule for the stochastic integrals. A few applications are also discussed. - Highlights: ► Fokker–Planck equation corresponding to the Langevin equation with mul- tiplicative white noise is presented. ► Transformation of diffusion processes into the Wiener process in different prescriptions is provided. ► The prescription parameter is associated with the growth rate for a Gompertz-type model.

  1. Nucleocytoplasmic trafficking of Nipah virus W protein involves multiple discrete interactions with the nuclear import and export machinery

    International Nuclear Information System (INIS)

    Audsley, Michelle D.; Jans, David A.; Moseley, Gregory W.

    2016-01-01

    Paramyxoviruses replicate in the cytoplasm with no obvious requirement to interact with the nucleus. Nevertheless, the W protein of the highly lethal bat-borne paramyxovirus Nipah virus (NiV) is known to undergo specific targeting to the nucleus, mediated by a single nuclear localisation signal (NLS) within the C-terminal domain. Here, we report for the first time that additional sites modulate nucleocytoplasmic localisation of W. We show that the N-terminal domain interacts with importin α1 and contributes to nuclear accumulation of W, indicative of a novel N-terminal NLS. We also find that W undergoes exportin-1 mediated nuclear export, dependent on a leucine at position 174. Together, these data enable significant revision of the generally accepted model of W trafficking, with implications for understanding of the mechanisms of NiV immune evasion. - Highlights: • A new model for Nipah virus W protein nucleocytoplasmic trafficking is proposed. • Nipah W protein is shown to undergo active nuclear export via exportin-1. • Nipah W nuclear import is mediated by multiple nuclear localisation signals.

  2. 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)

  3. Nuclear Aerosols: Direct Simulation and Elucidation of the Role of Multiple Components, Radioactivity, Charge, Shape and Spatial Inhomogeneity

    International Nuclear Information System (INIS)

    Sudarshan K. Loyalka

    2008-01-01

    Nuclear aerosols can originate from severe core damage in light water reactors, core disruptive accidents in fast reactors, nuclear accidents during nuclear material transport, at waste disposal sites, or explosions. These aerosols evolve under natural transport processes as well as under the influence of engineered safety features. Such aerosols can be hazardous for the equipment inside the reactor, and when leaked into the environment, pose potential risks to the public. Hence, the origin, movement and distribution of these aerosols need to be studied and controlled

  4. Maintaining a Technology-Neutral Approach to Hydrogen Production Process Development through Conceptual Design of the Next Generation Nuclear Plant

    International Nuclear Information System (INIS)

    Michael W. Patterson

    2008-01-01

    The Next Generation Nuclear Plant (NGNP) project was authorized in the Energy Policy Act of 2005 (EPAct), tasking the U.S. Department of Energy (DOE) with demonstrating High Temperature Gas-Cooled Reactor (HTGR) technology. The demonstration is to include the technical, licensing, operational, and commercial viability of HTGR technology for the production of electricity and hydrogen. The Nuclear Hydrogen Initiative (NHI), a component of the DOE Hydrogen Program managed by the Office of Nuclear Energy, is also investigating multiple approaches to cost effective hydrogen production from nuclear energy. The objective of NHI is development of the technology and information basis for a future decision on commercial viability. The initiatives are clearly intertwined. While the objectives of NGNP and NHI are generally consistent, NGNP has progressed to the project definition phase and the project plan has matured. Multiple process applications for the NGNP require process heat, electricity and hydrogen in varied combinations and sizes. Coupling these processes to the reactor in multiple configurations adds complexity to the design, licensing and demonstration of both the reactor and the hydrogen production process. Commercial viability of hydrogen production may depend on the specific application and heat transport configuration. A component test facility (CTF) is planned by the NGNP to support testing and demonstration of NGNP systems, including those for hydrogen production, in multiple configurations. Engineering-scale demonstrations in the CTF are expected to start in 2012 to support scheduled design and licensing activities leading to subsequent construction and operation. Engineering-scale demonstrations planned by NHI are expected to start at least two years later. Reconciliation of these schedules is recommended to successfully complete both initiatives. Hence, closer and earlier integration of hydrogen process development and heat transport systems is sensible

  5. Spent Nuclear Fuel (SNF) Process Validation Technical Support Plan

    Energy Technology Data Exchange (ETDEWEB)

    SEXTON, R.A.

    2000-03-13

    The purpose of Process Validation is to confirm that nominal process operations are consistent with the expected process envelope. The Process Validation activities described in this document are not part of the safety basis, but are expected to demonstrate that the process operates well within the safety basis. Some adjustments to the process may be made as a result of information gathered in Process Validation.

  6. Spent Nuclear Fuel (SNF) Process Validation Technical Support Plan

    International Nuclear Information System (INIS)

    SEXTON, R.A.

    2000-01-01

    The purpose of Process Validation is to confirm that nominal process operations are consistent with the expected process envelope. The Process Validation activities described in this document are not part of the safety basis, but are expected to demonstrate that the process operates well within the safety basis. Some adjustments to the process may be made as a result of information gathered in Process Validation

  7. Field theoretical approach to proton-nucleus reactions: II-Multiple-step excitation process

    International Nuclear Information System (INIS)

    Eiras, A.; Kodama, T.; Nemes, M.

    1989-01-01

    A field theoretical formulation to multiple step excitation process in proton-nucleus collision within the context of a relativistic eikonal approach is presented. A closed form expression for the double differential cross section can be obtained whose structure is very simple and makes the physics transparent. Glauber's formulation of the same process is obtained as a limit of ours and the necessary approximations are studied and discussed. (author) [pt

  8. Multifractal properties of diffusion-limited aggregates and random multiplicative processes

    International Nuclear Information System (INIS)

    Canessa, E.

    1991-04-01

    We consider the multifractal properties of irreversible diffusion-limited aggregation (DLA) from the point of view of the self-similarity of fluctuations in random multiplicative processes. In particular we analyse the breakdown of multifractal behaviour and phase transition associated with the negative moments of the growth probabilities in DLA. (author). 20 refs, 5 figs

  9. Congressional-executive interaction and the nuclear waste repository site selection process

    International Nuclear Information System (INIS)

    Thurber, J.A.; Evanson, T.C.

    1993-01-01

    The Nuclear Waste Policy Act of 1982 (NWPA) (P.L. 97-425) and the Nuclear Waste Policy Amendments Act of 1987 (NWPAA) (Title V of P.L. 100-203) provide the framework for the DOE Office of Civilian Radioactive Waste Management (OCRWM) to find a permanent means for disposing of high-level nuclear waste in the US. The focus of this study is the congressional decision-making process associated with passage of the Nuclear Waste Policy Amendments Act of 1987. The passage of NWPAA was a direct result of the failure of the policy adopted in the Nuclear Waste Policy Act of 1982. This study analyzes the nature of congressional nuclear waste policy-making through the lens of subsystems theory. The data analysis is primarily based on confidential interviews with over fifty key actors in the nuclear waste policy subsystem as well as an analysis of primary source documents

  10. Hidden symmetries and equilibrium properties of multiplicative white-noise stochastic processes

    Science.gov (United States)

    González Arenas, Zochil; Barci, Daniel G.

    2012-12-01

    Multiplicative white-noise stochastic processes continue to attract attention in a wide area of scientific research. The variety of prescriptions available for defining them makes the development of general tools for their characterization difficult. In this work, we study equilibrium properties of Markovian multiplicative white-noise processes. For this, we define the time reversal transformation for such processes, taking into account that the asymptotic stationary probability distribution depends on the prescription. Representing the stochastic process in a functional Grassmann formalism, we avoid the necessity of fixing a particular prescription. In this framework, we analyze equilibrium properties and study hidden symmetries of the process. We show that, using a careful definition of the equilibrium distribution and taking into account the appropriate time reversal transformation, usual equilibrium properties are satisfied for any prescription. Finally, we present a detailed deduction of a covariant supersymmetric formulation of a multiplicative Markovian white-noise process and study some of the constraints that it imposes on correlation functions using Ward-Takahashi identities.

  11. Hidden symmetries and equilibrium properties of multiplicative white-noise stochastic processes

    International Nuclear Information System (INIS)

    Arenas, Zochil González; Barci, Daniel G

    2012-01-01

    Multiplicative white-noise stochastic processes continue to attract attention in a wide area of scientific research. The variety of prescriptions available for defining them makes the development of general tools for their characterization difficult. In this work, we study equilibrium properties of Markovian multiplicative white-noise processes. For this, we define the time reversal transformation for such processes, taking into account that the asymptotic stationary probability distribution depends on the prescription. Representing the stochastic process in a functional Grassmann formalism, we avoid the necessity of fixing a particular prescription. In this framework, we analyze equilibrium properties and study hidden symmetries of the process. We show that, using a careful definition of the equilibrium distribution and taking into account the appropriate time reversal transformation, usual equilibrium properties are satisfied for any prescription. Finally, we present a detailed deduction of a covariant supersymmetric formulation of a multiplicative Markovian white-noise process and study some of the constraints that it imposes on correlation functions using Ward–Takahashi identities. (paper)

  12. Process and system to encapsulate spent nuclear fuel

    International Nuclear Information System (INIS)

    Gunasekaran, Muthian; Fleischer, L.R.

    1980-01-01

    System for encapsulating spent nuclear fuel containing active fission matter and comprised in a metal casing, where concrete covers this casing in a contiguous, uniform and complete manner. It is characterized in that this concrete contains metal fibres to raise the thermal conductivity and polymers for increasing impermeability and that convection facilities are provided for cooling the outer surface of the concrete [fr

  13. Modularization in construction processes New Nuclear Power Plants

    International Nuclear Information System (INIS)

    Martinez, I.; Cobos, A.; Herrera Ropero, D.

    2012-01-01

    The aim of this work is that it has the capacity and expertise to analyze the suitability of modular technology design and construction compared to conventional nuclear plants. It will define the criteria for selecting the areas of modularity and the impact on design and its interfaces with engineering, supply, including logistics and construction.

  14. Parallel 3-D image processing for nuclear emulsion

    International Nuclear Information System (INIS)

    Nakano, Toshiyuki

    2001-01-01

    The history of nuclear plate was explained. The first nuclear plate was named as pellicles covered with 600 μm of emulsion in Europe. In Japan Emulsion Cloud Chamber (ECC) using thin emulsion (50 μm) type nuclear plate was developed in 1960. Then, the semi-automatic analyzer (1971) and automatic analyzer (1980), Track Selector (TS) with memory stored 16 layer images in 512 x 512 x 16 pixel were developed. Moreover, NTS (New Track Selector), speeding up analyzer, was produced for analysis of results of CHORUS experiment in 1996. Simultaneous readout of 16 layer images had been carried out, but UTS (Ultra Track Selector) made possible to progressive treatment of 16 layers of some data and determination of traces in all angles. Direct detection of tau neutrino (VT) was studied by DONUT (FNAL E872) using UTS and nuclear plate. Neutrino beam was produced by 800 GeV proton beam hitting the fixed target. About 1100 phenomena of neutrino reactions were observed during six months of irradiation. 203 phenomena were detected. 4 examples were shown in this paper. OPERA experiment by SK is explained. (S.Y.)

  15. Decommissioning process of nuclear power plants and legislative base

    International Nuclear Information System (INIS)

    Bachovsky, J.

    2003-01-01

    The present paper contains some considerations about applicability and completeness of existing Regulation No. 10 in the field of decommissioning of nuclear power plants. No pretence exists for comprehensiveness, representativeness, or even applicability of these considerations. This paper presents personal views of the author and not official position of Risk Engineering Ltd

  16. The challenges of integrating multiple safeguards systems in a large nuclear facility

    International Nuclear Information System (INIS)

    Lavietes, A.; Liguori, C.; Pickrell, M.; Plenteda, R.; Sweet, M.

    2009-01-01

    Full-text: Implementing safeguards in a cost-effective manner in large nuclear facilities such as fuel conditioning, fuel reprocessing, and fuel fabrication plants requires the extensive use of instrumentation that is operated in unattended mode. The collected data is then periodically reviewed by the inspectors either on-site at a central location in the facility or remotely in the IAEA offices. A wide variety of instruments are deployed in large facilities, including video surveillance cameras, electronic sealing devices, non-destructive assay systems based on gamma ray and neutron detection, load cells for mass measurement, ID-readers, and other process-specific monitors. The challenge to integrate these different measurement instruments into an efficient, reliable, and secure system requires implementing standardization at various levels throughout the design process. This standardization includes the data generator behaviour and interface, networking solutions, and data security approaches. This standardization will provide a wide range of savings, including reduced training for inspectors and technicians, reduced periodic technical maintenance, reduced spare parts inventory, increased system robustness, and more predictive system behaviour. The development of standard building blocks will reduce the number of data generators required and allow implementation of simplified architectures that do not require local collection computers but rather utilize transmission of the acquired data directly to a central server via Ethernet connectivity. This approach will result in fewer system components and therefore reduced maintenance efforts and improved reliability. This paper discusses in detail the challenges and the subsequent solutions in the various areas that the IAEA Department of Safeguards has committed to pursue as the best sustainable way of maintaining the ability to implement reliable safeguards systems. (author)

  17. Literature on fabrication of tungsten for application in pyrochemical processing of spent nuclear fuels

    International Nuclear Information System (INIS)

    Edstrom, C.M.; Phillips, A.G.; Johnson, L.D.; Corle, R.R.

    1980-01-01

    The pyrochemical processing of nuclear fuels requires crucibles, stirrers, and transfer tubing that will withstand the temperature and the chemical attack from molten salts and metals used in the process. This report summarizes the literature that pertains to fabrication (joining, chemical vapor deposition, plasma spraying, forming, and spinning) is the main theme. This report also summarizes a sampling of literature on molbdenum and the work previously performed at Argonne National Laboratory on other container materials used for pyrochemical processing of spent nuclear fuels

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

    OpenAIRE

    Mardha, Amil

    2009-01-01

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

  19. The environmental impact assessment process for nuclear facilities: An examination of the Indian experience

    International Nuclear Information System (INIS)

    Ramana, M.V.; Rao, Divya Badami

    2010-01-01

    India plans to construct numerous nuclear plants and uranium mines across the country, which could have significant environmental, health, and social impacts. The national Environmental Impact Assessment process is supposed to regulate these impacts. This paper examines how effective this process has been, and the extent to which public inputs have been taken into account. In addition to generic problems associated with the EIA process for all kinds of projects in India, there are concerns that are specific to nuclear facilities. One is that some nuclear facilities are exempt from the environmental clearance process. The second is that data regarding radiation baseline levels and future releases, which is the principle environmental concern with respect to nuclear facilities, is controlled entirely by the nuclear establishment. The third is that members of the nuclear establishment take part in almost every level of the environmental clearance procedure. For these reasons and others, the EIA process with regard to nuclear projects in India is of dubious quality. We make a number of recommendations that could address these lacunae, and more generally the imbalance of power between the nuclear establishment on the one hand, and civil society and the regulatory agencies on the other.

  20. The development of application technology for image processing in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Bum; Kim, Woog Ki; Sohn, Surg Won; Kim, Seung Ho; Hwang, Suk Yeoung; Kim, Byung Soo

    1991-01-01

    The object of this project is to develop application technology of image processing in nuclear facilities where image signal are used for reliability and safety enhancement of operation, radiation exposure reduce of operator, and automation of operation processing. We has studied such application technology for image processing in nuclear facilities as non-tactile measurement, remote and automatic inspection, remote control, and enhanced analysis of visual information. On these bases, automation system and real-time image processing system are developed. Nuclear power consists in over 50% share of electic power supply of our country nowdays. So, it is required of technological support for top-notch technology in nuclear industry and its related fields. Especially, it is indispensable for image processing technology to enhance the reliabilty and safety of operation, to automate the process in a place like a nuclear power plant and radioactive envionment. It is important that image processing technology is linked to a nuclear engineering, and enhance the reliability abd safety of nuclear operation, as well as decrease the dose rate. (Author)

  1. Spatial dose and microdose distribution in tissues. Ionization, nuclear reactions, multiple scattering simulation of beam transport

    International Nuclear Information System (INIS)

    Jacquot, C.

    1976-01-01

    Computer simulation and nuclear emulsion and gelatin techniques enabled to give the total elastic and inelastic cross sections and to forecast the spatial microdose distributions in cells, nuclei and molecules. For this purpose, the transport of a beam into tissues having a given composition is calculated, the nuclear reactions are generated and the energy depositions in standard planes perpendicular to the beam are recorded

  2. Public views on multiple dimensions of security: nuclear weapons, terrorism, energy, and the environment: 2007

    International Nuclear Information System (INIS)

    Herron, Kerry Gale; Jenkins-Smith, Hank C.

    2008-01-01

    We analyze and compare findings from identical national surveys of the US general public on nuclear security and terrorism administered by telephone and Internet in mid-2007. Key areas of investigation include assessments of threats to US security; valuations of US nuclear weapons and nuclear deterrence; perspectives on nuclear proliferation, including the specific cases of North Korea and Iran; and support for investments in nuclear weapons capabilities. Our analysis of public views on terrorism include assessments of the current threat, progress in the struggle against terrorism, preferences for responding to terrorist attacks at different levels of assumed casualties, and support for domestic policies intended to reduce the threat of terrorism. Also we report findings from an Internet survey conducted in mid 2007 that investigates public views of US energy security, to include: energy supplies and reliability; energy vulnerabilities and threats, and relationships among security, costs, energy dependence, alternative sources, and research and investment priorities. We analyze public assessments of nuclear energy risks and benefits, nuclear materials management issues, and preferences for the future of nuclear energy in the US. Additionally, we investigate environmental issues as they relate to energy security, to include expected implications of global climate change, and relationships among environmental issues and potential policy options.

  3. Public views on multiple dimensions of security : nuclear waepons, terrorism, energy, and the environment : 2007.

    Energy Technology Data Exchange (ETDEWEB)

    Herron, Kerry Gale (University of Oklahoma, Norman, OK); Jenkins-Smith, Hank C. (University of Oklahoma, Norman, OK)

    2008-01-01

    We analyze and compare findings from identical national surveys of the US general public on nuclear security and terrorism administered by telephone and Internet in mid-2007. Key areas of investigation include assessments of threats to US security; valuations of US nuclear weapons and nuclear deterrence; perspectives on nuclear proliferation, including the specific cases of North Korea and Iran; and support for investments in nuclear weapons capabilities. Our analysis of public views on terrorism include assessments of the current threat, progress in the struggle against terrorism, preferences for responding to terrorist attacks at different levels of assumed casualties, and support for domestic policies intended to reduce the threat of terrorism. Also we report findings from an Internet survey conducted in mid 2007 that investigates public views of US energy security, to include: energy supplies and reliability; energy vulnerabilities and threats, and relationships among security, costs, energy dependence, alternative sources, and research and investment priorities. We analyze public assessments of nuclear energy risks and benefits, nuclear materials management issues, and preferences for the future of nuclear energy in the US. Additionally, we investigate environmental issues as they relate to energy security, to include expected implications of global climate change, and relationships among environmental issues and potential policy options.

  4. Automatic welding processes for reactor coolant pipes used in PWR type nuclear power plant

    International Nuclear Information System (INIS)

    Hamada, T.; Nakamura, A.; Nagura, Y.; Sakamoto, N.

    1979-01-01

    The authors developed automatic welding processes (submerged arc welding process and TIG welding process) for application to the welding of reactor coolant pipes which constitute the most important part of the PWR type nuclear power plant. Submerged arc welding process is suitable for flat position welding in which pipes can be rotated, while TIG welding process is suitable for all position welding. This paper gives an outline of the two processes and the results of tests performed using these processes. (author)

  5. NJOY. A comprehensive system for the processing of ENDF formatted nuclear data

    International Nuclear Information System (INIS)

    Muir, D.W.

    1990-07-01

    An introduction to the program system NJOY is given which processes data files of evaluated neutron nuclear data coded in ENDF format. NJOY is primarily used for neutron and photon transport calculations for nuclear power reactor design. The NJOY code is not available from the IAEA Nuclear Data Section but may be obtained from the Reactor Shielding Information Center, Oak Ridge, USA. (author). 10 refs, 1 fig

  6. Nuclear data needs for studying the astrophysical r- and p-processes

    International Nuclear Information System (INIS)

    Howard, W.M.; Meyer, B.S.

    1991-09-01

    Recent advances in understanding the astrophysical sites for the r-, p- and 3-processes has led to an increased understanding of the nuclear physics requires to calculate the thermonuclear origin of the heavy elements in nature. We review specific examples of where nuclear information obtained with Radioactive Nuclear Beams can greatly help our understanding of the thermonuclear origin of the elements in nature. 4 figs

  7. The NJOY nuclear data processing system: Volume 2, The NJOY, RECONR, BROADR, HEATR, and THERMR modules

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Muir, D.W.; Boicourt, R.M.

    1982-05-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections and related nuclear parameters from ENDF/B evaluated nuclear data. This volume provides detailed descriptions of the NJOY module, which contains the executive program and utility subroutines used by the other modules, and it discusses the theory and computational methods of four of the modules used for producing pointwise cross sections: RECONR, BROADR, HEATR, and THERMR

  8. Machining of AISI D2 Tool Steel with Multiple Hole Electrodes by EDM Process

    Science.gov (United States)

    Prasad Prathipati, R.; Devuri, Venkateswarlu; Cheepu, Muralimohan; Gudimetla, Kondaiah; Uzwal Kiran, R.

    2018-03-01

    In recent years, with the increasing of technology the demand for machining processes is increasing for the newly developed materials. The conventional machining processes are not adequate to meet the accuracy of the machining of these materials. The non-conventional machining processes of electrical discharge machining is one of the most efficient machining processes is being widely used to machining of high accuracy products of various industries. The optimum selection of process parameters is very important in machining processes as that of an electrical discharge machining as they determine surface quality and dimensional precision of the obtained parts, even though time consumption rate is higher for machining of large dimension features. In this work, D2 high carbon and chromium tool steel has been machined using electrical discharge machining with the multiple hole electrode technique. The D2 steel has several applications such as forming dies, extrusion dies and thread rolling. But the machining of this tool steel is very hard because of it shard alloyed elements of V, Cr and Mo which enhance its strength and wear properties. However, the machining is possible by using electrical discharge machining process and the present study implemented a new technique to reduce the machining time using a multiple hole copper electrode. In this technique, while machining with multiple holes electrode, fin like projections are obtained, which can be removed easily by chipping. Then the finishing is done by using solid electrode. The machining time is reduced to around 50% while using multiple hole electrode technique for electrical discharge machining.

  9. Quark Energy Loss and Shadowing in Nuclear Drell-Yan Process

    International Nuclear Information System (INIS)

    Duan Chungui; Cui Shuwen; Yan Zhanyuan

    2005-01-01

    The energy loss effect in nuclear matter is another nuclear effect apart from the nuclear effects on the parton distribution as in deep inelastic scattering process. The quark energy loss can be measured best by the nuclear dependence of the high energy nuclear Drell-Yan process. By means of three kinds of quark energy loss parameterizations given in literature and the nuclear parton distribution extracted only with lepton-nucleus deep inelastic scattering experimental data, measured Drell-Yan production cross sections are analyzed for 800 GeV proton incident on a variety of nuclear targets from FNAL E866. It is shown that our results with considering the energy loss effect are much different from those of the FNAL E866, who analyzes the experimental data with the nuclear parton distribution functions obtained by using the deep inelastic lA collisions and pA nuclear Drell-Yan data. Considering the existence of energy loss effect in Drell-Yan lepton pairs production, we suggest that the extraction of nuclear parton distribution functions should not include Drell-Yan experimental data.

  10. Quark Energy Loss and Shadowing in Nuclear Drell-Yan Process

    Institute of Scientific and Technical Information of China (English)

    DUAN Chun-Gui; CUI Shu-Wen; YAN Zhan-Yuan

    2005-01-01

    The energy loss effect in nuclear matter is another nuclear effect apart from the nuclear effects on the parton distribution as in deep inelastic scattering process. The quark energy loss can be measured best by the nuclear dependence of the high energy nuclear Drell-Yan process. By means of three kinds of quark energy loss parameterizations given in literature and the nuclear parton distribution extracted only with lepton-nucleus deep inelastic scattering experimental data, measured Drell-Yan production cross sections are analyzed for 800 GeV proton incident on a variety of nuclear targets from FNAL E866. It is shown that our results with considering the energy loss effect are much different from those of the FNAL E866, who analyzes the experimental data with the nuclear parton distribution functions obtained by using the deep inelastic IA collisions and pA nuclear Drell-Yan data. Considering the existence of energy loss effect in Drell-Yan lepton pairs production, we suggest that the extraction of nuclear parton distribution functions should not include Drell-Yan experimental data.

  11. Visual processing of multiple elements in the dyslexic brain: evidence for a superior parietal dysfunction

    Directory of Open Access Journals (Sweden)

    Muriel Anne Lobier

    2014-07-01

    Full Text Available The visual attention (VA span deficit hypothesis of developmental dyslexia posits that impaired multiple element processing can be responsible for poor reading outcomes. In VA span impaired dyslexic children, poor performance on letter report tasks is associated with reduced parietal activations for multiple letter processing. While this hints towards a non-specific, attention-based dysfunction, it is still unclear whether reduced parietal activity generalizes to other types of stimuli. Furthermore, putative links between reduced parietal activity and reduced ventral occipito-temporal (vOT in dyslexia have yet to be explored. Using fMRI, we measured brain activity in 12 VA span impaired dyslexic adults and 12 adult skilled readers while they carried out a categorization task on single or multiple alphanumeric or non-alphanumeric characters. While healthy readers activated parietal areas more strongly for multiple than single element processing (right-sided for alphanumeric and bilateral for non-alphanumeric, similar stronger multiple element right parietal activations were absent for dyslexic participants. Contrasts between skilled and dyslexic readers revealed significantly reduced right superior parietal lobule (SPL activity for dyslexic readers regardless of stimuli type. Using a priori anatomically defined ROI, we showed that neural activity was reduced for dyslexic participants in both SPL and vOT bilaterally. Finally, we used multiple regressions to test whether SPL activity could predict vOT activity in each group. In the left hemisphere, SPL activity modulated vOT activity for both normal and dyslexic readers. In contrast, in the right hemisphere, SPL activity modulated vOT activity only for dyslexic readers. These results bring critical support to the visual attention interpretation of the VA Span deficit. In addition, they offer a new insight on how deficits in automatic vOT based word recognition could arise in developmental dyslexia.

  12. Software for the nuclear reactor dynamics study using time series processing

    International Nuclear Information System (INIS)

    Valero, Esbel T.; Montesino, Maria E.

    1997-01-01

    The parametric monitoring in Nuclear Power Plant (NPP) permits the operational surveillance of nuclear reactor. The methods employed in order to process this information such as FFT, autoregressive models and other, have some limitations when those regimens in which appear strongly non-linear behaviors are analyzed. In last years the chaos theory has offered new ways in order to explain complex dynamic behaviors. This paper describes a software (ECASET) that allow, by time series processing from NPP's acquisition system, to characterize the nuclear reactor dynamic as a complex dynamical system. Here we show using ECASET's results the possibility of classifying the different regimens appearing in nuclear reactors. The results of several temporal series processing from real systems are introduced. This type of analysis complements the results obtained with traditional methods and can constitute a new tool for monitoring nuclear reactors. (author). 13 refs., 3 figs

  13. IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

  14. Determination of spent nuclear fuel assembly multiplication with the differential die-away self-interrogation instrument

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, Alexis C. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States); Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States); Henzl, Vladimir; Menlove, Howard O.; Swinhoe, Martyn T.; Belian, Anthony P. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States); Flaska, Marek; Pozzi, Sara A. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States)

    2014-09-01

    We present a novel method for determining the multiplication of a spent nuclear fuel assembly with a Differential Die-Away Self-Interrogation (DDSI) instrument. The signal, which is primarily created by thermal neutrons, is measured with four {sup 3}He detector banks surrounding a spent fuel assembly. The Rossi-alpha distribution (RAD) at early times reflects coincident events from single fissions as well as fission chains. Because of this fact, the early time domain contains information about both the fissile material and spontaneous fission material in the assembly being measured. A single exponential function fit to the early time domain of the RAD has a die-away time proportional to the spent fuel assembly (SFA) multiplication. This correlation was tested by simulating assay of 44 different SFAs with the DDSI instrument. The SFA multiplication was determined with a variance of 0.7%.

  15. Processing used nuclear fuel with nanoscale control of uranium and ultrafiltration

    Energy Technology Data Exchange (ETDEWEB)

    Wylie, Ernest M.; Peruski, Kathryn M.; Prizio, Sarah E. [Department of Civil and Environmental Engineering and Earth Sciences, University of Notre Dame, Notre Dame, IN 46556 (United States); Bridges, Andrea N.A.; Rudisill, Tracy S.; Hobbs, David T. [Savannah River National Laboratory, Aiken, SC 29808 (United States); Phillip, William A. [Department of Chemical and Biomolecular Engineering, University of Notre Dame, Notre Dame, IN 46556 (United States); Burns, Peter C., E-mail: pburns@nd.edu [Department of Civil and Environmental Engineering and Earth Sciences, University of Notre Dame, Notre Dame, IN 46556 (United States); Department of Chemistry and Biochemistry, University of Notre Dame, Notre Dame, IN 46556 (United States)

    2016-05-15

    Current separation and purification technologies utilized in the nuclear fuel cycle rely primarily on liquid–liquid extraction and ion-exchange processes. Here, we report a laboratory-scale aqueous process that demonstrates nanoscale control for the recovery of uranium from simulated used nuclear fuel (SIMFUEL). The selective, hydrogen peroxide induced oxidative dissolution of SIMFUEL material results in the rapid assembly of persistent uranyl peroxide nanocluster species that can be separated and recovered at moderate to high yield from other process-soluble constituents using sequestration-assisted ultrafiltration. Implementation of size-selective physical processes like filtration could results in an overall simplification of nuclear fuel cycle technology, improving the environmental consequences of nuclear energy and reducing costs of processing. - Highlights: • Nanoscale control in irradiated fuel reprocessing. • Ultrafiltration to recover uranyl cage clusters. • Alternative to solvent extraction for uranium purification.

  16. Nuclear heat source design for an advanced HTGR process heat plant

    International Nuclear Information System (INIS)

    McDonald, C.F.; O'Hanlon, T.W.

    1983-01-01

    A high-temperature gas-cooled reactor (HTGR) coupled with a chemical process facility could produce synthetic fuels (i.e., oil, gasoline, aviation fuel, methanol, hydrogen, etc.) in the long term using low-grade carbon sources (e.g., coal, oil shale, etc.). The ultimate high-temperature capability of an advanced HTGR variant is being studied for nuclear process heat. This paper discusses a process heat plant with a 2240-MW(t) nuclear heat source, a reactor outlet temperature of 950 0 C, and a direct reforming process. The nuclear heat source outputs principally hydrogen-rich synthesis gas that can be used as a feedstock for synthetic fuel production. This paper emphasizes the design of the nuclear heat source and discusses the major components and a deployment strategy to realize an advanced HTGR process heat plant concept

  17. Secure Software Configuration Management Processes for nuclear safety software development environment

    International Nuclear Information System (INIS)

    Chou, I.-Hsin

    2011-01-01

    Highlights: → The proposed method emphasizes platform-independent security processes. → A hybrid process based on the nuclear SCM and security regulations is proposed. → Detailed descriptions and Process Flow Diagram are useful for software developers. - Abstract: The main difference between nuclear and generic software is that the risk factor is infinitely greater in nuclear software - if there is a malfunction in the safety system, it can result in significant economic loss, physical damage or threat to human life. However, secure software development environment have often been ignored in the nuclear industry. In response to the terrorist attacks on September 11, 2001, the US Nuclear Regulatory Commission (USNRC) revised the Regulatory Guide (RG 1.152-2006) 'Criteria for use of computers in safety systems of nuclear power plants' to provide specific security guidance throughout the software development life cycle. Software Configuration Management (SCM) is an essential discipline in the software development environment. SCM involves identifying configuration items, controlling changes to those items, and maintaining integrity and traceability of them. For securing the nuclear safety software, this paper proposes a Secure SCM Processes (S 2 CMP) which infuses regulatory security requirements into proposed SCM processes. Furthermore, a Process Flow Diagram (PFD) is adopted to describe S 2 CMP, which is intended to enhance the communication between regulators and developers.

  18. Nuclear heat for high temperature fossil fuel processing

    International Nuclear Information System (INIS)

    Walton, G.N.

    1981-01-01

    This is a report of a one-day symposium held at the Royal Institution, London, on 28 April 1981. It was organized by the Institute of Energy (London and Home Counties section) under the chairmanship of Dr A M Brown with the assistance of the Institute of Energy's Nuclear Special Interest Group. The following five papers were presented (available as a booklet, from the Institute of Energy, price Pound12.00): 1) The Dragon project and the High Temperature Reactor (HTR) position. Dr L Shepherd, UKAEA, Winfrith. 2) Coal gasification technology. Dr M St J Arnold, NCB, Stoke Orchard Laboratories. 3) The utilization of nuclear energy for coal gasification. Dr K H van Heek, G Hewing, R Kirchhoff and H J Schroter, Bergbau Forschung, Essen, West Germany. 4) The hydrogen economy. K F Langley, Energy Technology Support Unit, Harwell. 5) Economic perspectives and high temperature reactors. J D Thorn, director, Technical Services and Planning, UKAEA. (author)

  19. Alcohol-free alkoxide process for containing nuclear waste

    Science.gov (United States)

    Pope, James M.; Lahoda, Edward J.

    1984-01-01

    Disclosed is a method of containing nuclear waste. A composition is first prepared of about 25 to about 80%, calculated as SiO.sub.2, of a partially hydrolyzed silicon compound, up to about 30%, calculated as metal oxide, of a partially hydrolyzed aluminum or calcium compound, about 5 to about 20%, calculated as metal oxide, of a partially hydrolyzed boron or calcium compound, about 3 to about 25%, calculated as metal oxide, of a partially hydrolyzed sodium, potassium or lithium compound, an alcohol in a weight ratio to hydrolyzed alkoxide of about 1.5 to about 3% and sufficient water to remove at least 99% of the alcohol as an azeotrope. The azeotrope is boiled off and up to about 40%, based on solids in the product, of the nuclear waste, is mixed into the composition. The mixture is evaporated to about 25 to about 45% solids and is melted and cooled.

  20. Nuclear data processing and multigroup cross section generation

    International Nuclear Information System (INIS)

    Kim, Jeong Do; Kil, Chung Sub

    1996-01-01

    The multigroup constants for WIMS/CASMO were updated with ENDF/B-VI and were tested. The continuous energy MCNP library developed last year was validated against the LWR-simulated critical experiments. The MCNP library will be used to design and analyze nuclear and shielding facilities. The system for generation of MATXS multigroup library and TRANSX code, which is able to prepare the data for the discrete ordinates and diffusion codes from the MATXS library, was established. The MATXS libraries for analyses of thermal and fast critical experiments were generated and tested. The MATXS/TRANSX system for the discrete ordinates and diffusion codes will be useful for nuclear analyses. 10 tabs., 5 figs., 17 refs. (Author)