WorldWideScience

Sample records for evaluated nuclear data file

  1. Evaluated Nuclear Structure Data File

    Science.gov (United States)

    Tuli, Jagdish K.

    2004-10-01

    The Evaluated Nuclear Structure Data File (ENSDF) is a leading resource for the experimental nuclear data. It is maintained and distributed by the National Nuclear Data Center, Brookhaven National Laboratory. The file is mainly contributed to by an international network of evaluators under the auspice of the International Atomic Energy Agency. The ENSDF is updated, generally by mass number, i.e., evaluating together all isobars for a given mass number. If, however, experimental activity in an isobaric chain is limited to a particular nuclide then only that nuclide is updated. The evaluations are published in the journal Nuclear Data Sheets, a publication of Elsevier. This presentation will briefly review this and other databases and dissemination services of the US and international network, and reflect on how the network resources can help scientists in both the basic as well as the applied fields.

  2. Evaluated Nuclear Structure Data File and Related Products

    Science.gov (United States)

    Tuli, Jagdish K.

    2005-05-01

    The Evaluated Nuclear Structure Data File (ENSDF) is a leading resource for experimental nuclear data. It is maintained and distributed by the National Nuclear Data Center, Brookhaven National Laboratory. The file is mainly contributed to by an international network of evaluators under the auspice of the International Atomic Energy Agency. The ENSDF is updated, generally by mass number, i.e., evaluating together all isobars for a given mass number. If, however, experimental activity in an isobaric chain is limited to a particular nuclide, then only that nuclide is updated. The evaluations are published in the Journal of Nuclear Data Sheets, Academic Press, a division of Elsevier.

  3. EVALUATED NUCLEAR STRUCTURE DATA FILE -- A MANUAL FOR PREPARATION OF DATA SETS.

    Energy Technology Data Exchange (ETDEWEB)

    TULI, J.K.

    2001-02-01

    This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A {le} 293), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses A {ge} 44, this information is published in the Nuclear Data Sheets; for A < 44, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chain or by nuclide with a varying cycle time dependent on the availability of new information.

  4. Evaluated nuclear structure data file: A manual for preparation of data sets

    Energy Technology Data Exchange (ETDEWEB)

    Tuli, J.K.

    1987-04-01

    This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, Aless than or equal to263), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses Agreater than or equal to45, this information is documented in the Nuclear Data Sheets; for A<45, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chains with a present cycle time of approximately six years.

  5. Evaluated nuclear structure data file. a manual for preparation of data sets

    CERN Document Server

    Tuli, J K

    2001-01-01

    This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A = 44, this information is published in the Nuclear Data Sheets; for A < 44, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chain or by nuclide with a varying cycle time dependent on the availability of new information.

  6. Data formats and procedures for the Evaluated Nuclear Data File, ENDF

    Energy Technology Data Exchange (ETDEWEB)

    Garber, D.; Dunford, C.; Pearlstein, S.

    1975-10-01

    This report describes the philosophy of the Evaluated Nuclear Data File (ENDF) and the data formats and procedures that have been developed for it. The ENDF system was designed for the storage and retrieval of the evaluated nuclear data that are required for neutronics, photonics and decay heat calculations. This system is composed of several parts that include a series of data processing codes and neutron and photon cross section nuclear structure libraries.

  7. ENDF-102 DATA FORMATS AND PROCEDURES FOR THE EVALUATION NUCLEAR DATA FILE ENDF-6.

    Energy Technology Data Exchange (ETDEWEB)

    MCLANE,V.

    2001-05-15

    The Evaluated Nuclear Data File (ENDF) formats and libraries are decided by the Cross Section Evaluation Working Group (CSEWG), a cooperative effort of national laboratories, industry, and universities in the U.S. and Canada, and are maintained by the National Nuclear Data Center (NNDC). Earlier versions of the ENDF format provided representations for neutron cross sections and distributions, photon production from neutron reactions, a limited amount of charged-particle production from neutron reactions, photo-atomic interaction data, thermal neutron scattering data, and radionuclide production and decay data (including fission products). Version 6 (ENDF-6) allows higher incident energies, adds more complete descriptions of the distributions of emitted particles, and provides for incident charged particles and photonuclear data by partitioning the ENDF library into sub-libraries. Decay data, fission product yield data, thermal scattering data, and photo-atomic data have also been formally placed in sub-libraries. In addition, this rewrite represents an extensive update to the Version V manual.

  8. Release of the ENDF/B-VII.1 Evaluated Nuclear Data File

    Energy Technology Data Exchange (ETDEWEB)

    Brown, David

    2012-06-30

    The Cross Section Evaluation Working Group (CSEWG) released the ENDF/B-VII.1 library on December 22, 2011. The ENDF/B-VII.1 library is CSEWG's latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0, including: many new evaluation in the neutron sublibrary (423 in all and over 190 of these contain covariances), new fission product yields and a greatly improved decay data sublibrary. This summary barely touches on the five years worth of advances present in the ENDF/B-VII.1 library. We expect that these changes will lead to improved integral performance in reactors and other applications. Furthermore, the expansion of covariance data in this release will allow for better uncertainty quantification, reducing design margins and costs. The ENDF library is an ongoing and evolving effort. Currently, the ENDF data community embarking on several parallel efforts to improve library management: (1) The adoption of a continuous integration system to provide evaluators 'instant' feedback on the quality of their evaluations and to provide data users with working 'beta' quality libraries in between major releases. (2) The transition to new hierarchical data format - the Generalized Nuclear Data (GND) format. We expect GND to enable new kinds of evaluated data which cannot be accommodated in the legacy ENDF format. (3) The development of data assimilation and uncertainty propagation techniques to enable the consistent use of integral experimental data in the evaluation process.

  9. Visual system of recovering and combination of information for ENDF (Evaluated Nuclear Data File) format libraries; Sistema visual de recuperacao e combinacao de informacoes para bibliotecas no formato ENDF (Evaluated Nuclear Data File)

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Claudia A.S. Velloso [Centro Tecnico Aeroespacial, Sao Jose dos Campos, SP (Brazil); Corcuera, Raquel A. Paviotti [Instituto Nacional de Pesquisas Espaciais (INPE), Sao Jose dos Campos, SP (Brazil)

    1997-04-01

    This report presents a data information retrieval and merger system for ENDF (Evaluated Nuclear Data File) format libraries, which can be run on personal computers under the Windows {sup TM} environment. The input is the name of an ENDF/B library, which can be chosen in a proper window. The system has a display function which allows the user to visualize the reaction data of a specific nuclide and to produce a printed copy of these data. The system allows the user to retrieve and/or combine evaluated data to create a single file of data in ENDF format, from a number of different files, each of which is in the ENDF format. The user can also create a mini-library from an ENDF/B library. This interactive and easy-to-handle system is a useful tool for Nuclear Data Centers and it is also of interest to nuclear and reactor physics researchers. (author)

  10. Evaluated Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    Oblozinsky, P.; Oblozinsky,P.; Herman,M.; Mughabghab,S.F.

    2010-10-01

    This chapter describes the current status of evaluated nuclear data for nuclear technology applications. We start with evaluation procedures for neutron-induced reactions focusing on incident energies from the thermal energy up to 20 MeV, though higher energies are also mentioned. This is followed by examining the status of evaluated neutron data for actinides that play dominant role in most of the applications, followed by coolants/moderators, structural materials and fission products. We then discuss neutron covariance data that characterize uncertainties and correlations. We explain how modern nuclear evaluated data libraries are validated against an extensive set of integral benchmark experiments. Afterwards, we briefly examine other data of importance for nuclear technology, including fission yields, thermal neutron scattering and decay data. A description of three major evaluated nuclear data libraries is provided, including the latest version of the US library ENDF/B-VII.0, European JEFF-3.1 and Japanese JENDL-3.3. A brief introduction is made to current web retrieval systems that allow easy access to a vast amount of up-to-date evaluated nuclear data for nuclear technology applications.

  11. Nuclear Structure Data Evaluation and the US Nuclear Data Program

    Science.gov (United States)

    Helmer, Richard G.

    2001-10-01

    The United States Nuclear Data Program and the Nuclear Structure and Decay Data network of the International Atomic Energy Agency work in collaboration to provide recommended nuclear structure and decay data for use in basic and applied research. Data are evaluted for nuclear levels and for various types of radiation. In addition, an extensive bibliographic database of nuclear structure, reaction, and decay data references is maintained. The databases maintained by the National Nuclear Data Center at Brookhaven National Laboratory include the Evaluated Nuclear Structure Data File (ENSDF), the Experimental Unevaluated Nuclear Data Library (XUNDL), and the Nuclear Sciences References (NSR). These data are all available via the Internet and some are available in hard-copy. Although the data in the ENSDF database for a particular nucleus has often not been updated in the last few fears, XUNDL provides compiled experimental data from papers with a delay of only about one month. Also, the NSR bibliographic database is current for the many journals that are monitored regularly.

  12. New approaches to provide feedback from nuclear and covariance data adjustment for effective improvement of evaluated nuclear data files

    Energy Technology Data Exchange (ETDEWEB)

    Palmiotti, Giuseppe; Salvatores, Massimo; Hursin, Mathieu; Kodeli, Ivo; Gabrielli, Fabrizio; Hummel, Andrew

    2016-11-01

    A critical examination of the role of uncertainty assessment, target accuracies, role of integral experiment for validation and, consequently, of data adjustments methods is underway since several years at OECD-NEA, the objective being to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and experimentalists in order to improve without ambiguities the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications and to meet new requirements and constraints for innovative reactor and fuel cycle system design. An approach will be described that expands as much as possible the use in the adjustment procedure of selected integral experiments that provide information on “elementary” phenomena, on separated individual physics effects related to specific isotopes or on specific energy ranges. An application to a large experimental data base has been performed and the results are discussed in the perspective of new evaluation projects like the CIELO initiative.

  13. New approaches to provide feedback from nuclear and covariance data adjustment for effective improvement of evaluated nuclear data files

    Science.gov (United States)

    Palmiotti, Giuseppe; Salvatores, Massimo; Hursin, Mathieu; Kodeli, Ivo; Gabrielli, Fabrizio; Hummel, Andrew

    2017-09-01

    A critical examination of the role of uncertainty assessment, target accuracies, role of integral experiment for validation and, consequently, of data adjustments methods is underway since several years at OECD-NEA, the objective being to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and experimentalists in order to improve without ambiguities the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications and to meet new requirements and constraints for innovative reactor and fuel cycle system design. An approach will be described that expands as much as possible the use in the adjustment procedure of selected integral experiments that provide information on "elementary" phenomena, on separated individual physics effects related to specific isotopes or on specific energy ranges. An application to a large experimental data base has been performed and the results are discussed in the perspective of new evaluation projects like the CIELO initiative.

  14. An evaluated neutronic data file for bismuth

    Energy Technology Data Exchange (ETDEWEB)

    Guenther, P.T.; Lawson, R.D.; Meadows, J.W.; Smith, A.B.; Smith, D.L.; Sugimoto, M. (Argonne National Lab., IL (USA)); Howerton, R.J. (Lawrence Livermore National Lab., CA (USA))

    1989-11-01

    A comprehensive evaluated neutronic data file for bismuth, extending from 10{sup {minus}5} eV to 20.0 MeV, is described. The experimental database, the application of the theoretical models, and the evaluation rationale are outlined. Attention is given to uncertainty specification, and comparisons are made with the prior ENDF/B-V evaluation. The corresponding numerical file, in ENDF/B-VI format, has been transmitted to the National Nuclear Data Center, Brookhaven National Laboratory. 106 refs., 10 figs., 6 tabs.

  15. A new tool for the search of nuclides with properties suitable for nuclear solid state physics based on the Evaluated Nuclear Structure Data Files

    Energy Technology Data Exchange (ETDEWEB)

    Nagl, M.A., E-mail: matthias@nagl.eu [II. Physikalisches Institut, Georg-August-Universität, Friedrich-Hund-Platz 1, 37077 Göttingen (Germany); Barbosa, M.B. [IFIMUP and IN-Institute of Nanoscience and Nanotechnology, Departamento de Física e Astronomia da Faculdade de Ciências da Universidade do Porto, Rua do Campo Alegre, 687, 4169-007 Porto (Portugal); CERN-EP, 1211 Geneva 23 (Switzerland); Vetter, U. [II. Physikalisches Institut, Georg-August-Universität, Friedrich-Hund-Platz 1, 37077 Göttingen (Germany); Correia, J.G. [CERN-EP, 1211 Geneva 23 (Switzerland); ITN, IST, Universidade Técnica de Lisboa, Estrada Nacional 10, 2686-953 Sacavém (Portugal); Centro de Física Nuclear da Universidade de Lisboa, Avenida Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Hofsäss, H.C. [II. Physikalisches Institut, Georg-August-Universität, Friedrich-Hund-Platz 1, 37077 Göttingen (Germany)

    2013-10-21

    A software tool for the displaying of nuclear decay schemes, the calculation of angular γ emission anisotropies, and the automated search for appropriate decay cascade properties based on the Evaluated Nuclear Structure Data Files (ENSDF) was created and published for free download. After a short introduction of this tool, candidate nuclides for time differential perturbed γ–γ angular correlation (TDPAC) measurements are presented. These candidates are grouped according to their parent nuclides’ half-life periods in groups for online, on-site, and off-site measurements. For all candidates angular correlation coefficients (also called anisotropy values) were computed and are shown alongside magnetic and quadrupole moments from the ENSDF database and other sources. An extension of the presented software for the search of nuclides for Mössbauer spectroscopy, Nuclear Resonant Scattering, and other methods is easily possible.

  16. A new tool for the search of nuclides with properties suitable for nuclear solid state physics based on the Evaluated Nuclear Structure Data Files

    Science.gov (United States)

    Nagl, M. A.; Barbosa, M. B.; Vetter, U.; Correia, J. G.; Hofsäss, H. C.

    2013-10-01

    A software tool for the displaying of nuclear decay schemes, the calculation of angular γ emission anisotropies, and the automated search for appropriate decay cascade properties based on the Evaluated Nuclear Structure Data Files (ENSDF) was created and published for free download. After a short introduction of this tool, candidate nuclides for time differential perturbed γ-γ angular correlation (TDPAC) measurements are presented. These candidates are grouped according to their parent nuclides’ half-life periods in groups for online, on-site, and off-site measurements. For all candidates angular correlation coefficients (also called anisotropy values) were computed and are shown alongside magnetic and quadrupole moments from the ENSDF database and other sources. An extension of the presented software for the search of nuclides for Mössbauer spectroscopy, Nuclear Resonant Scattering, and other methods is easily possible.

  17. Nuclear decay data files of the Dosimetry Research Group

    Energy Technology Data Exchange (ETDEWEB)

    Eckerman, K.F.; Westfall, R.J.; Ryman, J.C.; Cristy, M.

    1993-12-01

    This report documents the nuclear decay data files used by the Dosimetry Research Group at Oak Ridge National Laboratory and the utility DEXRAX which provides access to the files. The files are accessed, by nuclide, to extract information on the intensities and energies of the radiations associated with spontaneous nuclear transformation of the radionuclides. In addition, beta spectral data are available for all beta-emitting nuclides. Two collections of nuclear decay data are discussed. The larger collection contains data for 838 radionuclides, which includes the 825 radionuclides assembled during the preparation of Publications 30 and 38 of the International Commission on Radiological Protection (ICRP) and 13 additional nuclides evaluated in preparing a monograph for the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine. The second collection is composed of data from the MIRD monograph and contains information for 242 radionuclides. Abridged tabulations of these data have been published by the ICRP in Publication 38 and by the Society of Nuclear Medicine in a monograph entitled ``MIRD: Radionuclide Data and Decay Schemes.`` The beta spectral data reported here have not been published by either organization. Electronic copies of the files and the utility, along with this report, are available from the Radiation Shielding Information Center at Oak Ridge National Laboratory.

  18. Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh)], E-mail: jahirulkhan@yahoo.com; Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2009-10-15

    The aim of this paper is to present the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through the analysis of the integral parameters of TRX and BAPL benchmark lattices of thermal reactors for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. In this process, the 69-group cross-section library for lattice code WIMS was generated using the basic evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 with the help of nuclear data processing code NJOY99.0. Integral measurements on the thermal reactor lattices TRX-1, TRX-2, BAPL-UO{sub 2}-1, BAPL-UO{sub 2}-2 and BAPL-UO{sub 2}-3 served as standard benchmarks for testing nuclear data files and have also been selected for this analysis. The integral parameters of the said lattices were calculated using the lattice transport code WIMSD-5B based on the generated 69-group cross-section library. The calculated integral parameters were compared to the measured values as well as the results of Monte Carlo Code MCNP. It was found that in most cases, the values of integral parameters show a good agreement with the experiment and MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through benchmarking the integral parameters of TRX and BAPL lattices and can also be essential to implement further neutronic analysis of TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh.

  19. NUCLEAR DATA EVALUATIONS AND RECOMMENDATIONS

    Energy Technology Data Exchange (ETDEWEB)

    HOLDEN, N.E.

    2005-05-08

    The published scientific literature is scanned and periodically evaluated for neutron and non-neutron nuclear data and the resulting recommendations are published [1,2]. After the literature has been scanned and appropriate data collected, there are often problems with regard to the treatment of the various types of data during this evaluation process and with regard to the method by which the recommendations are drawn from the assessment of the collection of individual measurements. Some-problems with uncertainties are presented.

  20. Decay data file based on the ENSDF file

    Energy Technology Data Exchange (ETDEWEB)

    Katakura, J. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    A decay data file with the JENDL (Japanese Evaluated Nuclear Data Library) format based on the ENSDF (Evaluated Nuclear Structure Data File) file was produced as a tentative one of special purpose files of JENDL. The problem using the ENSDF file as primary source data of the JENDL decay data file is presented. (author)

  1. ENDF-6 Formats Manual Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII

    Energy Technology Data Exchange (ETDEWEB)

    Herman, M.; Members of the Cross Sections Evaluation Working Group

    2009-06-01

    In December 2006, the Cross Section Evaluation Working Group (CSEWG) of the United States released the new ENDF/B-VII.0 library. This represented considerable achievement as it was the 1st major release since 1990 when ENDF/B-VI has been made publicly available. The two libraries have been released in the same format, ENDF-6, which has been originally developed for the ENDF/B-VI library. In the early stage of work on the VII-th generation of the library CSEWG made important decision to use the same formats. This decision was adopted even though it was argued that it would be timely to modernize the formats and several interesting ideas were proposed. After careful deliberation CSEWG concluded that actual implementation would require considerable resources needed to modify processing codes and to guarantee high quality of the files processed by these codes. In view of this the idea of format modernization has been postponed and ENDF-6 format was adopted for the new ENDF/B-VII library. In several other areas related to ENDF we made our best to move beyond established tradition and achieve maximum modernization. Thus, the 'Big Paper' on ENDF/B-VII.0 has been published, also in December 2006, as the Special Issue of Nuclear Data Sheets 107 (1996) 2931-3060. The new web retrieval and plotting system for ENDF-6 formatted data, Sigma, was developed by the NNDC and released in 2007. Extensive paper has been published on the advanced tool for nuclear reaction data evaluation, EMPIRE, in 2007. This effort was complemented with release of updated set of ENDF checking codes in 2009. As the final item on this list, major revision of ENDF-6 Formats Manual was made. This work started in 2006 and came to fruition in 2009 as documented in the present report.

  2. Nuclear Structure and Decay Data Evaluation: Status and Perspectives

    Science.gov (United States)

    Kondev, F. G.; Browne, E.; Ouellet, C.; Pritychenko, B.; Reich, C.; Sonzogni, A.; Tandel, S.; Tuli, J. K.; Cameron, J.; Chen, A.; Singh, B.; Kelley, J.; Kwan, E.; Baglin, C.; Basunia, M. S.; Firestone, R. B.; Nica, N.; Nesaraja, C. D.; Smith, M. S.

    2009-10-01

    Reliable nuclear structure data represent the fundamental building blocks of nuclear structure physics and astrophysics research, and are also of vital importance in a large number of applications. Members of the Nuclear Structure and Decay Data Working Group of the U.S. Nuclear Data Program, in collaboration with scientists from Japan and other countries within the International Nuclear Structure and Decay Data Network (under the auspices of IAEA), are involved in compilation, evaluation, and dissemination of nuclear structure and decay data for all known nuclei. The network's principal effort is devoted to the timely revision of information in the Evaluated Nuclear Structure Data File (ENSDF) library, which is the only comprehensive nuclear structure and decay data database that is updated continuously. This presentation will briefly review recent achievements of the network, present on-going activities, and reflect on ideas for future projects and challenges in the field of nuclear structure and decay data evaluation.

  3. An evaluated neutronic data file for elemental cobalt

    Energy Technology Data Exchange (ETDEWEB)

    Guenther, P.; Lawson, R.; Meadows, J.; Sugimoto, M.; Smith, A.; Smith, D.; Howerton, R.

    1988-08-01

    A comprehensive evaluated neutronic data file for elemental cobalt is described. The experimental data base, the calculational methods, the evaluation techniques and judgments, and the physical content are outlined. The file contains: neutron total and scattering cross sections and associated properties, (n,2n) and (n,3n) processes, neutron radiative capture processes, charged-particle-emission processes, and photon-production processes. The file extends from 10/sup /minus/5/ eV to 20 MeV, and is presented in the ENDF/B-VI format. Detailed attention is given to the uncertainties and correlations associated with the prominent neutron-induced processes. The numerical contents of the file have been transmitted to the National Nuclear Data Center, Brookhaven National Laboratory. 143 refs., 16 figs., 5 tabs.

  4. Nuclear Structure and Decay Data Evaluation: Challenges and Perspectives

    Science.gov (United States)

    Kondev, F. G.; Tuli, J. K.

    2003-10-01

    The expression ``Nuclear Structure and Decay Data'' refers to complex nuclear level schemes and tables of numerical values, which quantify fundamental properties of nuclear structure, such as level energies, quantum numbers and state lifetimes, as well as various decay modes and associated radiation. These data are not only at the core of basic nuclear structure and nuclear astrophysics research, but they are also relevant for many applied technologies, including nuclear energy production, reactor design and safety, medical diagnostic and radiotherapy, health physics, environmental research and monitoring, safeguards, material analysis, etc. The mission of the Nuclear Structure and Decay Data Working Group of the US DOE funded Nuclear Data Program is to evaluate, compile, maintain, and disseminate nuclear structure and decay data for all known nuclei (more than 2900!). The network's principal effort is devoted to the timely revision of information in the ENSDF (Evaluated Nuclear Structure Data File) database. However, in recent years, special attention has been given to topical evaluations of properties of particular interest to the nuclear structure community, such as log ft values, α- and proton decay properties, super-deformed and magnetic dipole collective structures, nuclear moments, and nuclear isomers (under development). This presentation will briefly review recent achievements of the network, present on-going activities, and reflect on ideas for future projects and challenges in the field of nuclear structure and decay data evaluation.

  5. Modern Nuclear Data Evaluation with the TALYS Code System

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J., E-mail: koning@nrg.eu [Nuclear Research and Consultancy Group NRG, P.O. Box, 1755 ZG Petten (Netherlands); Rochman, D. [Nuclear Research and Consultancy Group NRG, P.O. Box, 1755 ZG Petten (Netherlands)

    2012-12-15

    This paper presents a general overview of nuclear data evaluation and its applications as developed at NRG, Petten. Based on concepts such as robustness, reproducibility and automation, modern calculation tools are exploited to produce original nuclear data libraries that meet the current demands on quality and completeness. This requires a system which comprises differential measurements, theory development, nuclear model codes, resonance analysis, evaluation, ENDF formatting, data processing and integral validation in one integrated approach. Software, built around the TALYS code, will be presented in which all these essential nuclear data components are seamlessly integrated. Besides the quality of the basic data and its extensive format testing, a second goal lies in the diversity of processing for different type of users. The implications of this scheme are unprecedented. The most important are: 1. Complete ENDF-6 nuclear data files, in the form of the TENDL library, including covariance matrices, for many isotopes, particles, energies, reaction channels and derived quantities. All isotopic data files are mutually consistent and are supposed to rival those of the major world libraries. 2. More exact uncertainty propagation from basic nuclear physics to applied (reactor) calculations based on a Monte Carlo approach: 'Total' Monte Carlo (TMC), using random nuclear data libraries. 3. Automatic optimization in the form of systematic feedback from integral measurements back to the basic data. This method of work also opens a new way of approaching the analysis of nuclear applications, with consequences in both applied nuclear physics and safety of nuclear installations, and several examples are given here. This applied experience and feedback is integrated in a final step to improve the quality of the nuclear data, to change the users vision and finally to orchestrate their integration into simulation codes.

  6. Coherent investigation of nuclear data at CEA DAM: Theoretical models, experiments and evaluated data

    Energy Technology Data Exchange (ETDEWEB)

    Bauge, E.; Belier, G.; Cartier, J.; Chatillon, A.; Daugas, J.M.; Delaroche, J.P.; Dossantos-Uzarralde, P.; Duarte, H.; Dubray, N.; Ducauze-Philippe, M.; Gaudefroy, L.; Gosselin, G.; Granier, T.; Hilaire, S.; Chau, Huu-Tai P.; Laborie, J.M.; Laurent, B.; Ledoux, X.; Le Luel, C.; Meot, V.; Morel, P.; Morillon, B.; Roig, O.; Romain, P.; Taieb, J.; Varignon, C. [CEA, DAM, DIF, Arpajon (France); Authier, N.; Casoli, P.; Richard, B. [CEA Valduc, Is-sur-Tille (France)

    2012-08-15

    The domain of evaluated nuclear data involves at the same time, a close interaction between the field of nuclear applications and that of nuclear physics, and a close interaction between experiments and theory. The final product, the evaluated data file, synthesises vast amounts of information stemming from all of the above fields. In CEA DAM, all these aspects of nuclear data are investigated in a consistent way, making full use of experimental facilities and high-performance computing as well as numerous national and international collaborations, for the measurement, calculation, evaluation, and validation of nuclear data. (orig.)

  7. Genetic algorithm for nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Arthur, Jennifer Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-02-02

    These are slides on genetic algorithm for nuclear data evaluation. The following is covered: initial population, fitness (outer loop), calculate fitness, selection (first part of inner loop), reproduction (second part of inner loop), solution, and examples.

  8. Programs for the work with ENSDF format files: Evaluator's editor EVE, Viewer for the nuclear level schemes

    CERN Document Server

    Shulyak, G I

    2010-01-01

    Tools for the regular work of the nuclear data evaluator are presented: the context-dependent editor EVE and the viewer for the level schemes of nuclei from ENSDF datasets. These programs may be used by everybody who works with the Evaluated Nuclear Structure Data File and for the educational purposed.

  9. Adaptive Monte Carlo for nuclear data evaluation

    Directory of Open Access Journals (Sweden)

    Schnabel Georg

    2017-01-01

    Full Text Available An adaptive Monte Carlo method for nuclear data evaluation is presented. A fast evaluation method based on the linearization of the nuclear model guides the adaptation of the sampling distribution towards the posterior distribution. The method is suited for parallel computation and provides detailed uncertainty information about nuclear model parameters. Especially, the posterior distribution of the model parameters is not restricted to be multivariate normal. The method is demonstrated in an evaluation of the 181Ta total cross section for incident neutrons. Future applications are as an efficient sampling scheme in the Total Monte Carlo method, and the restriction of parameter uncertainties in nuclear models by both differential and integral data.

  10. International Cooperation in Nuclear Data Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Herman, M.; Herman, M.; Katakura, J.; Koning, A. J.; Nordborg, C.

    2011-08-01

    The OECD Nuclear Energy Agency (NEA) is organising a co-operation between the major nuclear data evaluation projects in the world. The co-operation involves the ENDF, JEFF, and JENDL projects, and, owing to the collaboration with the International Atomic Energy Agency (IAEA), also the Russian BROND and the Chinese CENDL projects. The Working Party on international nuclear data Evaluation Cooperation (WPEC), comprised of about 20 core members, manages this co-operation and meets annually to discuss progress in each evaluation project and also related experimental activities. The WPEC assesses common needs for nuclear data improvements and these needs are then addressed by initiating joint evaluation efforts. The work is performed in specially established subgroups, consisting of experts from the participating evaluation projects. The outcome of these subgroups is published in reports, issued by the NEA. Current WPEC activities comprise for example a number of studies related to nuclear data uncertainties, including a review of methods for the combined use of integral experiments and covariance data, as well as evaluations of some of the major actinides, such as {sup 235}U and {sup 239}Pu. This paper gives an overview of current and planned activities within the WPEC.

  11. Bayesian Monte Carlo method for nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J. [Nuclear Research and Consultancy Group NRG, P.O. Box 25, ZG Petten (Netherlands)

    2015-12-15

    A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions using the nuclear model code TALYS and the experimental nuclear reaction database EXFOR. The method is applied to all nuclides at the same time. First, the global predictive power of TALYS is numerically assessed, which enables to set the prior space of nuclear model solutions. Next, the method gradually zooms in on particular experimental data per nuclide, until for each specific target nuclide its existing experimental data can be used for weighted Monte Carlo sampling. To connect to the various different schools of uncertainty propagation in applied nuclear science, the result will be either an EXFOR-weighted covariance matrix or a collection of random files, each accompanied by the EXFOR-based weight. (orig.)

  12. Bayesian Monte Carlo method for nuclear data evaluation

    Science.gov (United States)

    Koning, A. J.

    2015-12-01

    A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions using the nuclear model code TALYS and the experimental nuclear reaction database EXFOR. The method is applied to all nuclides at the same time. First, the global predictive power of TALYS is numerically assessed, which enables to set the prior space of nuclear model solutions. Next, the method gradually zooms in on particular experimental data per nuclide, until for each specific target nuclide its existing experimental data can be used for weighted Monte Carlo sampling. To connect to the various different schools of uncertainty propagation in applied nuclear science, the result will be either an EXFOR-weighted covariance matrix or a collection of random files, each accompanied by the EXFOR-based weight.

  13. The ENSDF_toolbox program package: tool for the evaluator of nuclear data

    OpenAIRE

    Shulyak, G. I.; A. A. Rodionov

    2010-01-01

    The program package for the work with the Evaluated Nuclear Structure Data File is discussed. The program shell designed for the unification of the process of the evaluation of the nuclear data is proposed. This program shell may be used in the regular work of the nuclear data evaluator and for common use by scientists and engineers who need the actual data about nuclear states and transitions from the ENSDF database.

  14. TUNL Nuclear Structure Data Evaluation on A = 2-20 Nuclides

    Science.gov (United States)

    Truong, Thinh; Kelley, John; Sheu, Grace

    2016-09-01

    Nuclear data represents measured or evaluated probabilities of various physical interactions involving the nuclei of atoms. The nuclear data group at Triangle Universities Nuclear Laboratory (TUNL) compiles, evaluates and disseminates nuclear structure data relevant to light nuclei in the mass region of A = 2 - 20. Our activities primarily involve surveying literature articles and producing recommended values for inclusion into various United States Nuclear Data Program databases, such as Experimental Unevaluated Nuclear Data List (XUNDL) and Evaluated Nuclear Structure Data File (ENSDF). We have projects related to analyzing beta-decay lifetimes, compiling structure data from recently published articles, and producing full nuclear structure data evaluations of nuclides based on all existing literature. The nuclear data disseminated is used for theoretical model development of nuclear physics and for applications involving radiation and nuclear power technologies. This work is supported by the U.S. National Science Foundation Grant No. NSF-PHY-1461204 and Duke/TUNL.

  15. Using NJOY to Create MCNP ACE Files and Visualize Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    Kahler, Albert Comstock [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-10-14

    We provide lecture materials that describe the input requirements to create various MCNP ACE files (Fast, Thermal, Dosimetry, Photo-nuclear and Photo-atomic) with the NJOY Nuclear Data Processing code system. Input instructions to visualize nuclear data with NJOY are also provided.

  16. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D., E-mail: mencarini@ieav.cta.b, E-mail: alexdc@ieav.cta.b [Instituto de Estudos Avancados (IEAv/CTA), Sao Jose dos Campos, SP (Brazil)

    2011-07-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  17. Introducing Nuclear Data Evaluations of Prompt Fission Neutron Spectra

    Energy Technology Data Exchange (ETDEWEB)

    Neudecker, Denise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-06-17

    Nuclear data evaluations provide recommended data sets for nuclear data applications such as reactor physics, stockpile stewardship or nuclear medicine. The evaluated data are often based on information from multiple experimental data sets and nuclear theory using statistical methods. Therefore, they are collaborative efforts of evaluators, theoreticians, experimentalists, benchmark experts, statisticians and application area scientists. In this talk, an introductions is given to the field of nuclear data evaluation at the specific example of a recent evaluation of the outgoing neutron energy spectrum emitted promptly after fission from 239Pu and induced by neutrons from thermal to 30 MeV.

  18. Computer program system for evaluation of FP nuclear data for JENDL. Smooth part

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Watanabe, Takashi; Iijima, Shungo

    1997-12-01

    This report describes computer programs used to evaluate nuclear data of fission product (FP) nuclides stored in an evaluated nuclear data library JENDL, especially in the smooth part above the resonance region. Many programs were used for determination of nuclear model parameters, calculation of nuclear data, handling of experimental and/or calculated data, and so on. Among them, reported here are programs for determination of level density parameters (ENSDFRET, LVLPLOT, LEVDES), for making sets of JCL and input data for the theoretical calculation program CASTHY (JOBSETTER, INDES/CASTHY), and for conversion of format of CASTHY output files to the ENDF format (CTOB2). (author). 51 refs.

  19. Bayesian Monte Carlo Method for Nuclear Data Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J., E-mail: koning@nrg.eu

    2015-01-15

    A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions using TALYS. The result will be either an EXFOR-weighted covariance matrix or a collection of random files, each accompanied by an experiment based weight.

  20. Development of a utility system for nuclear reaction data file: WinNRDF

    Energy Technology Data Exchange (ETDEWEB)

    Aoyama, Shigeyoshi [Information Processing Center, Kitami Inst. of Tech., Hokkaido (Japan); Ohbayasi, Yosihide; Masui, Hiroshi [Meme Media Lab., Hokkaido Univ., Sapporo (Japan); Chiba, Masaki [Graduate School of Science, Hokkaido Univ., Sapporo (Japan); Kato, Kiyoshi; Ohnishi, Akira [Faculty of Social Information, Sapporo Gakuin Univ., Ebetsu, Hokkaido (Japan)

    2000-03-01

    A utility system, WinNRDF, is developed for charged particle nuclear reaction data of NRDF (Nuclear Reaction Data File) on the Windows interface. By using this system, we can easily search the experimental data of a charged particle nuclear reaction in NRDF than old retrieval systems on the mainframe and also see graphically the experimental data on GUI (Graphical User Interface). We adopted a mechanism of making a new index of keywords to put to practical use of the time dependent properties of the NRDF database. (author)

  1. Review of recent benchmark experiments on integral test for high energy nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Nakashima, Hiroshi; Tanaka, Susumu; Konno, Chikara; Fukahori, Tokio; Hayashi, Katsumi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    A survey work of recent benchmark experiments on an integral test for high energy nuclear data evaluation was carried out as one of the work of the Task Force on JENDL High Energy File Integral Evaluation (JHEFIE). In this paper the results are compiled and the status of recent benchmark experiments is described. (author)

  2. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

    2006-10-02

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector

  3. Calculation of dose coefficients for radionuclides produced in a spallation neutron source utilizing NUBASE and the evaluated nuclear structure data file databases.

    Science.gov (United States)

    Shanahan, J; Eckerman, K; Arndt, A; Gold, C; Patton, P; Rudin, M; Brey, R; Gesell, T; Rusetski, V; Pagava, S

    2006-01-01

    Based on a mercury spallation neutron source target, the UNLV Transmutation Research Program has identified 72 radionuclides with a half-life greater than or equal to a minute as lacking an appropriate reference for a published dose coefficient according to existing radiation safety dose coefficient databases. A method was developed to compare the nuclear data presented in the ENSDF and NUBASE databases for these 72 radionuclides. Due to conflicting or lacking nuclear data in one or more of the databases, internal and external dose coefficient values have been calculated for only 14 radionuclides, which are not currently presented in Federal Guidance Reports Nos. 11, 12, and 13 or Publications 68 and 72 of the International Commission on Radiological Protection. Internal dose coefficient values are reported for inhalation and ingestion of 1 microm and 5 microm AMAD particulates along with the f1 values and absorption types for the adult worker. Internal dose coefficient values are also reported for inhalation and ingestion of 1 microm AMAD particulates as well as the f1 values and absorption types for members of the public. Additionally, external dose coefficient values for air submersion, exposure to contaminated ground surface, and exposure to soil contaminated to an infinite depth are also presented.

  4. Working Party on International Nuclear Data Evaluation Cooperation (WPEC)

    Energy Technology Data Exchange (ETDEWEB)

    Dupont, E.; Herman, M.; Dupont, E.; Chadwick, M. B.; Danon, Y.; De Saint Jean, C.; Dunn, M.; Fischer, U.; Forrest, R. A.; Fukahori, T.; Ge, Z.; Harada, H.; Herman, M.; Igashira, M.; Ignatyuk, A.; Ishikawa, M.; Iwamoto, O.; Jacqmin, R.; Kahler, A. C.; Kawano, T.; Koning, A. J.; Leal, L.; Lee, Y. O.; McKnight, R.; McNabb, D.; Mills, R. W.; Palmiotti, G.; Plompen, A.; Salvatores, M.; Schillebeeckx, P.

    2014-06-01

    The OECD Nuclear Energy Agency (NEA) organizes cooperation between the major nuclear data evaluation projects in the world. Moreover, the NEA Working Party on International Nuclear Data Evaluation Cooperation (WPEC) was established to promote the exchange of information on nuclear data evaluation, measurement, nuclear model calculation, validation, and related topics, and to provide a framework for cooperative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint activities in the framework of dedicated WPEC subgroups. Studies recently completed comprise a number of works related to nuclear data covariance and associated processing issues, as well as more specific studies related to the resonance parameter representation in the unresolved resonance region, the gamma production from fission product capture reactions, the 235U capture cross section, the EXFOR database, and the improvement of nuclear data for advanced reactor systems. Ongoing activities focus on the evaluation of 239Pu in the resonance region, scattering angular distribution in the fast energy range, and reporting/usage of experimental data for evaluation in the resolved resonance region. New activities include two subgroups on improved fission product yield evaluation methodologies and on modern nuclear database structures. Some future activities under discussion include a pilot project for a Collaborative International Evaluated Library Organization (CIELO) and methods to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data. In addition to the above mentioned short-term task-oriented subgroups, WPEC also hosts a longer-term subgroup charged with reviewing and compiling the most important nuclear data requirements in a high priority request list (HPRL).

  5. Working Party on International Nuclear Data Evaluation Cooperation (WPEC)

    Energy Technology Data Exchange (ETDEWEB)

    Dupont, E., E-mail: wpec@oecd-nea.org [OECD Nuclear Energy Agency, Issy-les-Moulineaux (France); Chadwick, M.B. [Los Alamos National Laboratory, Los Alamos, NM (United States); Danon, Y. [Rensselaer Polytechnic Institute, Troy, NY (United States); De Saint Jean, C. [CEA, Nuclear Energy Division, Cadarache (France); Dunn, M. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Fischer, U. [Karlsruhe Institute of Technology, Karlsruhe (Germany); Forrest, R.A. [Nuclear Data Section, International Atomic Energy Agency (Austria); Fukahori, T. [Japan Atomic Energy Agency (Japan); Ge, Z. [China Institute of Atomic Energy (China); Harada, H. [Japan Atomic Energy Agency (Japan); Herman, M. [Brookhaven National Laboratory, Upton, NY (United States); Igashira, M. [Tokyo Institute of Technology, Tokyo (Japan); Ignatyuk, A. [Institute of Physics and Power Engineering, Obninsk (Russian Federation); Ishikawa, M.; Iwamoto, O. [Japan Atomic Energy Agency (Japan); Jacqmin, R. [CEA, Nuclear Energy Division, Cadarache (France); Kahler, A.C.; Kawano, T. [Los Alamos National Laboratory, Los Alamos, NM (United States); Koning, A.J. [Nuclear Research and Consultancy Group, Petten (Netherlands); Leal, L. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); and others

    2014-06-15

    The OECD Nuclear Energy Agency (NEA) organizes cooperation between the major nuclear data evaluation projects in the world. The NEA Working Party on International Nuclear Data Evaluation Cooperation (WPEC) was established to promote the exchange of information on nuclear data evaluation, measurement, nuclear model calculation, validation, and related topics, and to provide a framework for cooperative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint activities in the framework of dedicated WPEC subgroups. Studies recently completed comprise a number of works related to nuclear data covariance and associated processing issues, as well as more specific studies related to the resonance parameter representation in the unresolved resonance region, the gamma production from fission product capture reactions, the {sup 235}U capture cross section, the EXFOR database, and the improvement of nuclear data for advanced reactor systems. Ongoing activities focus on the evaluation of {sup 239}Pu in the resonance region, scattering angular distribution in the fast energy range, and reporting/usage of experimental data for evaluation in the resolved resonance region. New activities include two subgroups on improved fission product yield evaluation methodologies and on modern nuclear database structures. Future activities under discussion include a pilot project for a Collaborative International Evaluated Library Organization (CIELO) and methods to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data. In addition to the above mentioned short-term task-oriented subgroups, WPEC also hosts a longer-term subgroup charged with reviewing and compiling the most important nuclear data requirements in a high priority request list (HPRL)

  6. THE AIMS AND ACTIVITIES OF THE INTERNATIONAL NETWORK OF NUCLEAR STRUCTURE AND DECAY DATA EVALUATORS.

    Energy Technology Data Exchange (ETDEWEB)

    NICHOLS,A.L.; TULI, J.K.

    2007-04-22

    International Network of Nuclear Structure and Decay Data (NSDD) Evaluators consists of a number of evaluation groups and data service centers in several countries that appreciate the merits of working together to maintain and ensure the quality and comprehensive content of the ENSDF database (Evaluated Nuclear Structure Data File). Biennial meetings of the network are held under the auspices of the International Atomic Energy Agency (IAEA) to assign evaluation responsibilities, monitor progress, discuss improvements and emerging difficulties, and agree on actions to be undertaken by individual members. The evaluated data and bibliographic details are made available to users via various media, such as the journals ''Nuclear Physics A'' and ''Nuclear Data Sheets'', the World Wide Web, on CD-ROM, wall charts of the nuclides and ''Nuclear Wallet Cards''. While the ENSDF master database is maintained by the US National Nuclear Data Center at the Brookhaven National Laboratory, these data are also available from other nuclear data centers including the IAEA Nuclear Data Section. The Abdus Salam International Centre for Theoretical Physics (ICTP), Trieste, Italy, in cooperation with the IAEA, organizes workshops on NSDD at regular intervals. The primary aims of these particular workshops are to provide hands-on training in the data evaluation processes, and to encourage new evaluators to participate in NSDD activities. The technical contents of these NSDD workshops are described, along with the rationale for the inclusion of various topics.

  7. Towards consistent nuclear models and comprehensive nuclear data evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Bouland, O [Los Alamos National Laboratory; Hale, G M [Los Alamos National Laboratory; Lynn, J E [Los Alamos National Laboratory; Talou, P [Los Alamos National Laboratory; Bernard, D [FRANCE; Litaize, O [FRANCE; Noguere, G [FRANCE; De Saint Jean, C [FRANCE; Serot, O [FRANCE

    2010-01-01

    The essence of this paper is to enlighten the consistency achieved nowadays in nuclear data and uncertainties assessments in terms of compound nucleus reaction theory from neutron separation energy to continuum. Making the continuity of theories used in resolved (R-matrix theory), unresolved resonance (average R-matrix theory) and continuum (optical model) rangcs by the generalization of the so-called SPRT method, consistent average parameters are extracted from observed measurements and associated covariances are therefore calculated over the whole energy range. This paper recalls, in particular, recent advances on fission cross section calculations and is willing to suggest some hints for future developments.

  8. CRECTJ: a computer program for compilation of evaluated nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1999-09-01

    In order to compile evaluated nuclear data in the ENDF format, the computer program CRECTJ has been developed. CRECTJ has two versions; CRECTJ5 treats the data in the ENDF/B-IV and ENDF/B-V format, and CRECTJ6 the data in the ENDF-6 format. These programs have been frequently used to make Japanese Evaluated Nuclear Data Library (JENDL). This report describes input data and examples of CRECTJ. (author)

  9. Update on the U.S. Nuclear Structure and Decay Data Evaluation Program*

    Science.gov (United States)

    Baglin, Coral M.

    2000-04-01

    The U.S. Nuclear Data Program (USNDP) maintains and provides easy access to several large databases to assist scientists to sift through and assess the vast quantity of published nuclear structure and decay data. The Evaluated Nuclear Structure Data File (ENSDF) presents evaluated experimental nuclear data; the Nuclear Structure Reference (NSR) database provides bibliographic information; an Experimental Unevaluated Data Listing (XUNDL)has also recently been established to provide rapid access to data from the most recent publications (primarily in high-spin physics). In addition to the ongoing revision of data in ENSDF, information from the latest evaluations for A=21-44 by Endt[1] and evaluated data for recently-discovered heavy elements (up to Z=118) are currently being incorporated into ENSDF. An overview of nuclear structure and decay data available through the USNDP will be presented, with emphasis on recent and forthcoming additions to the material available. Feedback concerning the extent to which users' nuclear structure and decay data needs are being met by this data program will be welcomed. 1. P.M. Endt, Nucl. Phys. A521, 1 (1998). *On behalf of the U.S. Nuclear Data Program

  10. CENDL project, the chinese evaluated nuclear data library

    Science.gov (United States)

    Ge, Zhigang; Wu, Haicheng; Chen, Guochang; Xu, Ruirui

    2017-09-01

    The status of Chinese Evaluated Nuclear Data Library (CENDL) and the relevant CENDL project are introduced in this paper. Recently, a new version CENDL-3.2b0 was being prepared on the basis of the previous CENDL-3.1. The data in the light and actinide nuclide regions are updated from CENDL-3.1, and the new evaluations and calculations are performed mainly around structure and fission product nuclide regions. Covariance was also evaluated for structure and actinide nuclides. At the same time, the methodologies are systematically developed to fulfil the requirements of evaluations for CENDL-3.2b0. The updated nuclear reaction models for light and middle-heavy nuclides, non-model dependent nuclear data evaluation, covariance evaluation approaches, systematics, and integral validation system of nuclear data are incorporated in present CENDL project. The future developments are also planned.

  11. EXTENSION OF THE NUCLEAR REACTION MODEL CODE EMPIRE TO ACTINIDES NUCLEAR DATA EVALUATION.

    Energy Technology Data Exchange (ETDEWEB)

    CAPOTE,R.; SIN, M.; TRKOV, A.; HERMAN, M.; CARLSON, B.V.; OBLOZINSKY, P.

    2007-04-22

    Recent extensions and improvements of the EMPIRE code system are outlined. They add new capabilities to the code, such as prompt fission neutron spectra calculations using Hauser-Feshbach plus pre-equilibrium pre-fission spectra, cross section covariance matrix calculations by Monte Carlo method, fitting of optical model parameters, extended set of optical model potentials including new dispersive coupled channel potentials, parity-dependent level densities and transmission through numerically defined fission barriers. These features, along with improved and validated ENDF formatting, exclusive/inclusive spectra, and recoils make the current EMPIRE release a complete and well validated tool for evaluation of nuclear data at incident energies above the resonance region. The current EMPIRE release has been used in evaluations of neutron induced reaction files for {sup 232}Th and {sup 231,233}Pa nuclei in the fast neutron region at IAEA. Triple-humped fission barriers and exclusive pre-fission neutron spectra were considered for the fission data evaluation. Total, fission, capture and neutron emission cross section, average resonance parameters and angular distributions of neutron scattering are in excellent agreement with the available experimental data.

  12. INTERNATIONAL CO-OPERATION IN NUCLEAR DATA EVALUATION

    Energy Technology Data Exchange (ETDEWEB)

    Herman, M.; Katakura,J.; Koning,A.; Nordborg,C.

    2010-04-30

    The OECD Nuclear Energy Agency (NEA) is organising a co-operation between the major nuclear data evaluation projects in the world. The co-operation involves the ENDF, JEFF, and JENDL projects, and, owing to the collaboration with the International Atomic Energy Agency (IAEA), also the Russian RUSFOND and the Chinese CENDL projects. The Working Party on international nuclear data Evaluation Cooperation (WPEC), comprised of about 20 core members, manages this co-operation and meets annually to discuss progress in each evaluation project and also related experimental activities. The WPEC assesses common needs for nuclear data improvements and these needs are then addressed by initiating joint evaluation efforts. The work is performed in specially established subgroups, consisting of experts from the participating evaluation projects. The outcome of these subgroups is published in reports, issued by the NEA. Current WPEC activities comprise for example a number of studies related to nuclear data uncertainties, including a review of methods for the combined use of integral experiments and covariance data, as well as evaluations of some of the major actinides, such as {sup 235}U and {sup 239}Pu. This paper gives an overview of current and planned activities within the WPEC.

  13. Nuclear data evaluation methodology including estimates of covariances

    Directory of Open Access Journals (Sweden)

    Smith D.L.

    2010-10-01

    Full Text Available Evaluated nuclear data rather than raw experimental and theoretical information are employed in nuclear applications such as the design of nuclear energy systems. Therefore, the process by which such information is produced and ultimately used is of critical interest to the nuclear science community. This paper provides an overview of various contemporary methods employed to generate evaluated cross sections and related physical quantities such as particle emission angular distributions and energy spectra. The emphasis here is on data associated with neutron induced reaction processes, with consideration of the uncertainties in these data, and on the more recent evaluation methods, e.g., those that are based on stochastic (Monte Carlo techniques. There is no unique way to perform such evaluations, nor are nuclear data evaluators united in their opinions as to which methods are superior to the others in various circumstances. In some cases it is not critical which approaches are used as long as there is consistency and proper use is made of the available physical information. However, in other instances there are definite advantages to using particular methods as opposed to other options. Some of these distinctions are discussed in this paper and suggestions are offered regarding fruitful areas for future research in the development of evaluation methodology.

  14. Summary documentation of LASL nuclear data evaluations for ENDF/B-V

    Energy Technology Data Exchange (ETDEWEB)

    Young, P.G. (comp.)

    1979-01-01

    Summaries are presented of nuclear data evaluations performed at Los Alamos Scientific Laboratory (LASL) that will comprise part of Version V of the Evaluated Nuclear Data File, ENDF/B. A total of 18 general purpose evaluations of neutron-induced data are summarized, together with 6 summaries directed specifically at covariance data evaluations. The general purpose evaluation summaries cover the following isotopes: /sup 1 -3/H, /sup 3/ /sup 4/He, /sup 6/ /sup 7/Li, /sup 10/B, /sup 14/ /sup 15/N, /sup 16/O, /sup 27/Al, /sup 182/ /sup 183/ /sup 184/ /sup 186/W, /sup 233/U, and /sup 242/Pu. The covariance data summaries are given for /sup 1/H, /sup 6/Li, /sup 10/B, /sup 14/N, /sup 16/O, and /sup 27/Al. 28 figures.

  15. TENDL-2011: TALYS-based Evaluated Nuclear Data Library

    Energy Technology Data Exchange (ETDEWEB)

    Rochman, D.; Koning, A. J. [Nuclear Research and Consultancy Group, Petten (Netherlands)

    2012-07-01

    The 4. release of the TENDL library, TENDL-2011 (TALYS-based Evaluated Nuclear Data Library) is described. This library consists of a complete set of nuclear reaction data for incident neutrons, photons, protons, deuterons, tritons, helions and alpha particles, from 10-5 eV up to 200 MeV, for all isotopes from {sup 6}Li to {sup 281}Ds that are either stable of have a half-life longer than 1 second. All data are completely and consistently evaluated using a software system consisting of the TALYS-1.2 nuclear reaction code, and other programs to handle resonance data, experimental data, data from existing evaluations, and to provide the final ENDF-6 formatting. The result is a nuclear data library with mutually consistent reaction information for all isotopes and a quality that increases with yearly updates. To produce this library, TALYS input parameters are adjusted for many nuclides so that calculated cross sections agree with experimental data, while for important nuclides experimental data are directly included. All information is available on www.talys.eu and www.talys.eu/TENDL-2011. (authors)

  16. Summary Report of a Specialized Workshop on Nuclear Structure and Decay Data (NSDD) Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, Alan L. [Univ. of Surrey, Guildford (United Kingdom); Dimitrious, P. [IAEA Nuclear Data Section, Vienna (Austria); Kondev, F. G. [Argonne National Lab. (ANL), Argonne, IL (United States); Ricard-McCutchan, E. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-04-27

    A three-day specialised workshop on Nuclear Structure and Decay Data Evaluations was organised and held at the headquarters of the International Atomic Energy Agency in Vienna, Austria, from 27 to 29 April 2015. This workshop covered a wide range of important topics and issues addressed when evaluating and maintaining the Evaluated Nuclear Structure Data File (ENSDF). The primary aim was to improve evaluators’ abilities to identify and understand the most appropriate evaluation processes to adopt in the formulation of individual ENSDF data sets. Participants assessed and reviewed existing policies, procedures and codes, and round-table discussions included the debate and resolution of specific difficulties experienced by ENSDF evaluators (i.e., all workshop participants). The contents of this report constitute a record of this workshop, based on the presentations and subsequent discussions.

  17. JENDL FP decay data file 2000

    Energy Technology Data Exchange (ETDEWEB)

    Katakura, Jun-ichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yoshida, Tadashi [Musashi Inst. of Tech., Tokyo (Japan); Oyamatsu, Kazuhiro [Aichi Shukutoku Univ., Nagakute, Aichi (Japan); Tachibana, Takahiro [Waseda Univ., Tokyo (Japan)

    2001-07-01

    A decay data file of fission product (FP) nuclides has been developed for the use in nuclear technology field as one of special purpose files of JENDL (Japanese Evaluated Nuclear Data Library) in the format of ENDF/B and it is called JENDL FP Decay Data File 2000. The file includes the decay data for 1229 fission product nuclides: 142 stable and 1087 unstable nuclides. The data included for a nuclide are decay modes, their Q values and branching ratios, average decay energy values of beta-rays, gamma-rays and alpha-particles and their spectral data. The primary source of the decay data is ENSDF (Evaluated Nuclear Structure Data File), which is the internationally recognized data file of nuclear structure properties. The data in ENSDF, however, cover only measured ones. The data of the short-lived nuclides needed for the application fields such as decay heat prediction are often incomplete or not measured because of their short half-lives. For such nuclides a theoretical model calculation is applied to derive the needed data such as average decay energies and spectral data. The data in JENDL FP Decay Data File 2000 have been tested by summation calculation comparing its results with measured data of decay heat values and aggregate fission product spectra of various fissioning nuclei. The comparison showed good agreement between the calculated results and the measured values. (author)

  18. Nuclear Data Sheets for A = 170

    Science.gov (United States)

    Baglin, Coral M.

    2002-08-01

    Nuclear structure data pertaining to all nuclei with mass number A=170 have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation supersedes the previous evaluation (Coral M. Baglin, Nuclear Data Sheets 77, 125 (1996), cutoff date October 1995) and subsequent updates of the ENSDF file for Yb (cutoff 17 February 1999), Lu (cutoff 8 October 1998), Pt (cutoff 17 February 1999) and Ta (cutoff 7 April 1998). It includes all literature available by 15 August 2002.

  19. The CCONE Code System and its Application to Nuclear Data Evaluation for Fission and Other Reactions

    Science.gov (United States)

    Iwamoto, O.; Iwamoto, N.; Kunieda, S.; Minato, F.; Shibata, K.

    2016-01-01

    A computer code system, CCONE, was developed for nuclear data evaluation within the JENDL project. The CCONE code system integrates various nuclear reaction models needed to describe nucleon, light charged nuclei up to alpha-particle and photon induced reactions. The code is written in the C++ programming language using an object-oriented technology. At first, it was applied to neutron-induced reaction data on actinides, which were compiled into JENDL Actinide File 2008 and JENDL-4.0. It has been extensively used in various nuclear data evaluations for both actinide and non-actinide nuclei. The CCONE code has been upgraded to nuclear data evaluation at higher incident energies for neutron-, proton-, and photon-induced reactions. It was also used for estimating β-delayed neutron emission. This paper describes the CCONE code system indicating the concept and design of coding and inputs. Details of the formulation for modelings of the direct, pre-equilibrium and compound reactions are presented. Applications to the nuclear data evaluations such as neutron-induced reactions on actinides and medium-heavy nuclei, high-energy nucleon-induced reactions, photonuclear reaction and β-delayed neutron emission are mentioned.

  20. Evaluating and adjusting {sup 239}Pu, {sup 56}Fe, {sup 28}Si and {sup 95}Mo nuclear data with a Monte Carlo technique

    Energy Technology Data Exchange (ETDEWEB)

    Rochman, D.; Koning, A. J. [Nuclear Research and Consultancy Group, Petten (Netherlands)

    2012-07-01

    In this paper, Monte Carlo optimization and nuclear data evaluation are combined to produce optimal adjusted nuclear data files. The methodology is based on the so-called 'Total Monte Carlo' and the TALYS system. Not only a single nuclear data file is produced for a given isotope, but virtually an infinite number, defining probability distributions for each nuclear quantity. Then each of these random nuclear data libraries is used in a series of benchmark calculations. With a goodness-of-fit estimator, best {sup 239}Pu, {sup 56}Fe, {sup 28}Si and {sup 95}Mo evaluations for that benchmark set can be selected. A few thousands of random files are used and each of them is tested with a large number of fast, thermal and intermediate energy criticality benchmarks. From this, the best performing random file is chosen and proposed as the optimum choice among the studied random set. (authors)

  1. Nuclear Data Sheets for 141Eu

    Science.gov (United States)

    Tuli, J. K.

    1998-06-01

    Nuclear structure data pertaining to 141Eu have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 141Eu supersedes the previous publication by L. K. Peker Nuclear Data Sheets 63,573 (1991). Abs; 141Eu is updated. Mostly the new information is from ( 35Cl,2p2nγ) reaction.

  2. Nuclear Data Sheets for 170Lu

    Science.gov (United States)

    Baglin, Coral M.

    1998-11-01

    Nuclear structure data pertaining to 170Lu have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 170Lu supersedes the previous publication (C. Baglin, Nuclear Data Sheets 77,125 (1996) (literature cutoff date October 1995)), and includes literature available by 8 Otober 1998.

  3. Evaluation of nuclear data for R and D projects; development of database for medical nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Tae Suk [Catholic University, Seoul (Korea); Shin, D. O. [Kyung Hee University, Seoul (Korea); Joh, C. W.; Chang, J. S. [Ajou University, Suwon (Korea); Choi, Y. [Sungkyunkwan University, Seoul (Korea); Kim, S. H. [Hanyang University, Seoul (Korea); Park, S. Y. [National Cancer Center, Seoul (Korea); Shin, D. H.; Lee, S [Kyonggi University, Seoul (Korea)

    2002-04-01

    Medical nuclear data used in the country is not provided by academic associations and organizations concerned and even by government organizations concerned. This is aimed to investigate the diagnostic and therapeutic equipments in the clinical use and the domestic present status of nuclear data and physical properties of sealed or unsealed radioactive isotopes and to establish the nuclear database. About 120 domestic centers take nuclear medicine tests and 52 medical centers do radiotherapy. The 30-odd different kinds of radionuclides are usually used in nuclear medicine in the country. The 30-odd kinds of unsealed sources are used for diagnosis and therapy and 10-odd kinds of sealed sources for brachytherapy in the country. The special radiotherapy includes Gamma-knife, linac-based stereotactic radiosurgery, conformal radiotherapy and Intensity modulated radiotherapy. The nuclear data base has been completed on the basis of these data collected and the web site made is available with ease to anyone who want to get nuclear data. 39 refs., 20 figs., 8 tabs. (Author)

  4. Evaluation of nuclear data of {sup 244}Pu and {sup 237}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Konshin, V.A. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1995-10-01

    The evaluation of nuclear data for {sup 244}Pu and {sup 237}Pu was made in the neutron energy region from 10{sup -5} eV to 20 MeV. For the both nuclides, the total, elastic and inelastic scattering, fission, capture, (n,2n) and (n,3n) reaction cross sections were evaluated on the basis of theoretical calculation. The resonance parameters were given for {sup 244}Pu. The angular and energy distributions of secondary neutrons were also estimated for the both nuclides. The results were compiled in the ENDF-5 format and will be adopted in JENDL Actinoid File. (author).

  5. Requirement and prospect of nuclear data activities for nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Kimura, Itsuro [Nuclear Safety System, Inc., Mihama, Fukui (Japan)

    2000-03-01

    Owing to continuous efforts by the members of JNDC (Japanese Nuclear Data Committee) and Nuclear Data Center in JAERI (Japan Atomic Energy Research Institute), several superb evaluated nuclear data files, such as JENDL, FP (fission product) yields and decay heat, have been compiled in Japan and opened to the world. However, they are seldom adopted in safety design and safety evaluation of light water reactors and are hardly found in related safety regulatory guidelines and standards except the decay heat. In this report, shown are a few examples of presently used nuclear data in the safety design and the safety evaluation of PWRs (pressurized water reactors) and so forth. And then, several procedures are recommended in order to enhance more utilization of Japanese evaluated nuclear data files for nuclear safety. (author)

  6. The US Nuclear Data Network

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-19

    This report discusses the following topics: US Nuclear Data Network Meeting; TUNL A=3--20 Data Project Activity Report 1993; INEL Mass-chain Evaluation Project Activity Report for 1993; 1993 Isotopes; Nuclear Data Project Activity Report; The NNDC Activity Report Parts A and B; Minutes of the Formats and Procedures Subcommittee; Evaluation of High-spin Nuclear Data for ENSDF and Table of Superdeformed Nuclear Bands; Proposal for Support of a Experimental High-spin; Data File/Data-Network Coordinator; Radioactive Decay and Applications; A Plan for a Horizontal Evaluation of Decay Data; ENSDF On-line System; The MacNuclide Project Expanding the Scope of the Nuclear Structure Reference File; ENSDAT: Evaluated Nuclear Structure Drawings and Tables; Cross Section Evaluation Working Group (CSEWG) and CSEWG Strategy Session; A Draft Proposal for a USNDN Program Advisory Council; Recommendations of Focus Group 1; Recommendations of Focus Group 2; Recommendations of Focus Group 3; Recommendations of Focus Group 4; The Table of Isotopes; The Isotopes CD-ROM; Electronic Table of Isotopes (ETOI); and Electronic Access to Nuclear Data.

  7. Sensitivity analysis of critical experiments with evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Fujiwara, D.; Kosaka, S. [Tepco Systems Corporation, Nuclear Engineering Dept., Tokyo (Japan)

    2008-07-01

    Criticality benchmark testing was performed with evaluated nuclear data libraries for thermal, low-enriched uranium fuel rod applications. C/E values for k{sub eff} were calculated with the continuous-energy Monte Carlo code MVP2 and its libraries generated from Endf/B-VI.8, Endf/B-VII.0, JENDL-3.3 and JEFF-3.1. Subsequently, the observed k{sub eff} discrepancies between libraries were decomposed to specify the source of difference in the nuclear data libraries using sensitivity analysis technique. The obtained sensitivity profiles are also utilized to estimate the adequacy of cold critical experiments to the boiling water reactor under hot operating condition. (authors)

  8. New Directions for Nuclear Data

    Science.gov (United States)

    Firestone, Richard

    2011-10-01

    The evaluation of nuclear data has gone on for over 75 years. After WWII it was realized that the rate of accumulation of nuclear data had become too rapid for individual scientists and engineers to scan the literature so the modern nuclear data program was funded in the US by an act of Congress under the leadership of Katherine Way. In the 1970's at Oak Ridge National Laboratory the Nuclear Data Sheets ENSDF file format was designed and continues to be used, largely unchanged, today. Although originally envisioned to support nuclear applications, ENSDF today now largely supports basic nuclear structure research. As data evaluation became a specialization a gulf developed between the research, application, and data communities that has widened over time. At this juncture in history we are facing the joint dilemmas of disconnects between research and data activities, an aging nuclear data workforce, and pressures from funding agencies to work more efficiently. In this talk I will discuss recent developments and opportunities in nuclear data and the challenges ahead of us to modernize the nuclear data program and better integrate it into the nuclear physics research community. This work was supported under U.S DOE Contract No. DE-AC02-05CH11231.

  9. Examination of various roles for covariance matrices in the development, evaluation, and application of nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.L.

    1988-01-01

    The last decade has been a period of rapid development in the implementation of covariance-matrix methodology in nuclear data research. This paper offers some perspective on the progress which has been made, on some of the unresolved problems, and on the potential yet to be realized. These discussions address a variety of issues related to the development of nuclear data. Topics examined are: the importance of designing and conducting experiments so that error information is conveniently generated; the procedures for identifying error sources and quantifying their magnitudes and correlations; the combination of errors; the importance of consistent and well-characterized measurement standards; the role of covariances in data parameterization (fitting); the estimation of covariances for values calculated from mathematical models; the identification of abnormalities in covariance matrices and the analysis of their consequences; the problems encountered in representing covariance information in evaluated files; the role of covariances in the weighting of diverse data sets; the comparison of various evaluations; the influence of primary-data covariance in the analysis of covariances for derived quantities (sensitivity); and the role of covariances in the merging of the diverse nuclear data information. 226 refs., 2 tabs.

  10. Kiwi: An Evaluated Library of Uncertainties in Nuclear Data and Package for Nuclear Sensitivity Studies

    Energy Technology Data Exchange (ETDEWEB)

    Pruet, J

    2007-06-23

    This report describes Kiwi, a program developed at Livermore to enable mature studies of the relation between imperfectly known nuclear physics and uncertainties in simulations of complicated systems. Kiwi includes a library of evaluated nuclear data uncertainties, tools for modifying data according to these uncertainties, and a simple interface for generating processed data used by transport codes. As well, Kiwi provides access to calculations of k eigenvalues for critical assemblies. This allows the user to check implications of data modifications against integral experiments for multiplying systems. Kiwi is written in python. The uncertainty library has the same format and directory structure as the native ENDL used at Livermore. Calculations for critical assemblies rely on deterministic and Monte Carlo codes developed by B division.

  11. RIPL - Reference Input Parameter Library for Calculation of Nuclear Reactions and Nuclear Data Evaluations

    Science.gov (United States)

    Capote, R.; Herman, M.; Obložinský, P.; Young, P. G.; Goriely, S.; Belgya, T.; Ignatyuk, A. V.; Koning, A. J.; Hilaire, S.; Plujko, V. A.; Avrigeanu, M.; Bersillon, O.; Chadwick, M. B.; Fukahori, T.; Ge, Zhigang; Han, Yinlu; Kailas, S.; Kopecky, J.; Maslov, V. M.; Reffo, G.; Sin, M.; Soukhovitskii, E. Sh.; Talou, P.

    2009-12-01

    We describe the physics and data included in the Reference Input Parameter Library, which is devoted to input parameters needed in calculations of nuclear reactions and nuclear data evaluations. Advanced modelling codes require substantial numerical input, therefore the International Atomic Energy Agency (IAEA) has worked extensively since 1993 on a library of validated nuclear-model input parameters, referred to as the Reference Input Parameter Library (RIPL). A final RIPL coordinated research project (RIPL-3) was brought to a successful conclusion in December 2008, after 15 years of challenging work carried out through three consecutive IAEA projects. The RIPL-3 library was released in January 2009, and is available on the Web through http://www-nds.iaea.org/RIPL-3/. This work and the resulting database are extremely important to theoreticians involved in the development and use of nuclear reaction modelling (ALICE, EMPIRE, GNASH, UNF, TALYS) both for theoretical research and nuclear data evaluations. The numerical data and computer codes included in RIPL-3 are arranged in seven segments: MASSES contains ground-state properties of nuclei for about 9000 nuclei, including three theoretical predictions of masses and the evaluated experimental masses of Audi et al. (2003). DISCRETE LEVELS contains 117 datasets (one for each element) with all known level schemes, electromagnetic and γ-ray decay probabilities available from ENSDF in October 2007. NEUTRON RESONANCES contains average resonance parameters prepared on the basis of the evaluations performed by Ignatyuk and Mughabghab. OPTICAL MODEL contains 495 sets of phenomenological optical model parameters defined in a wide energy range. When there are insufficient experimental data, the evaluator has to resort to either global parameterizations or microscopic approaches. Radial density distributions to be used as input for microscopic calculations are stored in the MASSES segment. LEVEL DENSITIES contains

  12. RIPL-Reference Input Parameter Library for Calculation of Nuclear Reactions and Nuclear Data Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Capote, R.; Herman, M.; Capote,R.; Herman,M.; Oblozinsky,P.; Young,P.G.; Goriely,S.; Belgy,T.; Ignatyuk,A.V.; Koning,A.J.; Hilaire,S.; Pljko,V.A.; Avrigeanu,M.; Bersillon,O.; Chadwick,M.B.; Fukahori,T.; Ge, Zhigang; Han,Yinl,; Kailas,S.; Kopecky,J.; Maslov,V.M.; Reffo,G.; Sin,M.; Soukhovitskii,E.Sh.; Talou,P

    2009-12-01

    We describe the physics and data included in the Reference Input Parameter Library, which is devoted to input parameters needed in calculations of nuclear reactions and nuclear data evaluations. Advanced modelling codes require substantial numerical input, therefore the International Atomic Energy Agency (IAEA) has worked extensively since 1993 on a library of validated nuclear-model input parameters, referred to as the Reference Input Parameter Library (RIPL). A final RIPL coordinated research project (RIPL-3) was brought to a successful conclusion in December 2008, after 15 years of challenging work carried out through three consecutive IAEA projects. The RIPL-3 library was released in January 2009, and is available on the Web through http://www-nds.iaea.org/RIPL-3/. This work and the resulting database are extremely important to theoreticians involved in the development and use of nuclear reaction modelling (ALICE, EMPIRE, GNASH, UNF, TALYS) both for theoretical research and nuclear data evaluations. The numerical data and computer codes included in RIPL-3 are arranged in seven segments: MASSES contains ground-state properties of nuclei for about 9000 nuclei, including three theoretical predictions of masses and the evaluated experimental masses of Audi et al. (2003). DISCRETE LEVELS contains 117 datasets (one for each element) with all known level schemes, electromagnetic and {gamma}-ray decay probabilities available from ENSDF in October 2007. NEUTRON RESONANCES contains average resonance parameters prepared on the basis of the evaluations performed by Ignatyuk and Mughabghab. OPTICAL MODEL contains 495 sets of phenomenological optical model parameters defined in a wide energy range. When there are insufficient experimental data, the evaluator has to resort to either global parameterizations or microscopic approaches. Radial density distributions to be used as input for microscopic calculations are stored in the MASSES segment. LEVEL DENSITIES contains

  13. Evaluation of the 125Sb nuclear decay data

    Science.gov (United States)

    Lile, Liu; Xiaolong, Huang; Mengxiao, Kang; Guochang, Chen; Jimin, Wang; Liyang, Jiang

    2016-02-01

    Evaluation of the complete decay scheme and data for 125Sb/125mTe decay to nuclear levels in 125Te is presented in this report; literature data available up to June 2015 are included. The Limitation of Relative Statistical Weight Method (LRSW) was applied to average numbers throughout the evaluation. The uncertainty assigned to the average value was always greater than or equal to the smallest uncertainty of the values used to calculate the average. The half-life has been determined to be 1007.4±0.3 days. All known measured γ-ray absolute or relative intensities have been examined; the γ-ray emission probability of the reference γ-ray line of 427.874 keV is recommended to be 29.54±0.10%. The theoretical internal conversion coefficients and their uncertainties were used to obtain the complete decay scheme intensity balance. The values of other decay characteristics were calculated using the ENSDF analysis program. Finally the updated decay scheme for 125Sb is presented.

  14. Evaluation of the {sup 125}Sb nuclear decay data

    Energy Technology Data Exchange (ETDEWEB)

    Lile, Liu; Xiaolong, Huang, E-mail: huang@ciae.ac.cn; Mengxiao, Kang; Guochang, Chen; Jimin, Wang; Liyang, Jiang

    2016-02-01

    Evaluation of the complete decay scheme and data for {sup 125}Sb/{sup 125m}Te decay to nuclear levels in {sup 125}Te is presented in this report; literature data available up to June 2015 are included. The Limitation of Relative Statistical Weight Method (LRSW) was applied to average numbers throughout the evaluation. The uncertainty assigned to the average value was always greater than or equal to the smallest uncertainty of the values used to calculate the average. The half-life has been determined to be 1007.4±0.3 days. All known measured γ-ray absolute or relative intensities have been examined; the γ-ray emission probability of the reference γ-ray line of 427.874 keV is recommended to be 29.54±0.10%. The theoretical internal conversion coefficients and their uncertainties were used to obtain the complete decay scheme intensity balance. The values of other decay characteristics were calculated using the ENSDF analysis program. Finally the updated decay scheme for {sup 125}Sb is presented.

  15. Nuclear Data Sheets for 225Fr

    Energy Technology Data Exchange (ETDEWEB)

    Baglin, Coral M.

    2005-05-16

    Nuclear structure data pertaining to {sup 225}Fr have been evaluated, and incorporated into the ENSDF data file. This evaluation includes literature available by 16 May 2005 and supersedes the previous publication for {sup 225}Fr (Y.A. Akovali, ''Nuclear Data Sheets 60, 617 (1990)'', literature cutoff date 1 June 1989). Data have been incorporated from the following references: 1987Co19, 1997BuO3 and 2003AuO3.

  16. Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    White, Morgan C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-23

    PowerPoint presentation targeted for educational use. Nuclear data comes from a variety of sources and in many flavors. Understanding where the data you use comes from and what flavor it is can be essential to understand and interpret your results. This talk will discuss the nuclear data pipeline with particular emphasis on providing links to additional resources that can be used to explore the issues you will encounter.

  17. Nuclear Data Sheets for 181Au

    Science.gov (United States)

    Baglin, Coral M.

    1999-06-01

    Nuclear structure data pertaining to 181Au have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 181Au supersedes the previous publication (R. B. Firestone, Nuclear Data Sheets 62, 101 (1991) (literature cutoff date October 1990)), and includes literature available by 2 July 1999. The newly incorporated references are: 1999Mu05, 1999So01, 1995Au04, 1995Bi01, 1991Ry01, 1979Ha10, 1970Ha18.

  18. Nuclear Data Sheets for 181Pt

    Science.gov (United States)

    Baglin, Coral M.

    1999-06-01

    Nuclear structure data pertaining to 181Pt have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 181Pt supersedes the previous publication (R. B. Firestone, Nuclear Data Sheets 62, 101 (1991) (literature cutoff date October 1990)), and includes literature available by 2 July 1999. New references since last publication: 1998RoZY, 1995Au04, 1993Me13, 1992Sa03 (supersedes 1990SaZU).

  19. Nuclear Data Sheets for 181Hg

    Science.gov (United States)

    Baglin, Coral M.

    1999-06-01

    Nuclear structure data pertaining to 181Hg have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 181Hg supersedes the previous publication (R. B. Firestone, Nuclear Data Sheets 62, 101 (1991) (literature cutoff date October 1990)), and includes literature available by 2 July 1999. The newly incorporated references are: 1997Va17, 1995Au04, 1987To09, 1986Ul02, 1979Ha10, 1975Ho02, 1971Ho07.

  20. Nuclear Data Sheets for 179Ir

    Science.gov (United States)

    Baglin, Coral M.

    1998-11-01

    Nuclear structure data pertaining to 179Ir have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 179Ir supersedes the previous publication (C. Baglin, Nuclear Data Sheets 72,617 (1994) (literature cutoff date September 1994)), and includes literature available by 8 October 1998. The newly incorporated references are: 96Ji04 (which supersedes 93JiZW), 95Au04, 95Bi01 and 94Mu18.

  1. Nuclear data sheets for 181Au

    Energy Technology Data Exchange (ETDEWEB)

    Baglin, Coral M.

    1999-07-02

    Nuclear structure data pertaining to 181Au have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 181Au supersedes the previous publication (R. B. Firestone, Nuclear Data Sheets 62, 101 (1991) (literature cutoff date October 1990)), and includes literature available by 2 July 1999. The newly incorporated references are: 1999Mu05, 1999So01, 1995Au04, 1995Bi01, 1991Ry01, 1979Ha10, 1970Ha18.

  2. Nuclear data requirements for accelerator driven sub-critical systems

    Indian Academy of Sciences (India)

    Qd; 29.25.Dz; 29.25.-t. 1. Introduction. This paper briefly presents the perspective of the author on the nuclear data require- .... to flow dynamics and problems arising from the gas formation. Thus, all nuclear data information ... izations, large data files information management, evaluations, that include nuclear model based ...

  3. Database Objects vs Files: Evaluation of alternative strategies for managing large remote sensing data

    Science.gov (United States)

    Baru, Chaitan; Nandigam, Viswanath; Krishnan, Sriram

    2010-05-01

    Increasingly, the geoscience user community expects modern IT capabilities to be available in service of their research and education activities, including the ability to easily access and process large remote sensing datasets via online portals such as GEON (www.geongrid.org) and OpenTopography (opentopography.org). However, serving such datasets via online data portals presents a number of challenges. In this talk, we will evaluate the pros and cons of alternative storage strategies for management and processing of such datasets using binary large object implementations (BLOBs) in database systems versus implementation in Hadoop files using the Hadoop Distributed File System (HDFS). The storage and I/O requirements for providing online access to large datasets dictate the need for declustering data across multiple disks, for capacity as well as bandwidth and response time performance. This requires partitioning larger files into a set of smaller files, and is accompanied by the concomitant requirement for managing large numbers of file. Storing these sub-files as blobs in a shared-nothing database implemented across a cluster provides the advantage that all the distributed storage management is done by the DBMS. Furthermore, subsetting and processing routines can be implemented as user-defined functions (UDFs) on these blobs and would run in parallel across the set of nodes in the cluster. On the other hand, there are both storage overheads and constraints, and software licensing dependencies created by such an implementation. Another approach is to store the files in an external filesystem with pointers to them from within database tables. The filesystem may be a regular UNIX filesystem, a parallel filesystem, or HDFS. In the HDFS case, HDFS would provide the file management capability, while the subsetting and processing routines would be implemented as Hadoop programs using the MapReduce model. Hadoop and its related software libraries are freely available

  4. Nuclear Data Sheets for 170Ta

    Science.gov (United States)

    Balin, Coral M.

    1998-06-01

    Nuclear structure data pertaining to 170Ta have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 170Ta supersedes the previous publications (Zhou Chunmei, Nuclear Data Sheets 50,351 (1987) (cutoff date November 1985), and Coral M. Baglin, Nuclear Data Sheets 77,125 (1996) (cutoff date October 1995)), and includes literature available by 7 April 1998. The newly incorporated references are: 97MeZZ ( 170W ɛ decay); 97Zh17 and 98Zh08 (a new (HI,xnγ) study). One collective band, previously assigned to 170Ta, has now been reassigned to 170Hf.

  5. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators; Summary Report of an IAEA Technical Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Abriola, D.; Tuli, J.

    2009-03-23

    The IAEA Nuclear Data Section convened the 18th meeting of the International Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 23 to 27 March 2009. This meeting was attended by 22 scientists from 14 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, recommendations/conclusions, data centre reports, and various proposals considered, modified and agreed by the participants are contained within this document. The International Network of Nuclear Structure and Decay Data (NSDD) Evaluators holds biennial meetings under the auspices of the IAEA, and consists of evaluation groups and data service centres in several countries. This network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration is included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS).

  6. Analysis of statistical model properties from discrete nuclear structure data

    OpenAIRE

    Firestone Richard B.

    2012-01-01

    Experimental M1, E1, and E2 photon strengths have been compiled from experimental data in the Evaluated Nuclear Structure Data File (ENSDF) and the Evaluated Gamma-ray Activation File (EGAF). Over 20,000 Weisskopf reduced transition probabilities were recovered from the ENSDF and EGAF databases. These transition strengths have been analyzed for their dependence on transition energies, initial and final level energies, spin/parity dependence, and nuclear deformation. ENSDF BE1W values were fou...

  7. Evaluation method of nuclear data: half-lives, gamma-ray intensities etc

    Energy Technology Data Exchange (ETDEWEB)

    Yoshizawa, Yasukazu; Miyatake, Osamu; Toyama, Masao

    1998-03-01

    The evaluation method has been studied. The basic problem is how to estimate and treat the systematic error. Nuclear decay data were evaluated. Eight practical examples of half-lives are shown in this report. (author)

  8. Status of nuclear data for actinides

    Energy Technology Data Exchange (ETDEWEB)

    Guzhovskii, B.Y.; Gorelov, V.P.; Grebennikov, A.N. [Russia Federal Nuclear Centre, Arzamas (Russian Federation)] [and others

    1995-10-01

    Nuclear data required for transmutation problem include many actinide nuclei. In present paper the analysis of neutron fission, capture, (n,2n) and (n,3n) reaction cross sections at energy region from thermal point to 14 MeV was carried out for Th, Pa, U, Np, Pu, Am and Cm isotops using modern evaluated nuclear data libraries and handbooks of recommended nuclear data. Comparison of these data indicates on substantial discrepancies in different versions of files, that connect with quality and completeness of original experimental data.

  9. Nuclear Structure Data for the Present Age

    Science.gov (United States)

    Baglin, Coral M.

    2005-05-01

    The US Nuclear Data Program maintains and provides easy and free access to several comprehensive databases that assist scientists to sift through and assess the vast quantity of published nuclear structure and decay data. These databases are an invaluable asset for nuclear-science experimentalists and theorists alike, and the recommended values provided for nuclear properties such as decay modes, level energies and lifetimes, and radiation properties can also be of great importance to specialists in other fields such as medicine, geophysics, and reactor design. The Evaluated Nuclear Structure Data File (ENSDF) contains experimental nuclear structure data for all known nuclides, evaluated by the US nuclear data program evaluators in collaboration with a number of international data groups; the Nuclear Science Reference (NSR) database provides complementary bibliographic information; the Experimental Unevaluated Nuclear Data Listing (XUNDL) exists to enable rapid access to experimental nuclear-structure data compiled from the most recent publications (primarily in high-spin physics). This paper presents an overview of the nuclear structure and decay data available through these databases, with emphasis on recent and forthcoming additions to and presentations of the available material.

  10. Evaluated data collections from ENSDF. [ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Ewbank, W. B.

    1979-01-01

    For several years the Nuclear Data Project has been maintaining an Evaluated Nuclear Structure Data File (ENSDF), which is designed to include critically evaluated values for most nuclear spectroscopic quantities. The information in ENSDF is the same as in the Nuclear Data Sheets, which illustrates two particular output formats (drawings and tables). Spectroscopic information for nuclei with A < 45 is put into ENSDF from the evaluations of Aizenberg-Selove and of Endt and van der Leun. An international network was organized to provide regular revisions of the data file. Computer facilities were developed to retrieve collections of evaluated data for special calculations or detailed examination.

  11. Methods of experimental settlement of contradicting data in evaluated nuclear data libraries

    Directory of Open Access Journals (Sweden)

    V. A. Libman

    2016-12-01

    Full Text Available The latest versions of the evaluated nuclear data libraries (ENDLs have contradictions concerning data about neutron cross sections. To resolve this contradiction we propose the method of experimental verification. This method is based on using of the filtered neutron beams and following measurement of appropriate samples. The basic idea of the method is to modify the suited filtered neutron beam so that the differences between the neutron cross sections in accordance with different ENDLs become measurable. Demonstration of the method is given by the example of cerium, which according to the latest versions of four ENDLs has significantly different total neutron cross section.

  12. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators

    Energy Technology Data Exchange (ETDEWEB)

    Ricard-McCutchan, E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Dimitriou, P. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Nichols, A. L. [Univ. of Surrey, Guildford (United Kingdom)

    2015-08-01

    The 21st meeting of the International Network of Nuclear Structure and Decay Data Evaluators was convened at the IAEA Headquarters, Vienna, from 20 to 24 April 2015 under the auspices of the IAEA Nuclear Data Section. This meeting was attended by 36 scientists from 15 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, data centre reports, various proposals considered, and actions agreed by the participants, as well as recommendations/conclusions are presented within this document.

  13. Nuclear Data Compilation for Beta Decay Isotope

    Science.gov (United States)

    Olmsted, Susan; Kelley, John; Sheu, Grace

    2015-10-01

    The Triangle Universities Nuclear Laboratory nuclear data group works with the Nuclear Structure and Decay Data network to compile and evaluate data for use in nuclear physics research and applied technologies. Teams of data evaluators search through the literature and examine the experimental values for various nuclear structure parameters. The present activity focused on reviewing all available literature to determine the most accurate half-life values for beta unstable isotopes in the A = 3-20 range. This analysis will eventually be folded into the ENSDF (Evaluated Nuclear Structure Data File). By surveying an accumulated compilation of reference articles, we gathered all of the experimental half-life values for the beta decay nuclides. We then used the Visual Averaging Library, a data evaluation software package, to find half-life values using several different averaging techniques. Ultimately, we found recommended half-life values for most of the mentioned beta decay isotopes, and updated web pages on the TUNL webpage to reflect these evaluations. To summarize, we compiled and evaluated literature reports on experimentally determined half-lives. Our findings have been used to update information given on the TUNL Nuclear Data Evaluation group website. This was an REU project with Triangle Universities Nuclear Laboratory.

  14. Reasons for 2011 Release of the Evaluated Nuclear Data Library (ENDL2011.0)

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hoffman, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Luu, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ormand, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Summers, N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-22

    LLNL's Computational Nuclear Physics Group and Nuclear Theory and Modeling Group have collaborated to create the 2011 release of the Evaluated Nuclear Data Library (ENDL2011). ENDL2011 is designed to sup- port LLNL's current and future nuclear data needs. This database is currently the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles, surpassing ENDL2009.0 [1]. The ENDL2011 release [2] contains 918 transport-ready eval- uations in the neutron sub-library alone. ENDL2011 was assembled with strong support from the ASC program, leveraged with support from NNSA science campaigns and the DOE/Offce of Science US Nuclear Data Pro- gram.

  15. Nuclear Data Sheets for 170Pt

    Science.gov (United States)

    Baglin, Coral M.

    1999-02-01

    Nuclear structure data pertaining to170Pt have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of170Pt supersedes the previous publication (Coral M. Baglin,Nuclear Data Sheets 77,125 (1996) (literature cutoff date October 1995)), and includes literature available by 17 February 1999. The newly incorporated references are: 98Se20, 98Ki20, 97Ju04, 96Bi07 and 95Au04. Three new data sets have been added, as follows:174Hg α decay,171Au p decay (1.02 ms), (HI,xnγ).

  16. Nuclear Data Sheets for 186W

    Science.gov (United States)

    Baglin, Coral M.

    1999-02-01

    Nuclear structure data pertaining to186W have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of186W supersedes the previous publication (C. Baglin,Nuclear Data Sheets 82,1 (1997) (literature cutoff date 31 August 1997)), and includes literature available by 17 February 1999. The newly incorporated references are: 98Wh02 (high-K structures), 97Ge15 (lower limit on T1/2for g.s.), 88GoZC (extensive new (n,n‧γ) data).

  17. Nuclear Data Sheets for A = 92

    Science.gov (United States)

    Baglin, Coral M.

    2012-10-01

    Nuclear structure and decay data pertaining to all nuclides with mass number A = 92 (As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd) have been compiled and evaluated, and incorporated into the ENSDF data file. All literature available by 15 September 2012 has been considered. This evaluation supersedes the previous publication for this mass chain (Coral M. Baglin, Nuclear Data Sheets 91, 423 (2000) (November 2000 cutoff date)), and subsequent unpublished reevaluations by C.M. Baglin for 92Kr (January 2004 literature cut-off) and 92Sr (August 2003 literature cut-off).

  18. Nuclear Data Sheets for 183Hg

    Science.gov (United States)

    Baglin, Coral M.

    2000-09-01

    Nuclear structure data pertaining to 183Hg have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 183Hg supersedes the previous publication (R.B. Firestone, Nuclear Data Sheets 65, 589 (1992) (literature cutoff date 9 January 1991)), and includes literature available by 25 September 2000. The newly incorporated references are: 1992BoZO, 1993Bi17, 1995Au04, 1995La10, 1995Sh04, 1999An10, 1999An36, 1999Ba45, 2000By02.

  19. Nuclear Data Sheets for 183Tl

    Science.gov (United States)

    Baglin, Coral M.

    2002-01-01

    Abstract: Nuclear structure data pertaining to 183Tl have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of 183Tl supersedes the previous publication (R.B. Firestone, Nuclear Data Sheets 65, 589 (1992) (literature cutoff date 9 January 1991)), and includes literature available by 1 January 2002. The newly incorporated references are: 2001Mu26, 2000Re04, 1999Ba45, 1998Ak04, 1995Au04, 1992BoZO, 1992BlZW, 1984ScZQ, 1980Sc09.

  20. Nuclear Data Sheets for 187Tl

    Science.gov (United States)

    Baglin, Coral M.

    1999-02-01

    Nuclear structure data pertaining to187Tl have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation of187Tl supersedes the previous publication (R. B. Fireston,Nuclear Data Sheets 62,159 (1991) (literature cutoff date September 1990)), and includes literature available by 17 February 1999. The newly incorporated references are: 98Ak04, 98Kr23, 97Au04, 95Au04, 95La08, 94Re18, 94La04, 94Re02, 92Sc25, 91Wa21.

  1. 2011 Release of the Evaluated Nuclear Data Library (ENDL2011.0)

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalles, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, J. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hoffman, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Navratil, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Nobre, G. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ormand, W. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Summers, N. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Vogt, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Barnowski, R. [Univ. of California, Berkeley, CA (United States)

    2015-05-12

    LLNL’s Computational Nuclear Physics Group and Nuclear Theory and Modeling Group have collaborated to produce the last of three major releases of LLNL’s evaluated nuclear database, ENDL2011. ENDL2011 is designed to support LLNL’s current and future nuclear data needs by providing the best nuclear data available to our programmatic customers. This library contains many new evaluations for radiochemical diagnostics, structural materials, and thermonuclear reactions. We have made an effort to eliminate all holes in reaction networks, allowing in-line isotopic creation and depletion calculations. We have striven to keep ENDL2011 at the leading edge of nuclear data library development by reviewing and incorporating new evaluations as they are made available to the nuclear data community. Finally, this release is our most highly tested release as we have strengthened our already rigorous testing regime by adding tests against IPPE Activation Ratio Measurements, many more new critical assemblies and a more complete set of classified testing (to be detailed separately).

  2. Proceedings of the 1991 symposium on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Baba, Mamoru [Tokyo Univ. (Japan); Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Japanese Nuclear Data Committee

    1992-03-15

    The 1991 Symposium on Nuclear data was held at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), on 28th and 29th of November 1991. This symposium was organized by Japanese Nuclear Data Committee and Nuclear Data Center, JAERI. In the oral session, presented were 15 papers on nuclear data activities in Thailand, status reviews of JENDL-3 and its special purpose files, OMEGA program and ESNIT promoted by JAERI and related nuclear data, reviews of nuclear theories, nuclear data in the intermediate energy region, topics on knowledge technology and reactor physics. In the poster session, twenty-three papers were presented, which were related to nuclear data measurements, benchmark tests of evaluated data and evaluation. All of the 38 papers are compiled in the proceedings.

  3. 2011.2 Revision of the Evaluated Nuclear Data Library (ENDL2011.2)

    Energy Technology Data Exchange (ETDEWEB)

    Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalles, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jurgenson, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-22

    LLNL's Computational Nuclear Physics Group and Nuclear Theory and Modeling Group have col- laborated to create the 2011.2 revised release of the Evaluated Nuclear Data Library (ENDL2011.2). ENDL2011.2 is designed to support LLNL's current and future nuclear data needs and will be em- ployed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. This database is currently the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. This library was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/O ce of Science's US Nuclear Data Program. This document lists the revisions made in ENDL2011.2 compared with the data existing in the original ENDL2011.0 release and the ENDL2011.1-rc4 re- lease candidate of April 2015. These changes are made in parallel with some similar revisions for ENDL2009.2.

  4. General Guidelines on Criteria for Adoption or Rejection of Evaluated Libraries and Data by the Nuclear Data Team

    Energy Technology Data Exchange (ETDEWEB)

    Neudecker, Denise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Conlin, Jeremy Lloyd [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gray, Mark Girard [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McCartney, Austin Paul [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Parsons, Donald Kent [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); White, Morgan Curtis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-04-12

    This memo contains general guidelines on what documentation and tools need to be in place as well as format and data testing requirements such that evaluated nuclear data sets or entire libraries can be adopted by the nuclear data team. Additional requirements beyond this memo might apply for specific nuclear data observables. These guidelines were established based on discussions between J.L. Conlin, M.G. Gray, A.P. McCartney, D. Neudecker, D.K. Parsons and M.C. White.

  5. 2009.3 Revision of the Evaluated Nuclear Data Library (ENDL2009.3)

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalle, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jurgenson, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-11-06

    LLNL's Computational Nuclear Data and Theory Group have created a 2009.3 revised release of the Evaluated Nuclear Data Library (ENDL2009.3). This library is designed to support LLNL's current and future nuclear data needs and will be employed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. The ENDL2009 database was the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. It was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/Office of Science's US Nuclear Data Program. This document lists the revisions and fixes made in a new release called ENDL2009.3, by com- paring with the existing data in the previous release ENDL2009.2. These changes are made in conjunction with the revisions for ENDL2011.3, so that both the .3 releases are as free as possible of known defects.

  6. 2009.1 Revision of the Evaluated Nuclear Data Library (ENDL2009.1)

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalles, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Summers, N. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-05-11

    LLNL’s Computational Nuclear Data and Theory Group have created a 2009.1 revised release of the Evaluated Nuclear Data Library (ENDL2009.1). This library is designed to support LLNL’s current and future nuclear data needs and will be employed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. The ENDL2009 database was the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. It was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/Office of Science’s US Nuclear Data Program. This document lists the revisions and fixes made in a new release called ENDL2009.1, by comparing with the existing data in the original release which is now called ENDL2009.0. These changes are made in conjunction with the revisions for ENDL2011.1, so that both the .1 releases are as free as possible of known defects.

  7. Nuclear data information-reference system NDX

    Energy Technology Data Exchange (ETDEWEB)

    Grebennikov, A.N.; Krut' ko, N.A.; Farafontov, G.G. [Russian Federal Nuclear Center, All-Russia Scientific Research Institute of Experimental Physics (VNIIEF), Sarov (Russian Federation)

    2002-08-01

    At present in the area of evaluated data support for nuclear and physics calculations, a wide arsenal of sources of various nuclear data is available in electronic form and used in practice. In essence, the data can be both the result of direct experimental measurements and estimates received from different theoretical models. The International Atomic Energy Agency (IAEA, Austria) distributes in electronic form both individual files of atomic nucleus structure data as well as libraries of evaluated data on the characteristics of particle-nucleus interactions. Developed at RFNC(Russian Federal Nuclear Center)-VNIIEF(All-Russia Scientific Research Institute of Experimental Physics) the information reference system of nuclear data, NDX (Nuclear Data eXpert studio) combines not only the evaluated data under a single graphic interface, but also specialized databases with information on nucleus structure, reaction energies, nuclei states et al. Graphic interface allows to represent both in table and graphic form practically the whole capacity of the magnitudes and dependencies stored and perform the comparison of these magnitudes. Computer codes included into the NDX system allow carrying out some evaluated data processing. The given system has been created using state-of-the-art programming techniques and represents a friendly tool for experts dealing with nuclear data issues. (author)

  8. Transport code and nuclear data in intermediate energy region

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, Akira; Odama, Naomitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Maekawa, F.; Ueki, K.; Kosaka, K.; Oyama, Y.

    1998-11-01

    We briefly reviewed the problems of intermediate energy nuclear data file and transport codes in connection with processing of the data. This is a summary of our group in the task force on JENDL High Energy File Integral Evaluation (JHEFIE). In this article we stress the necessity of the production of intermediate evaluated nuclear data file up to 3 GeV for the application of accelerator driven transmutation (ADT) system. And also we state the necessity of having our own transport code system to calculate the radiation fields using these evaluated files from the strategic points of view to keep our development of the ADT technology completely free from other conditions outside of our own such as imported codes and data with poor maintenance or unknown accuracy. (author)

  9. Identifiable Data Files - Denominator File

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Denominator File combines Medicare beneficiary entitlement status information from administrative enrollment records with third-party payer information and GHP...

  10. The Activities of the European Consortium on Nuclear Data Development and Analysis for Fusion

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, U., E-mail: ulrich.fischer@kit.edu [Karlsruhe Institute of Technology, Institute for Neutron Physic and Reactor Technology, 76344 Eggenstein-Leopoldshafen (Germany); Avrigeanu, M.; Avrigeanu, V. [Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), RO-077125 Magurele (Romania); Cabellos, O. [Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid, 28006 Madrid (Spain); Kodeli, I. [Jozef Stefan Institute (JSI), Jamova 39, 1000 Ljubljana (Slovenia); Koning, A. [Nuclear Research and Consultancy Group (NRG), Westerduinweg 3, 1755 LE Petten (Netherlands); Konobeyev, A.Yu. [Karlsruhe Institute of Technology, Institute for Neutron Physic and Reactor Technology, 76344 Eggenstein-Leopoldshafen (Germany); Leeb, H. [Technische Universitaet Wien, Atominstitut, Wiedner Hauptstrasse 8–10, 1040 Wien (Austria); Rochman, D. [Nuclear Research and Consultancy Group (NRG), Westerduinweg 3, 1755 LE Petten (Netherlands); Pereslavtsev, P. [Karlsruhe Institute of Technology, Institute for Neutron Physic and Reactor Technology, 76344 Eggenstein-Leopoldshafen (Germany); Sauvan, P. [Universidad Nacional de Educacion a Distancia, C. Juan del Rosal, 12, 28040 Madrid (Spain); Sublet, J.-C. [Euratom/CCFE Fusion Association, Culham Science Centre, OX14 3DB (United Kingdom); Trkov, A. [Jozef Stefan Institute (JSI), Jamova 39, 1000 Ljubljana (Slovenia); Dupont, E. [OECD Nuclear Energy Agency, Paris (France); Leichtle, D.; Izquierdo, J. [Fusion for Energy, Barcelona (Spain)

    2014-06-15

    This paper presents an overview of the activities of the European Consortium on Nuclear Data Development and Analysis for Fusion. The Consortium combines available European expertise to provide services for the generation, maintenance, and validation of nuclear data evaluations and data files relevant for ITER, IFMIF and DEMO, as well as codes and software tools required for related nuclear calculations.

  11. Nuclear Structure References (NSR) file. [Mostly information for input

    Energy Technology Data Exchange (ETDEWEB)

    Ewbank, W.B.

    1978-08-01

    The use of the Nuclear Structure References file by the Nuclear Data Project at ORNL is described. Much of the report concerns format information of interest only to those preparing input to the system or otherwise needing detailed knowledge of its internal structure. 17 figures. (RWR)

  12. Proceedings of the 1st conference on nuclear structure data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Firestone, R.B.; Shirley, V.S.; Dairiki, J.M. (eds.)

    1982-04-01

    The 1st Conference on Nuclear Structure Data Evaluation was organized by the Isotopes Project of the Lawrence Berkeley Laboratory in order to encourage the open discussion of the scientific aspects of ENSDF production and usage. Summaries of the roundtable discussion sessions, abstracts of the presented papers, and additional contributed papers are contained in these Proceedings.

  13. Nuclear Structure and Decay Data: Current Status and Future Perspectives

    Science.gov (United States)

    Kondev, Filip G.; International Nuclear Structure; Decay Data Network

    2006-03-01

    The nuclear structure databases provide physicists around the world with a useful collection of reliable and well documented datasets. The Evaluated Nuclear Structure Data File (ENSDF) database, produced by the International Nuclear Structure and Decay Data Network (NSDD) under the auspices of the International Atomic Energy Agency (IAEA), contains evaluated experimental information for all known nuclei. The bibliographical database Nuclear Science References (NSR) provides references to published data in the field of Nuclear Physics. The Experimental Unevaluated Nuclear Data List (XUNDL) provides a method for rapid access to formatted (compiled) data from recently published articles. Detailed information regarding these databases, as well as other products and services, can be found at the National Nuclear Data Center (NNDC) and IAEA web portals.

  14. 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.

  15. Nuclear Structure and Decay Data Working Group

    Science.gov (United States)

    Helmer, Richard G.

    1998-10-01

    Earlier this year, the U. S. Nuclear Data Program was reorganized; it now consists of a Coordinating Committee and three working groups. The Nuclear Structure and Decay Data Working Group consists of the persons at several U. S. laboratories and McMaster University who prepare the evaluated experimental structure and decay data that make up the Evaluated Nuclear Structure Data File (ENSDF), which is maintain at the National Nuclear Data Center. This Working Group is responsible for coordinating the work of the evaluators and approving improvements in the ENSDF format and data evaluation methodology. In this period of decreasing manpower, the Working Group helps set priorities for future work. While working to maintain the quality and currency of ENSDF, there is a need to be responsive to research ares of high current interest, such as data for astrophysics and high-spin levels. In support of astrophysics, the status of the decay data for atoms of interest is being determined and modifications of the ENSDF format will allow inclusion of data for the decay of ionized atoms. A compilation of published and unpublished data for high-spin levels is being created at Oak Ridge National Laboratory by D. Radford. The ENSDF evaluators may be able to make use of this compilation to improve the currency of ENSDF in this research area. For the case of super-deformed bands, a special publication of these data already exists and it is up-dated annually.

  16. NASA Thesaurus Data File

    Science.gov (United States)

    2012-01-01

    The NASA Thesaurus contains the authorized NASA subject terms used to index and retrieve materials in the NASA Aeronautics and Space Database (NA&SD) and NASA Technical Reports Server (NTRS). The scope of this controlled vocabulary includes not only aerospace engineering, but all supporting areas of engineering and physics, the natural space sciences (astronomy, astrophysics, planetary science), Earth sciences, and the biological sciences. The NASA Thesaurus Data File contains all valid terms and hierarchical relationships, USE references, and related terms in machine-readable form. The Data File is available in the following formats: RDF/SKOS, RDF/OWL, ZThes-1.0, and CSV/TXT.

  17. International scope of data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Pearlstein, S.

    1985-01-01

    This paper summarizes the principal national and international evaluation activities that contributed to the widespread use of evaluated data files. Emphasis is placed on those efforts that have become best known through the availability of data, documentation, and computer codes. Early attempts at nuclear data evaluation consisted of improving communication among measurers of similar information. As reactor methodology proceeded from a four factor formula to multi-group theory the demand for detailed representation of nuclear data increased. The systematic access to large volumes of data required placing the information in computer readable formats.

  18. Development of a new nuclear data library based on ROOT

    Science.gov (United States)

    Park, Tae-Sun; Min, Kyung Joo; In, Eun Jin; Bak, Sang-In; Hong, Seung-Woo

    2017-09-01

    We develop a new C++ nuclear data library for the Evaluated Nuclear Data File (ENDF) data, which we refer to as TNudy. Main motivation of the development is to provide systematic, powerful and intuitive interfaces and functionalities for browsing, visualizing and manipulating the detailed information embodied in the ENDF. To achieve this aim efficiently, the TNudy project is based on the ROOT system. TNudy is still in the stage of development, and the current status and future plans will be presented.

  19. Nuclear decay data for dosimetry calculation; Data for radionuclides with half-lives less than 10 minutes

    OpenAIRE

    遠藤 章; Eckerman, K. F.

    2007-01-01

    Nuclear decay data used for dose calculations have been compiled for 214 radionuclides with half-lives of less than 10 minutes. The decay data were assembled from decay data sets of the Evaluated Nuclear Structure Data File (ENSDF), the latest version as of May, 2007. Basic nuclear properties in the ENSDF that are particularly important for calculating the energies and intensities of radiations were examined and updated by referring to NUBASE2003/AME2003, the database for nuclear and decay pr...

  20. Report to the US Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data, 1986

    Energy Technology Data Exchange (ETDEWEB)

    None

    1987-05-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during calendar year 1986. Comments and observations are provided on operating experience at nuclear power plants and other NRC licensees, including results from selected AEOD studies; summaries of abnormal occurrences involving US nuclear plants; reviews of licensee event reports and their quality, reactor scram experience from 1984 to 1986, engineered safety features actuations, and the trends and patterns analysis program; and assessments of nonreactor and medical misadministration events. In addition, the report provides the year-end status of all recommendations included in AEOD studies, and listings of all AEOD reports issued from 1980 through 1986.

  1. Assessment of the current status of basic nuclear data compilations

    Energy Technology Data Exchange (ETDEWEB)

    Riemer, R.L.

    1992-12-31

    The Panel on Basic Nuclear Data Compilations believes that it is important to provide the user with an evaluated nuclear database of the highest quality, dependability, and currency. It is also important that the evaluated nuclear data are easily accessible to the user. In the past the panel concentrated its concern on the cycle time for the publication of A-chain evaluations. However, the panel now recognizes that publication cycle time is no longer the appropriate goal. Sometime in the future, publication of the evaluated A-chains will evolve from the present hard-copy Nuclear Data Sheets on library shelves to purely electronic publication, with the advent of universal access to terminals and the nuclear databases. Therefore, the literature cut-off date in the Evaluated Nuclear Structure Data File (ENSDF) is rapidly becoming the only important measure of the currency of an evaluated A-chain. Also, it has become exceedingly important to ensure that access to the databases is as user-friendly as possible and to enable electronic publication of the evaluated data files. Considerable progress has been made in these areas: use of the on-line systems has almost doubled in the past year, and there has been initial development of tools for electronic evaluation, publication, and dissemination. Currently, the nuclear data effort is in transition between the traditional and future methods of dissemination of the evaluated data. Also, many of the factors that adversely affect the publication cycle time simultaneously affect the currency of the evaluated nuclear database. Therefore, the panel continues to examine factors that can influence cycle time: the number of evaluators, the frequency with which an evaluation can be updated, the review of the evaluation, and the production of the evaluation, which currently exists as a hard-copy issue of Nuclear Data Sheets.

  2. Nuclear energy data 2011

    CERN Document Server

    2011-01-01

     . Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of statistics and country reports on nuclear energy, contains official information provided by OECD member country governments on plans for new nuclear plant construction, nuclear fuel cycle developments as well as current and projected nuclear generating capacity to 2035. For the first time, it includes data for Chile, Estonia, Israel and Slovenia, which recently became OECD members. Key elements of this edition show a 2% increase in nuclear and total electricity production and a 0.5% increase in nuclear generating ca

  3. Improvement of evaluated neutron nuclear data for {sup 237}Np and {sup 241}Am

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Iwamoto, Osamu; Hasegawa, Akira [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-01-01

    The nuclear data of {sup 237}Np and {sup 241}Am that are particularly important among the minor actinides were investigated by comparing JENDL-3.2 with the recent evaluated data and available experimental data. As a result of the study, several defects of JENDL-3.2 data were revealed. They were improved on the basis of experimental data or recent evaluated data. For the both nuclides, main quantities revised in the present work were the resonance parameters, cross sections, angular and energy distributions of secondary neutrons, number of neutrons per fission. The data were given in the neutron energy range from 10{sup -5} eV to 20 MeV, and compiled in the ENDF-6 format. (author)

  4. Nuclear energy data 2010

    CERN Document Server

    2010-01-01

    This 2010 edition of Nuclear Energy Data , the OECD Nuclear Energy Agency's annual compilation of official statistics and country reports on nuclear energy, provides key information on plans for new nuclear plant construction, nuclear fuel cycle developments as well as current and projected nuclear generating capacity to 2035 in OECD member countries. This comprehensive overview provides authoritative information for policy makers, experts and other interested stakeholders.

  5. Nuclear Data Sheets for A = 198

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Xiaolong; Kang, Mengxiao

    2016-03-15

    The 2009 version of Nuclear Data Sheets for A=198 (2009Hu11) has been updated and revised on the basis of the experimental results from various decay and reaction studies before December 2014. The experimental data for all known nuclei with mass number A=198 (Re,Os,Ir,Pt,Au,Hg,Tl,Pb,Bi,Po,At,Rn,Fr) have been revised, updated, and incorporated into the ENSDF data file. The experimental methods, references, Jπ arguments, and necessary comments are given in the text. The adopted levels for 198Re and 198Fr are firstly presented in this evaluation. In addition, Q values have been updated based on 2012Wa38.

  6. Update and evaluation of decay data for spent nuclear fuel analyses

    Science.gov (United States)

    Simeonov, Teodosi; Wemple, Charles

    2017-09-01

    Studsvik's approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group cross-sections, calculated by the CASMO5 or HELIOS2 lattice transport codes, with core irradiation history data from the SIMULATE5 reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code SNF to predict spent nuclear fuel characteristics. Recent advances in the generation procedure for the SNF decay data are presented. The SNF decay data includes basic data, such as decay constants, atomic masses and nuclide transmutation chains; radiation emission spectra for photons from radioactive decay, alpha-n reactions, bremsstrahlung, and spontaneous fission, electrons and alpha particles from radioactive decay, and neutrons from radioactive decay, spontaneous fission, and alpha-n reactions; decay heat production; and electro-atomic interaction data for bremsstrahlung production. These data are compiled from fundamental (ENDF, ENSDF, TENDL) and processed (ESTAR) sources for nearly 3700 nuclides. A rigorous evaluation procedure of internal consistency checks and comparisons to measurements and benchmarks, and code-to-code verifications is performed at the individual isotope level and using integral characteristics on a fuel assembly level (e.g., decay heat, radioactivity, neutron and gamma sources). Significant challenges are presented by the scope and complexity of the data processing, a dearth of relevant detailed measurements, and reliance on theoretical models for some data.

  7. Update and evaluation of decay data for spent nuclear fuel analyses

    Directory of Open Access Journals (Sweden)

    Simeonov Teodosi

    2017-01-01

    Full Text Available Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group cross-sections, calculated by the CASMO5 or HELIOS2 lattice transport codes, with core irradiation history data from the SIMULATE5 reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code SNF to predict spent nuclear fuel characteristics. Recent advances in the generation procedure for the SNF decay data are presented. The SNF decay data includes basic data, such as decay constants, atomic masses and nuclide transmutation chains; radiation emission spectra for photons from radioactive decay, alpha-n reactions, bremsstrahlung, and spontaneous fission, electrons and alpha particles from radioactive decay, and neutrons from radioactive decay, spontaneous fission, and alpha-n reactions; decay heat production; and electro-atomic interaction data for bremsstrahlung production. These data are compiled from fundamental (ENDF, ENSDF, TENDL and processed (ESTAR sources for nearly 3700 nuclides. A rigorous evaluation procedure of internal consistency checks and comparisons to measurements and benchmarks, and code-to-code verifications is performed at the individual isotope level and using integral characteristics on a fuel assembly level (e.g., decay heat, radioactivity, neutron and gamma sources. Significant challenges are presented by the scope and complexity of the data processing, a dearth of relevant detailed measurements, and reliance on theoretical models for some data.

  8. Nuclear Data Sheets for A = 81

    Science.gov (United States)

    Baglin, Coral M.

    2008-10-01

    Nuclear structure data pertaining to all nuclei with mass number A = 81 (Zn, Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb) have been compiled and evaluated and incorporated into the ENSDF data file. This publication for A = 81 supersedes the previous publication (Coral M. Baglin, Nuclear Data Sheets79, 447 (1996), literature cutoff 1 November 1996) and the subsequent updates by C. Baglin for 81Y (literature cutoff 8 October 1998) and 81Zr (literature cutoff 24 March 2000). All literature available prior to 15 August 2008 has been considered. Subsequent to previous A = 81 evaluations, excited states have been reported for the first time in 81Ga, and knowledge of excited state properties for 81Y and 81Zr has been significantly expanded. However, the expected ɛ+β decay of 81Zr has yet to be studied.

  9. The NUBASE2016 evaluation of nuclear properties

    Science.gov (United States)

    Audi, G.; Kondev, F. G.; Wang, Meng; Huang, W. J.; Naimi, S.

    2017-03-01

    This paper presents the NUBASE2016 evaluation that contains the recommended values for nuclear and decay properties of 3437 nuclides in their ground and excited isomeric (T1/2 >= 100 ns) states. All nuclides for which any experimental information is known were considered. NUBASE2016 covers all data published by October 2016 in primary (journal articles) and secondary (mainly laboratory reports and conference proceedings) references, together with the corresponding bibliographical information. During the development of NUBASE2016, the data available in the 'Evaluated Nuclear Structure Data File' (ENSDF) database were consulted and critically assessed for their validity and completeness. Furthermore, a large amount of new data and some older experimental results that were missing from ENSDF were compiled, evaluated and included in NUBASE2016. The atomic mass values were taken from the 'Atomic Mass Evaluation' (AME2016, second and third parts of the present issue). In cases where no experimental data were available for a particular nuclide, trends in the behavior of specific properties in neighboring nuclides (TNN) were examined. This approach allowed to estimate values for a range of properties that are labeled in NUBASE2016 as 'non-experimental' (flagged '#'). Evaluation procedures and policies used during the development of this database are presented, together with a detailed table of recommended values and their uncertainties. AMDC: http://amdc.impcas.ac.cn/ Contents The NUBASE2016 evaluation of nuclear propertiesAcrobat PDF (1.1 MB) Table I. The NUBASE2016 table of nuclear and decay propertiesAcrobat PDF (706 KB)

  10. Nuclear energy data 2005

    CERN Document Server

    Publishing, OECD

    2005-01-01

    This 2005 edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, offers a projection horizon lengthened to 2025 for the first time.  It presents the reader with a comprehensive overview on the status and trends in nuclear electricity generation in OECD countries and in the various sectors of the nuclear fuel cycle.

  11. Compilation of requests for nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Weston, L.W.; Larson, D.C. [eds.

    1993-02-01

    This compilation represents the current needs for nuclear data measurements and evaluations as expressed by interested fission and fusion reactor designers, medical users of nuclear data, nuclear data evaluators, CSEWG members and other interested parties. The requests and justifications are reviewed by the Data Request and Status Subcommittee of CSEWG as well as most of the general CSEWG membership. The basic format and computer programs for the Request List were produced by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory. The NNDC produced the Request List for many years. The Request List is compiled from a computerized data file. Each request has a unique isotope, reaction type, requestor and identifying number. The first two digits of the identifying number are the year in which the request was initiated. Every effort has been made to restrict the notations to those used in common nuclear physics textbooks. Most requests are for individual isotopes as are most ENDF evaluations, however, there are some requests for elemental measurements. Each request gives a priority rating which will be discussed in Section 2, the neutron energy range for which the request is made, the accuracy requested in terms of one standard deviation, and the requested energy resolution in terms of one standard deviation. Also given is the requestor with the comments which were furnished with the request. The addresses and telephone numbers of the requestors are given in Appendix 1. ENDF evaluators who may be contacted concerning evaluations are given in Appendix 2. Experimentalists contemplating making one of the requested measurements are encouraged to contact both the requestor and evaluator who may provide valuable information. This is a working document in that it will change with time. New requests or comments may be submitted to the editors or a regular CSEWG member at any time.

  12. Update and evaluation of decay data for spent nuclear fuel analyses

    OpenAIRE

    Simeonov Teodosi; Wemple Charles

    2017-01-01

    Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group cross-sections, calculated by the CASMO5 or HELIOS2 lattice transport codes, with core irradiation history data from the SIMULATE5 reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code SNF to predict spent nuclear fuel characteristics. Recent advances in the generation procedure for the SNF decay data are presented. The SNF decay data in...

  13. The role of nuclear data for fusion technology studies

    Energy Technology Data Exchange (ETDEWEB)

    Forrest, Robin A., E-mail: r.forrest@iaea.org [International Atomic Energy Agency, Vienna International Centre, P.O. Box 100, A-1400 Vienna (Austria)

    2011-10-15

    Highlights: > Nuclear data are of fundamental importance in studies of nuclear technology. > Data libraries cover: experiments (EXFOR), theory (RIPL) and evaluations (ENDF). > Libraries are general purpose or special purpose (decay, dosimetry and activation). > Activation files contain many reactions, only a fraction needs to be known precisely. > Covariance data are important, but details of formatting are being worked out. - Abstract: Nuclear data are of fundamental importance in studies of nuclear technology. In these studies, experiments to measure cross sections and decay properties and simulations of the design of fission power plants, fusion devices and accelerators are included. The large amount of data required is stored in computer readable formats in data libraries and the most common of these are the general purpose files used for neutronics or transport calculations. These files also contain the standards against which most measurements are made. The other class of libraries are the special purpose ones containing decay data, fission yields and cross section data for dosimetry and activation. This paper gives examples of what data are available and describes their use for various fusion applications. The focus will be on neutron-induced activation data with examples of how the reactions of particular importance can be identified. All data should be accompanied by estimates of the uncertainty. This is best achieved by including covariance data; however, this is extremely challenging and only a subset of the available data has such uncertainty data. The general principles of how covariance matrices are used are outlined.

  14. Data Testing CIELO Evaluations with ICSBEP Benchmarks

    Energy Technology Data Exchange (ETDEWEB)

    Kahler, Albert Comstock [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-09

    We review criticality data testing performed at Los Alamos with a combination of ENDF/B-VII.1 + potential CIELO nuclear data evaluations. The goal of CIELO is to develop updated, best available evaluated nuclear data files for 1H, 16O, 56Fe, 235,238U and 239Pu. because the major international evaluated nuclear data libraries don’t agree on the internal cross section details of these most important nuclides.

  15. INDC International Nuclear Data Committee

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, A. [Univ. of Surrey, Guildford (United Kingdom); McCutchan, E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Dimitriou, P. [Intl Atomic Energy Agency (IAEA), Vienna (Austria)

    2017-12-11

    The 22nd meeting of the International Network of Nuclear Structure and Decay Data Evaluators was convened at the Lawrence Berkeley National Laboratory, Berkeley, USA, from 22 to 26 May 2017 under the auspices of the IAEA Nuclear Data Section. This meeting was attended by 38 scientists from 12 Member States and the IAEA, all of whom are concerned primarily with the measurement, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, data centre reports, various proposals considered, technical discussions, actions agreed by the participants, and the resulting recommendations/conclusions are presented within this document.

  16. Nuclear Data Sheets for A = 195

    Science.gov (United States)

    Huang, Xiaolong; Kang, Mengxiao

    2014-09-01

    Experimental structure and decay data for all nuclides with mass number A=195 (Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po, At, Rn) have been revised, updated, and incorporated into the ENSDF data file. All literature available by March 2014 has been considered. This evaluation supersedes the previous one for this mass chain (Zhou Chunmei, Nuclear Data Sheets 86, 645 (1999), 1999Zh11). The detailed level schemes, decay schemes, experimental reaction and decay data on which they are based are summarized and presented here. References, Jπ arguments, and comments are given in the text. No excited state data are yet available for 195Re and 195Rn. The adopted levels for 195At are firstly presented in this evaluation. In addition, Q values have been updated based on 2012Wa38.

  17. Nuclear Data Sheets for A = 195

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Xiaolong; Kang, Mengxiao

    2014-09-15

    Experimental structure and decay data for all nuclides with mass number A=195 (Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po, At, Rn) have been revised, updated, and incorporated into the ENSDF data file. All literature available by March 2014 has been considered. This evaluation supersedes the previous one for this mass chain (Zhou Chunmei, Nuclear Data Sheets 86, 645 (1999), 1999Zh11). The detailed level schemes, decay schemes, experimental reaction and decay data on which they are based are summarized and presented here. References, Jπ arguments, and comments are given in the text. No excited state data are yet available for {sup 195}Re and {sup 195}Rn. The adopted levels for {sup 195}At are firstly presented in this evaluation. In addition, Q values have been updated based on 2012Wa38.

  18. NUCLEAR DATA REVIEW

    Energy Technology Data Exchange (ETDEWEB)

    HOLDEN,N.E.

    2004-12-01

    Non-neutron nuclear data are periodically reviewed and evaluated. The recommended values are published in the Table of the Isotopes of the Chemical Rubber Company's Handbook of Chemistry and Physics. A 2004 review has begun to re-examine some data of interest to the International Union of Geological Sciences (IUGS) sub-commission on Geochronology dealing with radioactive decay constants and isotopic abundance ratios. Among the decay constants that are being evaluated are those of the following nuclides: {sup 40}K, {sup 87}Rb, {sup 138}La, {sup 147}Sm, {sup 176}Lu, {sup 174}Hf, {sup 187}Re, {sup 190}Pt, {sup 232}Th, {sup 235}U, {sup 238}U.

  19. Deuteron nuclear data for the design of accelerator-based neutron sources: Measurement, model analysis, evaluation, and application

    Science.gov (United States)

    Watanabe, Yukinobu; Kin, Tadahiro; Araki, Shouhei; Nakayama, Shinsuke; Iwamoto, Osamu

    2017-09-01

    A comprehensive research program on deuteron nuclear data motivated by development of accelerator-based neutron sources is being executed. It is composed of measurements of neutron and gamma-ray yields and production cross sections, modelling of deuteron-induced reactions and code development, nuclear data evaluation and benchmark test, and its application to medical radioisotopes production. The goal of this program is to develop a state-of-the-art deuteron nuclear data library up to 200 MeV which will be useful for the design of future (d,xn) neutron sources. The current status and future plan are reviewed.

  20. The Decay Data Evaluation Project

    Science.gov (United States)

    Browne, E.

    1999-10-01

    Nuclear scientists from France, Germany, the United Kingdom, and the United States have joined their efforts to evaluate decay data for radionuclides specifically used in applied research and detector calibrations. The purpose of this collaboration, the Decay Data Evaluation Project (DDEP), is to produce recommended values, and to suggest new measurements for data that are unsatisfactory. Uniformity and reproducibility are features of importance for this work. These features, as well as the general scope of this project and its relation to the Evaluated Nuclear Structure Data File (ENSDF) will be presented and illustrated with examples. This work is presented on behalf of the Decay Data Evaluation Project. Work supported in part by the US Department of Energy under contract number DEAC03-76SF00098.

  1. Nuclear data interface retrospective

    Energy Technology Data Exchange (ETDEWEB)

    Gray, Mark G [Los Alamos National Laboratory

    2008-01-01

    The Nuclear Data Interface (NDI) code library and data formats are the standards for multigroup nuclear data at Los Alamos National Laboratory. NDI's analysis, design, implementation, testing, integration, and maintenance required a ten person-year and ongoing effort by the Nuclear Data Team. Their efforts provide a unique, contemporary experience in producing a standard component library. In reflection upon that experience at NDI's decennial, we have identified several factors critical to NDI's success: it addressed real problems with appropriate simplicity, it fully supported all users, it added extra value through the code to the raw nuclear data, and its team went the distance from analysis through maintenance. In this report we review these critical success factors and discuss their implications for future standardization projects.

  2. Status of experimental data of proton-induced reactions for intermediate-energy nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Yukinobu; Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan); Yamano, Naoki; Fukahori, Tokio

    1998-11-01

    The present status of experimental data of proton-induced reactions is reviewed, with particular attention to total reaction cross section, elastic and inelastic scattering cross section, double-differential particle production cross section, isotope production cross section, and activation cross section. (author)

  3. Berkeley Nuclear Data Cloud

    Energy Technology Data Exchange (ETDEWEB)

    2017-04-27

    The software was developed to serve and curate arbitrarily large datasets comprising data acquired from various mobile platforms. The software is contained in a number of server and client libraries. The former manage the ingestion, indexing, querying, and serving of the data. The latter libraries are distributed for Linux, Mac OSX, and Windows and enable users to interact with data downloaded from the service either in the form of an HDF5 file or streamed in a BSON data chunk. Using the Berkeley Data Cloud, researchers from varying fields can collaborate, compare results and curate both their raw data and the derived products of their analysis.

  4. Nuclear Data Evaluation for Mass Chain A=217:Odd-Proton Nuclei.

    Directory of Open Access Journals (Sweden)

    Sherif S Nafee

    Full Text Available Thallium (81(217Tl, Bismuth (83(217Bi, Astatine (85(217At, Francium (87(217Fr, Actinium (89(217Ac and Protactinium (91(217Pa are of odd-proton numbers among the mass chain A = 217. In the present work, the half-lives and gamma transitions for the six nuclei have been studied and adopted based on the recently published interactions or unevaluated nuclear data sets XUNDL. The Q (α has been updated based on the recent published work of the Atomic Mass Evaluation AME2012 as well. Moreover, the total conversion electrons as well as the K-Shell to L-Shell, L-Shell to M-Shell and L-Shell to N-Shell Conversion Electron Ratios have been calculated using BrIcc code v2.3. An updated skeleton decay scheme for each of the above nuclei has been presented here. The decay hindrance factors (HF calculated using the ALPHAD program, which is available from Brookhaven National Laboratory's website, have been calculated for the α- decay data sets for (221Fr-, (221Ac- and (221Pa-α-decays.

  5. Nuclear Data Evaluation for Mass Chain A=217:Odd-Proton Nuclei.

    Science.gov (United States)

    Nafee, Sherif S; Shaheen, Salem A; Al-Ramady, Amir M

    2016-01-01

    Thallium (81(217)Tl, Bismuth (83(217)Bi), Astatine (85(217)At), Francium (87(217)Fr), Actinium (89(217)Ac) and Protactinium (91(217)Pa) are of odd-proton numbers among the mass chain A = 217. In the present work, the half-lives and gamma transitions for the six nuclei have been studied and adopted based on the recently published interactions or unevaluated nuclear data sets XUNDL. The Q (α) has been updated based on the recent published work of the Atomic Mass Evaluation AME2012 as well. Moreover, the total conversion electrons as well as the K-Shell to L-Shell, L-Shell to M-Shell and L-Shell to N-Shell Conversion Electron Ratios have been calculated using BrIcc code v2.3. An updated skeleton decay scheme for each of the above nuclei has been presented here. The decay hindrance factors (HF) calculated using the ALPHAD program, which is available from Brookhaven National Laboratory's website, have been calculated for the α- decay data sets for (221)Fr-, (221)Ac- and (221)Pa-α-decays.

  6. Role of the National Nuclear Data Center in the field of nuclear waste transmutation

    Energy Technology Data Exchange (ETDEWEB)

    Rose, P.F.

    1980-01-01

    This report discusses the role of The National Nuclear Data Center (NNDC), formerly the National Neutron Cross Section Center. The NNDC collates and analyzes nuclear physics information for basic and applied research scientists. The NNDC performs functions that are characteristic of an information analysis center, namely bibliographic searches, data compilation, and critical appraisal of available information. Such compilations and searches are of unique importance for investigators in the field of nuclear waste transmutation. In addition, the NNDC issues publications, provides technical support to its sponsors, and conducts seminars on important topics. A primary concern of the NNDC is the timely production and revision of reference nuclear data. The NNDC coordinates the Cross Section Evaluation Working Group (CSEWG), a cooperative effort of over 20 laboratories, and the Nuclear Data Network (NDN), a group of US Nuclear Data Centers involved in the study of nuclear structure. The NNDC also interfaces with similar groups outside the United States in activities contributing to documented computerized reference data files. The Department of Energy has established the NNDC as the Center to service requests from the research community for bibliographic and data retrievals for neutron, charged particle, nuclear structure, and radioactive decay data.

  7. Proceedings of the 2000 symposium on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Yamano, Naoki (ed.) [Sumitomo Atomic Energy Industries, Ltd., Tokyo (Japan); Fukahori, Tokio (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    The 2000 Symposium on Nuclear Data was held at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), on 16th and 17th of November 2000. Japanese Nuclear Data Committee and Nuclear Data Center, JAERI organized this symposium. In the oral sessions, presented were 18 papers on topics of recent experiments, status of JENDL-3.3 and JENDL High Energy File, benchmark tests of JENDL-3.2, international activities and other subjects. In the poster session, presented were 40 papers concerning experiments, evaluations, benchmark tests and on-line database on nuclear data. Those presented papers are compiled in the proceedings. The 58 of the presented papers are indexed individually. (J.P.N.)

  8. Evaluation and assessment of 25 years of environmental radioactivity monitoring data at Tarapur (India) nuclear site.

    Science.gov (United States)

    Rao, D D; Baburajan, A; Sudheendran, V; Verma, P C; Hegde, A G

    2010-08-01

    The evaluation and assessment of monitoring data generated over a period of 1983-2007 (25 years) of a nuclear facility is presented. Time trends of particulate radioactivity, correlation between (137)Cs in discharge canal seawater and station discharged activity and correlation of (137)Cs, (60)Co, and (131)I in marine species such as sponge and Nerita (gastropod) and corresponding discharged activity are discussed. The concentration of (137)Cs and (131)I in seawater versus biota are discussed. A good correlation between (137)Cs in seawater and (137)Cs in liquid waste discharged was observed (R(2) = 0.8, p Nerita and discharged concentration of (137)Cs, (131)I and (60)Co (R(2) = 0.55-0.73 and p < 0.001). The measurements over the years indicated that there is no accumulation of radionuclides in either the terrestrial or aquatic environments. The mean (137)Cs decreased from the pre-operational levels: 7.0-3.6 Bq kg(-1) in soil, 0.91-0.016 Bq L(-1) in milk and 0.28-0.036 Bq kg(-1) in vegetation. Similarly, the mean (90)Sr in these matrixes decreased from 3.9 to 0.26 Bq kg(-1); 0.37-0.011 Bq L(-1) and 0.34-0.022 Bq kg(-1) respectively. Cesium-137 of about 700 microBq m(-3) was measured in the air filter disks during 1986 and there was a decrease of three orders of magnitude in concentration over the 25 years. The evaluation of environmental data indicated that the radionuclide concentrations and potential impacts, in terms of effective dose to the members of public, have significantly reduced since 1969. Copyright 2010 Elsevier Ltd. All rights reserved.

  9. Evaluation and assessment of 25 years of environmental radioactivity monitoring data at Tarapur (India) nuclear site

    Energy Technology Data Exchange (ETDEWEB)

    Rao, D.D., E-mail: raoddev@rediffmail.co [Environmental Survey Laboratory, Tarapur Atomic Power Station Staff Colony, TAPP (Post), Thane 401 504 (Dist.), Maharashtra State (India); Baburajan, A.; Sudheendran, V. [Environmental Survey Laboratory, Tarapur Atomic Power Station Staff Colony, TAPP (Post), Thane 401 504 (Dist.), Maharashtra State (India); Verma, P.C.; Hegde, A.G. [Health Physics Division, Health, Safety and Environment Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India)

    2010-08-15

    The evaluation and assessment of monitoring data generated over a period of 1983-2007 (25 years) of a nuclear facility is presented. Time trends of particulate radioactivity, correlation between {sup 137}Cs in discharge canal seawater and station discharged activity and correlation of {sup 137}Cs, {sup 60}Co, and {sup 131}I in marine species such as sponge and Nerita (gastropod) and corresponding discharged activity are discussed. The concentration of {sup 137}Cs and {sup 131}I in seawater versus biota are discussed. A good correlation between {sup 137}Cs in seawater and {sup 137}Cs in liquid waste discharged was observed (R{sup 2} = 0.8, p < 0.001). Similarly, correlation was good for Nerita and discharged concentration of {sup 137}Cs, {sup 131}I and {sup 60}Co (R{sup 2} = 0.55-0.73 and p < 0.001). The measurements over the years indicated that there is no accumulation of radionuclides in either the terrestrial or aquatic environments. The mean {sup 137}Cs decreased from the pre-operational levels: 7.0-3.6 Bq kg{sup -1} in soil, 0.91-0.016 Bq L{sup -1} in milk and 0.28-0.036 Bq kg{sup -1} in vegetation. Similarly, the mean {sup 90}Sr in these matrixes decreased from 3.9 to 0.26 Bq kg{sup -1}; 0.37-0.011 Bq L{sup -1} and 0.34-0.022 Bq kg{sup -1} respectively. Cesium-137 of about 700 {mu}Bq m{sup -3} was measured in the air filter disks during 1986 and there was a decrease of three orders of magnitude in concentration over the 25 years. The evaluation of environmental data indicated that the radionuclide concentrations and potential impacts, in terms of effective dose to the members of public, have significantly reduced since 1969.

  10. Nuclear Data Sheets for A = 166

    Energy Technology Data Exchange (ETDEWEB)

    Baglin, Coral M.

    2008-05-01

    Nuclear structure data pertaining to all known A = 166 nuclides (Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt) have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation for A = 166 supersedes the previous publication (E.N. Shurshikov and N.V. Timofeeva, Nuclear Data Sheets 67, 45 (1992) (literature cutoff date 1 October 1990)) and the revision by C.M. Baglin of {sup 166}W (literature cutoff data 16 April 2000). It includes literature available by 1 March 2008. Subsequent to the previous evaluation, {sup 166}Gd has been observed for the first time and the first observations of excited states in {sup 166}Tb, {sup 166}Re, {sup 166}Os and {sup 166}Ir have been reported: also, knowledge of collective structure in {sup 166}Dy. {sup 166}Ho, {sup 1676}Er, {sup 166}Tm, {sup 166}Yb, {sup 166}Lu, {sup 166}Hf, and {sup 166}Ta has been considerably expanded. However, the structure suggested here for {sup 166}Re is highly tentative and a further, more detailed study of {alpha} decay into (and out of) {sup 166}Re could be informative.

  11. Nuclear Data Sheets for A = 166

    Science.gov (United States)

    Baglin, Coral M.

    2008-05-01

    Nuclear structure data pertaining to all known A = 166 nuclides (Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt) have been compiled and evaluated, and incorporated into the ENSDF data file. This evaluation for A = 166 supersedes the previous publication (E.N. Shurshikov and N.V. Timofeeva, Nuclear Data Sheets67, 45 (1992) (literature cutoff date 1 October 1990)) and the revision by C.M. Baglin of 166W (literature cutoff date 16 April 2000). It includes literature available by 1 March 2008. Subsequent to the previous evaluation, 166Gd has been observed for the first time and the first observations of excited states in 166Tb, 166Re, 166Os and 166Ir have been reported; also, knowledge of collective structure in 166Dy, 166Ho, 166Er, 166Tm, 166Yb, 166Lu, 166Hf, and 166Ta has been considerably expanded. However, the structure suggested here for 166Re is highly tentative and a further, more detailed study of α decay into (and out of) 166Re could be informative.

  12. Evaluation of clinical data in childhood asthma. Application of a computer file system

    Energy Technology Data Exchange (ETDEWEB)

    Fife, D.; Twarog, F.J.; Geha, R.S.

    1983-10-01

    A computer file system was used in our pediatric allergy clinic to assess the value of chest roentgenograms and hemoglobin determinations used in the examination of patients and to correlate exposure to pets and forced hot air with the severity of asthma. Among 889 children with asthma, 20.7% had abnormal chest roentgenographic findings, excluding hyperinflation and peribronchial thickening, and 0.7% had abnormal hemoglobin values. Environmental exposure to pets or forced hot air was not associated with increased severity of asthma, as assessed by five measures of outcome: number of medications administered, requirement for corticosteroids, frequency of clinic visits, frequency of emergency room visits, and frequency of hospitalizations.

  13. On the use of Bayesian Monte-Carlo in evaluation of nuclear data

    Directory of Open Access Journals (Sweden)

    De Saint Jean Cyrille

    2017-01-01

    Full Text Available As model parameters, necessary ingredients of theoretical models, are not always predicted by theory, a formal mathematical framework associated to the evaluation work is needed to obtain the best set of parameters (resonance parameters, optical models, fission barrier, average width, multigroup cross sections with Bayesian statistical inference by comparing theory to experiment. The formal rule related to this methodology is to estimate the posterior density probability function of a set of parameters by solving an equation of the following type: pdf(posterior ∼ pdf(prior × a likelihood function. A fitting procedure can be seen as an estimation of the posterior density probability of a set of parameters (referred as x→ knowing a prior information on these parameters and a likelihood which gives the probability density function of observing a data set knowing x→. To solve this problem, two major paths could be taken: add approximations and hypothesis and obtain an equation to be solved numerically (minimum of a cost function or Generalized least Square method, referred as GLS or use Monte-Carlo sampling of all prior distributions and estimate the final posterior distribution. Monte Carlo methods are natural solution for Bayesian inference problems. They avoid approximations (existing in traditional adjustment procedure based on chi-square minimization and propose alternative in the choice of probability density distribution for priors and likelihoods. This paper will propose the use of what we are calling Bayesian Monte Carlo (referred as BMC in the rest of the manuscript in the whole energy range from thermal, resonance and continuum range for all nuclear reaction models at these energies. Algorithms will be presented based on Monte-Carlo sampling and Markov chain. The objectives of BMC are to propose a reference calculation for validating the GLS calculations and approximations, to test probability density distributions effects and to

  14. On the use of Bayesian Monte-Carlo in evaluation of nuclear data

    Science.gov (United States)

    De Saint Jean, Cyrille; Archier, Pascal; Privas, Edwin; Noguere, Gilles

    2017-09-01

    As model parameters, necessary ingredients of theoretical models, are not always predicted by theory, a formal mathematical framework associated to the evaluation work is needed to obtain the best set of parameters (resonance parameters, optical models, fission barrier, average width, multigroup cross sections) with Bayesian statistical inference by comparing theory to experiment. The formal rule related to this methodology is to estimate the posterior density probability function of a set of parameters by solving an equation of the following type: pdf(posterior) ˜ pdf(prior) × a likelihood function. A fitting procedure can be seen as an estimation of the posterior density probability of a set of parameters (referred as x→?) knowing a prior information on these parameters and a likelihood which gives the probability density function of observing a data set knowing x→?. To solve this problem, two major paths could be taken: add approximations and hypothesis and obtain an equation to be solved numerically (minimum of a cost function or Generalized least Square method, referred as GLS) or use Monte-Carlo sampling of all prior distributions and estimate the final posterior distribution. Monte Carlo methods are natural solution for Bayesian inference problems. They avoid approximations (existing in traditional adjustment procedure based on chi-square minimization) and propose alternative in the choice of probability density distribution for priors and likelihoods. This paper will propose the use of what we are calling Bayesian Monte Carlo (referred as BMC in the rest of the manuscript) in the whole energy range from thermal, resonance and continuum range for all nuclear reaction models at these energies. Algorithms will be presented based on Monte-Carlo sampling and Markov chain. The objectives of BMC are to propose a reference calculation for validating the GLS calculations and approximations, to test probability density distributions effects and to provide the

  15. Evaluation of environmental data relating to selected nuclear power plant sites. The Zion Nuclear Power Station site

    Energy Technology Data Exchange (ETDEWEB)

    Murarka, I.P.; Policastro, A.; Daniels, E.; Ferrante, J.; Vaslow, F.

    1976-11-01

    Environmental monitoring data for the years 1972 through 1975 pertaining to the Zion Station, which began commercial operation in 1974, were analyzed by the most practical qualitative and quantitative methods. Thermal plume, water chemistry and aquatic biota data were evaluated and the results are presented. The results showed no significant immediate deleterious effects, thus confirming preoperational predictions. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data utilized, the methods of analysis, and the results obtained are presented in detail, along with recommendations for improving monitoring techniques.

  16. The U.S. Nuclear Data Network: Summary of the twenty-first meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    The following progress reports and related documents from the members of the US Nuclear Data Network (USNDN) are included at attachments: INEL Decay Data and Mass-chain Evaluation Project; Decay-data Evaluation Project; Isotopes Project Report; Report on High-spin Data Evaluations; The NNDC Activity Report, Parts A and B; Nuclear Science References (NSR) Task Force Report; Status of Mass Chains A = 1 to 266; Nuclear Data Project Activity Report; and TUNL Nuclear Data Evaluation Project Report; The progress report of the Center for Nuclear Information Technology; An Overview of the USNDN; Evaluated Nuclear Structure Data File-Status; Report on High-spin Evaluations for ENSDF since November 1994; The High-spin Data and the Workshop on Data Analysis; Decay Data Evaluation Project; Compilation of High Energy Heavy-ion and Electron Interaction Data; Dissemination/code development update; 8th Edition of the Table of Isotopes/VuENSDF; Bits of Power-Issues in the Transborder Flow of Scientific and Technical Data; Data activities at the Center for Nuclear Information Technology (CNIT), San Jose State University; The Agenda and the Minutes of the Formats and Procedures Subcommittee of the NSDD; A status report on the US Nuclear Reaction Data Network (USNRDN); Coordination/Cooperation and Communication as applied to the USNDN; Nuclear Structure Data Evaluations: Issues/Concerns; Electronic Publishing of Nuclear Data; The status of the Nuclear Astrophysics Data Project; and Nuclear Astrophysics Data needs for A=3-20/Possible contributions by TUNL. The attendees formed the three Discussion Groups. The charge to these Discussion Groups was how to achieve the goal of the USNDN to make the ENSDF and the NSR the best nuclear structure and bibliographic databases available, while maintaining a proper balance between evaluations and data dissemination.

  17. 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.

  18. Analyzing data files in SWAN

    CERN Document Server

    Gajam, Niharika

    2016-01-01

    Traditionally analyzing data happens via batch-processing and interactive work on the terminal. The project aims to provide another way of analyzing data files: A cloud-based approach. It aims to make it a productive and interactive environment through the combination of FCC and SWAN software.

  19. Present status and history of nuclear data development for transmutation technology

    CERN Document Server

    Hasegawa, A

    2002-01-01

    A history of development of nuclear data from JENDL (Japanese Evaluated Nuclear Data Library)-1 to JENDL-3.3 and JENDL-HF (High energy File) and JENDL- Actinide File are stated. 5 nuclear data such as JENDL-1, JENDL-2, JENDL-3.1, JENDL-3.2 and JENDL-3.3 have been developed by JAERI. JENDL-1 for fast reactor (1977) has 66+6 nuclide and 15 MeV the largest energy. JENDL-2 for fast and light water reactor (1982) has 173+8 nuclide and 20 MeV. All-purpose nuclear data: JENDL-3.1 (1990) with 305+19 nuclide and 59 2nd gamma-ray data, JENDL-3.2 (1994) with 318+22 nuclide and 66 2nd gamma-ray data and JENDL-3.3 (2002) with 335+2 nuclide, 114 2nd gamma-ray data, 60 angular dependence neutron data and 20 MeV have been developed. JENDL-3.3 was opened at JAERI home page in May 2002. JENDL High Energy library consists of JENDL-HF, JENDL-Photonuclear Data File and JENDL-PKA/KERMA File. JENDL-HF includes nuclear reaction data of neutron and proton incidence, for example, total cross section, elastic scattering cross section a...

  20. Nuclear data for medical applications

    Energy Technology Data Exchange (ETDEWEB)

    Capote, Roberto [International Atomic Energy Agency (IAEA), Vienna (Austria). Nuclear Data Section

    2011-07-01

    Nuclear science plays an increasingly important role in medical applications, in particular the need for radioisotopes in both cancer therapy and diagnostic techniques is very well established. Over the previous thirty years, many laboratories have reported a significant body of experimental data relevant to medical radionuclide production, and international data centres have compiled most of these data. However, till late 90s no systematic effort had been devoted to their standardization and assembly. These needs are being addressed through three IAEA Coordinated Research Projects on Nuclear Data for the Production of Radionuclides that started in 1999. Monitor cross sections to be used in charged particle measurements have been also evaluated (see http://www-nds.iaea.org/medical/monitor reactions.html). A review of IAEA recommended cross sections for the production of medical radioisotopes will be presented. Theoretical modelling of nuclear reactions will be discussed both for nuclear data evaluation and validation. The role of the Recommended Input Parameter Library (RIPL) in defining the input for production codes like EMPIRE and TALYS will be highlighted. (author)

  1. Assessment of beryllium and molybdenum nuclear data files with the RPI neutron scattering system in the energy region from 0.5 to 20 MeV

    Science.gov (United States)

    Daskalakis, Adam; Blain, Ezekiel; Leinweber, Gregory; Rapp, Michael; Barry, Devin; Block, Robert; Danon, Yaron

    2017-09-01

    A series of neutron scattering benchmark measurements were performed on beryllium and molybdenum with the Rensselaer Polytechnic Institute's Neutron Scattering System. The pulsed neutron source was produced by the Rensselaer Polytechnic Institute's Linear Accelerator and a well collimated neutron beam was incident onto the samples located at a distance of 30.07 m. Neutrons that scattered from the sample were measured using the time-of-flight by eight EJ-301 liquid scintillator detectors positioned 0.5 m from the sample of interest. A total of eight experiments were performed with two sample thicknesses each, measured by detectors placed at two sets of angles. All data were processed using pulse shape analysis that separated the neutron and gamma ray events and included a gamma misclassification correction to account for erroneously identified gamma rays. A detailed model of the neutron scattering system simulated each experiment with several current evaluated nuclear data libraries and their predecessors. Results for each evaluation were compared to the experimental data using a figure-of-merit. The neutron scattering system has been used as a means to quantify a library's performance.

  2. Proceedings of the third specialists` meeting on high energy nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Fukahori, Tokio [ed.

    1998-11-01

    This report is the Proceedings of the Third Specialists` Meeting on High Energy Nuclear Data. The meeting was held on March 30-31, 1998, at the Tokai Research Establishment of Japan Atomic Energy Research Institute with the participation of forty-odd specialists, who were the evaluators, theorists, experimentalists and users of high energy nuclear data including the members of the Japanese Nuclear Data Committee. The need of the high energy nuclear data up to a few Gev has been stressed in the meeting for many applications, such as spallation neutron sources for radioactive waste treatment, accelerator shielding design, medical isotope production, radiation therapy, the effects of space radiation on astronauts and their equipments, and the cosmic history of meteorites and other galactic substances. Since the Second Specialists` Meeting in 1995, such an evaluation activity in Japan has been grown and the results are accumulated. Foreign activities of high energy nuclear data evaluation are also being increased. According to the above situation, with the view point of reviewing and validating an evaluated high energy nuclear data file, project of high energy nuclear data file production, differential and integral experiments, status of evaluation and reviewing methods, processing and transport calculation methods, benchmark tests, international trends, etc. were discussed. The 16 of the presented papers are indexed individually. (J.P.N.)

  3. Nuclear Data Sheets for A = 93

    Science.gov (United States)

    Baglin, Coral M.

    2011-05-01

    Nuclear structure data pertaining to all nuclei with mass number A=93 (Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag) have been compiled and evaluated and incorporated into the ENSDF data file. This publication for A=93 supersedes the previous publication by C.M. Baglin, Nuclear Data Sheets80, 1 (1997) (literature cutoff date November 1996) and subsequent revisions by C.M. Baglin of the ENSDF files for 93Br and 93Kr (literature cutoff 26 February 2001) and for 93Rh (literature cutoff 27 February 2001); it includes all data available prior to 15 December 2010. Significant changes since prior evaluations include the following: 2010Hw03 identified several high-spin states in 93Kr in 252Cf SF decay; in addition to the many low-spin levels already known in 93Rb from β decay, several higher-spin states have now been identified in a 252Cf SF decay study (2009Hw03); this SF decay has also been used to identify additional states in 93Sr (2003Hw01) and the 238U( 82Se,X γ) reaction (2007Bu35) has provided new information on 93Y. (HI,xn γ) reaction studies have expanded our knowledge of the structure of 93Zr (2002Fo03, 2005Pa48), 93Nb (2007Wa45), 93Mo (2005Fu01), 93Tc (2003Ha22) and 93Pd (2004So04,2004Ru02). Considerable information on 93Nb was provided by a (p,2n γ) study (2010Or01, 2006Or09, 2007Or01). The level schemes of 93Ru, 93Rh and 93Pd have undergone the most extensive revision thanks to studies of 93Rh ɛ decay (2004De40), 94Ag ɛp decay (2004Mu30) and 94Ag p decay (2005Mu15, 2005Mu30), respectively. The half-life of the Zr member of this chain is of particular interest because of 93Zr's large contribution to long-term activity of nuclear reactor waste and also due to its potential as a supernova chronometer. During 2010, two new well-documented measurements of T 1/2( 93Zr) were published (2010Ya01 and 2010Ca01); one agrees well with an earlier, undocumented measurement but, unfortunately, the other is many standard deviations lower for reasons which are

  4. Overview of Nuclear Physics Data: Databases, Web Applications and Teaching Tools

    Science.gov (United States)

    McCutchan, Elizabeth

    2017-01-01

    The mission of the United States Nuclear Data Program (USNDP) is to provide current, accurate, and authoritative data for use in pure and applied areas of nuclear science and engineering. This is accomplished by compiling, evaluating, and disseminating extensive datasets. Our main products include the Evaluated Nuclear Structure File (ENSDF) containing information on nuclear structure and decay properties and the Evaluated Nuclear Data File (ENDF) containing information on neutron-induced reactions. The National Nuclear Data Center (NNDC), through the website www.nndc.bnl.gov, provides web-based retrieval systems for these and many other databases. In addition, the NNDC hosts several on-line physics tools, useful for calculating various quantities relating to basic nuclear physics. In this talk, I will first introduce the quantities which are evaluated and recommended in our databases. I will then outline the searching capabilities which allow one to quickly and efficiently retrieve data. Finally, I will demonstrate how the database searches and web applications can provide effective teaching tools concerning the structure of nuclei and how they interact. Work supported by the Office of Nuclear Physics, Office of Science of the U.S. Department of Energy under Contract No. DE-AC02-98CH10886.

  5. Report to the US Nuclear Regulatory Commission on analysis and evaluation of operational data - 1987: Power reactors

    Energy Technology Data Exchange (ETDEWEB)

    None

    1988-10-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during 1987. The report is published in two volumes. NUREG-1272, Vol. 2, No. 1, covers Power Reactors and presents an overview of the operating experience of the nuclear power industry, with comments regarding the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year, and summarizes information from Licensee Event Reports, the NRC's Operations Center, and Diagnostic Evaluations. NUREG-1272, Vol. 2, No. 2, covers Nonreactors and presents a review of the nonreactors events and misadministration reports that were reported in 1987 and a brief synopsis of AEOD studies published in 1987. Each volume contains a list of the AEOD Reports issued for 1980-1987.

  6. Evaluation of High Energy Nuclear Data of Importance for Use in Accelerator and Space Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Ouk

    2005-10-15

    New evaluation were performed for neutron- and proton-induced reactions for energies up to 250 400 MeV on C-12, N-14, O-16, Al-27, Si-28, Ca-40, Ar-40, Fe-54,58, Ni-64, Cu-63,65, Zr-90, Pb-208, Th-232, U-233,234,236, and Cm-243246. The evaluated results are then applied to the accelerator and space technology. A set of optical model parameters were optimized by searching a number of adjustable coefficients with the Simulated Annealing(SA) method for the spherical nuclei. A parameterization of the empirical formula was proposed to describe the proton-nucleus non-elastic cross sections of high-priority elements for space shielding purpose for proton energies from reaction threshold up to 400 MeV, which was then implemented into the fast scoping space shielding code CHARGE, based on the results of the optical model analysis utilizing up-to-date measurements. For proton energies up to 400 MeV covering most of the incident spectrum for trapped protons and solar energetic particle events, energy-angle spectra of secondary neutrons produced from the proton-induced neutron production reaction were prepared. The evaluated cross section set was applied to the thick target yield (TTY) and promp radiation benchmarks for the accelerator shielding. As for the assessment of the radiological impact of the accelerator to the environment, relevant nuclear reaction cross sections for the activation of the air were recommended among the author's evaluations and existing library based on the available measurements.

  7. Establishment of nuclear data system

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Jong Hwa; Kim, J. D.; Oh, S. Y.; Lee, Y. O.; Gil, C. S.; Cho, Y. S.

    1997-01-01

    Fission fragment data have been collected and added to the existing nuclear database system. A computer program was written for generating on-line graphs of energy-dependent neutron reaction cross section. This program deals with about 300 major nuclides and serves on the internet. As a part of nuclear data evaluation works, the covariance data for neutron cross section of structural nuclides were evaluated. Also the elastic and inelastic cross sections were evaluated by using ABAREX and EGNASH2 code. In the field of nuclear data processing, a cross section library for TWODANT code for liquid metal reactor was generated and validated against Russian and French critical reactors. The resonance data for Pu-242 in CASMO-3 library were updated. In addition, continuous-energy libraries for MCNP were generated from ENDF/B-VI.2, JEF-2.2 and JENDL-3.2. These libraries were validated against the results from a series of critical experiments at HANARO. (author). 87 refs., 29 tabs., 23 figs.

  8. Annual report of the project CIS-03-95, `evaluation of actinide nuclear data`

    Energy Technology Data Exchange (ETDEWEB)

    Maslov, V.M. [Radiation Physics and Chemistry Problems Inst., Minsk-Sosny (Belarus)

    1997-03-01

    The evaluation of neutron data for {sup 243}Cm, {sup 245}Cm and {sup 246}Cm is made in the energy region from 10-5 eV up to 20 MeV. The results of the evaluation are compiled in the ENDF/B-VI format. This work is performed under the Project Agreement CIS-03-95 with the International Science and Technology Center (Moscow). This is the annual report of the project CIS-03-95. (author)

  9. Nuclear Data Sheets for A=213

    Energy Technology Data Exchange (ETDEWEB)

    Basunia, M. S.

    2007-03-01

    Evaluated spectroscopic data and level schemes from radioactive decay and nuclear reaction studies are presented for all nuclei with mass number A=213. This evaluation for A=213 supersedes the earlier one by Y. A. Akovali (1992Ak01), published in Nuclear Data Sheets 66, 237 (1992).

  10. JENDL decay data file 2015

    OpenAIRE

    片倉 純一; 湊 太志

    2016-01-01

    JENDL Decay Data File 2015 (JENDL/DDF-2015) has been produced. The decay data of nuclides with mass numbers from 1 to 260 are included. The nuclides with unknown gamma- and/or beta-emission are also included in order to keep decay chains. The data of 1,284 fission product nuclides with mass from 66 to 172 remain unchanged from JENDL/FPD-2011 except several corrections which had been claimed by users, and those of the newly added 1,953 nuclides are taken from ENSDF. Finally, the decay data of ...

  11. Nuclear Data Sheets for A = 168

    Science.gov (United States)

    Baglin, Coral M.

    2010-07-01

    Nuclear structure data pertaining to all nuclei with mass A=168 (Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt) have been evaluated and incorporated into the ENSDF data file. This evaluation supersedes the previous publication (V.S. Shirley, Nuclear Data Sheets 71, 261 (1994) (literature cutoff date July 1993)) and subsequent ENSDF file revisions for Tb and Dy (C. Baglin, literature cutoff date of 15 June 1999) and Hf (B. Singh, literature cutoff date of 30 April 2001), and includes literature available by 15 June 2010. Since the above evaluations, the first excited states in 168Pt have been identified (1998Ki20, 2009Go16) and α decay from 172Hg has been observed (2009Sa27, 2004Ke06, 1999Se14). New levels in 168Dy have been excited using the 170Er( 82Se, 84Kr γ) reaction (2010So03). (HI,xn γ) studies have significantly expanded our knowledge of level structure in 168Lu (1999Ka17, 2002Ha33), 168Ta (2008QiZZ), 168Yb (1995Fi01), 168Tm (2007CaZW), 168Hf (2009Ya21), 168Os (2001Jo11, 2009Od02) and, for 168Tm, important information has come also from (d,2n γ) and ( α,n γ) reactions (1995Si20). Revised decay schemes are available following new studies of 168Hf ɛ decay (6.7 min) (1997Ba26), 168Lu ɛ decay (1999Ba65), 168Ta ɛ decay (2007Mc08) and 172Au α decay (2009Ha42). Significant new information for 168Er is available from (p,t) (2006Bu09), (d,p) and (t,d) (1996Ma50), ( γ, γ') (1996Ma18), (136Xe, X γ) (2010Dr02), ( 238U, 238Uγ) (2003Wu07) and (n, nγ) (1998Be20, 1998Be62) reactions, and the availability of γγ coin data (1994Ju02, 1996Gi09) for the (n, γ) E=thermal reaction has resulted in some significant level scheme revisions.

  12. GTNDSE: the GA Tech nuclear data search engine

    Science.gov (United States)

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

    2003-10-01

    The Georgia Tech Nuclear Data Search Engine (GTNDSE) is a perl script developed to assist in extracting nuclear data from a database of ENSDF-formatted A-chain data files. Operation of the search engine will be demonstrated with results from studies of horizontal systematics across the nuclear mass surface, including B(E2) values for all doubly-even nuclei from the database ( ˜3100 measured values).

  13. Japanese evaluated nuclear data library version 3 revision-3: JENDL-3.3

    CERN Document Server

    Shibata, K; Kawano, T

    2002-01-01

    Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for sup 2 sup 3 sup 5 U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2. (author)

  14. Nuclear Data Verification and Standardization

    Energy Technology Data Exchange (ETDEWEB)

    Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

    2011-10-01

    The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

  15. Citation guidelines for nuclear data retrieved from databases resident at the Nuclear Data Centers Network

    Energy Technology Data Exchange (ETDEWEB)

    McLane, V.

    1996-07-01

    The Nuclear Data Centers Network is a world-wide cooperation of nuclear data centers under the auspices of the International Atomic Energy Agency. The Network organizes the task of collecting, compiling, standardizing, storing, assessing, and distributing the nuclear data on an international scale. Information available at the Centers includes bibliographic, experimental, and evaluated databases for nuclear reaction data and for nuclear structure and radioactive decay data. The objective of the Network is to provide the information to users in a convenient, readily-available form. To this end, online data services have been established at three of the centers: the National Nuclear Data Center (NNDC), the Nuclear Data Section of the International Atomic Energy Agency (NDS), and the OECD Nuclear Energy Agency Data Bank (NEADB). Some information is also available at the NNDC and NEADB World Wide Web sites.

  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. Nuclear data for designing the IFMIF accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    The objective of the International Fusion Materials Irradiation Facility (IFMIF) and the design concept of the IFMIF accelerator system are described. The status of the nuclear data, especially for the deuteron-induced reactions, to qualify the system design is reviewed. The requests for the nuclear data compilation and/or evaluation are summarized. (author)

  18. NDEC: A NEA platform for nuclear data testing, verification and benchmarking

    Directory of Open Access Journals (Sweden)

    Díez C.J.

    2017-01-01

    Full Text Available The selection, testing, verification and benchmarking of evaluated nuclear data consists, in practice, in putting an evaluated file through a number of checking steps where different computational codes verify that the file and the data it contains complies with different requirements. These requirements range from format compliance to good performance in application cases, while at the same time physical constraints and the agreement with experimental data are verified. At NEA, the NDEC (Nuclear Data Evaluation Cycle platform aims at providing, in a user friendly interface, a thorough diagnose of the quality of a submitted evaluated nuclear data file. Such diagnose is based on the results of different computational codes and routines which carry out the mentioned verifications, tests and checks. NDEC also searches synergies with other existing NEA tools and databases, such as JANIS, DICE or NDaST, including them into its working scheme. Hence, this paper presents NDEC, its current development status and its usage in the JEFF nuclear data project.

  19. Nuclear Data Sheets for A = 186

    Science.gov (United States)

    Baglin, Coral M.

    2003-05-01

    Nuclear structure data pertaining to all nuclei with mass number A=186 have been evaluated, and incorporated into the ENSDF database. This evaluation for A=186 includes data available by 4 April 2003. It supersedes the previous publication (C. Baglin, Nuclear Data Sheets 82, 1 (1997) (literature cutoff date 31 August 1997)) and subsequent revisions of Hf and Ta (literature cutoff date 26 November 1998) and W (literature cutoff date 17 February 1999).

  20. Annual report of nuclear code evaluation committee for fiscal 2000 year

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-03-01

    In this report, research results discussed in fiscal 2000 year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. In 2000, papers mainly on the three topics of (1) present status of burnup credit evaluation methods, (2) issues concerning convergence of criticality calculation and (3) estimation methods for errors associated with criticality calculation based on nuclear data covariance file, are presented and discussed. These results are sorted to grasp the present status of related technology and described in this report. (author)

  1. Evaluation of piping reliability and failure data for use in risk-based inspections of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, V. de; Soares, W.A.; Costa, A.C.L. da; Rabello, E.G.; Marques, R.O., E-mail: vasconv@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2016-07-01

    During operation of industrial facilities, components and systems can deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) involves inspection planning based on information about risks, through assessing of probability and consequence of failures. In-service inspections are used in nuclear power plants, in order to ensure reliable and safe operation. Traditional deterministic inspection approaches investigate generic degradation mechanisms on all systems. However, operating experience indicates that degradation occurs where there are favorable conditions for developing a specific mechanism. Inspections should be prioritized at these places. Risk-Informed In-service Inspections (RI-ISI) are types of RBI that use Probabilistic Safety Assessment results, increasing reliability and plant safety, and reducing radiation exposure. These assessments use both available generic reliability and failure data, as well as plant specific information. This paper proposes a method for evaluating piping reliability and failure data important for RI-ISI programs, as well as the techniques involved. (author)

  2. Measurement/Evaluation Techniques and Nuclear Data Associated with Fission of 239Pu by Fission Spectrum Neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Baisden, P; Bauge, E; Ferguson, J; Gilliam, D; Granier, T; Jeanloz, R; McMillan, C; Robertson, D; Thompson, P; Verdon, C; Wilkerson, C; Young, P

    2010-03-16

    This Panel was chartered to review and assess new evaluations of work on fission product data, as well as the evaluation process used by the two U.S. nuclear weapons physics laboratories. The work focuses on fission product yields resulting from fission spectrum neutrons incident on plutonium, and includes data from measurements that had not been previously published as well as new or revised fission product cumulative yield data, and related quantities such as Q values and R values. This report documents the Panel's assessment of the work presented by Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). Based on the work presented we have seven key observations: (1) Experiments conducted in the 1970s at LANL, some of which were performed in association with a larger, NIST-led, program, have recently been documented. A preliminary assessment of this work, which will be referred to in this document as ILRR-LANL, shows it to be technically sound. (2) LLNL has done a thorough, unbiased review and evaluation of the available literature and is in the process of incorporating the previously unavailable LANL data into its evaluation of key fission product yields. The results of the LLNL effort, which includes a preliminary evaluation of the ILRR-LANL data, have been documented. (3) LANL has also conducted an evaluation of fission product yields for fission spectrum neutrons on plutonium including a meta-analysis of benchmark data as part of a planned upgrade to the ENDF/B compilation. We found that the approach of using meta-analysis provides valuable additional insight for evaluating the sparse data sets involved in this assessment. (4) Both laboratories have provided convincing evidence for energy dependence in the fission product yield of {sup 147}Nd produced from the bombardment of {sup 239}Pu with fission spectrum neutrons over an incident neutron energy range of 0.2 to 1.9 MeV. (5) Consistent, complete, and explicit treatment

  3. Transfer-induced fission in inverse kinematics: Impact on experimental and evaluated nuclear data bases

    Energy Technology Data Exchange (ETDEWEB)

    Farget, F.; Schmidt, K.H.; Clement, E.; Delaune, O.; Derkx, X.; Dijon, A.; Golabek, C.; Lemasson, A.; Roger, T.; Schmitt, C. [CEA/DSM-CNRS/IN2P3, GANIL, Caen (France); Caamano, M.; Ramos, D.; Benlliure, J.; Cortina, D.; Fernandez-Dominguez, B.; Paradela, C. [Universidade de Santiago de Compostela, Santiago de Compostela (Spain); Rodriguez-Tajes, C. [CEA/DSM-CNRS/IN2P3, GANIL, Caen (France); Universidade de Santiago de Compostela, Santiago de Compostela (Spain); Audouin, L. [Universite Paris-Sud 11, CNRS/IN2P3, Institut de Physique Nucleaire, Orsay (France); Casarejos, E. [Universidade de Vigo, Vigo (Spain); Dore, D.; Salsac, M.D. [Centre de Saclay, CEA, Irfu, Gif-sur-Yvette (France); Gaudefroy, L. [CEA DAM Ile-de-France, BP 12, Bruyeres-le-Chatel (France); Heinz, A. [Chalmers Tekniska Hoegskola, Fundamental Fysik, Goeteborg (Sweden); Jurado, B. [Universite Bordeaux, CENBG, UMR 5797 CNRS/IN2P3, Gradignan (France)

    2015-12-15

    Inverse kinematics is a new tool to study nuclear fission. Its main advantage is the possibility to measure with an unmatched resolution the atomic number of fission fragments, leading to new observables in the properties of fission-fragment distributions. In addition to the resolution improvement, the study of fission based on nuclear collisions in inverse kinematics beneficiates from a larger view with respect to the neutron-induced fission, as in a single experiment the number of fissioning systems and the excitation energy range are widden. With the use of spectrometers, mass and kinetic-energy distributions may now be investigated as a function of the proton and neutron number sharing. The production of fissioning nuclei in transfer reactions allows studying the isotopic yields of fission fragments as a function of the excitation energy. The higher excitation energy resulting in the fusion reaction leading to the compound nucleus {sup 250}Cf at an excitation energy of 45MeV is also presented. With the use of inverse kinematics, the charge polarisation of fragments at scission is now revealed with high precision, and it is shown that it cannot be neglected, even at higher excitation energies. In addition, the kinematical properties of the fragments inform on the deformation configuration at scission. (orig.)

  4. Nuclear Data Sheets for A = 91

    Science.gov (United States)

    Baglin, Coral M.

    2013-10-01

    Experimental nuclear structure and decay data for all known A=91 nuclides (As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd) have been evaluated. This evaluation, covering data received by 1 September 2013, supersedes the 1998 evaluation by C. M. Baglin published in Nuclear Data Sheets86, 1 (1999) (15 December 1998 literature cutoff), and subsequent evaluations by C. M. Baglin added to the ENSDF database for Kr, Sr and Zr (29 December 2000 literature cutoff) and by B. Singh for 91Tc (6 November 2000 literature cutoff).

  5. Nuclear Data Sheets for A = 91

    Energy Technology Data Exchange (ETDEWEB)

    Baglin, Coral M.

    2013-10-15

    Experimental nuclear structure and decay data for all known A=91 nuclides (As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd) have been evaluated. This evaluation, covering data received by 1 September 2013, supersedes the 1998 evaluation by C. M. Baglin published in Nuclear Data Sheets86, 1 (1999) (15 December 1998 literature cutoff), and subsequent evaluations by C. M. Baglin added to the ENSDF database for Kr, Sr and Zr (29 December 2000 literature cutoff) and by B. Singh for {sup 91}Tc (6 November 2000 literature cutoff)

  6. Contents of GPS Data Files

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, John P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Carver, Matthew Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Norman, Benjamin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-12-09

    There are no very detailed descriptions of most of these instruments in the literature – we will attempt to fix that problem in the future. The BDD instruments are described in [1]. One of the dosimeter instruments on CXD boxes is described in [2]. These documents (or web links to them) and a few others are in this directory tree. The cross calibration of the CXD electron data with RBSP is described in [3]. Each row in the data file contains the data from one time bin from a CXD or BDD instrument along with a variety of parameters derived from the data. Time steps are commandable but 4 minutes is a typical setting. These instruments are on many (but not all) GPS satellites which are currently in operation. The data come from either BDD instruments on GPS Block IIR satellites (SVN41 and 48), or else CXD-IIR instruments on GPS Block IIR and IIR-M satellites (SVN53-61) or CXD-IIF instruments on GPS block IIF satellites (SVN62-73). The CXD-IIR instruments on block IIR and IIR(M) satellites use the same design.

  7. Neutron nuclear data measurements for criticality safety

    Directory of Open Access Journals (Sweden)

    Guber Klaus

    2017-01-01

    Full Text Available To support the US Department of Energy Nuclear Criticality Safety Program, neutron-induced cross section experiments were performed at the Geel Electron Linear Accelerator of the Joint Research Center Site Geel, European Union. Neutron capture and transmission measurements were carried out using metallic natural cerium and vanadium samples. Together with existing data, the measured data will be used for a new evaluation and will be submitted with covariances to the ENDF/B nuclear data library.

  8. 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.

  9. White Paper on Nuclear Data Needs and Capabilities for Basic Science

    Energy Technology Data Exchange (ETDEWEB)

    Batchelder, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kawano, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kelley, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kondev, F. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McCutchan, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Smith, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sonzogni, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thoennessen, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-05-14

    Reliable nuclear structure and reaction data represent the fundamental building blocks of nuclear physics and astrophysics research, and are also of importance in many applications. There is a continuous demand for high-quality updates of the main nuclear physics databases via the prompt compilation and evaluation of the latest experimental and theoretical results. The nuclear physics research community benefits greatly from comprehensive, systematic and up-to-date reviews of the experimentally determined nuclear properties and observables, as well as from the ability to rapidly access these data in user-friendly forms. Such credible databases also act as a bridge between science, technology, and society by making the results of basic nuclear physics research available to a broad audience of users, and hence expand the societal utilization of nuclear science. Compilation and evaluation of nuclear data has deep roots in the history of nuclear science research, as outlined in Appendix 1. They have an enormous impact on many areas of science and applications, as illustrated in Figure 2 for the Evaluated Nuclear Structure Data File (ENSDF) database. The present workshop concentrated on the needs of the basic nuclear science community for data and capabilities. The main role of this community is to generate and use data in order to understand the basic nuclear forces and interactions that are responsible for the existence and the properties of all nuclides and, as a consequence, to gain knowledge about the origins, evolution and structure of the universe. Thus, the experiments designed to measure a wealth of nuclear properties towards these fundamental scientific goals are typically performed from within this community.

  10. Proceedings of the 1998 symposium on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, Tadashi; Fukahori, Tokio [eds.] [Japanese Nuclear Data Committee, Tokai, Ibaraki (Japan)

    1999-03-01

    The 1998 Symposium on Nuclear Data was held at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), on 19th and 20th of November 1998. Japanese Nuclear Data Committee and Nuclear Data Center, JAERI organized this symposium. In the oral sessions, presented papers were on accelerator facilities, astrophysics and nuclear data, international session, radiation damage study and nuclear data, and integral test of nuclear data. In the poster session, presented papers were concerning experiments, evaluations, benchmark tests and on-line database on nuclear data. Those presented papers are compiled in this proceedings. The 50 of the presented papers are indexed individually. (J.P.N.)

  11. Nuclear data uncertainty propagation: Perturbation vs. Monte Carlo

    Energy Technology Data Exchange (ETDEWEB)

    Rochman, D., E-mail: rochman@nrg.eu [Nuclear Research and Consultancy Group NRG, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten (Netherlands); Koning, A.J., E-mail: koning@nrg.eu [Nuclear Research and Consultancy Group NRG, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten (Netherlands); Marck, S.C. van der, E-mail: vandermarck@nrg.eu [Nuclear Research and Consultancy Group NRG, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten (Netherlands); Hogenbirk, A., E-mail: hogenbirk@nrg.eu [Nuclear Research and Consultancy Group NRG, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten (Netherlands); Sciolla, C.M., E-mail: sciolla@nrg.eu [Nuclear Research and Consultancy Group NRG, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten (Netherlands)

    2011-05-15

    Research highlights: > Two uncertainty propagation methods are compared. > MCNP Criticality-safety benchmarks are used to perform the comparisons. > The majority of differences can be explained by methods deficiencies or format approximations. - Abstract: Two methods of nuclear data uncertainty propagation are compared, using the same nuclear data uncertainties and criticality-safety benchmarks. The first method, based on perturbation theory uses covariance files, covariance processing and the perturbation card of MCNP. The second method makes use of a large number of MCNP calculations, all alike, but using different random nuclear data libraries, consistent with the covariance files of the first method. The consistency of the nuclear data used by both methods is checked and results for 33 criticality-safety benchmarks are presented. Relatively good agreements are found, but depending on the benchmark cases, differences due to the elastic cross-section, {nu}-bar, angular and energy distributions are observed.

  12. Nuclear Data Sheets for A = 27

    Science.gov (United States)

    Shamsuzzoha Basunia, M.

    2011-08-01

    Evaluated spectroscopic data and level schemes from radioactive decay and nuclear reaction studies are presented for 27F, 27Ne, 27Na, 27Mg, 27Al, 27Si, 27P, and 27S. This evaluation for A=27 supersedes the earlier evaluation by P.M. Endt (1998En04 and 1990En08).

  13. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k{sub eff} and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  14. Half-lives of radionuclides used in nuclear geochronology and cosmochronology (evaluated data)

    CERN Document Server

    Chechev, V P

    2001-01-01

    Evaluated half-life values are given for the radionuclides sup 2 sup 6 Al, sup 4 sup 0 K, sup 5 sup 3 Mn, sup 6 sup 0 Fe, sup 8 sup 7 Rb, sup 9 sup 3 Zr, sup 9 sup 8 Tc, sup 1 sup 0 sup 7 Pd, sup 1 sup 2 sup 9 I, sup 1 sup 3 sup 5 Cs, sup 1 sup 4 sup 6 Sm, sup 1 sup 7 sup 6 Lu, sup 1 sup 8 sup 2 Hf, sup 1 sup 8 sup 7 Re, sup 2 sup 0 sup 5 Pb, sup 2 sup 3 sup 2 Th, sup 2 sup 3 sup 5 U, sup 2 sup 3 sup 8 U, sup 2 sup 4 sup 4 Pu and sup 2 sup 4 sup 7 Cm. These were obtained from an analysis of published information up to 2001. These half-lives are used in geochronology and cosmochronology to determine different radiometric ages in the history of the earth, solar system and galaxy.

  15. Establishment of Nuclear Data for Future Nuclear R and D

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. O.; Gil, C. S.; Cho, Y. S.; Kim, D. H.; Kim, H. I.; Lee, C. W.; Yoo, K. J.; Yang, S. C.; Namkung, W.; Lee, H. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-10-15

    A computer code system was established to process variance-covariance of the evaluated cross sections in order to quantify uncertainties of nuclear system. Covariance data of major actinides of JENDL-3.3 were processed and their inherent uncertainties and sensitivities to the nuclear system was analyzed. In collaboration with BNL, a new method for neutron resonance parameter evaluation which makes use of recent measurements as well as the existing evaluations was established and applied to the evaluation of a number of fission products. A computation code was developed to evaluate the photo-nuclear fission cross sections. Localization of the code has been examined through the evaluations for some major nuclear materials below 30 MeV region. Neutron-induced gamma spectra, which are essential in the fields of nuclear industry and space engineering, are newly evaluated for W isotopes by introducing improved gamma strength function to describe irregular bumps. The evaluated data has been processed by NJOY and validated through some benchmark calculations by MCNPX. The proton cross sections of 27Al were evaluated by theoretical model calculations. TALYS computer code system was used for the theoretical model calculation and the evaluations for Cu-nat and Fe-nat were also carried out. PAL facilities were utilized for measurements of total cross sections, activation experiments, and beam-time supports to develop various radiation detectors. Neutron total cross sections of Nb, Pb, and Tm and thermal neutron cross sections and resonance parameters of Zr-96 and Ta-181 were measured at the facility. At the Pohang neutron facility, a target system was installed to measure photo-fission cross sections using activation analysis. Photo-fission products were measured for thin film samples of Pb-nat, Pb-208, and Bi-209.

  16. Nuclear data for fusion technology - the European approach

    Science.gov (United States)

    Fischer, Ulrich; Avrigeanu, Marilena; Avrigeanu, Vlad; Cabellos, Oscar; Dzysiuk, Natalia; Koning, Arjan; Klix, Axel; Konobeev, Alexander; Kodeli, Ivo; Leeb, Helmut; Leichtle, Dieter; Nunnenmann, Elena; Packer, Lee; Rochman, Dimitri; Pereslavtsev, Pavel; Sauvan, Patrick; Trkov, Andrej

    2017-09-01

    The European approach for the development of nuclear data for fusion technology applications is presented. Related R&D activities are conducted by the Consortium on Nuclear Data Development and Analysis for Fusion to satisfy the nuclear data needs of the major projects including ITER, the Early Neutron Source (ENS) and DEMO. Recent achievements are presented in the area of nuclear data evaluations, benchmarking and validation, nuclear model improvements, and uncertainty assessments.

  17. Nuclear data for fusion technology – the European approach

    Directory of Open Access Journals (Sweden)

    Fischer Ulrich

    2017-01-01

    Full Text Available The European approach for the development of nuclear data for fusion technology applications is presented. Related R&D activities are conducted by the Consortium on Nuclear Data Development and Analysis for Fusion to satisfy the nuclear data needs of the major projects including ITER, the Early Neutron Source (ENS and DEMO. Recent achievements are presented in the area of nuclear data evaluations, benchmarking and validation, nuclear model improvements, and uncertainty assessments.

  18. Adolescent Fertility: National File [Machine-Readable Data File].

    Science.gov (United States)

    Moore, Kristin A.; And Others

    This computer file contains recent cross sectional data on adolescent fertility in the United States for 1960, 1965, 1970, 1975 and 1980-85. The following variables are included: (1) births; (2) birth rates; (3) abortions; (4) non-marital childbearing; (5) infant mortality; and (6) low birth weight. Data for both teenagers and women aged 20-24 are…

  19. Denominator File - Limited Data Set

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Denominator File combines Medicare beneficiary entitlement status information from administrative enrollment records with third-party payer information and GHP...

  20. A New Format for Handling Nuclear Data

    CERN Document Server

    Bak, S I; Tenreiro, C; Kadi, Y; Hong, S W; Manchanda, V; Gheata, M; Chai, J S; Carminati, F; Park, T S; Brun, R

    2011-01-01

    The ASCII ENDF format for nuclear data has been used for four decades. It is practical for human inspection and portability, but; it is not very effective for manipulating and displaying the data or for using them in Monte-Carlo applications. In this paper we present a prototype of a nuclear data manipulation package (TNudy) based on the ROOT system (http://root.cern.ch). The ROOT object-oriented C++ framework is the de-facto standard in high energy and nuclear physics since ten years. Starting from the ENDF format, the data. is stored in machine-portable binary format. Root files also offer a powerful direct access capability to their different sections and compressibility upon writing, minimising the disk occupancy. ROOT offers a complete library of visualisation and mathematical routines and the Virtual Monte-Carlo system, which allows running different transport Monte-Carlo (Geant 4, Geant 3) with common scoring and geometry modellers, which comes as part of ROOT. ROOT contains isotope decay data and the ...

  1. Inter-comparison of JEF-2.2 and JEFF-3.1 evaluated nuclear data through Monte Carlo analysis of VVER-1000 MOX Core Computational Benchmark

    Energy Technology Data Exchange (ETDEWEB)

    Thilagam, L., E-mail: thilagam@igcar.gov.i [AERB-Safety Research Institute, Kalpakkam, Tamilnadu 603 102 (India); Karthikeyan, R., E-mail: rkarthi@barc.gov.i [Light Water Reactors Physics Section, Reactor Physics Design Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Jagannathan, V., E-mail: v_jagan1952@rediffmail.co [Light Water Reactors Physics Section, Reactor Physics Design Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Subbaiah, K.V.; Lee, S.M. [AERB-Safety Research Institute, Kalpakkam, Tamilnadu 603 102 (India)

    2010-02-15

    The nuclear data forms a vital component in reactor core physics computations. The nuclear data is evaluated and modified on a continuous basis by different nuclear data centres and laboratories worldwide. The work on upgradation of the nuclear data is being carried out using new evaluations obtained through experiments and theoretical models to enhance their accuracy. Use of different sets of cross-section data in the analysis of a benchmark problem is a source of strong feedback for further improvements in data by mutual comparison of results. These comparisons also help to find out the best evaluated cross-section data released. Towards this objective, an attempt has been made to inter-compare JEF-2.2 and JEFF-3.1 evaluated nuclear data through the Monte Carlo simulation of 'VVER-1000 MOX Core Computational Benchmark'. This study deals with the calculation and inter-comparison of reactor parameters such as multiplication factors, cell average and assembly average fission reaction rate distributions estimated for various reactor state descriptions specified in the benchmark. Point-wise cross-section libraries processed from the JEF-2.2 and JEFF-3.1 evaluated data are used in the analysis. Concerning the multiplication factors and fission rate distributions, considerable differences are observed between the two libraries. While performing the MCNP calculations with JEFF-3.1 data, it is observed that the deviations of effective neutron multiplication factors (k{sub eff}) from those of benchmark standard MCU results are lower by about approx0.100% for the most of the states than those computed using JEF-2.2. Fission rate distributions using JEFF-3.1 data are also found to have significant deviations up to +-9.2% compared to calculations with its earlier version JEF-2.2 data. Some interesting trends on the used nuclear data are identified from the discrepancies of the individual results. The cause for considerable changes in the calculated parameters are

  2. Nuclear Data Sheets for A=256

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Balraj

    2017-03-15

    Available nuclear structure information for the known A=256 nuclei (Cf, Es, Fm, Md, No, Lr, Rf and Db) is presented together with Adopted properties of levels and gamma rays. This evaluation supersedes data in the previous evaluations of A=256 nuclides by 1999Ak02, 1989Sc26, 1981Sc06 and 1976Sc02.

  3. Analyzing Log Files using Data-Mining

    Directory of Open Access Journals (Sweden)

    Marius Mihut

    2008-01-01

    Full Text Available Information systems (i.e. servers, applications and communication devices create a large amount of monitoring data that are saved as log files. For analyzing them, a data-mining approach is helpful. This article presents the steps which are necessary for creating an ‘analyzing instrument’, based on an open source software called Waikato Environment for Knowledge Analysis (Weka [1]. For exemplification, a system log file created by a Windows-based operating system, is used as input file.

  4. Identifiable Data Files - Health Outcomes Survey (HOS)

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Medicare Health Outcomes Survey (HOS) identifiable data files are comprised of the entire national sample for a given 2-year cohort (including both respondents...

  5. Identifiable Data Files - Medicare Provider Analysis and ...

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Medicare Provider Analysis and Review (MEDPAR) File contains data from claims for services provided to beneficiaries admitted to Medicare certified inpatient...

  6. Uncertainty analysis on reactivity and discharged inventory for a pressurized water reactor fuel assembly due to {sup 235,238}U nuclear data uncertainties

    Energy Technology Data Exchange (ETDEWEB)

    Da Cruz, D. F.; Rochman, D.; Koning, A. J. [Nuclear Research and Consultancy Group NRG, Westerduinweg 3, 1755 ZG Petten (Netherlands)

    2012-07-01

    This paper discusses the uncertainty analysis on reactivity and inventory for a typical PWR fuel element as a result of uncertainties in {sup 235,238}U nuclear data. A typical Westinghouse 3-loop fuel assembly fuelled with UO{sub 2} fuel with 4.8% enrichment has been selected. The Total Monte-Carlo method has been applied using the deterministic transport code DRAGON. This code allows the generation of the few-groups nuclear data libraries by directly using data contained in the nuclear data evaluation files. The nuclear data used in this study is from the JEFF3.1 evaluation, and the nuclear data files for {sup 238}U and {sup 235}U (randomized for the generation of the various DRAGON libraries) are taken from the nuclear data library TENDL. The total uncertainty (obtained by randomizing all {sup 238}U and {sup 235}U nuclear data in the ENDF files) on the reactor parameters has been split into different components (different nuclear reaction channels). Results show that the TMC method in combination with a deterministic transport code constitutes a powerful tool for performing uncertainty and sensitivity analysis of reactor physics parameters. (authors)

  7. Integrated system for production of neutronics and photonics calculational constants. Volume 15, Part D, Rev. 1. The LLL Evaluated Nuclear Data Library (ENDL): descriptions of individual evaluations for Z = 0--98

    Energy Technology Data Exchange (ETDEWEB)

    Howerton, R.J.; MacGregor, M.H.

    1978-05-17

    Descriptions of evaluated nuclear data sets for 86 isotopes in the range Z = 0 to 98 are presented. The evaluation procedures that were used are discussed. At the beginning of the discussion for each individual isotope, a computer-generated listing is given which summarizes the main properties of the data sets that are contained in the evaluation.

  8. Status of nuclear data activities in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young-Ouk; Chang, Jonghwa [Nuclear Data Evaluation Lab., Korea Atomic Energy Research Inst., Yusung, Taejon 305-600 (Korea, Republic of)

    1998-03-01

    Although nuclear data activities in Korea are still in the early stage, considerable demands for more accurate and wide-range nuclear data from nuclear R and D fields activated a new nuclear data project titled as `Development of Nuclear Data System`. It was launched this year as one of nation-wide long-term nuclear R and D programs in Korea for the next decade. Its main goals are (1) to establish nuclear data system, (2) to build up the infra-structure for utilization of nuclear data and (3) to develop highly reliable nuclear data system. To achieve these goals, international cooperation and cultivation of human resource as well as construction of measurement facilities will be indispensable. This report briefly describes the demands of nuclear data from the nuclear R and D programs, current nuclear data activities and future plan with its strategy. (author)

  9. DATA Act File C Award Financial - Social Security

    Data.gov (United States)

    Social Security Administration — The DATA Act Information Model Schema Reporting Submission Specification File C. File C includes the agency award information from the financial accounting system at...

  10. NADS - Nuclear And Atomic Data System

    Energy Technology Data Exchange (ETDEWEB)

    McKinley, M S; Beck, B; McNabb, D

    2004-09-17

    We have developed NADS (Nuclear and Atomic Data System), a web-based graphical interface for viewing pointwise and grouped cross-sections and distributions. Our implementation is a client / server model. The client is a Java applet that displays the graphical interface, which has interactive 2-D, 3-D, and 4-D plots and tables. The server, which can serve and perform computations the data, has been implemented in Python using the FUDGE package developed by Bret Beck at LLNL. Computational capabilities include algebraic manipulation of nuclear evaluated data in databases such as LLNL's ENDL-99, ENDF/B-V and ENDF/B-VI as well as user data. Processed data used in LLNL's transport codes are accessible as well. NADS is available from http://nuclear.llnl.gov/

  11. Nuclear Data Online Services at Peking University

    Science.gov (United States)

    Fan, T. S.; Guo, Z. Y.; Ye, W. G.; Liu, W. L.; Liu, T. J.; Liu, C. X.; Chen, J. X.; Tang, G. Y.; Shi, Z. M.; Huang, X. L.; Chen, J. E.

    2005-05-01

    The Institute of Heavy Ion Physics at Peking University has developed a new nuclear data online services software package. Through the web site (http://ndos.nst.pku.edu.cn), it offers online access to main relational nuclear databases: five evaluated neutron libraries (BROND, CENDL, ENDF, JEF, JENDL), the ENSDF library, the EXFOR library, the IAEA photonuclear library and the charged particle data of the FENDL library. This software allows the comparison and graphic representations of the different data sets. The computer programs of this package are based on the Linux implementation of PHP and the MySQL software.

  12. Fast probabilistic file fingerprinting for big data

    NARCIS (Netherlands)

    Tretjakov, K.; Laur, S.; Smant, G.; Vilo, J.; Prins, J.C.P.

    2013-01-01

    Background: Biological data acquisition is raising new challenges, both in data analysis and handling. Not only is it proving hard to analyze the data at the rate it is generated today, but simply reading and transferring data files can be prohibitively slow due to their size. This primarily

  13. Parallel file system performances in fusion data storage

    Energy Technology Data Exchange (ETDEWEB)

    Iannone, F., E-mail: francesco.iannone@enea.it [Associazione EURATOM-ENEA sulla Fusione, C.R.ENEA Frascati, via E.Fermi, 45 - 00044 Frascati, Rome (Italy); Podda, S.; Bracco, G. [ENEA Information Communication Tecnologies, Lungotevere Thaon di Revel, 76 - 00196 Rome (Italy); Manduchi, G. [Associazione EURATOM-ENEA sulla Fusione, Consorzio RFX, Corso Stati Uniti, 4 - 35127 Padua (Italy); Maslennikov, A. [CASPUR Inter-University Consortium for the Application of Super-Computing for Research, via dei Tizii, 6b - 00185 Rome (Italy); Migliori, S. [ENEA Information Communication Tecnologies, Lungotevere Thaon di Revel, 76 - 00196 Rome (Italy); Wolkersdorfer, K. [Juelich Supercomputing Centre-FZJ, D-52425 Juelich (Germany)

    2012-12-15

    High I/O flow rates, up to 10 GB/s, are required in large fusion Tokamak experiments like ITER where hundreds of nodes store simultaneously large amounts of data acquired during the plasma discharges. Typical network topologies such as linear arrays (systolic), rings, meshes (2-D arrays), tori (3-D arrays), trees, butterfly, hypercube in combination with high speed data transports like Infiniband or 10G-Ethernet, are the main areas in which the effort to overcome the so-called parallel I/O bottlenecks is most focused. The high I/O flow rates were modelled in an emulated testbed based on the parallel file systems such as Lustre and GPFS, commonly used in High Performance Computing. The test runs on High Performance Computing-For Fusion (8640 cores) and ENEA CRESCO (3392 cores) supercomputers. Message Passing Interface based applications were developed to emulate parallel I/O on Lustre and GPFS using data archival and access solutions like MDSPLUS and Universal Access Layer. These methods of data storage organization are widely diffused in nuclear fusion experiments and are being developed within the EFDA Integrated Tokamak Modelling - Task Force; the authors tried to evaluate their behaviour in a realistic emulation setup.

  14. Nuclear Data Sheets for A = 179

    Science.gov (United States)

    Baglin, Coral M.

    2009-02-01

    Nuclear structure data pertaining to all nuclei with mass number A = 179 (Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl) have been compiled and evaluated, and incorporated into the ENSDF database. This evaluation for A = 179, which considers data available by 15 November 2008, supersedes the previous complete publication (E. Browne, Nuclear Data Sheets55, 483 (1988), cutoff September 1987) and the update-mode publication (C. Baglin, Nuclear Data Sheets72, 617 (1994), cutoff date September 1994), as well as the subsequent evaluations of Ta, Ir and Tl by C. Baglin (literature cutoff dates January 2000, October 1998 and February 2001, respectively). The newly evaluated literature provides new Coulomb excitation data for Hf, transfer reaction data for Hf and Ta, new information on Au and Hg from α decay and significant (HI,xnγ) reaction data for Hf, Ta, Re, Au and Hg. At the time of the 1994 evaluation, no γ-ray information was available for Au or Hg; that situation has now changed dramatically, although additional work on details of the low-lying structure of Au could be instructive.

  15. HIRENASD Experimental Data, Static Cp Plots and Data files

    Data.gov (United States)

    National Aeronautics and Space Administration — Tecplot (ascii) and matlab files are posted here for the Static pressure coefficient data sets. To download all of the data in either tecplot format or matlab...

  16. Nuclear power data; Kernenergie in Zahlen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-05-15

    The report ''nuclear power data'' includes data on the following issues: nuclear power plants in Germany including their operational characteristics, gross data on electricity generation in Germany, primary energy consumption in Germany, nuclear power plants worldwide, top ten nuclear power plants worldwide with respect to electricity generation in 2012.

  17. Methodology and issues of integral experiments selection for nuclear data validation

    Directory of Open Access Journals (Sweden)

    Tatiana Ivanova

    2017-01-01

    Full Text Available Nuclear data validation involves a large suite of Integral Experiments (IEs for criticality, reactor physics and dosimetry applications. [1] Often benchmarks are taken from international Handbooks. [2, 3] Depending on the application, IEs have different degrees of usefulness in validation, and usually the use of a single benchmark is not advised; indeed, it may lead to erroneous interpretation and results. [1] This work aims at quantifying the importance of benchmarks used in application dependent cross section validation. The approach is based on well-known General Linear Least Squared Method (GLLSM extended to establish biases and uncertainties for given cross sections (within a given energy interval. The statistical treatment results in a vector of weighting factors for the integral benchmarks. These factors characterize the value added by a benchmark for nuclear data validation for the given application. The methodology is illustrated by one example, selecting benchmarks for 239Pu cross section validation. The studies were performed in the framework of Subgroup 39 (Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files established at the Working Party on International Nuclear Data Evaluation Cooperation (WPEC of the Nuclear Science Committee under the Nuclear Energy Agency (NEA/OECD.

  18. Methodology and issues of integral experiments selection for nuclear data validation

    Science.gov (United States)

    Tatiana, Ivanova; Ivanov, Evgeny; Hill, Ian

    2017-09-01

    Nuclear data validation involves a large suite of Integral Experiments (IEs) for criticality, reactor physics and dosimetry applications. [1] Often benchmarks are taken from international Handbooks. [2, 3] Depending on the application, IEs have different degrees of usefulness in validation, and usually the use of a single benchmark is not advised; indeed, it may lead to erroneous interpretation and results. [1] This work aims at quantifying the importance of benchmarks used in application dependent cross section validation. The approach is based on well-known General Linear Least Squared Method (GLLSM) extended to establish biases and uncertainties for given cross sections (within a given energy interval). The statistical treatment results in a vector of weighting factors for the integral benchmarks. These factors characterize the value added by a benchmark for nuclear data validation for the given application. The methodology is illustrated by one example, selecting benchmarks for 239Pu cross section validation. The studies were performed in the framework of Subgroup 39 (Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files) established at the Working Party on International Nuclear Data Evaluation Cooperation (WPEC) of the Nuclear Science Committee under the Nuclear Energy Agency (NEA/OECD).

  19. Nuclear Data Sheets for A = 209

    Energy Technology Data Exchange (ETDEWEB)

    Chen, J. [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Present address: National Superconducting Cyclotron Laboratory, Michigan State University, East Lansing, Michigan 48824 (United States); Kondev, F.G. [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States)

    2015-05-15

    The experimental data are evaluated for known nuclides of mass number A = 209 (Au,Hg,Tl,Pb,Bi,Po,At,Rn, Fr,Ra,Ac,Th). Detailed evaluated level properties and related nuclear structure information are presented, with the best values recommended for level energies, half-lives, γ–ray energies and intensities, decay data (energies, intensities and placement of radiations), and other spectroscopic data. This work supersedes the earlier full evaluation of A = 209 by M.J. Martin (1991Ma16)

  20. Nuclear Data Sheets for A = 248

    Energy Technology Data Exchange (ETDEWEB)

    Martin, M.J.

    2014-11-15

    Detailed level schemes, decay schemes, and the experimental data on which they are based are presented for all nuclei with mass number A=248. The experimental reaction and decay data are evaluated; inconsistencies and discrepancies are noted; and adopted values are given for various level properties (including spin and parity, halflife, and configuration), γ properties (including energy, intensity, and multipole character) and α properties (including energy, intensity, and hindrance factor). This evaluation replaces the A=248 evaluation published by A. Akovali in Nuclear Data Sheets 87, 249 (1999)

  1. Use of integral experiments in support to the validation of JEFF-3.2 nuclear data evaluation

    Science.gov (United States)

    Leclaire, Nicolas; Cochet, Bertrand; Jinaphanh, Alexis; Haeck, Wim

    2017-09-01

    For many years now, IRSN has developed its own Monte Carlo continuous energy capability, which allows testing various nuclear data libraries. In that prospect, a validation database of 1136 experiments was built from cases used for the validation of the APOLLO2-MORET 5 multigroup route of the CRISTAL V2.0 package. In this paper, the keff obtained for more than 200 benchmarks using the JEFF-3.1.1 and JEFF-3.2 libraries are compared to benchmark keff values and main discrepancies are analyzed regarding the neutron spectrum. Special attention is paid on benchmarks for which the results have been highly modified between both JEFF-3 versions.

  2. Nuclear Data Sheets for A = 230

    Energy Technology Data Exchange (ETDEWEB)

    Browne, E.; Tuli, J.K. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, New York 11973-5000 (United States)

    2012-08-15

    The evaluators present in this publication spectroscopic data and level schemes from radioactive decay and nuclear reactions for all isobars with mass number A=230. This evaluation includes the first experimental evidence of {sup 230}Am, produced through the {sup 197}Au({sup 40}Ar,3n){sup 234}Bk ({alpha} decay to {sup 230}Am) reaction, E({sup 40}Ar)=188.4 MeV (2003MoZX).

  3. Retrieval system of nuclear data for transmutation of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Mitsutane; Utsumi, Misako; Noda, Tetsuji [National Research Inst. for Metals, Tsukuba, Ibaraki (Japan)

    1997-03-01

    A database storing the data on nuclear reaction was built to calculate for simulating transmutation behaviours of materials /1/-/3/. In order to retrieve and maintain the database, the user interface for the data retrieval was developed where special knowledge on handling of the database or the machine structure is not required for end-user. It is indicated that using the database, the possibility of He formation and radioactivity in a material can be easily retrieved though the evaluation is qualitatively. (author)

  4. Proceedings of the 1999 symposium on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Yamano, Naoki; Fukahori, Tokio [eds.

    2000-03-01

    The 1999 Symposium on Nuclear Data was held at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), on 18th and 19th of November 1999. Japanese Nuclear Data Committee and Nuclear Data Center, JAERI organized this symposium. In the oral sessions, presented papers were on keynote address, nuclear data measurement for long-lived RI and in medium energy region, status of JENDL, international session and other topics. In the poster session, presented papers were concerning experiments, evaluations, benchmark tests and on-line database on nuclear data. Those presented papers are compiled in the proceedings. The 64 of the presented papers are indexed individually. (J.P.N.)

  5. Recent Nuclear Astrophysics Data Activities in the US

    Energy Technology Data Exchange (ETDEWEB)

    Bardayan, D.W.; Blackmon, J.C.; Browne, E.; Firestone, R.B.; Hale, G.M.; Hoffman, R.D.; Ma, Z.; McLane, V.; Norman, E.B.; Shu, N.; Smith, D.L.; Smith, M.S.; Van Wormer, L.A.; Woosley, S.E.; Wu, S.-C.

    1999-08-30

    Measurements in nuclear physics laboratories form the empirical foundation for new, realistic, sophisticated theoretical models of a wide variety of astrophysical systems. The predictive power of these models has, in many instances, a strong dependence on the input nuclear data, and more extensive and accurate nuclear data is required for these models than ever before. Progress in astrophysics can be aided by providing scientists with more usable, accurate, and significant amounts of nuclear data in a timely fashion in formats that can be easily incorporated into their models. A number of recent data compilations, evaluations, calculations, and disseminations that address nuclear astrophysics data needs will be described.

  6. Nuclear explosives testing readiness evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Valk, T.C.

    1993-09-01

    This readiness evaluation considers hole selection and characterization, verification, containment issues, nuclear explosive safety studies, test authorities, event operations planning, canister-rack preparation, site preparation, diagnostic equipment setup, device assembly facilities and processes, device delivery and insertion, emplacement, stemming, control room activities, readiness briefing, arming and firing, test execution, emergency response and reentry, and post event analysis to include device diagnostics, nuclear chemistry, and containment. This survey concludes that the LLNL program and its supporting contractors could execute an event within six months of notification, and a second event within the following six months, given the NET group`s evaluation and the following three restraints: (1) FY94 (and subsequent year) funding is essentially constant with FY93, (2) Preliminary work for the initial event is completed to the historical sic months status, (3) Critical personnel, currently working in dual use technologies, would be recallable as needed.

  7. Horizontal Compilations of Nuclear Data III

    Science.gov (United States)

    Soroko, Z. N.; Sukhoruchkin, S. I.; Sukhoruchkin, D. S.

    2001-11-01

    Compilations of resonance parameters for all nuclei (horizontal-type compilations) derived from study of reactions with neutrons and charge particles are described. Systematic trends in experimental data due to the differences in energy scales of spectrometers were found after comparison of data for many nuclei. The combination of data from horizontal-type compilations with data from the well-known file ENSDF expands the usefulness of these data files.

  8. Propagation of nuclear data uncertainty: Exact or with covariances

    Directory of Open Access Journals (Sweden)

    van Veen D.

    2010-10-01

    Full Text Available Two distinct methods of propagation for basic nuclear data uncertainties to large scale systems will be presented and compared. The “Total Monte Carlo” method is using a statistical ensemble of nuclear data libraries randomly generated by means of a Monte Carlo approach with the TALYS system. These libraries are then directly used in a large number of reactor calculations (for instance with MCNP after which the exact probability distribution for the reactor parameter is obtained. The second method makes use of available covariance files and can be done in a single reactor calculation (by using the perturbation method. In this exercise, both methods are using consistent sets of data files, which implies that covariance files used in the second method are directly obtained from the randomly generated nuclear data libraries from the first method. This is a unique and straightforward comparison allowing to directly apprehend advantages and drawbacks of each method. Comparisons for different reactions and criticality-safety benchmarks from 19F to actinides will be presented. We can thus conclude whether current methods for using covariance data are good enough or not.

  9. Use of integral experiments in support to the validation of JEFF-3.2 nuclear data evaluation

    Directory of Open Access Journals (Sweden)

    Leclaire Nicolas

    2017-01-01

    Full Text Available For many years now, IRSN has developed its own Monte Carlo continuous energy capability, which allows testing various nuclear data libraries. In that prospect, a validation database of 1136 experiments was built from cases used for the validation of the APOLLO2-MORET 5 multigroup route of the CRISTAL V2.0 package. In this paper, the keff obtained for more than 200 benchmarks using the JEFF-3.1.1 and JEFF-3.2 libraries are compared to benchmark keff values and main discrepancies are analyzed regarding the neutron spectrum. Special attention is paid on benchmarks for which the results have been highly modified between both JEFF-3 versions.

  10. Nuclear Data Sheets for A = 183

    Science.gov (United States)

    Baglin, Coral M.

    2016-05-01

    Evaluated nuclear structure and decay data for all nuclides with mass number A=183 (Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb) are presented here. At, Po and Fr have not yet been observed, but for prediction of ground state and/or isomer properties see, e.g., 2015Bh08 (At, Fr), 2013Ba41 (Tl), 2013Ho05 (Po). This evaluation includes structure and decay data information available by 15 April 2015 and supersedes that by R.B. Firestone published in Nuclear Data Sheets65, 589 (1992) (literature cutoff 9 January 1991), and subsequent revisions by C.M. Baglin for 183Au in ENSDF database (literature cutoff 13 March 1999), 183Hg in Nuclear Data Sheets91, 117 (2000) (literature cutoff 25 September 2000), 183Tl in Nuclear Data Sheets95, 49 (2002) (literature cutoff 1 January 2002) and 183Pb in ENSDF (literature cutoff 6 January 2003). Since the prior Nuclear Data Sheets publication of this mass chain: 183Yb (2012Ku26) and 183Pb (2006An11, 2006Se18, 2007De09, 2009Se13) have been observed; our knowledge of high-spin states has been significantly expanded for 183Ta (2009Sh17), 183W (1999Sa60), 183Re (1998Ha51, 2001Sh41), 183Au (2002Jo18, 2005So01) and 183Tl (2001Mu26, 2004Ra28); a large amount of new structure information for 183W has been obtained from transfer reactions (1997Pr02, 2011Bo09), (n,n'γ) (1993Pr09) and thermal neutron capture (1993Pr09, 1997Pr02, 2011Bo09, 2014Hu02), as well as from the two-photon cascade study by 2005Su29.

  11. Nuclear Data Sheets for A = 183

    Energy Technology Data Exchange (ETDEWEB)

    Baglin, Coral M.

    2016-05-15

    Evaluated nuclear structure and decay data for all nuclides with mass number A=183 (Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb) are presented here. At, Po and Fr have not yet been observed, but for prediction of ground state and/or isomer properties see, e.g., 2015Bh08 (At, Fr), 2013Ba41 (Tl), 2013Ho05 (Po). This evaluation includes structure and decay data information available by 15 April 2015 and supersedes that by R.B. Firestone published in Nuclear Data Sheets65, 589 (1992) (literature cutoff 9 January 1991), and subsequent revisions by C.M. Baglin for {sup 183}Au in ENSDF database (literature cutoff 13 March 1999), {sup 183}Hg in Nuclear Data Sheets91, 117 (2000) (literature cutoff 25 September 2000), {sup 183}Tl in Nuclear Data Sheets95, 49 (2002) (literature cutoff 1 January 2002) and {sup 183}Pb in ENSDF (literature cutoff 6 January 2003). Since the prior Nuclear Data Sheets publication of this mass chain: {sup 183}Yb (2012Ku26) and {sup 183}Pb (2006An11, 2006Se18, 2007De09, 2009Se13) have been observed; our knowledge of high–spin states has been significantly expanded for {sup 183}Ta (2009Sh17), {sup 183}W (1999Sa60), {sup 183}Re (1998Ha51, 2001Sh41), {sup 183}Au (2002Jo18, 2005So01) and {sup 183}Tl (2001Mu26, 2004Ra28); a large amount of new structure information for {sup 183}W has been obtained from transfer reactions (1997Pr02, 2011Bo09), (n,n'γ) (1993Pr09) and thermal neutron capture (1993Pr09, 1997Pr02, 2011Bo09, 2014Hu02), as well as from the two–photon cascade study by 2005Su29.

  12. Construction of a nuclear data server using TCP/IP

    Energy Technology Data Exchange (ETDEWEB)

    Kawano, Toshihiko; Sakai, Osamu [Kyushu Univ., Fukuoka (Japan)

    1997-03-01

    We construct a nuclear data server which provides data in the evaluated nuclear data library through the network by means of TCP/IP. The client is not necessarily a user but a computer program. Two examples with a prototype server program are demonstrated, the first is data transfer from the server to a user, and the second is to a computer program. (author)

  13. Nuclear Criticality Safety Data Book

    Energy Technology Data Exchange (ETDEWEB)

    Hollenbach, D. F. [Y-12 National Security Complex, Oak Ridge, TN (United States)

    2016-11-14

    The objective of this document is to support the revision of criticality safety process studies (CSPSs) for the Uranium Processing Facility (UPF) at the Y-12 National Security Complex (Y-12). This design analysis and calculation (DAC) document contains development and justification for generic inputs typically used in Nuclear Criticality Safety (NCS) DACs to model both normal and abnormal conditions of processes at UPF to support CSPSs. This will provide consistency between NCS DACs and efficiency in preparation and review of DACs, as frequently used data are provided in one reference source.

  14. File and object replication in data grids

    CERN Document Server

    Stockinger, H E; Allcock, B; Foster, I; Holtman, K; Tierney, B L

    2001-01-01

    Data replication is a key issue in a data grid and can be managed in different ways and at different levels of granularity: for example, at the file level or the object level. In the high-energy physics community, data grids are being developed to support the distributed analysis of experimental data. We have produced a prototype data replication tool, the Grid Data Management Pilot (GDMP) that is in production use in one physics experiment, with middleware provided by the Globus toolkit used for authentication, data movement and other purposes. We present a new, enhanced GDMP architecture and prototype implementation that uses Globus data-grid tools for efficient file replication. We also explain how this architecture can address object replication issues in an object-oriented database management system. File transfer over wide-area networks requires specific performance tuning in order to gain optimal data transfer rates. We present performance results obtained with GridFTP, an enhanced version of FTP, and ...

  15. Sandia Data Archive (SDA) file specifications

    Energy Technology Data Exchange (ETDEWEB)

    Dolan, Daniel H. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ao, Tommy [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-01

    The Sandia Data Archive (SDA) format is a specific implementation of the HDF5 (Hierarchal Data Format version 5) standard. The format was developed for storing data in a universally accessible manner. SDA files may contain one or more data records, each associated with a distinct text label. Primitive records provide basic data storage, while compound records support more elaborate grouping. External records allow text/binary files to be carried inside an archive and later recovered. This report documents version 1.0 of the SDA standard. The information provided here is sufficient for reading from and writing to an archive. Although the format was original designed for use in MATLAB, broader use is encouraged.

  16. Analysis of statistical model properties from discrete nuclear structure data

    Science.gov (United States)

    Firestone, Richard B.

    2012-02-01

    Experimental M1, E1, and E2 photon strengths have been compiled from experimental data in the Evaluated Nuclear Structure Data File (ENSDF) and the Evaluated Gamma-ray Activation File (EGAF). Over 20,000 Weisskopf reduced transition probabilities were recovered from the ENSDF and EGAF databases. These transition strengths have been analyzed for their dependence on transition energies, initial and final level energies, spin/parity dependence, and nuclear deformation. ENSDF BE1W values were found to increase exponentially with energy, possibly consistent with the Axel-Brink hypothesis, although considerable excess strength observed for transitions between 4-8 MeV. No similar energy dependence was observed in EGAF or ARC data. BM1W average values were nearly constant at all energies above 1 MeV with substantial excess strength below 1 MeV and between 4-8 MeV. BE2W values decreased exponentially by a factor of 1000 from 0 to 16 MeV. The distribution of ENSDF transition probabilities for all multipolarities could be described by a lognormal statistical distribution. BE1W, BM1W, and BE2W strengths all increased substantially for initial transition level energies between 4-8 MeV possibly due to dominance of spin-flip and Pygmy resonance transitions at those excitations. Analysis of the average resonance capture data indicated no transition probability dependence on final level spins or energies between 0-3 MeV. The comparison of favored to unfavored transition probabilities for odd-A or odd-Z targets indicated only partial support for the expected branching intensity ratios with many unfavored transitions having nearly the same strength as favored ones. Average resonance capture BE2W transition strengths generally increased with greater deformation. Analysis of ARC data suggest that there is a large E2 admixture in M1 transitions with the mixing ratio δ ≈ 1.0. The ENSDF reduced transition strengths were considerably stronger than those derived from capture gamma ray

  17. Analysis of statistical model properties from discrete nuclear structure data

    Directory of Open Access Journals (Sweden)

    Firestone Richard B.

    2012-02-01

    Full Text Available Experimental M1, E1, and E2 photon strengths have been compiled from experimental data in the Evaluated Nuclear Structure Data File (ENSDF and the Evaluated Gamma-ray Activation File (EGAF. Over 20,000 Weisskopf reduced transition probabilities were recovered from the ENSDF and EGAF databases. These transition strengths have been analyzed for their dependence on transition energies, initial and final level energies, spin/parity dependence, and nuclear deformation. ENSDF BE1W values were found to increase exponentially with energy, possibly consistent with the Axel-Brink hypothesis, although considerable excess strength observed for transitions between 4-8 MeV. No similar energy dependence was observed in EGAF or ARC data. BM1W average values were nearly constant at all energies above 1 MeV with substantial excess strength below 1 MeV and between 4-8 MeV. BE2W values decreased exponentially by a factor of 1000 from 0 to 16 MeV. The distribution of ENSDF transition probabilities for all multipolarities could be described by a lognormal statistical distribution. BE1W, BM1W, and BE2W strengths all increased substantially for initial transition level energies between 4-8 MeV possibly due to dominance of spin-flip and Pygmy resonance transitions at those excitations. Analysis of the average resonance capture data indicated no transition probability dependence on final level spins or energies between 0-3 MeV. The comparison of favored to unfavored transition probabilities for odd-A or odd-Z targets indicated only partial support for the expected branching intensity ratios with many unfavored transitions having nearly the same strength as favored ones. Average resonance capture BE2W transition strengths generally increased with greater deformation. Analysis of ARC data suggest that there is a large E2 admixture in M1 transitions with the mixing ratio δ ≈ 1.0. The ENSDF reduced transition strengths were considerably stronger than those derived from

  18. Proceedings of the 1992 symposium on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Baba, Mamoru [ed.] [Tohoku Univ., Sendai (Japan); Nakagawa, Tsuneo [ed.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1993-03-15

    The 1992 Symposium on Nuclear Data was held at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), on 26th and 27th of November, 1992. The symposium was organized by Japanese Nuclear Data Committee and Nuclear Data Center, JAERI. The program of the symposium is listed below. In the oral session, a total of 15 papers were presented under the sessions of present status of revision work of JENDL-3, adjustment of group constants, nuclear data in medium energy region, nuclear data evaluation methods, integral data analyses and topics. In the poster session, presented were 25 papers concerning experiments, evaluations and benchmark tests of nuclear data. Activities of JNDC working groups were also displayed in the poster session. All of the 40 papers except the reports from JNDC working groups are compiled in this proceedings.

  19. Nuclear data evaluation for sup 2 sup 3 sup 7 Np, sup 2 sup 4 sup 1 Am, sup 2 sup 4 sup 2 sup g Am and sup 2 sup 4 sup 2 sup m Am irradiated by neutrons and protons at energies up to 250 MeV

    CERN Document Server

    Konobeyev, A Y; Iwamoto, O

    2002-01-01

    Evaluation of nuclear data has been performed for sup 2 sup 3 sup 7 Np, sup 2 sup 4 sup 1 Am, sup 2 sup 4 sup 2 sup g Am and sup 2 sup 4 sup 2 sup m Am. Neutron data were obtained at energies from 20 to 250 MeV and combined with JENDL-3.3 data at 20 MeV. Evaluation of the proton data has been done from 1 to 250 MeV. The coupled channel optical model was used to obtain angular distributions for elastic and inelastic scattering and transmission coefficients. Pre-equilibrium exciton model and Hauser-Feshbach statistical model were used to describe neutron and charged particles emission from excited nuclei. These evaluation is the first work for producing full sets of evaluated file up to 250 MeV for sup 2 sup 3 sup 7 Np and Americium isotopes.

  20. Nuclear data evaluation for sup 2 sup 3 sup 8 Pu, sup 2 sup 3 sup 9 Pu, sup 2 sup 4 sup 0 Pu, sup 2 sup 4 sup 1 Pu and sup 2 sup 4 sup 2 Pu irradiated by neutrons and protons at the energies up to 250 MeV

    CERN Document Server

    Konobeyev, A Y; Iwamoto, O

    2002-01-01

    The evaluation of nuclear data for plutonium isotopes with atomic mass number from 238 to 242 has been performed. Neutron data were obtained at the energies from 20 to 250 MeV and combined with JENDL-3.3 data at 20 MeV. Evaluation of the proton data has been done from 1 to 250 MeV. The coupled channel optical model was used to obtain angular distributions for elastic and inelastic scattering and transmission coefficients. Pre-equilibrium exciton model and Hauser-Feshbach statistical model were used to describe neutron and charged particles emission from the excited nuclei. These evaluation is the first work for producing the full set of evaluated file up to 250 MeV for plutonium isotopes.

  1. Distributed PACS using distributed file system with hierarchical meta data servers.

    Science.gov (United States)

    Hiroyasu, Tomoyuki; Minamitani, Yoshiyuki; Miki, Mitsunori; Yokouchi, Hisatake; Yoshimi, Masato

    2012-01-01

    In this research, we propose a new distributed PACS (Picture Archiving and Communication Systems) which is available to integrate several PACSs that exist in each medical institution. The conventional PACS controls DICOM file into one data-base. On the other hand, in the proposed system, DICOM file is separated into meta data and image data and those are stored individually. Using this mechanism, since file is not always accessed the entire data, some operations such as finding files, changing titles, and so on can be performed in high-speed. At the same time, as distributed file system is utilized, accessing image files can also achieve high-speed access and high fault tolerant. The introduced system has a more significant point. That is the simplicity to integrate several PACSs. In the proposed system, only the meta data servers are integrated and integrated system can be constructed. This system also has the scalability of file access with along to the number of file numbers and file sizes. On the other hand, because meta-data server is integrated, the meta data server is the weakness of this system. To solve this defect, hieratical meta data servers are introduced. Because of this mechanism, not only fault--tolerant ability is increased but scalability of file access is also increased. To discuss the proposed system, the prototype system using Gfarm was implemented. For evaluating the implemented system, file search operating time of Gfarm and NFS were compared.

  2. Task force for integral test of High Energy nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    According to completion of the JENDL-High Energy file for neutron nuclear cross sections up to 50 MeV, a task force for integral test of high energy nuclear data was organized to discuss a guide line for integral test activities. A status of existing differential and integral experiments and how to perform such a test were discussed in the task force. Here the purpose and outline of the task force is explained with some future problems raised in discussion among the task member. (author)

  3. Compilation of nuclear decay data used for dose calculations. Data for radionuclides not listed in ICRP publication 38

    Energy Technology Data Exchange (ETDEWEB)

    Endo, Akira; Yamaguchi, Yasuhiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Tamura, Tsutomu

    1999-07-01

    Nuclear decay data used for dose calculations were compiled for 162 nuclides with half-lives greater than or equal to 10 min that are not listed in ICRP Publication 38 (Publ. 38) and their 28 daughter nuclides. Additional 14 nuclides that are considered to be important in fusion reactor facilities were also included. The data were compiled using decay data sets of the Evaluated Nuclear Structure Data File (ENSDF), the latest version in August 1997. Investigations of the data sets were performed to check their consistency by referring to recent literature and NUBASE, the database for nuclear and decay properties of nuclides, and by using the utility programs of ENSDF. Possible revisions of the data sets were made for their format and syntax errors, level schemes, normalization records, and so on. The revised data sets were processed by EDISTR in order to calculate the energies and intensities of {alpha} particles, {beta} particles, {gamma} rays including annihilation photons, internal conversion electrons, X rays, and Auger electrons emitted in nuclear transformations of the radionuclides. For spontaneously fissioning nuclides, the average energies and intensities of neutrons, fission fragments, prompt {gamma} rays, delayed {gamma} rays, and {beta} particles were also calculated. The compiled data were presented in two types of format; Publ. 38 and NUCDECAY formats. This report provides the decay data in the Publ. 38 format along with decay scheme drawings. The data will be widely used for internal and external dose calculations in radiation protection. (author)

  4. Covariance Data File Formats for Whisper-1.0 & Whisper-1.1

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rising, Michael Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-01-09

    Whisper is a statistical analysis package developed in 2014 to support nuclear criticality safety (NCS) validation. It uses the sensitivity profile data for an application as computed by MCNP6 along with covariance files for the nuclear data to determine a baseline upper-subcritical-limit (USL) for the application. Whisper version 1.0 was first developed and used at LANL in 2014. During 2015-2016, Whisper was updated to version 1.1 and is to be included with the upcoming release of MCNP6.2. This report describes the file formats used for the covariance data in both Whisper-1.0 and Whisper-1.1.

  5. Nuclear Data Sheets for A = 247

    Energy Technology Data Exchange (ETDEWEB)

    Nesaraja, C.D.

    2015-03-15

    Available information pertaining to the nuclear structure of all nuclei with mass numbers A=247 is presented. Various decay and reaction data are evaluated and compared. Adopted data, levels, spin, parity and configuration assignments are given. When there are insufficient data, expected values from systematics of nuclear properties or/and theoretical calculations are quoted. Unexpected or discrepant experimental results are also noted. A summary and compilation of the discovery of various isotopes in this mass region is given in 2013Fr02 ({sup 247}Pu, {sup 247}Am, {sup 247}Cm, {sup 243}Bk, {sup 247}Cf), 2011Me01 ({sup 247}Es), and 2013Th02 ({sup 247}Fm, {sup 247}Md)

  6. Nuclear Data Sheets for A = 243

    Energy Technology Data Exchange (ETDEWEB)

    Nesaraja, C.D. [Physics Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831–6354 (United States); McCutchan, E.A. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, New York 11973–5000 (United States)

    2014-09-15

    Available information pertaining to the nuclear structure of all nuclei with mass numbers A=243 is presented. Various decay and reaction data are evaluated and compared. Adopted data, levels, spin, parity and configuration assignments are given. When there are insufficient data, expected values from systematics of nuclear properties or/and theoretical calculations are quoted. Unexpected or discrepant experimental results are also noted. A summary and compilation of the discovery of various isotopes in this mass region is given in 2013Fr02 ({sup 243}Np, {sup 243}Pu, {sup 243}Am, {sup 243}Cm, {sup 243}Bk, and {sup 243}Cf), 2011Me01 ({sup 243}Es), and 2013Th02 ({sup 243}Fm)

  7. Distributed Data Management and Distributed File Systems

    CERN Document Server

    Girone, Maria

    2015-01-01

    The LHC program has been successful in part due to the globally distributed computing resources used for collecting, serving, processing, and analyzing the large LHC datasets. The introduction of distributed computing early in the LHC program spawned the development of new technologies and techniques to synchronize information and data between physically separated computing centers. Two of the most challenges services are the distributed file systems and the distributed data management systems. In this paper I will discuss how we have evolved from local site services to more globally independent services in the areas of distributed file systems and data management and how these capabilities may continue to evolve into the future. I will address the design choices, the motivations, and the future evolution of the computing systems used for High Energy Physics.

  8. Distributed Data Management and Distributed File Systems

    Science.gov (United States)

    Girone, Maria

    2015-12-01

    The LHC program has been successful in part due to the globally distributed computing resources used for collecting, serving, processing, and analyzing the large LHC datasets. The introduction of distributed computing early in the LHC program spawned the development of new technologies and techniques to synchronize information and data between physically separated computing centers. Two of the most challenges services are the distributed file systems and the distributed data management systems. In this paper I will discuss how we have evolved from local site services to more globally independent services in the areas of distributed file systems and data management and how these capabilities may continue to evolve into the future. I will address the design choices, the motivations, and the future evolution of the computing systems used for High Energy Physics.

  9. Nuclear Data Sheets for A = 192

    Science.gov (United States)

    Baglin, Coral M.

    2012-08-01

    Experimental structure and decay data for all nuclei with mass A=192 (Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po, At) have been evaluated. This evaluation, covering data received by 15 June 2012, supersedes the 1998 evaluation by C. M. Baglin (Nuclear Data Sheets84, 717 (1998), literature cutoff August 1998) and the subsequent inclusion in the ENSDF database of the new nuclide 192At (C. M. Baglin, literature cutoff 16 May 2006). It also incorporates the current evaluation of superdeformed-band information by B. Singh. Since the last publication, 192Ta, 192W and 192At have been observed, and an isomeric state has been identified in 192Re. The ɛ decay of 192Au has been studied using a multidetector array resulting in an extensively revised level scheme for 192Pt.

  10. Neutron- and proton-induced nuclear data evaluation of thorium, uranium and curium isotopes for energies up to 250 MeV

    CERN Document Server

    Young, Ouk Lee; Jonghwa, Chang; Konobeyev, A Yu

    2004-01-01

    The evaluation of neutron- and proton nuclear data for thorium-232, U-233,234,236, and Cm-243,244,245,246 isotopes have been performed at energies up to 250 MeV. Neutron data was evaluated at energies from 20 MeV to 250 MeV, and combined with the JENDL-3.3 data at 20 MeV while proton data was obtained for energies from 1 to 250 MeV. Nuclear model parameters are largely based on the IAEA-RIPL recommendation, and adjusted to better reproduce the available measurements. The coupled channel optical model was applied to calculate the total, reaction, elastic, and direct inelastic cross sections, and to obtain the transmission coefficients. Decay of excited nuclei was described with the Hauser-Feshbach and exciton models using the GNASH code to simultaneously handle neutron, proton, deuteron, triton, helium-3, alpha , gamma emissions and fissions. Special attention was paid on the fission cross sections for energies where experimental data are scant, using appropriate systematics and fittings. Particles and gamma e...

  11. Establishment and Analysis of Nuclear Structure Data DB for Nuclear Safety Regulation Technique Applications

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Ouk; Yoo, Jae Kwon; Gil, Choong; Cho, Young Sik; Kim, Hyung Il; Kim, Jong Woon; Kwon, Duk Hee; Lee, Jong Hwa

    2013-10-15

    The contents of the project consisting of four research fields carried out are: Ο Installation of DB with nuclear structure/decay datasets - Setup a computer system for production of nuclear structure/decay data in ENSDF format - Production of nuclear structure/decay data in ENSDF format({sup 211}, {sup 215}Po, {sup 136}Cs) and setup a data converting system from ENSDF format to ENDF-6 format. Ο Computer simulation of nuclear decay and burnup using the ENSDF DB - Calculation of decay heats of the several radioactive nuclides with Geant4 - Burnup calculation with full decay chain using Monte Carlo method Ο Comparison and analysis of nuclear structure/decay and fission product yields data. - Acquisitions and Analyses of decay and fission yields data in ENDF-6 format - Research for theoretical evaluation method of fission product yields data. Ο Analysis of SCALE(ORIGEN-s, -ARP) libraries - Analysis of ORIGEN library structure of nuclear decay/yields data. - Methodological studies to improve nuclear decay/yield ORIGEN libraries by use of nuclear structure/yield data in ENDF-6 format. The results of this project will be a basis to establish the nuclear decay and fission yield data DB in Korea. Additionally, new decay and yield data can be immediately served for the users to utilize those data for nuclear research and/or development.

  12. Central Personnel Data File (CPDF) Status Data

    Data.gov (United States)

    Office of Personnel Management — Precursor to the Enterprise Human Resources Integration-Statistical Data Mart (EHRI-SDM). It contains data about the employee and their position, along with various...

  13. The nuclear data program at rensselaer

    Science.gov (United States)

    Danon, Y.; Blain, Z.; Bahran, R.; Rapp, M.; Thompson, J.; Williams, D.; Leinweber, G.; Barry, D.; Block, R.; Hoole, J.

    2010-10-01

    The nuclear data program at the Rensselaer Polytechnic Institute (RPI) is centered around a 60 MeV pulsed electron Linear Accelerator (LINAC) configured to deliver pulsed neutron beams. The LINAC electron pulse width can vary between 5 ns and 5 us, a repetition rate of 1-500 pulses per second and neutron yield of up to 1013 n/s. Over the years several experimental setups and techniques were developed to enable a variety of measurement capabilities. The experiments cover the energy range from 0.001 eV to 20 MeV and included neutron transmission, capture, scattering and fission measurements. The facility is also equipped with a Lead Slowing-Down Spectrometer (LSDS) producing a high neutron flux that is used for simultaneous measurements of the fission cross section and fission fragment mass and energy distributions. Detectors for (n, alpha) and (n, p) cross section measurements using the LSDS were also developed and measurements of (n, alpha) cross section were completed. The high neutron flux inside the LSDS enables measurements on small samples (sub micrograms) or samples with small cross section (sub millibarns). In order to fully utilize the capabilities of the facility, several measurement techniques were developed; high accuracy (modular detectors for both fast and resonance region neutron detection were developed and deployed. These developments result in numerous measurements on different materials and provide input to improved evaluated nuclear data libraries and thus help improve the accuracy of calculations of nuclear reactors and other nuclear systems.

  14. A nuclear cross section data handbook

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, H.O.M.

    1989-12-01

    Isotopic information, reaction data, data availability, heating numbers, and evaluation information are given for 129 neutron cross-section evaluations, which are the source of the default cross sections for the Monte Carlo code MCNP. Additionally, pie diagrams for each nuclide displaying the percent contribution of a given reaction to the total cross section are given at 14 MeV, 1 MeV, and thermal energy. Other information about the evaluations and their availability in continuous-energy, discrete-reaction, and multigroup forms is provided. The evaluations come from ENDF/B-V, ENDL85, and the Los Alamos Applied Nuclear Science Group T-2. Graphs of all neutron and photon production cross-section reactions for these nuclides have been categorized and plotted. 21 refs., 5 tabs.

  15. Estimation of covariances of Cr and Ni neutron nuclear data in JENDL-3.2

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Oh, Soo Youl [Korea Atomic Energy Research Institute, Taejon (Korea)

    2000-02-01

    Covariances of nuclear data have been estimated for 2 nuclides contained in JENDL-3.2. The nuclides considered are Cr and Ni, which are regarded as important for the nuclear design study of fast reactors. The physical quantities for which covariances are deduced are cross sections and the first order Legendre-polynomial coefficient for the angular distribution of elastically scattered neutrons. The covariances were estimated by using the same methodology that had been used in the JENDL-3.2 evaluation in order to keep a consistency between mean values and their covariances. The least-squares fitting code GMA was used in estimating covariances for reactions of which JENDL-3.2 cross sections had been evaluated by taking account of measurements. Covariances of nuclear model calculations were deduced by using the KALMAN system. The covariance data obtained were compiled in the ENDF-6 format, and will be put into the JENDL-3.2 Covariance File which is one of JENDL special purpose files. (author)

  16. Supplemental Security Income Public-Use Microdata File, 2001 Data

    Data.gov (United States)

    Social Security Administration — The SSI Public-Use Microdata File contains an extract of data fields from SSA's Supplemental Security Record file and consists of a 5 percent random, representative...

  17. Status and future plan of nuclear data activities in China

    Energy Technology Data Exchange (ETDEWEB)

    Zhuang Youxiang; Tang Hongqing [Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy

    1997-03-01

    The present status and future plan of nuclear data measurement and evaluation in China are presented, including the supplement, improvement on CENDL-2.1 and benchmark test of CENDL-2.1, the progress on nuclear data measurement and CENDL-3. (author)

  18. Strategy on review method for JENDL High Energy File

    Energy Technology Data Exchange (ETDEWEB)

    Yamano, Naoki [Sumitomo Atomic Energy Industries Ltd., Tokyo (Japan)

    1998-11-01

    Status on review method and problems for a High Energy File of Japanese Evaluated Nuclear Data Library (JENDL-HE File) has been described. Measurements on differential and integral data relevant to the review work for the JENDL-HE File have been examined from a viewpoint of data quality and applicability. In order to achieve the work effectively, strategy on development of standard review method has been discussed as well as necessity of tools to be used in the review scheme. (author)

  19. Proposal of new 235U nuclear data to improve keff biases on 235U enrichment and temperature for low enriched uranium fueled lattices moderated by light water

    OpenAIRE

    Wu, H; 奥村 啓介; 柴田 恵一

    2005-01-01

    The under prediction of keff depending on 235U enrichment in low enriched uranium fueled systems was studied in this report. Benchmark testing was carried out with several evaluated nuclear data files, including the new uranium evaluations from preliminary ENDF/B-VII and CENDL-3.1. Another problem reviewed here was keff underestimation vs. temperature increase, which was observed in the slightly enriched system with recent JENDL and ENDF/B uranium evaluations. Through the substitute analysis ...

  20. The NUBASE2016 evaluation of nuclear properties

    Energy Technology Data Exchange (ETDEWEB)

    Audi, G.; Kondev, F. G.; Wang, Meng; Huang, W. J.; Naimi, S.

    2017-03-01

    This paper presents the NUBASE2016 evaluation that contains the recommended values for nuclear and decay properties of 3437 nuclides in their ground and excited isomeric (T1/2≥100 ns) states. All nuclides for which any experimental information is known were considered. NUBASE2016 covers all data published by October 2016 in primary (journal articles) and secondary (mainly laboratory reports and conference proceedings) references, together with the corresponding bibliographical information. During the development of NUBASE2016, the data available in the “Evaluated Nuclear Structure Data File” (ENSDF) database were consulted and critically assessed for their validity and completeness. Furthermore, a large amount of new data and some older experimental results that were missing from ENSDF were compiled, evaluated and included in NUBASE2016. The atomic mass values were taken from the “Atomic Mass Evaluation” (AME2016, second and third parts of the present issue). In cases where no experimental data were available for a particular nuclide, trends in the behavior of specific properties in neighboring nuclides (TNN) were examined. This approach allowed to estimate values for a range of properties that are labeled in NUBASE2016 as “non-experimental” (flagged “#”). Evaluation procedures and policies used during the development of this database are presented, together with a detailed table of recommended values and their uncertainties. AMDC: http://amdc.impcas.ac.cn/

  1. Nuclear Data Sheets for A = 80

    Science.gov (United States)

    Singh, Balraj

    2005-06-01

    Nuclear spectroscopic information for known nuclides of mass number 80 (Cu,Zn,Ga,Ge,As,Se,Br,Kr,Rb,Sr,Y,Zr) with Z = 29 to 40 and N = 51 to 40 have been evaluated and presented together with adopted energies and Jπ of levels in these nuclei. No excited state data are yet available for 80Cu and 80Zn. In 80Sr, four superdeformed bands have been reported. The half-life of fully-ionized 80Y isomer at 228.5 keV has been measured as 6.8 s 5, as compared to 4.8 s 3 for the neutral atom. This evaluation supersedes previous full evaluations of A = 80 published by 1982Si20 and 1975Gr19, a midstream evaluation of A = 80 published in 'up-date mode' by 1992Si19, and an update of 80Y nuclide for ENSDF by J.K. Tuli in August 2003.

  2. The Decay Data Evaluation Project (DDEP) and the JEFF-3.3 radioactive decay data library: Combining international collaborative efforts on evaluated decay data

    Science.gov (United States)

    Kellett, Mark A.; Bersillon, Olivier

    2017-09-01

    The Decay Data Evaluation Project (DDEP), is an international collaboration of decay data evaluators formed with groups from France, Germany, USA, China, Romania, Russia, Spain and the UK, mainly from the metrology community. DDEP members have evaluated over 220 radionuclides, following an agreed upon methodology, including a peer review. Evaluations include all relevant parameters relating to the nuclear decay and the associated atomic processes. An important output of these evaluations are recommendations for new measurements, which can serve as a basis for future measurement programmes. Recently evaluated radionuclides include: 18F, 59Fe, 82Rb, 82Sr, 88Y, 90Y, 89Zr, 94mTc, 109Cd, 133Ba, 140Ba, 140La, 151Sm and 169Er. The DDEP recommended data have recently been incorporated into the JEFF-3.3 Radioactive Decay Data Library. Other sources of nuclear data include 900 or so radionuclides converted from the Evaluated Nuclear Structure Data File (ENSDF), 500 from two UK libraries (UKPADD6.12 and UKHEDD2.6), the IAEA Actinide Decay Data Library, with the remainder converted from the NUBASE evaluation of nuclear properties. Mean decay energies for a number of radionuclides determined from total absorption gamma-ray spectroscopy (TAGS) have also been included, as well as more recent European results from TAGS measurements performed at the University of Jyväskylä by groups from the University of Valencia, Spain and SUBATECH, the University of Nantes, France. The current status of the DDEP collaboration and the JEFF Radioactive Decay Data Library will be presented. Note to the reader: the pdf file has been changed on September 22, 2017.

  3. Nuclear Data Needs and Capabilities for Applications

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-05-27

    In July 2014, DOE NP carried out a review of the US Nuclear Data Program. This led to several recommendations, including that the USNDP should “devise effective and transparent mechanisms to solicit input and feedback from all stakeholders on nuclear data needs and priorities.” The review also recommended that USNDP pursue experimental activities of relevance to nuclear data; the revised 2014 Mission Statement accordingly states that the USNDP uses “targeted experimental studies” to address gaps in nuclear data. In support of these recommendations, DOE NP requested that USNDP personnel organize a Workshop on Nuclear Data Needs and Capabilities for Applications (NDNCA). This Workshop was held at Lawrence Berkeley National Laboratory (LBNL) on 27-29 May 2015. The goal of the NDNCA Workshop was to compile nuclear data needs across a wide spectrum of applied nuclear science, and to provide a summary of associated capabilities (accelerators, reactors, spectrometers, etc.) available for the required measurements. The first two days of the workshop consisted of 25 plenary talks by speakers from 16 different institutions, on nuclear energy (NE), national security (NS), isotope production (IP), and industrial applications (IA). There were also shorter “capabilities” talks that described the experimental facilities and instrumentation available for the measurement of nuclear data. This was followed by a third day of topic-specific “breakout” sessions and a final closeout session. The agenda and copies of these talks are available online at http://bang.berkeley.edu/events/NDNCA/agenda. The importance of nuclear data to both basic and applied nuclear science was reflected in the fact that while the impetus for the workshop arose from the 2014 USNDP review, joint sponsorship for the workshop was provided by the Nuclear Science and Security Consortium, a UC-Berkeley based organization funded by the National Nuclear Security Administration (NNSA).

  4. Nuclear data in the proton induced reactions

    Energy Technology Data Exchange (ETDEWEB)

    Bhang, H. C. [Seoul National Univ., Seoul (Korea); Cha, D. W. [Inha Univ., Incheon (Korea); Yu, K. H. [Daebul Eng. College, Youngam (Korea); Kim, Y. D. [Sejong Univ., Seoul (Korea); Chai, J. S. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2001-04-01

    Nuclear data in the intermediate energy nuclear reaction are much needed in many research areas like nuclear transmutation, burning of the long lived nuclear waste materials, accelerator driven subcritical nuclear reactor engineering, nuclear medical physics and cosmic sciences. Currently available nuclear data for the intermediate energy nuclear reaction are not sufficient enough for the basic research and development in these areas. Though many of the required data are generated from the theoretical model calculations, there are limits for such applications and the real data produced in the laboratory experiments are very much needed. In Korea the capability to produce such nuclear data from laboratory experiments are primitive. So far no infrastructure has been established for the measurements of nuclear data in such energy regions. In the current research we have developed an intranuclear cascade code, from the scratch, for the production and the propagation of nucleons in the intermediate energy nuclear reaction region, whose data are more uncertain compared to those of the intermediate energy nuclear reaction region, whose data are more uncertain compared to those of the statistical region and the direct reaction region. We have also performed a few proton induced nuclear reaction experiments, for instance, (p,p), (p,n), and (p,a), using the 50 MeV and 35 MeV protons from the MC-50 cyclotron of KCCH. Through these experiments we have developed a Csl high energy charged particle detector, a neutron TOF system, and the {delta}-E-E telescope for the wide dynamic charged particle measurements. Two papers from these experiments have been published and one in the process or refreeing in the SCI journal, JKPS. 26 refs., 23 figs., 3 tabs. (Author)

  5. Quantification of Uncertainties due to 235,238U, 239,240,241Pu and Fission Products Nuclear Data Uncertainties for a PWR Fuel Assembly

    Science.gov (United States)

    da Cruz, D. F.; Rochman, D.; Koning, A. J.

    2014-04-01

    Uncertainty analysis on reactivity and discharged inventory for a typical PWR fuel element as a result of uncertainties in 235,238U, 239,240,241Pu, and fission products nuclear data was performed. The Total Monte-Carlo (TMC) method was applied using the deterministic transport code DRAGON. The nuclear data used in this study is from the JEFF-3.1 evaluations, with the exception of the nuclear data files for U, Pu and fission products isotopes, which are taken from the nuclear data library TENDL-2012. Results show that the calculated total uncertainty in keff (as result of uncertainties in nuclear data of the considered isotopes) is virtually independent on fuel burnp and amounts to 700 pcm. The uncertainties in inventory of the discharged fuel is dependent on the element considered and lies in the range 1-15% for most fission products, and is below 5% for the most important actinides.

  6. Nuclear Data for Astrophysical Modeling

    OpenAIRE

    Pritychenko, Boris

    2016-01-01

    Nuclear physics has been playing an important role in modern astrophysics and cosmology. Since the early 1950's it has been successfully applied for the interpretation and prediction of astrophysical phenomena. Nuclear physics models helped to explain the observed elemental and isotopic abundances and star evolution and provided valuable insights on the Big Bang theory. Today, the variety of elements observed in stellar surfaces, solar system and cosmic rays, and isotope abundances are calcul...

  7. Nuclear reliability assurance data source guide

    Energy Technology Data Exchange (ETDEWEB)

    1976-11-01

    Seven sources of reliability and maintainability data are reviewed for their potential for providing nuclear equipment data. Consideration is given to similarity to nuclear application, variety of equipment types reported, availability of data, and obsolescence of data. In addition, discussions of advantages and disadvantages of each data source are presented, and samples of either the data or the character of the data are included as appendixes.

  8. The nuclear data program at rensselaer

    Directory of Open Access Journals (Sweden)

    Barry D.

    2010-10-01

    Full Text Available The nuclear data program at the Rensselaer Polytechnic Institute (RPI is centered around a 60 MeV pulsed electron Linear Accelerator (LINAC configured to deliver pulsed neutron beams. The LINAC electron pulse width can vary between 5 ns and 5 us, a repetition rate of 1–500 pulses per second and neutron yield of up to 1013 n/s. Over the years several experimental setups and techniques were developed to enable a variety of measurement capabilities. The experiments cover the energy range from 0.001 eV to 20 MeV and included neutron transmission, capture, scattering and fission measurements. The facility is also equipped with a Lead Slowing-Down Spectrometer (LSDS producing a high neutron flux that is used for simultaneous measurements of the fission cross section and fission fragment mass and energy distributions. Detectors for (n, alpha and (n, p cross section measurements using the LSDS were also developed and measurements of (n, alpha cross section were completed. The high neutron flux inside the LSDS enables measurements on small samples (sub micrograms or samples with small cross section (sub millibarns. In order to fully utilize the capabilities of the facility, several measurement techniques were developed; high accuracy (<1% total cross sections were measured using iron and uranium filtered neutron beams. A system for fast neutron scattering measurements using an array of liquid scintillators and a digital data acquisition system was recently developed and used for several measurements and is now being adapted for fission neutron studies. Methods for simultaneous measurements of fission and capture cross sections using the RPI multiplicity detector are under development and new modular detectors for both fast and resonance region neutron detection were developed and deployed. These developments result in numerous measurements on different materials and provide input to improved evaluated nuclear data libraries and thus help

  9. Nuclear Data Sheets for A = 215

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Balraj; Mukherjee, Gopal; Abriola, Daniel [International Atomic Energy Agency (IAEA), Vienna (Austria); Basu, Swapan Kumar [VECC, Kolkata (India); Demetriou, Paraskevi [IAEA, Vienna (Austria); Jain, Ashok [Indian Institute of Technology (IIT), Roorkee (India); Kumar, Suresh [Delhi University, Delhi (India); Singh, Sukhjeet [M.M. University, Mullana, Ambala (India); Tuli, Jagdish [Brookhaven National Laboratory (NNDC, BNL), Upton, NY (United States)

    2013-12-15

    The evaluated spectroscopic data are presented for 12 known nuclides of mass 215 (Hg, Tl, Pb, Bi, Po, At, Rn, Fr, Ra, Ac, Th, Pa). For {sup 215}Hg, {sup 215}Tl, {sup 215}Pb, and {sup 215}Pa nuclei, no excited states are known. The decay characteristics of {sup 215}Hg and {sup 215}Tl are unknown. The decay scheme of {sup 215}Pb is considered as incomplete. Ordering of γ cascades in the decay of 36.9–s isomer of {sup 215}Bi and for high–spin states above 2251 keV in {sup 215}Fr are not established. High–spin excitations, including several isomeric states, are well known in {sup 215}Bi, {sup 215}Po, {sup 215}Rn, {sup 215}Fr, {sup 215}Ra, and {sup 215}Ac. No particle–transfer reaction data are available for any of the A=215 nuclei. The rms charge radii for {sup 215}Pb, {sup 215}Bi, {sup 215}Po, {sup 215}Rn, {sup 215}Fr and {sup 215}Ra have been evaluated by Daniel Abriola, from extrapolation or interpolation of available evaluated data in 2013An02 for radii of respective Z chains using formula 9 in 2004An14. This evaluation was carried out as part of ENSDD–workshop at VECC, Kolkata for Nuclear Structure and Decay Data, organized and hosted by VECC and Board of Research in Nuclear Sciences (BRNS) in Kolkata, India, November 26–29, 2012. This work supersedes the previous A = 215 evaluation (2001Br31) published by E. Browne which covered literature prior to May 2001.

  10. Reports to the ERDA Nuclear Data Committee

    Energy Technology Data Exchange (ETDEWEB)

    Heath, R. L.; Jackson, H.; Smith, A.; Reeder, P.; Chrien, R. E.; Havens, Jr., W. W.; Talbert, Jr., W. L.; Friesenhahn, S. J.; Lurie, N. A.; Lederer, C. M.; Anderson, J. D.; Browne, J. C.; Gardner, D. G.; Jurney, E. T.; Motz, H.; Beghian, L.; Knoll, G.; Bowman, C.; Perey, F. G.; Gentry, J. C.; Lane, R. O.; Ajzenberg-Selove, F.; Block, R. C.; Newson, H.; Woodruff, G.; Firk, F. W.; McEllistrem, M.

    1977-03-01

    This document consists of reports submitted to the Energy Research and Development Administration Nuclear Data Committee in March 1977. It includes the following subjects: microscopic neutron cross sections relevant to the nuclear energy program (including pertinent inverse reactions); relevant charged-particle cross sections; gamma-ray production, radioactive decay, and theoretical developments in nuclear structure applicable to nuclear energy programs; and proton and alpha cross sections up to 1 GeV of interest to the space program. The data should be regarded as preliminary. Papers with significant amounts of data are listed separately by title. (RWR)

  11. Nuclear Data Sheets for A = 79

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Balraj

    2016-07-15

    Nuclear spectroscopic information for known nuclides of mass number 79 (Ni,Cu,Zn,Ga,Ge,As,Se,Br,Kr,Rb, Sr,Y,Zr) has been evaluated and presented together with adopted energies, Jπ, and decay modes of levels in these nuclei. No data are yet available for excited states in {sup 79}Ni, {sup 79}Cu and {sup 79}Zr. The half–life of {sup 79}Se, a nuclide of importance in reactor–irradiated fuel composition has been measured by several independent groups and reported in a number of publications after 1995, and seems to be converging to a narrow margin of experimental values. These measurements were likely prompted by a recommendation made in the 1993 update of A = 79 nuclides (1993Si28), that since a 1949PaZZ report, there had been no measurement until 1993, and that based on simulation studies by 1993HeZW, the value listed in 1949PaZZ, and cited in all data tables and charts for 44 years, was quite likely in error, being too low by a factor of 10. According to conclusions in recent papers such as 2014Do20, there is still room for improvement in the measurement of this half–life, and further experiments are expected. This evaluation supersedes earlier Nuclear Data Sheets for A = 79 (2002Si13,1993Si28, 1982Si21,1975Ur03).

  12. Development of a utility system for charged particle nuclear reaction data by using intelligentPad

    Energy Technology Data Exchange (ETDEWEB)

    Aoyama, Shigeyoshi; Ohbayashi, Yoshihide [Information Processing Center, Kitami Institute of Technology, Kitami, Hokkaido (Japan); Masui, Hiroshi [Meme Media Laboratory, Hokkaido University, Sapporo, Hokkaido (Japan); Kato, Kiyoshi [Hokkaido University, Graduate School of Science, Sapporo, Hokkaido (Japan); Chiba, Masaki [Faculty of Social Information, Sapporo Gakuin Univ., Ebetsu, Hokkaido (Japan)

    2000-03-01

    We have developed a utility system, WinNRDF2, for a nuclear charged particle reaction data of NRDF (Nuclear Reaction Data File) on the IntelligentPad architecture. By using the system, we can search the experimental data of a charged particle reaction of NRDF. Furthermore, we also see the experimental data by using graphic pads which was made through the CONTIP project. (author)

  13. Prospective economical study of the nuclear power file; Etude economique prospective de la filiere electrique nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Charpin, J.M. [Commissariat General du Plan, 75 - Paris (France); Dessus, B. [Ecodev-CNRS, 92 - Meudon (France); Pellat, R. [CEA, 75 - Paris (France)

    2000-07-01

    On May 7, 1999 an economical study of the overall nuclear file, and in particular, of the back-end part of the fuel cycle and including the reprocessing, was requested by the French Prime Minister. This study includes the cost comparisons with the other means of power production and takes into consideration the environmental costs. The study is shared into five chapters dealing with: 1 - the legacy of the past: todays park of nuclear plants, economical and material status; 2 - the international evolution: the dynamics of nuclear policies worldwide (existing parks and R and D programs), the rise of environmental problems worldwide (CO{sub 2} and the climate convention, nuclear risks, attempts of including environment in the power costs), the choices made for the management of spent fuels in the main countries; 3 - the technological prospects for the power production and use: technologies for the mastery of power demand (residential, industrial and tertiary sectors, power transportation), technologies of power production (production from nuclear, fossil and renewable energies); 4 - prospective scenarios for France: two demand scenarios at the year 2050 vista (energy, electric power), power supply (supply structure with respect to scenarios, nuclear parks, power capacities), environmental aspects (CO{sub 2} emissions, plutonium and minor actinides production); 5 - the economical status of the different scenarios: data preparation, fossil fuel price scenarios, investment and operation costs of the different power production means (nuclear, fossil and renewable energies, natural gas and power distribution networks), comparison between fluxes and cumulated economic costs linked with the different scenarios (investments, exploitation, fuels, R and D, status for 2000 to 2050), time structure of expenditures with respect to the different scenarios (chronology, statuses, kWh costs, sensitivity with respect to the rate of discount, valorization of existing parks in 2050

  14. Compilation of nuclear decay data used for dose calculation. Revised data for radionuclides listed in ICRP Publication 38

    Energy Technology Data Exchange (ETDEWEB)

    Endo, Akira; Yamaguchi, Yasuhiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    New nuclear decay data used for dose calculation have been compiled for 817 radionuclides that are listed in ICRP Publication 38 (Publ. 38) and for 6 additional isomers. The decay data were prepared using decay data sets from the Evaluated Nuclear Structure Data File (ENSDF), the latest version in August 1997. Basic nuclear properties in the decay data sets that are particularly important for calculating energies and intensities of emissions were examined and updated by referring to NUBASE, the database for nuclear and decay properties of nuclides. The reviewed and updated data were half-life, decay mode and its branching ratio, spin and parity of the ground and isomeric states, excitation energy of isomers, and Q value. In addition, possible revisions of partial and incomplete decay data sets were done for their format and syntax errors, level schemes, normalization records, and so on. After that, the decay data sets were processed by EDISTR in order to compute the energies and intensities of {alpha} particles, {beta} particles, {gamma} rays, internal conversion electrons, X rays, and Auger electrons emitted in nuclear transformation. For spontaneously fissioning nuclides, the average energies and intensities of neutrons, fission fragments, prompt {gamma} rays, delayed {gamma} rays, and {beta} particles were also calculated. The compiled data were prepared in two different types of format: Publ. 38 and NUCDECAY formats. Comparison of the compiled decay data with those in Publ. 38 was also presented. The decay data will be widely used for internal and external dose calculations in radiation protection and will be beneficial to a future revision of ICRP Publ. 38. (author)

  15. Activities on covariance estimation in Japanese Nuclear Data Committee

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    Described are activities on covariance estimation in the Japanese Nuclear Data Committee. Covariances are obtained from measurements by using the least-squares methods. A simultaneous evaluation was performed to deduce covariances of fission cross sections of U and Pu isotopes. A code system, KALMAN, is used to estimate covariances of nuclear model calculations from uncertainties in model parameters. (author)

  16. Reports to the DOE Nuclear Data Committee

    Energy Technology Data Exchange (ETDEWEB)

    1988-05-01

    The report in this document were submitted to the Department of Energy, Nuclear Data Committee (DOE-NDC) in April 1988. The reporting laboratories are those with a substantial program for the measurement of neutron and nuclear cross sections of relevance to the US applied nuclear energy program. Appropriate subjects are microscopic neutron cross sections relevant to the nuclear energy program, including shielding. Inverse reactions where pertinent are included; charged-particle cross sections where relevant to developing and testing nuclear models; gamma ray production, radioactive decay, and theoretical developments in nuclear structure which are applicable to nuclear energy programs; and proton and alpha-particle cross sections, at energies of up to 1 GeV, which are of interest to the space program.

  17. Data Analysis & Statistical Methods for Command File Errors

    Science.gov (United States)

    Meshkat, Leila; Waggoner, Bruce; Bryant, Larry

    2014-01-01

    This paper explains current work on modeling for managing the risk of command file errors. It is focused on analyzing actual data from a JPL spaceflight mission to build models for evaluating and predicting error rates as a function of several key variables. We constructed a rich dataset by considering the number of errors, the number of files radiated, including the number commands and blocks in each file, as well as subjective estimates of workload and operational novelty. We have assessed these data using different curve fitting and distribution fitting techniques, such as multiple regression analysis, and maximum likelihood estimation to see how much of the variability in the error rates can be explained with these. We have also used goodness of fit testing strategies and principal component analysis to further assess our data. Finally, we constructed a model of expected error rates based on the what these statistics bore out as critical drivers to the error rate. This model allows project management to evaluate the error rate against a theoretically expected rate as well as anticipate future error rates.

  18. Evaluation of cutting ability and plastic deformation of reciprocating files

    Directory of Open Access Journals (Sweden)

    Alexandre KOWALCZUCK

    2016-01-01

    Full Text Available Abstract This in vitro study evaluated the cutting ability of reciprocating files and the deformations caused by their multiple use. Five Reciproc® R25 files were divided into five groups for 10 simulated root canal preparations each. The resin blocks were weighed and photographed (12.5X and 20X before and after preparation. The canals were prepared according to the manufacturer’s instructions. Enlargement of the root canals was evaluated by comparison of pre- and post-preparation images using a computer software. The preoperative and postoperative weight differences determined the cutting ability of repeatedly used instruments. The data were analyzed using Lilliefors and Friedman statistical tests. The cutting ability and enlargement of the canals gradually decreased after each use, with significant differences observed at the 8th and 9th repetitions, respectively. There was no evidence of file deformation. The cutting ability and enlargement of the simulated canals gradually decreased when a reciprocating file was used up to 10 times.

  19. Nuclear Data Sheets for A = 139

    Energy Technology Data Exchange (ETDEWEB)

    Joshi, Paresh K.; Singh, Balraj; Singh, Sukhjeet; Jain, Ashok K.

    2016-12-15

    The experimental nuclear spectroscopic data for known nuclides of mass number 139 (Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy) have been evaluated and presented together with adopted properties for levels and gamma rays. This evaluation represents a revision of previous one (2001Bu16) by T.W. Burrows. Since then extensive new data have become available for many A=139 nuclides although, no excited state data are yet available for {sup 139}Sn, {sup 139}Sb, {sup 139}Tb, and {sup 139}Dy. The decay schemes of {sup 139}Sn, {sup 139}Sb, {sup 139}I, {sup 139}Tb and {sup 139}Dy nuclei are not known, and those for {sup 139}Gd and {sup 139}Eu are poorly known. Particle-transfer data are available for {sup 139}Ba, {sup 139}La, {sup 139}Ce and {sup 139}Pr. Limited high-spin data are available for {sup 139}Te, {sup 139}I, {sup 139}Cs, {sup 139}Ba, {sup 139}La and {sup 139}Ce, while such data are extensive for {sup 139}Pr, {sup 139}Nd, {sup 139}Pm, {sup 139}Sm, {sup 139}Eu and {sup 139}Gd. Recent {sup 139}Pm high-spin data from two independent studies using the same reaction and similar beam energy are in conflict and could be improved using state-of-the-art large gamma-detector arrays in contrast to the smaller arrays currently used. Cases for which no new experimental information are available since the last update have undergone checking resulting in some changes in the current work, but for the most part these are taken from the previous evaluations. Thus, the present work has greatly benefited from all prior NDS evaluations (2001Bu16, 1989Bu12, 1981Pe04, 1974Gr46), but at the same time data presented herein supersede those in the earlier evaluations.

  20. Nuclear Data Sheets for A = 224

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Sukhjeet; Singh, Balraj

    2015-12-15

    The experimental nuclear spectroscopic data for ten experimentally known nuclides of mass number 224 (Bi, Po, At, Rn, Fr, Ra, Ac, Th, Pa, U) have been evaluated and presented together with the Adopted properties for levels and γ rays. For {sup 224}Bi, {sup 224}Po, {sup 224}At, {sup 224}Rn, {sup 224}Fr, {sup 224}Pa and {sup 224}U nuclei, only the ground–state information is known. Half–lives of ground states of 224Bi and 224Po have not yet been measured. The decay of {sup 224}Rn to {sup 224}Fr has been studied, but no decay scheme has been proposed. The decay of {sup 224}Ac to {sup 224}Ra is reported only in an abstract style conference proceedings. For a definite Jπ assignment for ground state of {sup 224}Ac, a detailed study of this decay may be helpful. In the decay of {sup 228}Pa to {sup 224}Ac, authors of 1994Ah03 state that the lowest state observed in their work may not be the ground state. Thus an extensive study of {sup 228}Pa α decay, and studies involving nuclear reactions are warranted since the level scheme of {sup 224}Ac presented in this evaluation is considered as incomplete due to the lack of confirmed information about multipolarities, mixing ratios and other spectroscopic details. Three new nuclides {sup 224}Bi, {sup 224}Po, and {sup 224}At are added in this revision, together with new in–beam γ–ray and Coulomb excitation data for {sup 224}Ra. Although, not much new experimental data have appeared since the previous evaluation (1997Ar05), extensive modifications have been made in almost all the datasets. This work supersedes the information presented in the previous NDS evaluations of A = 224: 1997Ar05, 1986Ma45 and 1976El05.

  1. Nuclear Data Sheets for A = 42

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Jun [Department of Physics and Astronomy, McMaster University, Hamilton, ON L8S 4M1 (Canada); Singh, Balraj [Department of Physics and Astronomy, McMaster University, Hamilton, ON L8S 4M1 (Canada)

    2016-07-15

    The experimental data are evaluated for known nuclides of mass number A = 42 (Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr). Detailed evaluated level properties and related information are presented, including adopted values of level and γ–ray energies, decay data (energies, intensities and placement of radiations), and other spectroscopic data. This work supersedes earlier full evaluations of A = 42 published by B. Singh, J.A. Cameron – Nucl.Data Sheets 92, 1 (2001) and P.M. Endt – Nucl. Phys. A521, 1 (1990); Errata and Addenda Nucl. Phys. A529, 763 (1991); Errata Nucl. Phys. A564, 609 (1993) (also P.M. Endt – Nucl. Phys. A633, 1 (1998) update). No excited states are known in {sup 42}Al, {sup 42}P, {sup 42}V and {sup 42}Cr, and structure information for {sup 42}Si and {sup 42}S is quite limited. There are no decay schemes available for the decay of {sup 42}Al, {sup 42}Si, {sup 42}P, {sup 42}V and {sup 42}Cr, while the decay schemes of {sup 42}Cl and {sup 42}Ti are incomplete in view of scarcity of data, and large gap between their Q–values and the highest energy levels populated in corresponding daughter nuclei. Structures of {sup 42}Ca, {sup 42}K, {sup 42}Sc and {sup 42}Ar nuclides remain the most extensively studied via many different nuclear reactions and decays.

  2. Nuclear Data Sheets for A = 84

    Science.gov (United States)

    Abriola, Daniel; Bostan, Melih; Erturk, Sefa; Fadil, Manssour; Galan, Monica; Juutinen, Sakari; Kibédi, Tibor; Kondev, Filip; Luca, Aurelian; Negret, Alexandru; Nica, Ninel; Pfeiffer, Bernd; Singh, Balraj; Sonzogni, Alejandro; Timar, Janos; Tuli, Jagdish; Venkova, Tsanka; Zuber, Kazimierz

    2009-11-01

    The evaluated spectroscopic data are presented for 12 known nuclides of mass 84 (Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo). Except for the stable nuclides 84Sr and 84Kr, extensive new data are available for all the other nuclides since the 1997 evaluation by J.K. Tuli (1997Tu02) of A = 84 nuclides. Many precise Penning-trap mass measurements since AME-2003 for A = 84 nuclides (2009Re03,2008Ha23,2008We10,2007Ke09,2006Ka48,2006De36,2006Ri15) have resulted in improved Q values and separation energies. However, many deficiencies still remain. Some examples are given below. Excited-state data for 84Ga and 84As are nonexistent, and those for 84Ge are scarce. The radioactive decay schemes of 84Ga, 84Ge, 84Se, 84Y (39.5 min), 84Y (4.6 s), 84Zr and 84Nb suffer from incompleteness and that for 84Mo decay is not known at all. The energy ordering of the two activities (39.5 min and and 4.6 s) of 84Y is not well established, although, high-spin with tentative spin-parity of (6+) is adopted here as the ground state of 84Y based on weak arguments. From a conference report published in 2000, it is clear that extensive experiments were done to investigate decays of 84Zr and 84Y, but details of these studies never appeared in literature and none were made available to the evaluators when requested from original authors. This evaluation was carried out as part of ENSDF workshop for Nuclear Structure and Decay Data Evaluators, organized and hosted by the "Horia Hulubei" National Institute for Physics and Nuclear Engineering, Bucharest, Romania during March 30, 2009 - April 3, 2009. Names of the evaluators principally responsible for evaluation of individual nuclides are given under the respective Adopted data sets.

  3. Adding Data Management Services to Parallel File Systems

    Energy Technology Data Exchange (ETDEWEB)

    Brandt, Scott [Univ. of California, Santa Cruz, CA (United States)

    2015-03-04

    The objective of this project, called DAMASC for “Data Management in Scientific Computing”, is to coalesce data management with parallel file system management to present a declarative interface to scientists for managing, querying, and analyzing extremely large data sets efficiently and predictably. Managing extremely large data sets is a key challenge of exascale computing. The overhead, energy, and cost of moving massive volumes of data demand designs where computation is close to storage. In current architectures, compute/analysis clusters access data in a physically separate parallel file system and largely leave it scientist to reduce data movement. Over the past decades the high-end computing community has adopted middleware with multiple layers of abstractions and specialized file formats such as NetCDF-4 and HDF5. These abstractions provide a limited set of high-level data processing functions, but have inherent functionality and performance limitations: middleware that provides access to the highly structured contents of scientific data files stored in the (unstructured) file systems can only optimize to the extent that file system interfaces permit; the highly structured formats of these files often impedes native file system performance optimizations. We are developing Damasc, an enhanced high-performance file system with native rich data management services. Damasc will enable efficient queries and updates over files stored in their native byte-stream format while retaining the inherent performance of file system data storage via declarative queries and updates over views of underlying files. Damasc has four key benefits for the development of data-intensive scientific code: (1) applications can use important data-management services, such as declarative queries, views, and provenance tracking, that are currently available only within database systems; (2) the use of these services becomes easier, as they are provided within a familiar file

  4. New evaluations of n + Cu and n + Zr cross-section data for neutron energies up to 200 MeV

    Science.gov (United States)

    Pereslavtsev, P.; Leal, L.; Konobeyev, A.; Fischer, U.

    2017-09-01

    This work presents evaluated general purpose nuclear data files for the n+ 63,65Cu and n+ 90,91,92,94,96Zr reactions for neutron energies up to 200 MeV. The TALYS-1.8 code was used for the nuclear model simulations in the energy range from 1 keV to 200 MeV. To improve the pre-equilibrium particle emission the Geometry-Dependent Hybrid model (GDH) was used as option implemented in an extended version of the code as option. Resonance data based on recent measurements and their covariances were included in the files. A set of covariance data for all nuclear reactions was also prepared and included in the evaluations. The adjustments of the nuclear model parameters were performed to fit both available differential and integral measured data. The evaluated data were carefully checked against the latest fusion relevant integral measurements.

  5. New evaluations of n + Cu and n + Zr cross-section data for neutron energies up to 200 MeV

    Directory of Open Access Journals (Sweden)

    Pereslavtsev P.

    2017-01-01

    Full Text Available This work presents evaluated general purpose nuclear data files for the n+ 63,65Cu and n+ 90,91,92,94,96Zr reactions for neutron energies up to 200 MeV. The TALYS-1.8 code was used for the nuclear model simulations in the energy range from 1 keV to 200 MeV. To improve the pre-equilibrium particle emission the Geometry-Dependent Hybrid model (GDH was used as option implemented in an extended version of the code as option. Resonance data based on recent measurements and their covariances were included in the files. A set of covariance data for all nuclear reactions was also prepared and included in the evaluations. The adjustments of the nuclear model parameters were performed to fit both available differential and integral measured data. The evaluated data were carefully checked against the latest fusion relevant integral measurements.

  6. Nuclear Data Sheets for A=217

    Energy Technology Data Exchange (ETDEWEB)

    Kondev, F. G.; McCutchan, E. A.; Singh, B.; Banerjee, K.; Bhattacharya, S.; Chakraborty, A.; Garg, S.; Jovancevic, N.; Kumar, S.; Rathi, S. K.; Roy, T.; Lee, J.; Shearman, R.

    2018-01-01

    The evaluated spectroscopic data are presented for 12 known nuclides with A=217 (Tl, Pb, Bi, Po, At, Rn, Fr, Ra, Ac, Th, Pa, U). For Tl-217, Pb-217, Pa-217, and U-217 nuclei, only information on the ground state is available. Levels in Bi-217 are known only from isomer decay following fragmentation reaction and those in At-217 and Rn-217 only from the a decay of Fr-221 and Ra-221, respectively. High spin levels in Ra-217 are mainly from 1987SuZY and 2011MuZZ which are a lab report and thesis, respectively. Due to differences between these studies, further experimental study is needed to firmly establish the level scheme.This evaluation was carried out as part of a joint IAEA-ICTP workshop for Nuclear Structure and Decay Data, organized and hosted by the IAEA, Vienna and ICTP, Trieste, Aug 22 to Sept 2 2016. The evaluation work was coordinated by E.A. McCutchan (BNL). This work supersedes the previous previous A=217 evaluation (2003Ak06) by Y.A. Akovali.

  7. NUCLEAR INFORMATION SERVICES AT THE NATIONAL NUCLEAR DATA CENTER.

    Energy Technology Data Exchange (ETDEWEB)

    BURROWS,T.W.; DUNFORD,C.L.

    2004-09-26

    The National Nuclear Data Center has provided remote access to its databases and other resources since 1986. This year we have completed the modernization of our databases and Web site. Resources available from our Web site will be summarized and some of the major improvements described in more detail.

  8. Nuclear Data Sheets for A = 211

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Balraj; Abriola, Daniel; Baglin, Coral; Demetriou, Vivian; Johnson, Timothy; McCutchan, Elizabeth; Mukherjee, Gopal; Singh, Sukhjeet; Sonzogni, Alejandro; Tuli, Jagdish

    2013-06-15

    The evaluated spectroscopic data are presented for 11 known nuclides of mass 211 (Hg, Tl, Pb, Bi, Po, At, Rn, Fr, Ra, Ac, Th). The {sup 211}Pa nuclide is included here but its identification remains uncertain. For {sup 211}Hg, {sup 211}Tl, {sup 211}Ac and {sup 211}Th nuclei, only the ground–state information is available. Their decay characteristics are mostly unknown. {sup 211}Fr is suggested to decay partially through ε decay mode, but its decay scheme remains poorly known. While high–spin excitations, including several isomers, are well studied in {sup 211}Pb, {sup 211}Bi, {sup 211}Po, {sup 211}At, {sup 211}Rn and {sup 211}Fr, the particle–transfer data are available for only {sup 211}Po and {sup 211}Bi. This evaluation was carried out as part of joint IAEA–ICTP workshop for Nuclear Structure and Decay Data, organized and hosted by the IAEA, Vienna and ICTP, Trieste, August 6–17, 2012. This work supersedes previous A=211 evaluation (2004Br45) published by E. Browne which covered literature before January 2003.

  9. Quantification and Propagation of Nuclear Data Uncertainties

    Science.gov (United States)

    Rising, Michael E.

    The use of several uncertainty quantification and propagation methodologies is investigated in the context of the prompt fission neutron spectrum (PFNS) uncertainties and its impact on critical reactor assemblies. First, the first-order, linear Kalman filter is used as a nuclear data evaluation and uncertainty quantification tool combining available PFNS experimental data and a modified version of the Los Alamos (LA) model. The experimental covariance matrices, not generally given in the EXFOR database, are computed using the GMA methodology used by the IAEA to establish more appropriate correlations within each experiment. Then, using systematics relating the LA model parameters across a suite of isotopes, the PFNS for both the uranium and plutonium actinides are evaluated leading to a new evaluation including cross-isotope correlations. Next, an alternative evaluation approach, the unified Monte Carlo (UMC) method, is studied for the evaluation of the PFNS for the n(0.5 MeV)+Pu-239 fission reaction and compared to the Kalman filter. The UMC approach to nuclear data evaluation is implemented in a variety of ways to test convergence toward the Kalman filter results and to determine the nonlinearities present in the LA model. Ultimately, the UMC approach is shown to be comparable to the Kalman filter for a realistic data evaluation of the PFNS and is capable of capturing the nonlinearities present in the LA model. Next, the impact that the PFNS uncertainties have on important critical assemblies is investigated. Using the PFNS covariance matrices in the ENDF/B-VII.1 nuclear data library, the uncertainties of the effective multiplication factor, leakage, and spectral indices of the Lady Godiva and Jezebel critical assemblies are quantified. Using principal component analysis on the PFNS covariance matrices results in needing only 2-3 principal components to retain the PFNS uncertainties. Then, using the polynomial chaos expansion (PCE) on the uncertain output

  10. Database structure and file layout of Nuclear Power Plant Database. Database for design information on Light Water Reactors in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, Nobuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Izumi, Fumio

    1995-12-01

    The Nuclear Power Plant Database (PPD) has been developed at the Japan Atomic Energy Research Institute (JAERI) to provide plant design information on domestic Light Water Reactors (LWRs) to be used for nuclear safety research and so forth. This database can run on the main frame computer in the JAERI Tokai Establishment. The PPD contains the information on the plant design concepts, the numbers, capacities, materials, structures and types of equipment and components, etc, based on the safety analysis reports of the domestic LWRs. This report describes the details of the PPD focusing on the database structure and layout of data files so that the users can utilize it efficiently. (author).

  11. JANIS: NEA JAva-based Nuclear Data Information System

    Science.gov (United States)

    Soppera, Nicolas; Bossant, Manuel; Cabellos, Oscar; Dupont, Emmeric; Díez, Carlos J.

    2017-09-01

    JANIS (JAva-based Nuclear Data Information System) software is developed by the OECD Nuclear Energy Agency (NEA) Data Bank to facilitate the visualization and manipulation of nuclear data, giving access to evaluated nuclear data libraries, such as ENDF, JEFF, JENDL, TENDL etc., and also to experimental nuclear data (EXFOR) and bibliographical references (CINDA). It is available as a standalone Java program, downloadable and distributed on DVD and also a web application available on the NEA website. One of the main new features in JANIS is the scripting capability via command line, which notably automatizes plots generation and permits automatically extracting data from the JANIS database. Recent NEA software developments rely on these JANIS features to access nuclear data, for example the Nuclear Data Sensitivity Tool (NDaST) makes use of covariance data in BOXER and COVERX formats, which are retrieved from the JANIS database. New features added in this version of the JANIS software are described along this paper with some examples.

  12. Material composition and nuclear data libraries' influence on nickel-chromium alloys activation evaluation: a comparison with decay heat experiments

    CERN Document Server

    Cepraga, D G

    2000-01-01

    The paper presents the activation analyses on Inconel-600 nickel-chromium alloy. Three activation data libraries, namely the EAF-4.1, the EAF-97 and the FENDL/A-2, and the FENDL/D-2 decay data library, have been used to perform the calculation with the European activation code ANITA-4/M. The neutron flux distribution into the material samples was provided by JAERI as results of 3D Monte-Carlo MCNP transport code experiment simulation. A comparison with integral decay heat measurement performed at the Fusion Neutronics Source (FNS), JAERI, Tokai, Japan, is used to validate the computational approach. The calculation results are given and discussed. The impact of the material composition, including impurities, on the decay heat of samples irradiated in fusion-like neutron spectra is assessed and discussed. The discrepancies calculations-experiments are within the experimental errors, that is between 6% and 10%, except for the short cooling times (less than 40 min after the end of irradiation). To improve calcul...

  13. Applied nuclear data research and development. Progress report, January 1--March 31, 1976. [Activities of LASL Nuclear Data Group

    Energy Technology Data Exchange (ETDEWEB)

    Baxman, C.I.; Hale, G.M.; Young, P.G. (comps.)

    1976-08-01

    This report describes the activities of the Los Alamos Nuclear Data Group for the period January 1 to March 31, 1976. The following areas are discussed: Theory and evaluation of nuclear cross sections, including calculations of neutron cross sections; Nuclear cross-section processing, including developments concerning the computer codes used; Cross sections for HTGR safety research; Effect of dispersion matrix structure on a data adjustment and consistency analysis; Fission product and decay data studies; and Medium-energy library. 20 figures, 18 tables. (RWR)

  14. Exploratory study of nuclear reaction data utility framework of Japan charged particle reaction data group (JCPRG)

    Energy Technology Data Exchange (ETDEWEB)

    Masui, Hiroshi; Ohnishi, Akira; Kato, Kiyoshi [Hokkaido Univ., Graduate School of Science, Sapporo, Hokkaido (Japan); Ohbayasi, Yosihide [Hokkaido Univ., Meme Media Lab., Sapporo, Hokkaido (Japan); Aoyama, Shigeyoshi [Kitami Institute of Technology, Information Processing Center, Kitami, Hokkaido (Japan); Chiba, Masaki [Sapporo Gakuin Univ., Faculty of Social Information, Ebetsu, Hokkaido (Japan)

    2002-08-01

    Compilation, evaluation and dissemination are essential pieces of work for the nuclear data activities. We, Japan charged particle data group, have researched the utility framework for the nuclear reaction data on the basis of recent progress of computer and network technologies. These technologies will be not only for the data dissemination but for the compilation and evaluation assistance among the many corresponding researchers of all over the world. In this paper, current progress of our research and development is shown. (author)

  15. Evaluation of the efficacy of rotary vs. hand files in root canal preparation of primary teeth in vitro using CBCT.

    Science.gov (United States)

    Musale, P K; Mujawar, S A V

    2014-04-01

    This in vitro study aimed to evaluate the efficacy of rotary ProFile, ProTaper, Hero Shaper and K-files in shaping ability, cleaning efficacy, preparation time and instrument distortion in primary molars. Sixty extracted primary mandibular second molars were divided into four equal groups: Group I K-file, Group II ProFile, Group III ProTaper file and Group IV Hero Shaper file. The shaping ability was determined by comparing pre- and post-instrumentation CBCT scans and data analysed with SPSS program using the Chi-square test. Cleaning efficacy was evaluated by the degree of India ink removal from the canal walls under stereomicroscopy. Instrumentation times were calculated for each tooth and instrument distortion was visually checked and duly noted. The cleaning efficacy and instrumentation time were determined using ANOVA with Tukey's correction. Instrument distortion was analysed using Chi-square test. The canal taper was significantly more conical for rotary files as compared to K-files with Chi-square test (p rotary files with average scores (Groups II- 0.68, III- 0.48 and IV- 0.58) was significantly better than K-files (Group I- 0.93) (p rotary files (Groups II 8.9, III 5.6, and IV 8.1 min) (p rotary files were distorted. Rotary files prepared more conical canals in primary teeth than manual instruments. Reduced preparation time with rotary files enhances patient cooperation especially in young children.

  16. Nuclear Data Sheets for A = 26

    Science.gov (United States)

    Basunia, M. S.; Hurst, A. M.

    2016-05-01

    Evaluated spectroscopic data and level schemes from radioactive decay and nuclear reaction studies are presented for 26O, 26F, 26Ne, 26Na, 26Mg, 26Al, 26Si, 26P, and 26S. This evaluation for A = 26 supersedes the earlier one by P. M. Endt (1998En04) and updates for some nuclides in ENSDF. Highlights of this evaluation are the following: This evaluation includes search results for 26S nuclide and its proton-decay mode (2011Fo08). An isomeric state (2.2 ms) in 26F has been discovered by 2013Le03. The state is proposed at 643.4 keV 1 from γ-ray measurements. Internal-transition and beta-decay branches for the state are also determined. New excited levels in 26Ne have been identified from 26F β- decay (2.2 ms). For some 26Si resonance states conflicting spin-parity assignments exist in the literature. These are identified by footnotes. 2015Do07 (3He,nγ) propose the first 0+ state above proton separation energy at an excitation energy of 5890 keV and suggested for additional independent measurements to confirm or refute the existence of 5946 keV 4. 2016Ch09 consider 5946 keV level as a distinct excited state in their reanalysis of the literature data with possible spin-parity assignment of 0+ or 4+ This evaluation also includes discovery of an isomeric state, at 164.1 keV 1, in 26P by 2014NiZZ.

  17. Nuclear Data Sheets for A = 26

    Energy Technology Data Exchange (ETDEWEB)

    Basunia, M.S.; Hurst, A.M.

    2016-05-15

    Evaluated spectroscopic data and level schemes from radioactive decay and nuclear reaction studies are presented for {sup 26}O, {sup 26}F, {sup 26}Ne, {sup 26}Na, {sup 26}Mg, {sup 26}Al, {sup 26}Si, {sup 26}P, and {sup 26}S. This evaluation for A = 26 supersedes the earlier one by P. M. Endt (1998En04) and updates for some nuclides in ENSDF. Highlights of this evaluation are the following: This evaluation includes search results for {sup 26}S nuclide and its proton–decay mode (2011Fo08). An isomeric state (2.2 ms) in {sup 26}F has been discovered by 2013Le03. The state is proposed at 643.4 keV 1 from γ–ray measurements. Internal-transition and beta-decay branches for the state are also determined. New excited levels in {sup 26}Ne have been identified from {sup 26}F β{sup −} decay (2.2 ms). For some {sup 26}Si resonance states conflicting spin-parity assignments exist in the literature. These are identified by footnotes. 2015Do07 ({sup 3}He,nγ) propose the first 0+ state above proton separation energy at an excitation energy of 5890 keV and suggested for additional independent measurements to confirm or refute the existence of 5946 keV 4. 2016Ch09 consider 5946 keV level as a distinct excited state in their reanalysis of the literature data with possible spin-parity assignment of 0+ or 4+ This evaluation also includes discovery of an isomeric state, at 164.1 keV 1, in {sup 26}P by 2014NiZZ.

  18. Alternative Approach to Nuclear Data Representation

    Energy Technology Data Exchange (ETDEWEB)

    Pruet, J; Brown, D; Beck, B; McNabb, D P

    2005-07-27

    This paper considers an approach for representing nuclear data that is qualitatively different from the approach currently adopted by the nuclear science community. Specifically, they examine a representation in which complicated data is described through collections of distinct and self contained simple data structures. This structure-based representation is compared with the ENDF and ENDL formats, which can be roughly characterized as dictionary-based representations. A pilot data representation for replacing the format currently used at LLNL is presented. Examples are given as is a discussion of promises and shortcomings associated with moving from traditional dictionary-based formats to a structure-rich or class-like representation.

  19. Nuclear Data Sheets for A = 182

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Balraj

    2015-12-15

    Nuclear spectroscopic information for known nuclides of mass number 182 (Yb,Lu,Hf,Ta,W,Re,Os,Ir,Pt,Au, Hg,Tl,Pb) with Z=70 to 82 and N=112 to 100 have been evaluated and presented together with adopted energies and Jπ of levels in these nuclei. No excited state data are yet available for {sup 182}Y and {sup 182}Lu, while only limited structure information is available for {sup 182}Pb and {sup 182}Tl. Rotational band structures are known for {sup 182}Hg and {sup 182}Au but spin–parity assignments remain largely tentative. The decays of {sup 182}Lu, {sup 182}Hg, {sup 182}Au and {sup 182}Tl are not well established. The {sup 182}Hf isotope is of geophysical and astrophysical interest. This evaluation supersedes previous full evaluations of A = 182 published by 2010Si13, 1988Fi05 and 1975Sc13, and a selected (mainly high–spin) update of A = 182 published by 1995Si04. Only the Adopted properties of levels and gamma rays are presented in NDS, consult the ENSDF database at (www.nndc.bnl.gov/ensdf/) for details of individual reaction and decay datasets.

  20. Sigma: Web Retrieval Interface for Nuclear Reaction Data

    Energy Technology Data Exchange (ETDEWEB)

    Pritychenko,B.; Sonzogni, A.A.

    2008-06-24

    The authors present Sigma, a Web-rich application which provides user-friendly access in processing and plotting of the evaluated and experimental nuclear reaction data stored in the ENDF-6 and EXFOR formats. The main interface includes browsing using a periodic table and a directory tree, basic and advanced search capabilities, interactive plots of cross sections, angular distributions and spectra, comparisons between evaluated and experimental data, computations between different cross section sets. Interactive energy-angle, neutron cross section uncertainties plots and visualization of covariance matrices are under development. Sigma is publicly available at the National Nuclear Data Center website at www.nndc.bnl.gov/sigma.

  1. Integral Benchmark Data for Nuclear Data Testing Through the ICSBEP & IRPhEP

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; John D. Bess; Jim Gulliford; Ian Hill

    2013-10-01

    The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiment Evaluation Project (IRPhEP) was last discussed directly with the nuclear data community at ND2007. Since ND2007, integral benchmark data that are available for nuclear data testing have increased significantly. The status of the ICSBEP and the IRPhEP is discussed and selected benchmark configurations that have been added to the ICSBEP and IRPhEP Handbooks since ND2007 are highlighted.

  2. Nuclear Data Sheets for A = 227

    Energy Technology Data Exchange (ETDEWEB)

    Kondev, Filip [ANL, Argonne, IL (United States); McCutchan, Elizabeth [NNDC, BNL, Upton, NY (United States); Singh, Balraj, E-mail: balraj@mcmaster.ca [McMaster Univ., Hamilton (Canada); Tuli, Jagdish [NNDC, BNL, Upton, NY (United States)

    2016-02-15

    The evaluated spectroscopic data are presented for ten known nuclides of mass 227 (Po, At, Rn, Fr, Ra, Ac, Th, Pa, U, Np). For {sup 227}Po, {sup 227}At, {sup 227}Rn, {sup 227}Pa, {sup 227}U and {sup 227}Np nuclei, only the ground-state information is available. Their decay characteristics are mostly unknown. Levels in {sup 227}Fr are known only from the decay of {sup 227}Rn to {sup 227}Fr. This decay scheme at present cannot be normalized to deduce γ intensities per 100 decays due to lack of knowledge about multipolarities of many low-energy transitions. The levels in {sup 227}Ra, {sup 227}Ac and {sup 227}Th are known from several decays and reactions, including particle-transfer data for {sup 227}Ra and {sup 227}Ac. The decay scheme of {sup 227}Ra to {sup 227}Ac was last studied in 1971 using small Ge detectors. Improved γ-ray intensity data need to be obtained with a better γ-detection system. The datasets for {sup 227}Ac have undergone extensive revisions, including detailed data for 231Pa α decay from 1986BaYK report, and single-proton transfer data from 1986MaYU thesis. High-spin (J>13/2 or so) structures are known only for 227Th. Level lifetime data are quite scarce for all the nuclides in this mass chain, thus limiting the knowledge of reduced transition probabilities. Band structures for {sup 227}Fr, {sup 227}Ra, {sup 227}Ac and {sup 227}Th are known in detail, together with evidence of weak octupole deformation and consequent parity-doublet structures. This evaluation was carried out as part of a joint IAEA-ICTP workshop for Nuclear Structure and Decay Data, organized and hosted by the IAEA, Vienna and ICTP, Trieste, March 24–28, 2014. The evaluation work was coordinated by B. Singh (McMaster). This work supersedes previous A=227 evaluation (2001Br31) published by E. Browne which covered literature before May 2001.

  3. The Decay Data Evaluation Project (DDEP and the JEFF-3.3 radioactive decay data library: Combining international collaborative efforts on evaluated decay data

    Directory of Open Access Journals (Sweden)

    Kellett Mark A.

    2017-01-01

    Full Text Available The Decay Data Evaluation Project (DDEP, is an international collaboration of decay data evaluators formed with groups from France, Germany, USA, China, Romania, Russia, Spain and the UK, mainly from the metrology community. DDEP members have evaluated over 220 radionuclides, following an agreed upon methodology, including a peer review. Evaluations include all relevant parameters relating to the nuclear decay and the associated atomic processes. An important output of these evaluations are recommendations for new measurements, which can serve as a basis for future measurement programmes. Recently evaluated radionuclides include: 18F, 59Fe, 82Rb, 82Sr, 88Y, 90Y, 89Zr, 94mTc, 109Cd, 133Ba, 140Ba, 140La, 151Sm and 169Er. The DDEP recommended data have recently been incorporated into the JEFF-3.3 Radioactive Decay Data Library. Other sources of nuclear data include 900 or so radionuclides converted from the Evaluated Nuclear Structure Data File (ENSDF, 500 from two UK libraries (UKPADD6.12 and UKHEDD2.6, the IAEA Actinide Decay Data Library, with the remainder converted from the NUBASE evaluation of nuclear properties. Mean decay energies for a number of radionuclides determined from total absorption gamma-ray spectroscopy (TAGS have also been included, as well as more recent European results from TAGS measurements performed at the University of Jyväskylä by groups from the University of Valencia, Spain and SUBATECH, the University of Nantes, France. The current status of the DDEP collaboration and the JEFF Radioactive Decay Data Library will be presented.

  4. The evaluated gamma-ray activation file (EGAF)

    Energy Technology Data Exchange (ETDEWEB)

    Firestone, R.B.; Molnar, G.L.; Revay, Zs.; Belgya, T.; McNabb, D.P.; Sleaford, B.W.

    2004-09-22

    The Evaluated Gamma-ray Activation File (EGAF), a new database of prompt and delayed neutron capture g-ray cross sections, has been prepared as part of an International Atomic Energy Agency (IAEA) Coordinated Research Project to develop a ''Database of Prompt Gamma-rays from Slow Neutron Capture for Elemental Analysis.'' Recent elemental g-ray cross-section measurements performed with the guided neutron beam at the Budapest Reactor have been combined with data from the literature to produce the EGAF database. EGAF contains thermal cross sections for {approx} 35,000 prompt and delayed g-rays from 262 isotopes. New precise total thermal radiative cross sections have been derived for many isotopes from the primary and secondary gamma-ray cross sections and additional level scheme data. An IAEA TECDOC describing the EGAF evaluation and tabulating the most prominent g-rays will be published in 2004. The TECDOC will include a CD-ROM containing the EGAF database in both ENSDF and tabular formats with an interactive viewer for searching and displaying the data. The Isotopes Project, Lawrence Berkeley National Laboratory continues to maintain and update the EGAF file. These data are available on the Internet from both the IAEA and Isotopes Project websites.

  5. The Evaluated Gamma-ray Activation File (EGAF)

    Science.gov (United States)

    Firestone, R. B.; Molnár, G. L.; Révay, Zs.; Belgya, T.; McNabb, D. P.; Sleaford, B. W.

    2006-03-01

    The Evaluated Gamma-ray Activation File (EGAF), a new database of prompt and delayed neutron capture γ ray cross sections, has been prepared as part of an International Atomic Energy Agency (IAEA) Coordinated Research Project to develop a "Database of Prompt Gamma-rays from Slow Neutron Capture for Elemental Analysis". Recent elemental γ-ray cross-section measurements performed with the guided neutron beam at the Budapest Reactor have been combined with data from the literature to produce the EGAF database. EGAF contains thermal cross sections for ≈35,000 prompt and delayed γ-rays from 262 isotopes. New precise total thermal radiative cross sections have been derived for many isotopes from the primary and secondary gamma-ray cross sections and additional level scheme data. An IAEA TECDOC describing the EGAF evaluation and tabulating the most prominent γ-rays will be published in 2004. The TECDOC will include a CD-ROM containing the EGAF database in both ENSDF and tabular formats with an interactive viewer for searching and displaying the data. The Isotopes Project, Lawrence Berkeley National Laboratory continues to maintain and update the EGAF file. These data are available on the Internet from both the IAEA and Isotopes Project websites.

  6. Evaluation of Oracle Big Data Integration Tools

    OpenAIRE

    Urhan, Harun; Baranowski, Zbigniew

    2015-01-01

    Abstract The project’s objective is evaluating Oracle’s Big Data Integration Tools. The project covers evaluation of two of Oracle’s tools, Oracle Data Integrator: Application Adapters for Hadoop to load data from Oracle Database to Hadoop and Oracle SQL Connectors for HDFS to query data stored on a Hadoop file system by using SQL statements executed on an Oracle Database.

  7. Overcoming data locality: An in-memory runtime file system with symmetrical data distribution

    NARCIS (Netherlands)

    Uta, A.; Sandu, A.; Kielmann, T.

    2016-01-01

    In many-task computing (MTC), applications such as scientific workflows or parameter sweeps communicate via intermediate files; application performance strongly depends on the file system in use. The state of the art uses runtime systems providing in-memory file storage that is designed for data

  8. Shuttle Data Center File-Processing Tool in Java

    Science.gov (United States)

    Barry, Matthew R.; Miller, Walter H.

    2006-01-01

    A Java-language computer program has been written to facilitate mining of data in files in the Shuttle Data Center (SDC) archives. This program can be executed on a variety of workstations or via Web-browser programs. This program is partly similar to prior C-language programs used for the same purpose, while differing from those programs in that it exploits the platform-neutrality of Java in implementing several features that are important for analysis of large sets of time-series data. The program supports regular expression queries of SDC archive files, reads the files, interleaves the time-stamped samples according to a chosen output, then transforms the results into that format. A user can choose among a variety of output file formats that are useful for diverse purposes, including plotting, Markov modeling, multivariate density estimation, and wavelet multiresolution analysis, as well as for playback of data in support of simulation and testing.

  9. Air and Soil Data Files from Sumas Study

    Data.gov (United States)

    U.S. Environmental Protection Agency — The data are summarized in the manuscript, but users may wish to apply them from these files. This dataset is associated with the following publication: Wroble, J.,...

  10. EDISTR: a computer program to obtain a nuclear decay data base for radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Dillman, L.T.

    1980-01-01

    This report provides documentation for the computer program EDISTR. EDISTR uses basic radioactive decay data from the Evaluated Nuclear Structure Data File developed and maintained by the Nuclear Data Project at the Oak Ridge National Laboratory as input, and calculates the mean energies and absolute intensities of all principal radiations associated with the radioactive decay of a nuclide. The program is intended to provide a physical data base for internal dosimetry calculations. The principal calculations performed by EDISTR are the determination of (1) the average energy of beta particles in a beta transition, (2) the beta spectrum as function of energy, (3) the energies and intensities of x-rays and Auger electrons generated by radioactive decay processes, (4) the bremsstrahlung spectra accompanying beta decay and monoenergetic Auger and internal conversion electrons, and (5) the radiations accompanying spontaneous fission. This report discusses the theoretical and empirical methods used in EDISTR and also practical aspects of the computer implementation of the theory. Detailed instructions for preparing input data for the computer program are included, along with examples and discussion of the output data generated by EDISTR.

  11. PKA spectrum file

    Energy Technology Data Exchange (ETDEWEB)

    Kawai, M. [Toshiba Corp., Kawasaki, Kanagawa (Japan). Nuclear Engineering Lab.

    1997-03-01

    In the Japanese Nuclear Data Committee, the PKA/KERMA file containing PKA spectra, KERMA factors and DPA cross sections in the energy range between 10{sup -5} eV and 50 MeV is being prepared from the evaluated nuclear data. The processing code ESPERANT was developed to calculate quantities of PKA, KERMA and DPA from evaluated nuclear data for medium and heavy elements by using the effective single particle emission approximation (ESPEA). For light elements, the PKA spectra are evaluated by the SCINFUL/DDX and EXIFON codes, simultaneously with other neutron cross sections. The DPA cross sections due to charged particle emitted from light elements are evaluated for high neutron energy above 20 MeV. (author)

  12. Open file data on the Cerro Prieto geothermal field

    Energy Technology Data Exchange (ETDEWEB)

    Lippman, M.J.; Aguirre, B.D.; Wollenberg, H.A.; Witherspoon, P.A.

    1977-04-01

    Some of the unpublished data presently available on open file at the Lawrence Berkeley Laboratory are listed and described. In addition, in the files are a number of internal memoranda of the Commission Federal de Electricidad of Mexico (CFE) on chemical characteristics of the produced fluids and incrustations; published papers on Cerro Prieto and the geologic setting of the Salton Trough; and data on the hydrogeology of the Mexicali Valley. (MHR)

  13. Status of nuclear data activities at Karlsruhe

    Energy Technology Data Exchange (ETDEWEB)

    Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan)

    1997-03-01

    This is a brief introduction to nuclear data activity at Karlsruhe Research Center. Some URLs concerned are given. Topics mentioned here are, the FENDL and JEF/EFF project at INR, and measurements of neutron capture cross sections at IK III. (author)

  14. Nuclear Data Sheets for A = 222

    Science.gov (United States)

    Singh, Sukhjeet; Jain, A. K.; Tuli, Jagdish K.

    2011-11-01

    The ENSDF evaluation for A=222 mass chain (1996El01) has been updated on the basis of the experimental results, since September 1995 (literature cutoff date in 1996El01), from various reaction and decay studies for all nuclides in A=222 mass chain (Z=84 to 92). A new nuclide ( 222Po) has since been observed. In addition, new measurements have been reported in Rn, Th and Ra nuclides. The results obtained from various theoretical studies are given as comments. The updated level and decay schemes, and experimental decay and reaction data on which they are based, are summarized and presented for all the nuclides with mass number A=222. The adopted values of level energies, level spins and parities are given, and γ-ray energies, intensities, as well as other nuclear properties are presented. The references, J π arguments, and necessary comments are given in the text. All Q values have been adopted from 2011AuZZ. Theoretical work of 2009Mo27 was consulted.

  15. Advances in HELIOS2 nuclear data library

    Energy Technology Data Exchange (ETDEWEB)

    Wemple, Charles [Studsvik Scandpower, Inc., Iadho Falls, ID (United States); Simeonov, Teodosi [Studsvik Scandpower, Inc., Waltham, MA (United States)

    2017-09-15

    The ongoing development of the HELIOS2 code system at Studsvik includes periodic updates of the nuclear data library. The library expansion includes an update of the cross section data source to ENDF/B-VIIR1, a significant expansion of the burnup chains, the addition of a more complete set of gamma production data, and the development of new resonance treatment options. The goal is to provide the capability for HELIOS2 to more accurately model a wider array of reactor applications and enhance interoperability with SNF, the Studsvik spent fuel analysis code. This paper will also provide a discussion of the nuclear data library benchmarking effort and an overview of other HELIOS2 development efforts.

  16. Nuclear data and reactor physics activities in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Liem, P.H. [National Atomic Energy Agency, Tangerang (Indonesia). Center for Multipurpose Reactor

    1998-03-01

    The nuclear data and reactor physics activities in Indonesia, especially, in the National Atomic Energy Agency are presented. In the nuclear data field, the Agency is now taking the position of a user of the main nuclear data libraries such as JENDL and ENDF/B. These nuclear data libraries become the main sources for producing problem dependent cross section sets that are needed by cell calculation codes or transport codes for design, analysis and safety evaluation of research reactors. In the reactor physics field, besides utilising the existing core analysis codes obtained from bilateral and international co-operation, the Agency is putting much effort to self-develop Batan`s codes for reactor physics calculations, in particular, for research reactor and high temperature reactor design, analysis and fuel management. Under the collaboration with JAERI, Monte Carlo criticality calculations on the first criticality of RSG GAS (MPR-30) first core were done using JAERI continuous energy, vectorized Monte Carlo code, MVP, with JENDL-3.1 and JENDL-3.2 nuclear data libraries. The results were then compared with the experiment data collected during the commissioning phase. Monte Carlo calculations with both JENDL-3.1 and -3.2 libraries produced k{sub eff} values with excellent agreement with experiment data, however, systematically, JENDL-3.2 library showed slightly higher k{sub eff} values than JENDL-3.1 library. (author)

  17. CIF (Crystallographic Information File): A Standard for Crystallographic Data Interchange

    Science.gov (United States)

    Brown, I. D.

    1996-01-01

    The Crystallographic Information File (CIF) uses the self-defining STAR file structure. This requires the creation of a dictionary of data names and definitions. A basic dictionary of terms needed to describe the crystal structures of small molecules was approved in 1991 and is currently used for the submission of papers to Acta Crystallographica C. A number of extensions to this dictionary are in preparation. By storing the dictionary itself as a STAR file, the definitions and relationships in the CIF dictionary become computer interpretable. This offers many possibilities for the automatic handling of crystallographic information. PMID:27805170

  18. Constructing AppleWorks Data Base Files for the Apple IIe Computer.

    Science.gov (United States)

    Schlenker, Richard M.

    This step-by-step guide to creating database files using the AppleWorks software on the Apple IIe computer covers (1) loading the program; (2) adding files to the desktop; (3) selecting the database option; (4) naming the file; (5) naming categories or fields; (6) inserting data; (7) changing database file formats; (8) altering the file layout;…

  19. Development of utility system of charged particle Nuclear Reaction Data on Unified Interface

    Energy Technology Data Exchange (ETDEWEB)

    Aoyama, Shigeyoshi; Ohbayashi, Yosihide; Kato, Kiyoshi [Information Processing Center, Kitami Institute of Technology, Kitami, Hokkaido (Japan); Masui, Hiroshi; Ohnishi, Akira; Chiba, Masaki

    1999-03-01

    We have developed a utility system, WinNRDF, for a nuclear charged particle reaction data of NRDF (Nuclear Reaction Data File) on a unified interface of Windows95, 98/NT. By using the system, we can easily search the experimental data of a charged particle reaction in NRDF and also see the graphic data on GUI (Graphical User Interface). Furthermore, we develop a mechanism of making a new index of keywords in order to include the time developing character of the NRDF database. (author)

  20. High priority nuclear data request list. The data for long-lived fission products, minor actinides and the thorium cycle

    Energy Technology Data Exchange (ETDEWEB)

    Rowlands, J. [Organisation for Economic Co-Operation and Development, Nuclear Energy Agency, 75 - Paris (France)

    2002-07-01

    This workshop is organised by the Research Group GEDEON together with CERN, OECD-NEA and the CFDN (French Committee for Nuclear Data). It is the continuation of the one at CERN on September 21 and 22, 1998, jointly organised with EC, GEDEON and OCDE-NEA. This last one is centred on the CERN proposal of a facility for neutron production up to 250 MeV, devoted to neutron data measurements. The first aim of the Paris workshop is to identify the present status of specific nuclear data relevant to innovative options (accelerator driven system - ADS and thorium) in the nuclear fuel cycle, beyond what has been gathered for standard reactors (PWR, FBR) and for the associated fuel cycles based on uranium and plutonium. The following topics were presented and discussed: 1. extension of present evaluated nuclear data files beyond 20 MeV needed to correctly describe the high energy part (up to approximately 200 MeV) of the spallation process used to generate the external neutrons needed for the sub-critical assemblies; 2. differential and integral cross section data in relation with the use of a thorium based; 3. the same for minor actinides and some long-lived fission residues likely to be destroyed in reactors; 4. the same for new type of materials such as lead or lead-bismuth, to be used as spallation target or as cooling, in relation with corrosion and irradiation effects. Beyond these specific issues, ADS will also take advantage of better known nuclear data coming from the existing reactors in operation. Very recent results related to spallation target physics such as neutron and residues production from heavy targets were also presented at this workshop. One very important aim of this workshop is also to bring physicists from different origin, especially from CERN, to cooperate in a program on nuclear data in relation with innovative options. This document brings together two articles entitled ''high priority nuclear data request list. The data for long lived

  1. DATA Act File B Object Class and Program Activity - Social Security

    Data.gov (United States)

    Social Security Administration — The DATA Act Information Model Schema Reporting Submission Specification File B. File B includes the agency object class and program activity detail obligation and...

  2. DataNet: A flexible metadata overlay over file resources

    CERN Multimedia

    CERN. Geneva

    2014-01-01

    Managing and sharing data stored in files results in a challenge due to data amounts produced by various scientific experiments [1]. While solutions such as Globus Online [2] focus on file transfer and synchronization, in this work we propose an additional layer of metadata over file resources which helps to categorize and structure the data, as well as to make it efficient in integration with web-based research gateways. A basic concept of the proposed solution [3] is a data model consisting of entities built from primitive types such as numbers, texts and also from files and relationships among different entities. This allows for building complex data structure definitions and mix metadata and file data into a single model tailored for a given scientific field. A data model becomes actionable after being deployed as a data repository which is done automatically by the proposed framework by using one of the available PaaS (platform-as-a-service) platforms and is exposed to the world as a REST service, which...

  3. Python-Based Tool for Universal Nuclear Data Extraction

    Science.gov (United States)

    McDonald, William; Blair, Hayden; Consalvi, Peter; Garbiso, Markus; Grover, Hannah; Harget, Alex; Martin, Matthew; Natzke, Connor; Leach, Kyle

    2017-09-01

    Over the past 70 years, nuclear physics experiments have provided a vast wealth of experimental data on both ground and excited state properties across the nuclear chart. In many cases, searching for and parsing the relevant nuclear structure data from previous work can be tedious and difficult. Although the compilation, evaluation, and digitization of this data by multiple groups around the world over the past several decades has helped dramatically in this respect, the process of performing systematic studies using this data can still be cumbersome and limited. We are in the process of creating a python-based program to extract, sort, and manipulate nuclear and atomic data efficiently. In its current state, the program is able to extract all atomic-shell ionization energies, excited- and ground-state nuclear properties, and all beta-decay rates and ratios. As a part of this ongoing project, we plan to use this tool to examine beta-decay rates in extreme astrophysical environments.

  4. Investigation of activation cross-sections of proton induced nuclear reactions on {sup nat}Mo up to 40 MeV: New data and evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Tarkanyi, F. [Institute of Nuclear Research of the Hungarian Academy of Sciences (ATOMKI), 4026 Debrecen (Hungary); Ditroi, F., E-mail: ditroi@atomki.hu [Institute of Nuclear Research of the Hungarian Academy of Sciences (ATOMKI), 4026 Debrecen (Hungary); Hermanne, A. [Cyclotron Laboratory, Vrije Universiteit Brussel (VUB), Laarbeeklaan 103, 1090 Brussels (Belgium); Takacs, S. [Institute of Nuclear Research of the Hungarian Academy of Sciences (ATOMKI), 4026 Debrecen (Hungary); Ignatyuk, A.V. [Institute of Physics and Power Engineering (IPPE), Obninsk 249020 (Russian Federation)

    2012-06-01

    Highlights: Black-Right-Pointing-Pointer Excitation function measurement of proton induced reactions on molybdenum up to 40 MeV. Black-Right-Pointing-Pointer Model code calculations with EMPIRE, ALICE and TALYS. Black-Right-Pointing-Pointer Integral production yield calculation. Black-Right-Pointing-Pointer Medical radioisotope production; {sup 99m}Tc and {sup 99}Mo. Black-Right-Pointing-Pointer Monitor reactions. - Abstract: Cross-sections of proton induced nuclear reactions on natural molybdenum have been studied in the frame of a systematic investigation of charged particle induced nuclear reactions on metals for different applications. The excitation functions of {sup 93m}Tc, {sup 93g}Tc{sup (m+)}, {sup 94m}Tc, {sup 94g}Tc, {sup 95m}Tc, {sup 95g}Tc, {sup 96g}Tc{sup (m+)}, {sup 99m}Tc, {sup 90}Mo{sup (cum)}, {sup 93m}Mo, {sup 99}Mo{sup (cum)}, {sup 90}Nb{sup (cum)}, {sup 92m}Nb, {sup 95m}Nb, {sup 95g}Nb, {sup 96}Nb and {sup 88}Zr{sup (cum)}, {sup 89}Zr{sup (cum)} were measured up to 40 MeV proton energy by a using stacked foil technique and activation method. The main goals of this work were to study the production possibility of the medically important {sup 99m}Tc and its {sup 99}Mo parent nucleus, to get experimental data for accelerator technology, for monitoring of proton beam, for thin layer activation technique and for testing nuclear reaction theories. The experimental data were compared with critically analysed published data and with the results of model calculations, obtained by using the ALICE-IPPE, EMPIRE-II and TALYS codes.

  5. Investigation of activation cross-sections of proton induced nuclear reactions on natTl up to 42 MeV: review, new data and evaluation

    OpenAIRE

    Tárkányi, F.; Ditrói, F.; Hermanne, A.; Takács, S.; Adam-Rebeles, R.; Walravens, N.; Cichelli, O.; Ignatyuk, A. V.

    2013-01-01

    Cross-sections of proton induced nuclear reactions on natural thallium have been studied for investigation of the production of the medical important 201Tl diagnostic radioisotope. The excitation functions of 204mPb, 203Pb, 202mPb, 201Pb, 200Pb, 199Pb, 202Tl (direct, cumulative), 201Tl (direct, cumulative), 200Tl(direct), and 203Hg were measured up to 42 MeV proton energy by stacked foil technique and activation method. The experimental data were compared with the critically analyzed experime...

  6. The version control service for ATLAS data acquisition configuration files

    CERN Document Server

    Soloviev, Igor; The ATLAS collaboration

    2012-01-01

    To configure data taking session the ATLAS systems and detectors store more than 160 MBytes of data acquisition related configuration information in OKS XML files [1]. The total number of the files exceeds 1300 and they are updated by many system experts. In the past from time to time after such updates we had experienced problems caused by XML syntax errors or inconsistent state of files from a point of view of the overall ATLAS configuration. It was not always possible to know who made a modification causing problems or how to go back to a previous version of the modified file. Few years ago a special service addressing these issues has been implemented and deployed on ATLAS Point-1. It excludes direct write access to XML files stored in a central database repository. Instead, for an update the files are copied into a user repository, validated after modifications and committed using a version control system. The system's callback updates the central repository. Also, it keeps track of all modifications pro...

  7. Dynamic testing of nuclear power plant structures: an evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Weaver, H.J.

    1980-02-01

    Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants.

  8. Compilation of requests for nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    1979-04-01

    The purpose of this compilation is to summarize the current needs of US Nuclear Energy programs and other applied technologies for nuclear data. At the present time needs fall primarily in the area of neutron cross sections, although no such limitation is intended. This request list is ordered by target nucleus (isotope) and then reaction type (quantity). An attempt is made to describe the quantity in standard notation. A glossary of these symbols with a short explanatory text is provided. All requests must give the energy (or range of energy) for the incident particle when appropriate. The accuracy needed in percent is also given. The error quoted is assumed to be 1 sigma at each measured point in the energy range requested unless a comment specifies otherwise. (RWR)

  9. Proceedings of the first internet symposium on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Fukahori, Tokio; Iwamoto, Osamu; Nakagawa, Tsuneo [eds.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    The First Internet Symposium on Nuclear Data (ISND-1) was held on the WWW home page of Nuclear Data Center at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), from April 8 to June 15, 1996. This symposium was organized by Japanese Nuclear Data Committee and Nuclear Data Center, JAERI and was the first trial to use `Internet` for the symposium in a nuclear data field. In ISND-1, presented were 25 papers on various topics of nuclear data. Those presented papers are compiled in this proceedings as well as brief description about management of ISND-1. (author)

  10. Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study

    Energy Technology Data Exchange (ETDEWEB)

    Garcia-Herranz, N., E-mail: nuria@din.upm.e [Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid (Spain); Instituto de Fusion Nuclear, Universidad Politecnica de Madrid (Spain); Cabellos, O. [Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid (Spain); Instituto de Fusion Nuclear, Universidad Politecnica de Madrid (Spain); Alvarez-Velarde, F. [CIEMAT (Spain); Sanz, J. [Instituto de Fusion Nuclear, Universidad Politecnica de Madrid (Spain); Departamento de Ingenieria Energetica, UNED (Spain); Gonzalez-Romero, E.M. [CIEMAT (Spain); Juan, J. [Laboratorio de Estadistica, Universidad Politecnica de Madrid (Spain)

    2010-11-15

    In this paper, we assess the impact of activation cross-section uncertainties on relevant fuel cycle parameters for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) with a 'double strata' fuel cycle. Next, the nuclear data requirements are evaluated so that the parameters can meet the assigned design target accuracies. Different discharge burn-up levels are considered: a low burn-up, corresponding to the equilibrium cycle, and a high burn-up level, simulating the effects on the fuel of the multi-recycling scenario. In order to perform this study, we propose a methodology in two steps. Firstly, we compute the uncertainties on the system parameters by using a Monte Carlo simulation, as it is considered the most reliable approach to address this problem. Secondly, the analysis of the results is performed by a sensitivity technique, in order to identify the relevant reaction channels and prioritize the data improvement needs. Cross-section uncertainties are taken from the EAF-2007/UN library since it includes data for all the actinides potentially present in the irradiated fuel. Relevant uncertainties in some of the fuel cycle parameters have been obtained, and we conclude with recommendations for future nuclear data measurement programs, beyond the specific results obtained with the present nuclear data files and the limited available covariance information. A comparison with the uncertainty and accuracy analysis recently published by the WPEC-Subgroup26 of the OECD using BOLNA covariance matrices is performed. Despite the differences in the transmuter reactor used for the analysis, some conclusions obtained by Subgroup26 are qualitatively corroborated, and improvements for additional cross sections are suggested.

  11. Dealing with the data deluge: file systems and storage technologies

    Science.gov (United States)

    Denson, David H.

    2012-06-01

    As defense and intelligence agencies seek to use the increasing amount of available data to make mission critical decisions on the battlefield, there is heavy emphasis on smart data and imagery collection: the capture, storage, and analysis necessary to drive real-time intelligence. This reality leads to an inevitable challenge-warfighters are increasingly swimming in sensors and drowning in data. With the millions, if not billions, of sensors in place that provide all-seeing reports of the combat environment, managing and tackling the overload is critical. This session highlights the capabilities of file systems and storage technologies that can interactively manage 100M+ files and 1PB+ single directory file systems.

  12. Validation of iron nuclear data for the neutron calculation of nuclear reactors; Validation de donnees nucleaires du fer pour le calcul neutronique des reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Vaglio-Gaudard, C.

    2010-03-29

    iterative technique (limitation to the first Gauss-Newton iteration in this study). The re-evaluation process shows that the {sup 56}Fe nuclear data in the JEFF3.1.1 library are known with accuracy. It is the first main thesis result which makes it possible to clearly validate the iron nuclear data in the JEFF3 library, for the fission reactor calculation. A new a posteriori covariance matrix associated with JEFF3 can then be deduced. An important result shows that the a posteriori uncertainties are reduced by a ratio of two on the inelastic cross section compared with prior uncertainties. The second thesis result relies on obtaining a realistic covariance matrix associated with the JEFF3 iron nuclear data. This matrix can be used as reference for the realistic uncertainty propagation studies on safety parameters of GEN-III and GEN-IV reactors (core safety parameters, vessel pressure fluence, etc). Furthermore, the impact of the {sup 56}Fe elastic angular distributions was not taken into account in the nuclear data re-evaluation process; their accuracy can however have a non-negligible impact on the calculation of the fast flux attenuation in the reflector. Analysis of the {sup 56}Fe elastic angular distributions in the JEFF3 file shows that they are not very well known and could be improved, which is an interesting prospect developed in the thesis. (author)

  13. Neutron and proton nuclear data evaluation for sup 2 sup 3 sup 5 U and sup 2 sup 3 sup 8 U at energies up to 250 MeV

    CERN Document Server

    Konobeyev, A Y; Iwamoto, O

    2002-01-01

    Basic features of nuclear data evaluation for uranium isotopes sup 2 sup 3 sup 5 U and sup 2 sup 3 sup 8 U at intermediate energies are described. The coupled channel optical model was used to obtain total cross section, reaction cross section, angular distributions and transmission coefficients. The direct, pre-compound and evaporation models were used to describe neutron and charged particles emission from excited nuclei. The neutron data evaluated were combined with JENDL-3.3 data below 20 MeV to obtain a full data set in the whole energy range between 10 sup - sup 5 eV an 250 MeV. Evaluation of the proton data has been done at energies from 1 to 250 MeV.

  14. Nuclear Fuel Cycle Evaluation and Real Options

    Directory of Open Access Journals (Sweden)

    L. Havlíček

    2008-01-01

    Full Text Available The first part of this paper describes the nuclear fuel cycle. It is divided into three parts. The first part, called Front-End, covers all activities connected with fuel procurement and fabrication. The middle part of the cycle includes fuel reload design activities and the operation of the fuel in the reactor. Back-End comprises all activities ensuring safe separation of spent fuel and radioactive waste from the environment. The individual stages of the fuel cycle are strongly interrelated. Overall economic optimization is very difficult. Generally, NPV is used for an economic evaluation in the nuclear fuel cycle. However the high volatility of uranium prices in the Front-End, and the large uncertainty of both economic and technical parameters in the Back-End, make the use of NPV difficult. The real option method is able to evaluate the value added by flexibility of decision making by a company under conditions of uncertainty. The possibility of applying this method to the nuclear fuel cycle evaluation is studied. 

  15. An information retrieval system for research file data

    Science.gov (United States)

    Joan E. Lengel; John W. Koning

    1978-01-01

    Research file data have been successfully retrieved at the Forest Products Laboratory through a high-speed cross-referencing system involving the computer program FAMULUS as modified by the Madison Academic Computing Center at the University of Wisconsin. The method of data input, transfer to computer storage, system utilization, and effectiveness are discussed....

  16. Nuclear core activity reconstruction using heterogeneous instruments with data assimilation

    Directory of Open Access Journals (Sweden)

    Bouriquet Bertrand

    2015-01-01

    Full Text Available Evaluating the neutronic state (neutron flux, power… of the whole nuclear core is a very important topic that has strong implication for nuclear core management and for security monitoring. The core state is evaluated using measurements and calculations. Usually, parts of the measurements are used, and only one kind of instrument is taken into account. However, the core state evaluation should be more accurate when more measurements are collected in the core. But using information from heterogeneous sources is at glance a difficult task. This difficulty can be overcome by Data Assimilation techniques. Such a method allows to combine in a coherent framework the information coming from numerical model and the one coming from various types of observations. Beyond the inner advantage to use heterogeneous instruments, this leads to obtaining a significant increase of the quality of neutronic global state reconstruction with respect to individual use of measures. In order to describe this approach, we introduce here the basic principles of data assimilation (focusing on BLUE, Best Unbiased Linear Estimation. Then we present the configuration of the method within the nuclear core problematic. Finally, we present the results obtained on nuclear measurements coming from various instruments.

  17. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

    2001-03-15

    This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

  18. Building Foundations for Nuclear Security Enterprise Analysis Utilizing Nuclear Weapon Data

    Energy Technology Data Exchange (ETDEWEB)

    Josserand, Terry Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Security Enterprise and Cost Analysis; Young, Leone [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Security Enterprise and Cost Analysis; Chamberlin, Edwin Phillip [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Security Enterprise and Cost Analysis

    2017-09-01

    The Nuclear Security Enterprise, managed by the National Nuclear Security Administration - a semiautonomous agency within the Department of Energy - has been associated with numerous assessments with respect to the estimating, management capabilities, and practices pertaining to nuclear weapon modernization efforts. This report identifies challenges in estimating and analyzing the Nuclear Security Enterprise through an analysis of analogous timeframe conditions utilizing two types of nuclear weapon data - (1) a measure of effort and (2) a function of time. The analysis of analogous timeframe conditions that utilizes only two types of nuclear weapon data yields four summary observations that estimators and analysts of the Nuclear Security Enterprise will find useful.

  19. Nuclear Decay Data for the International Reactor Dosimetry Library for Fission and Fusion (IRDFF): Updated Evaluations of the Half-Lives and Gamma Ray Intensities

    Science.gov (United States)

    Chechev, Valery P.; Kuzmenko, Nikolay K.

    2016-02-01

    Updated evaluations of the half-lives and prominent gamma ray intensities have been presented for 20 radionuclides - dosimetry reaction residuals. The new values of these decay characteristics recommended for the IRDFF library were obtained using the approaches and methodology adopted by the working group of the Decay Data Evaluation Project (DDEP) cooperation. The experimental data published up to 2014 were taken into account in updated evaluations. The list of radionuclides includes 3H, 18F, 22Na, 24Na, 46Sc, 51Cr, 54Mn, 59Fe, 57Co, 60Co, 57Ni, 64Cu, 88Y, 132Te, 131I, 140Ba, 140La, 141Ce, 182Ta, 198Au.

  20. Using Nuclear Theory, Data and Uncertainties in Monte Carlo Transport Applications

    Energy Technology Data Exchange (ETDEWEB)

    Rising, Michael Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-11-03

    These are slides for a presentation on using nuclear theory, data and uncertainties in Monte Carlo transport applications. The following topics are covered: nuclear data (experimental data versus theoretical models, data evaluation and uncertainty quantification), fission multiplicity models (fixed source applications, criticality calculations), uncertainties and their impact (integral quantities, sensitivity analysis, uncertainty propagation).

  1. Nuclear Data Sheets for A=228

    Energy Technology Data Exchange (ETDEWEB)

    Abusaleem, Khalifeh

    2014-02-01

    The evaluated spectroscopic data are presented for known nuclides of mass 228 (Ac, At, Fr, Np, Pa, Pu, Ra, Rn, Th, and U). Excited states in {sup 228}At, {sup 228}Rn, {sup 228}Fr, {sup 228}Np, and {sup 228}Pu have not been identified as yet. Significant amounts of new data have been added since the last evaluation of A=228 nuclides. This work supersedes earlier full evaluations of A=228 published by 1997Ar08.

  2. Development of JENDL Decay and Fission Yield Data Libraries

    Science.gov (United States)

    Katakura, J.

    2014-04-01

    Decay and fission yield data of fission products have been developed for decay heat calculations to constitute one of the special purpose files of JENDL (Japanese Nuclear Data Library). The decay data in the previous JENDL decay data file have been updated based on the data extracted from ENSDF (Evaluated Nuclear Structure Data File) and those by Total Absorption Gamma-ray Spectroscopy (TAGS) measurements reported recently. Fission yield data have also been updated in order to maintain consistency between the decay and yield data files. Decay heat calculations were performed using the updated decay and yield data, and the results were compared with measured decay heat data to demonstrate their applicability. The uncertainties of the calculated results were obtained by sensitivity analyses. The resulting JENDL calculations and their uncertainty were compared with those from the ENDF and JEFF evaluated files.

  3. Basic data for integrated assessment of nuclear fuel cycle system

    Energy Technology Data Exchange (ETDEWEB)

    Nomura, Yasushi; Tamaki, Hitoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ito, Chihiro; Saegusa, Toshiari [Central Research Inst. of Electric Power Industry, Tokyo (Japan)

    2001-03-01

    In our country, where natural energy resources such as oil and coal are scarce, it is vital to establish a nuclear fuel cycle to reprocess spent fuel and reuse valuable nuclear fuel in electric power generation reactors. However spent fuel is now being accumulated too much so that, for the time being, it is necessary to establish a system for tentatively storing spent fuel. In this report, in order to deal with these issues, evaluation methods, which were developed, prepared and discussed by Japan Atomic Energy Research Institute (JAERI) and Central Research Institute of Electric Power Industry (CRIEPI), are rendered together with sample results of their application. Also reported is some important information on the data and methods for the safety assessment of nuclear fuel cycle facilities, which have been surveyed by JAERI and CRIEPI. (author)

  4. Performance and Scalability Evaluation of the Ceph Parallel File System

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Feiyi [ORNL; Nelson, Mark [Inktank Storage, Inc.; Oral, H Sarp [ORNL; Settlemyer, Bradley W [ORNL; Atchley, Scott [ORNL; Caldwell, Blake A [ORNL; Hill, Jason J [ORNL

    2013-01-01

    Ceph is an open-source and emerging parallel distributed file and storage system technology. By design, Ceph assumes running on unreliable and commodity storage and network hardware and provides reliability and fault-tolerance through controlled object placement and data replication. We evaluated the Ceph technology for scientific high-performance computing (HPC) environments. This paper presents our evaluation methodology, experiments, results and observations from mostly parallel I/O performance and scalability perspectives. Our work made two unique contributions. First, our evaluation is performed under a realistic setup for a large-scale capability HPC environment using a commercial high-end storage system. Second, our path of investigation, tuning efforts, and findings made direct contributions to Ceph's development and improved code quality, scalability, and performance. These changes should also benefit both Ceph and HPC communities at large. Throughout the evaluation, we observed that Ceph still is an evolving technology under fast-paced development and showing great promises.

  5. Development of an Integrity Evaluation System for Nuclear Power Plants

    Science.gov (United States)

    Kim, Young-Jin; Choi, Jae-Boong; Lee, Joon-Seong; Jun, Hyun-Kyu; Park, Youn-Won

    This paper describes the structure and development strategy for integrity evaluation system for nuclear power plants called NPP-KINS/SAFE. NPP-KINS/SAFE consists of three different programs covering the integrity assessment of reactor pressure vessel, pipings, and pressure tubes, respectively. The system has been developed based on currently available codes and standards, and includes a number of databases, expert systems, and numerical analysis schemes. NPP-KINS/SAFE is applicable for various types of nuclear power plants constructed in Korea with the aid of attached database systems including plant specific data. Case studies for the developed system are also provided.

  6. High energy nuclear database: a test-bed for nuclear data information technology

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D.A.; Vogt, R.; Beck, B.; Pruet, J. [Lawrence Livermore National Lab, Livermore, CA (United States); Vogt, R. [Davis Univ. of California, CA (United States)

    2008-07-01

    We describe the development of an on-line high-energy heavy-ion experimental database. When completed, the database will be searchable and cross-indexed with relevant publications, including published detector descriptions. While this effort is relatively new, it will eventually contain all published data from older heavy-ion programs as well as published data from current and future facilities. These data include all measured observables in proton-proton, proton-nucleus and nucleus-nucleus collisions. Once in general use, this database will have tremendous scientific payoff as it makes systematic studies easier and allows simpler benchmarking of theoretical models for a broad range of experiments. Furthermore, there is a growing need for compilations of high-energy nuclear data for applications including stockpile stewardship, technology development for inertial confinement fusion, target and source development for upcoming facilities such as the International Linear Collider and homeland security. This database is part of a larger proposal that includes the production of periodic data evaluations and topical reviews. These reviews would provide an alternative and impartial mechanism to resolve discrepancies between published data from rival experiments and between theory and experiment. Since this database will be a community resource, it requires the high-energy nuclear physics community's financial and manpower support. This project serves as a test-bed for the further development of an object-oriented nuclear data format and database system. By using 'off-the-shelf' software tools and techniques, the system is simple, robust, and extensible. Eventually we envision a 'Grand Unified Nuclear Format' encapsulating data types used in the ENSDF, Endf/B, EXFOR, NSR and other formats, including processed data formats. (authors)

  7. Analysis of sample and fuel pin irradiation experiments in Phenix for basic nuclear data validation

    Energy Technology Data Exchange (ETDEWEB)

    D' Angelo, A.; Cleri, F. (ENEA, Casaccia Nuclear Research Centre, Dipartimento Reattori Veloci, 0060 Casaccia (IT)); Marimbeau, P.; Salvatores, M.; Grouiller, J.P. (Centre d' Etudes Nucleaires de Cadarache, Service de Physique des Reacteurs et du Cycle, Dept. de Recherche Physique, 13108 St. Paul-lez-Durance (FR))

    1990-07-01

    This paper presents comparisons between calculations and experimental data from fuel irradiation experiments performed in Phenix. Both the French CARNAVAL-IV system and the recently developed JEF-1 basic data file are used. The global consistency of the results is excellent and the compared values are, in general, very satisfactory. In some cases, indications for evaluated data modifications are obtained.

  8. Part B Carrier Summary Data File

    Data.gov (United States)

    U.S. Department of Health & Human Services — Data sets are summarized at the carrier level by meaningful Healthcare Common Procedure Coding-Current Procedural Terminology, (HCPC-CPT), code ranges. The data set...

  9. Nuclear Decay Data for the International Reactor Dosimetry Library for Fission and Fusion (IRDFF: Updated Evaluations of the Half-Lives and Gamma Ray Intensities

    Directory of Open Access Journals (Sweden)

    Chechev Valery P.

    2016-01-01

    Full Text Available Updated evaluations of the half-lives and prominent gamma ray intensities have been presented for 20 radionuclides – dosimetry reaction residuals. The new values of these decay characteristics recommended for the IRDFF library were obtained using the approaches and methodology adopted by the working group of the Decay Data Evaluation Project (DDEP cooperation. The experimental data published up to 2014 were taken into account in updated evaluations. The list of radionuclides includes 3H, 18F, 22Na, 24Na, 46Sc, 51Cr, 54Mn, 59Fe, 57Co, 60Co, 57Ni, 64Cu, 88Y, 132Te, 131I, 140Ba, 140La, 141Ce, 182Ta, 198Au.

  10. Gene expression data (CEL files) - Open TG-GATEs | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us Open TG-GATEs Gene expression data (CEL files) Data detail Data name Gene expression data (C... of the file formats that expresses gene expression data (raw data) generated from Affymetrix GeneChip®. Dat...gates/LATEST/Rat/ File size: 12.0GB total File name: Gene expression data from hu...Simple search URL - Data acquisition method Gene expression data were generated from Affymetrix GeneChip®. I...olicy | Contact Us Gene expression data (CEL files) - Open TG-GATEs | LSDB Archive ...

  11. EQPT, a data file preprocessor for the EQ3/6 software package: User`s guide and related documentation (Version 7.0); Part 2

    Energy Technology Data Exchange (ETDEWEB)

    Daveler, S.A.; Wolery, T.J.

    1992-12-17

    EQPT is a data file preprocessor for the EQ3/6 software package. EQ3/6 currently contains five primary data files, called datao files. These files comprise alternative data sets. These data files contain both standard state and activity coefficient-related data. Three (com, sup, and nea) support the use of the Davies or B-dot equations for the activity coefficients; the other two (hmw and pit) support the use of Pitzer`s (1973, 1975) equations. The temperature range of the thermodynamic data on these data files varies from 25{degrees}C only to 0-300{degrees}C. The principal modeling codes in EQ3/6, EQ3NR and EQ6, do not read a data0 file, however. Instead, these codes read an unformatted equivalent called a data1 file. EQPT writes a datal file, using the corresponding data0 file as input. In processing a data0 file, EQPT checks the data for common errors, such as unbalanced reactions. It also conducts two kinds of data transformation. Interpolating polynomials are fit to data which are input on temperature adds. The coefficients of these polynomials are then written on the datal file in place of the original temperature grids. A second transformation pertains only to data files tied to Pitzer`s equations. The commonly reported observable Pitzer coefficient parameters are mapped into a set of primitive parameters by means of a set of conventional relations. These primitive form parameters are then written onto the datal file in place of their observable counterparts. Usage of the primitive form parameters makes it easier to evaluate Pitzer`s equations in EQ3NR and EQ6. EQPT and the other codes in the EQ3/6 package are written in FORTRAN 77 and have been developed to run under the UNIX operating system on computers ranging from workstations to supercomputers.

  12. TENDL nuclear data library for calculation of fuel composition change

    Energy Technology Data Exchange (ETDEWEB)

    Abramovich, S.N.; Gorelov, V.P.; Gorshikhin, A.A.; Grebennikov, A.N.; Farafontov, G.G. [Russian Federal Nuclear Center - VNIIEF, Arzamas (Russian Federation)

    1997-09-01

    There is description TENDL1 first version of evaluated nuclear data for calculation of fuel composition change in transmutation design. TENDL1 contain data for actinides and fission fragments. Selection of data for TENDL1 was made from ENDL-82, JENDL-3, ENDF/B-6 and BROND-2. TEND1 could be recommended for the usage in the equations of fuel composition kinetics in the course of multigroup neutron constants preparation. TENDL development was preceded by the analytical work. Its results are also discussed in the present paper. 25 refs., 8 tabs.

  13. Penyembunyian Data pada File Video Menggunakan Metode LSB dan DCT

    Directory of Open Access Journals (Sweden)

    Mahmuddin Yunus

    2014-01-01

    Full Text Available Abstrak Penyembunyian data pada file video dikenal dengan istilah steganografi video. Metode steganografi yang dikenal diantaranya metode Least Significant Bit (LSB dan Discrete Cosine Transform (DCT. Dalam penelitian ini dilakukan penyembunyian data pada file video dengan menggunakan metode LSB, metode DCT, dan gabungan metode LSB-DCT. Sedangkan kualitas file video yang dihasilkan setelah penyisipan dihitung dengan menggunakan Mean Square Error (MSE dan Peak Signal to Noise Ratio (PSNR.Uji eksperimen dilakukan berdasarkan ukuran file video, ukuran file berkas rahasia yang disisipkan, dan resolusi video. Hasil pengujian menunjukkan tingkat keberhasilan steganografi video dengan menggunakan metode LSB adalah 38%, metode DCT adalah 90%, dan gabungan metode LSB-DCT adalah 64%. Sedangkan hasil perhitungan MSE, nilai MSE metode DCT paling rendah dibandingkan metode LSB dan gabungan metode LSB-DCT. Sedangkan metode LSB-DCT mempunyai nilai yang lebih kecil dibandingkan metode LSB. Pada pengujian PSNR diperoleh databahwa nilai PSNR metode DCTlebih tinggi dibandingkan metode LSB dan gabungan metode LSB-DCT. Sedangkan nilai PSNR metode gabungan LSB-DCT lebih tinggi dibandingkan metode LSB.   Kata Kunci— Steganografi, Video, Least Significant Bit (LSB, Discrete Cosine Transform (DCT, Mean Square Error (MSE, Peak Signal to Noise Ratio (PSNR                             Abstract Hiding data in video files is known as video steganography. Some of the well known steganography methods areLeast Significant Bit (LSB and Discrete Cosine Transform (DCT method. In this research, data will be hidden on the video file with LSB method, DCT method, and the combined method of LSB-DCT. While the quality result of video file after insertion is calculated using the Mean Square Error (MSE and Peak Signal to Noise Ratio (PSNR. The experiments were conducted based on the size of the video file, the file size of the inserted secret files, and

  14. Nuclear structure database

    Energy Technology Data Exchange (ETDEWEB)

    Firestone, R.B.; Browne, E.

    1980-06-01

    A nuclear structure database has been created from the Table of Isotopes level-scheme file. This database contains evaluated data (through 1977) on level and deexcitation properties for all known isotopes from radioactive decay and nuclear reaction studies. The data are organized in simple array formats to enable rapid searches for specific level or decay information. Examples of the use of this database to study the properties of first excited J/sup ..pi../ = 2/sup +/ states in even-even nuclei and Weisskopf enhancements of delayed ..gamma..-ray transitions are shown. 6 figures, 3 tables.

  15. Part B National Summary Data File

    Data.gov (United States)

    U.S. Department of Health & Human Services — Previously known as BESS. The data sets are summarized by meaningful Healthcare Common Procedure Coding Current Procedural Terminology, HCPC CPT, code ranges. Brief...

  16. Health Care Information System (HCIS) Data File

    Data.gov (United States)

    U.S. Department of Health & Human Services — The data was derived from the Health Care Information System (HCIS), which contains Medicare Part A (Inpatient, Skilled Nursing Facility, Home Health Agency (Part A...

  17. Tables of nuclear data (JENDL/TND-2012)

    OpenAIRE

    行川 正和; 深堀 智生

    2012-01-01

    Several numerical data (mass, level energy, spin and parity, abundance, mass excess, beta-decay energy, and half-life) of nuclides were collected with each element into the "Tables of Nuclear Data (JENDL/TND-2012)." These tables are related to the "Chart of the Nuclides" published by Japanese Nuclear Data Committee and Nuclear Data Center of Japan Atomic Energy Agency (JAEA), and data of the nuclides synthesized in the chart. Moreover, new determinations are adopted instead of the values in E...

  18. [Required procedure for nominal data files processing in biomedical research].

    Science.gov (United States)

    Chambon-Savanovitch, C; Dubray, C; Albuisson, E; Sauvant, M P

    2001-12-01

    To date, biomedical research using nominal data files for the data collection, data acquisition or data processing has had to comply with 2 French laws (Law of December, 20, 1988, modified, relating to the protection of patients participating in biomedical research, and the Law of January, 6, 1978, completed by the Law of July 1, 1994 n degrees 94-548, chapter V bis). This later law dictates rules not only for the establishment of nominal data files, but also confer individual rights to filed persons. These regulations concern epidemiological research, clinical trials, drug watch studies and economic health research. In this note, we describe the obligations and specific general and simplified procedure required for conducting biomedical research. Included in the requirements are an information and authorization procedure with the local and national consultative committees on data processing in biomedical research (CCTIRS, Comité Consultatif sur le Traitement de l'Information en Recherche Biomédicale, and CNIL, Commission Nationale Informatique et Libertés).

  19. Nuclear data uncertainty propagation by the XSUSA method in the HELIOS2 lattice code

    Science.gov (United States)

    Wemple, Charles; Zwermann, Winfried

    2017-09-01

    Uncertainty quantification has been extensively applied to nuclear criticality analyses for many years and has recently begun to be applied to depletion calculations. However, regulatory bodies worldwide are trending toward requiring such analyses for reactor fuel cycle calculations, which also requires uncertainty propagation for isotopics and nuclear reaction rates. XSUSA is a proven methodology for cross section uncertainty propagation based on random sampling of the nuclear data according to covariance data in multi-group representation; HELIOS2 is a lattice code widely used for commercial and research reactor fuel cycle calculations. This work describes a technique to automatically propagate the nuclear data uncertainties via the XSUSA approach through fuel lattice calculations in HELIOS2. Application of the XSUSA methodology in HELIOS2 presented some unusual challenges because of the highly-processed multi-group cross section data used in commercial lattice codes. Currently, uncertainties based on the SCALE 6.1 covariance data file are being used, but the implementation can be adapted to other covariance data in multi-group structure. Pin-cell and assembly depletion calculations, based on models described in the UAM-LWR Phase I and II benchmarks, are performed and uncertainties in multiplication factor, reaction rates, isotope concentrations, and delayed-neutron data are calculated. With this extension, it will be possible for HELIOS2 users to propagate nuclear data uncertainties directly from the microscopic cross sections to subsequent core simulations.

  20. Decay data evaluation project (DDEP): updated evaluations of the 233Th and 241Am decay characteristics.

    Science.gov (United States)

    Chechev, Valery P; Kuzmenko, Nikolay K

    2010-01-01

    The results of new decay data evaluations are presented for (233)Th (beta(-)) decay to nuclear levels in (233)Pa and (241)Am (alpha) decay to nuclear levels in (237)Np. These evaluated data have been obtained within the Decay Data Evaluation Project using information published up to 2009. Copyright 2009 Elsevier Ltd. All rights reserved.

  1. CIRFT Data Update and Data Analyses for Spent Nuclear Fuel Vibration Reliability Study

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wang, Hong [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-08-01

    The objective of this research is to collect experimental data on spent nuclear fuel (SNF) from pressurized water reactors (PWRs), including the H. B. Robinson Nuclear Power Station (HBR), Catawba Nuclear Station, North Anna Nuclear Power Station (NA), and the Limerick Nuclear Power Station (LMK) boiling water reactor (BWR).

  2. Nuclear imaging evaluation of galactosylation of chitosan

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Hwan Jeong; Kim, Eun Mi; Kim, Chang Guhn [School of Medicine, Wonkwang Univ., Iksan (Korea, Republic of); Park, In Kyu; Cho, Chong Su [Seoul National Univ., Seoul (Korea, Republic of); Bom, Hee Seung [School of Medicine, Chonnam National Univ., Gwangju (Korea, Republic of)

    2004-06-01

    Chitosan has been studied as a non-viral gene delivery vector, drug delivery carrier, metal chelater, food additive, and radiopharmaceutical, among other things. Recently, galactose-graft chitosan was studied as a non-viral gene and drug delivery vector to target hepatocytes. The aim of this study was to investigate the usefulness of nuclear imaging for in vivo evaluation of targeting the hepatocyte by galactose grafting. Galactosyl methylated chitosan (GMC) was produced by methylation to lactobionic acid coupled chitosan Cytotoxicity of {sup 99}mTc-GMC was determined by MTT assay. Rabbits were injected via their auricular vein with {sup 99}mTc-GMC and {sup 99}mTc-methylated chitosan (MC), the latter of which does not contain a galactose group, and images were acquired with a gamma camera equipped with a parallel hole collimator. The composition of the galactose group in galactosylated chitosan (GC), as well as the tri-, di-, or mono-methylation of GMC, was confirmed by NMR spectroscopy. The results of MTT assay indicated that {sup 99}mTc-GMC was non-toxic. {sup 99}mTc-GMC specifically accumulated in the liver within 10 minutes of injection and maintained high hepatic uptake. In contrast, {sup 99}mTc-MC showed faint liver uptake. {sup 99}mTc-GMC scintigraphy of rabbits showed that the galactose ligand principally targeted the liver while the chitosan functionalities led to excretion through the urinary system. Bioconjugation with a specific ligand endows some degree of targetability to an administered molecule or drug, as in the case of galactose for hepatocyte in vivo, and evaluating said targetability is a clear example of the great benefit proffered by nuclear imaging.

  3. Monte Carlo simulation of nuclear energy study (II). Annual report on Nuclear Code Evaluation Committee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-01-01

    In the report, research results discussed in 1999 fiscal year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. Present status of Monte Carlo simulation on nuclear energy study was described. Especially, besides of criticality, shielding and core analyses, present status of applications to risk and radiation damage analyses, high energy transport and nuclear theory calculations of Monte Carlo Method was described. The 18 papers are indexed individually. (J.P.N.)

  4. Tables and graphs of photon-interaction cross sections from 0. 1 keV to 100 MeV derived from the LLL evaluated-nuclear-data library

    Energy Technology Data Exchange (ETDEWEB)

    Plechaty, E.F.; Cullen, D.E.; Howerton, R.J.

    1981-11-11

    Energy-dependent evaluated photon interaction cross sections and related parameters are presented for elements H through Cf(Z = 1 to 98). Data are given over the energy range from 0.1 keV to 100 MeV. The related parameters include form factors and average energy deposits per collision (with and without fluorescence). Fluorescence information is given for all atomic shells that can emit a photon with a kinetic energy of 0.1 keV or more. In addition, the following macroscopic properties are given: total mean free path and energy deposit per centimeter. This information is derived from the Livermore Evaluated-Nuclear-Data Library (ENDL) as of October 1978.

  5. Research in nondestructive evaluation techniques for nuclear reactor concrete structures

    Science.gov (United States)

    Clayton, Dwight; Smith, Cyrus

    2014-02-01

    The purpose of the Materials Aging and Degradation (MAaD) Pathway of the Department of Energy's Light Water Reactor Sustainability (LWRS) Program is to develop the scientific basis for understanding and predicting longterm environmental degradation behavior of material in nuclear power plants and to provide data and methods to assess the performance of systems, structures, and components (SSCs) essential to safe and sustained nuclear power plant operations. The understanding of aging-related phenomena and their impacts on SSCs is expected to be a significant issue for any nuclear power plant planning for long-term operations (i.e. service beyond the initial license renewal period). Management of those phenomena and their impacts during long-term operations can be better enable by improved methods and techniques for detection, monitoring, and prediction of SSC degradation. The MAaD Pathway R&D Roadmap for Concrete, "Light Water Reactor Sustainability Nondestructive Evaluation for Concrete Research and Development Roadmap", focused initial research efforts on understanding the recent concrete issues at nuclear power plants and identifying the availability of concrete samples for NDE techniques evaluation and testing. [1] An overview of the research performed by ORNL in these two areas is presented here.

  6. Fifty years of nuclear fission: Nuclear data and measurements series

    Energy Technology Data Exchange (ETDEWEB)

    Lynn, J.E.

    1989-06-01

    This report is the written version of a colloquium first presented at Argonne National Laboratory in January 1989. The paper begins with an historical preamble about the events leading to the discovery of nuclear fission. This leads naturally to an account of early results and understanding of the fission phenomena. Some of the key concepts in the development of fission theory are then discussed. The main theme of this discussion is the topography of the fission barrier, in which the interplay of the liquid-drop model and nucleon shell effects lead to a wide range of fascinating phenomena encompassing metastable isomers, intermediate-structure effects in fission cross-sections, and large changes in fission product properties. It is shown how study of these changing effects and theoretical calculations of the potential energy of the deformed nucleus have led to broad qualitative understanding of the nature of the fission process. 54 refs., 35 figs.

  7. The ORSphere Benchmark Evaluation and Its Potential Impact on Nuclear Criticality Safety

    Energy Technology Data Exchange (ETDEWEB)

    John D. Bess; Margaret A. Marshall; J. Blair Briggs

    2013-10-01

    In the early 1970’s, critical experiments using an unreflected metal sphere of highly enriched uranium (HEU) were performed with the focus to provide a “very accurate description…as an ideal benchmark for calculational methods and cross-section data files.” Two near-critical configurations of the Oak Ridge Sphere (ORSphere) were evaluated as acceptable benchmark experiments for inclusion in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook). The results from those benchmark experiments were then compared with additional unmoderated and unreflected HEU metal benchmark experiment configurations currently found in the ICSBEP Handbook. For basic geometries (spheres, cylinders, and slabs) the eigenvalues calculated using MCNP5 and ENDF/B-VII.0 were within 3 of their respective benchmark values. There appears to be generally a good agreement between calculated and benchmark values for spherical and slab geometry systems. Cylindrical geometry configurations tended to calculate low, including more complex bare HEU metal systems containing cylinders. The ORSphere experiments do not calculate within their 1s uncertainty and there is a possibility that the effect of the measured uncertainties for the GODIVA I benchmark may need reevaluated. There is significant scatter in the calculations for the highly-correlated ORCEF cylinder experiments, which are constructed from close-fitting HEU discs and annuli. Selection of a nuclear data library can have a larger impact on calculated eigenvalue results than the variation found within calculations of a given experimental series, such as the ORCEF cylinders, using a single nuclear data set.

  8. 2010 Review of Neutron and Non-Neutron Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    Holden, N. E. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2011-05-27

    The results of a review and evaluation of neutron and nonneutron nuclear data published in the scientific literature over the past three years are presented. The status of new chemical elements is examined. Ten elements have had their atomic weight and uncertainty replaced by interval values of upper and lower bounds. Data on revised values for the isotopic composition of the elements are reviewed and new recommended values are presented for germanium. Radioactive half-lives are reviewed and latest values presented which include measurements on nuclides of interest and very long-lived nuclides such as double beta decay, double electron capture, long-lived alpha decay and long-lived beta decay. The latest information and the status on the evaluation of atomic masses are discussed. Data from new measurements on the very heavy elements (trans-meitnerium elements) are discussed and tabulated. Data on various recent neutron cross-section and resonance integral measurements are also discussed and the latest measurements are tabulated in both cases. The JENDL-4.0 and ENDF/B-VII.1 nuclear data libraries are discussed. A new initiative on the existence and importance of isotopes is presented.

  9. Reconstructing historical populations from genealogical data: an overview of methods used for aggregating data from GEDCOM files

    NARCIS (Netherlands)

    Gellatly, C.

    2014-01-01

    The GEDCOM file format is by far the most widely used means of exchanging genealogical data and extensive collections of these files are available online. There is a huge potential bene-fit for historians and other academics who are able to make use of the data contained in availa-ble GEDCOM files,

  10. Data Conversion Tool For Tobii Pro Glasses 2 Live Data Files

    DEFF Research Database (Denmark)

    Wulff-Jensen, Andreas

    2017-01-01

    The data gathered through the Tobii Pro Glasses 2 is saved in a .json file called livedata.json. This format is convenient for the Tobii analysis software, but for any other analysis software packages it can be rather troublesome as the software packages do not know how to interpret the .json fil....... This paper will describe a small Java program which is capable of converting the .json file to a comma separated .txt file, which is ready to be used in either Ogama , Matlab or another eye-tracking analysis software....

  11. Evaluation of Contact Friction in Fracture of Rotationally Bent Nitinol Endodontic Files

    Science.gov (United States)

    Haimed, Tariq Abu

    2011-12-01

    maximum strain amplitude (MSA) for each file size were determined based on images of the files inside the glass tubes. The force of insertion for each file type under each condition was also measured inside 45 and 60 degree glass tube paths, static and while dynamic. The results showed that NCF of Ni-Ti files is strongly inversely related to the CF which ranged from 0.15 for ODS and 3-HEPT coated files to 0.43 for irrigant bleach. High CF (in the presence of bleach) significantly reduced the NCF. Conversely, lower CF (in the presence of other solutions and file coatings) resulted in significantly higher NCF. CF was found to be directly related to the surface tension of the media used. Similarly, high MSA typical of low radius of curvature and high bending angle significantly diminished the fatigue life of Ni-Ti files. The integral of the force of insertion versus time curve was the highest for bleach irrigation which also showed the highest CF. Scanning electron microscope inspection of file fracture surfaces illustrated a 2-step progressive failure mode characterized by creation of a smooth initial fatigue area (striation marks) followed by catastrophic ductile fracture (dimple area) when the intact file shaft area was sufficiently reduced. The bleach-lubricated files failed earlier and with a smaller fatigue area (23%) than all other groups (31-35%) indicating premature fracture in the presence of higher frictional forces. The acquired data demonstrate that the combination of low MSA and low CF (by using coatings or solutions with low surface tension), related to the magnitude of the superficial drag force, can lead to statistically longer rotational bending lifetimes for Ni-Ti files. Based on the data of this study, lubricant solutions with low surface tension could significantly improve the fracture life of Ni-Ti files in root canal glass model. Laboratory testing using natural teeth should be performed to evaluate the effect of using such solutions on the fatigue

  12. Feasibility Study on Nuclear Propulsion Ship according to Economic Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Gil, Youngmi; Yoo, Seongjin; Oh, June; Byun, Yoonchul; Woo, Ilguk [Daewoo Shipbuilding and Marine Engineering Co., Ltd, Seoul (Korea, Republic of); Kim, Jiho; Choi, Suhn [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The use of nuclear ships has been extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, the relevant regulations need to be considered. In this study, we reviewed the nuclear ship-related regulations. In addition, economic value is one of the most important factors which should be considered in the pre-design phase. To evaluate the economics of the nuclear ship, we calculated Capital Expenditure (abbreviated as CAPEX) and Operation Expenditure (abbreviated as OPEX) for various types of ships. We reviewed the nuclear ship-related regulations and evaluated the economics of the nuclear ship compared to the diesel ship. The calculation result shows that economic feasibility of the nuclear ship depends on the oil price as well as the cost of the nuclear reactor.

  13. Extrapolated Orbital data files to be read via SDP toolkit, Binary Format

    Data.gov (United States)

    National Aeronautics and Space Administration — AM1EPHNE is the Terra Near Real Time (NRT) 2-hour spacecraft Extrapolated ephemeris data file in native format. The file name format is the following:...

  14. Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations

    Energy Technology Data Exchange (ETDEWEB)

    Garcia-Herranz, Nuria [Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid, UPM (Spain)], E-mail: nuria@din.upm.es; Cabellos, Oscar [Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid, UPM (Spain); Sanz, Javier [Departamento de Ingenieria Energetica, Universidad Nacional de Educacion a Distancia, UNED (Spain); Juan, Jesus [Laboratorio de Estadistica, Universidad Politecnica de Madrid, UPM (Spain); Kuijper, Jim C. [NRG - Fuels, Actinides and Isotopes Group, Petten (Netherlands)

    2008-04-15

    Two methodologies to propagate the uncertainties on the nuclide inventory in combined Monte Carlo-spectrum and burn-up calculations are presented, based on sensitivity/uncertainty and random sampling techniques (uncertainty Monte Carlo method). Both enable the assessment of the impact of uncertainties in the nuclear data as well as uncertainties due to the statistical nature of the Monte Carlo neutron transport calculation. The methodologies are implemented in our MCNP-ACAB system, which combines the neutron transport code MCNP-4C and the inventory code ACAB. A high burn-up benchmark problem is used to test the MCNP-ACAB performance in inventory predictions, with no uncertainties. A good agreement is found with the results of other participants. This benchmark problem is also used to assess the impact of nuclear data uncertainties and statistical flux errors in high burn-up applications. A detailed calculation is performed to evaluate the effect of cross-section uncertainties in the inventory prediction, taking into account the temporal evolution of the neutron flux level and spectrum. Very large uncertainties are found at the unusually high burn-up of this exercise (800 MWd/kgHM). To compare the impact of the statistical errors in the calculated flux with respect to the cross uncertainties, a simplified problem is considered, taking a constant neutron flux level and spectrum. It is shown that, provided that the flux statistical deviations in the Monte Carlo transport calculation do not exceed a given value, the effect of the flux errors in the calculated isotopic inventory are negligible (even at very high burn-up) compared to the effect of the large cross-section uncertainties available at present in the data files.

  15. Status and future plan of nuclear data activities in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Soo-Youl; Chang, Jonghwa [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    1997-03-01

    It was reviewed the nuclear data related activities in Korea, and was explained a 15-year term nation-wide R and D project that had been launched at 1996. The experiences up to now show, as a whole, that the nuclear data field in Korea is in the early stage. Through the long term project, however, it is expected that a firm foundation be established. Then it would be possible to contribute actively to the international nuclear data community as well as to meet domestic requests for nuclear data. Also it was pointed out the necessity of the international collaboration such as consultings and co-works. (author)

  16. Nuclear Data Sheets for A = 210

    Energy Technology Data Exchange (ETDEWEB)

    Shamsuzzoha Basunia, M.

    2014-09-15

    Evaluated spectroscopic data for {sup 210}Au, {sup 210}Hg, {sup 210}Tl, {sup 210}Pb, {sup 210}Bi, {sup 210}Po, {sup 210}At, {sup 210}Rn, {sup 210}Fr, {sup 210}Ra, {sup 210}Ac, and {sup 210}Th and corresponding level schemes from radioactive decay and reaction studies are presented. This evaluation supersedes the previous evaluation by E. Browne (2003Br13). Highlights of this publication are the identification of new μs isomers of {sup 210}Hg by 2013Go10 and measurement of an excited level energy at 1709 keV 30 of {sup 210}Rn from {sup 214}Rn α decay: 68.6 μs by 2006Ku26 denoted as x+1664.6 in the Adopted Levels. Earlier experimental limits for x≤50 keV was proposed in 1979Po19 and 1982Po03 – (HI,xnγ)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-06-01

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

  18. Re-evaluation of neutron nuclear data for sup 2 sup 4 sup 2 sup m Am, sup 2 sup 4 sup 3 Am, sup 9 sup 9 Tc and sup 1 sup 4 sup 0 Ce

    CERN Document Server

    Nakagawa, T; Iwamoto, O

    2002-01-01

    The evaluated nuclear data given in JENDL-3.2 were compared with other evaluated data sets and available experimental data, for important minor actinides of sup 2 sup 4 sup 2 sup m Am and sup 2 sup 4 sup 3 Am, and fission product nuclides of sup 9 sup 9 Tc and sup 1 sup 4 sup 0 Ce. Since problems were found as a result of the comparison, the data of JENDL-3.2 were improved for these nuclides. It was found that the evaluated data of Maslov et al. were superior to the others. They were adopted for sup 2 sup 4 sup 2 sup m Am and sup 2 sup 4 sup 3 Am after further improvements. For sup 9 sup 9 Tc and sup 1 sup 4 sup 0 Ce, resonance parameters and optical model parameters were improved. The cross sections of these two nuclides in the smooth part were re-calculated. The present results were given in the neutron energy range from 10 sup - sup 5 eV to 20 MeV in the ENDF-6 format, and adopted to JENDL-3.3.

  19. Propagation of nuclear data Uncertainties for PWR core analysis

    Energy Technology Data Exchange (ETDEWEB)

    Cabellos, O.; Castro, E.; Ahnert, C.; Holgado, C. [Dept. of Nuclear Engineering, Universidad Politecnica de Madrid, Madrid (Spain)

    2014-06-15

    An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear design analysis to assess the impact of nuclear data uncertainties. The importance of the nuclear data uncertainties for {sup 235,238}U, {sup 239}Pu, and the thermal scattering library for hydrogen in water is analyzed. This uncertainty analysis is compared with the design and acceptance criteria to assure the adequacy of bounding estimates in safety margins.

  20. PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS

    Directory of Open Access Journals (Sweden)

    O. CABELLOS

    2014-06-01

    Full Text Available An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear design analysis to assess the impact of nuclear data uncertainties. The importance of the nuclear data uncertainties for 235,238U, 239Pu, and the thermal scattering library for hydrogen in water is analyzed. This uncertainty analysis is compared with the design and acceptance criteria to assure the adequacy of bounding estimates in safety margins.

  1. Effect of Autoclave Cycles on Surface Characteristics of S-File Evaluated by Scanning Electron Microscopy.

    Science.gov (United States)

    Razavian, Hamid; Iranmanesh, Pedram; Mojtahedi, Hamid; Nazeri, Rahman

    2016-01-01

    Presence of surface defects in endodontic instruments can lead to unwanted complications such as instrument fracture and incomplete preparation of the canal. The current study was conducted to evaluate the effect of autoclave cycles on surface characteristics of S-File by scanning electron microscopy (SEM). In this experimental study, 17 brand new S-Files (#30) were used. The surface characteristics of the files were examined in four steps (without autoclave, 1 autoclave cycle, 5 autoclave cycles and 10 autoclave cycles) by SEM under 200× and 1000× magnifications. Data were analyzed using the SPSS software and the paired sample t-test, independent sample t-test and multifactorial repeated measures ANOVA. The level of significance was set at 0.05. New files had debris and pitting on their surfaces. When the autoclave cycles were increased, the mean of surface roughness also increased at both magnifications (Pautoclave increased the surface roughness of the files and this had was directly related to the number of autoclave cycles.

  2. Hierarchical remote data possession checking method based on massive cloud files

    Directory of Open Access Journals (Sweden)

    Ma Haifeng

    2017-06-01

    Full Text Available Cloud storage service enables users to migrate their data and applications to the cloud, which saves the local data maintenance and brings great convenience to the users. But in cloud storage, the storage servers may not be fully trustworthy. How to verify the integrity of cloud data with lower overhead for users has become an increasingly concerned problem. Many remote data integrity protection methods have been proposed, but these methods authenticated cloud files one by one when verifying multiple files. Therefore, the computation and communication overhead are still high. Aiming at this problem, a hierarchical remote data possession checking (hierarchical-remote data possession checking (H-RDPC method is proposed, which can provide efficient and secure remote data integrity protection and can support dynamic data operations. This paper gives the algorithm descriptions, security, and false negative rate analysis of H-RDPC. The security analysis and experimental performance evaluation results show that the proposed H-RDPC is efficient and reliable in verifying massive cloud files, and it has 32–81% improvement in performance compared with RDPC.

  3. INTEGRAL BENCHMARK DATA FOR NUCLEAR DATA TESTING THROUGH THE ICSBEP AND THE NEWLY ORGANIZED IRPHEP

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

    2007-04-01

    The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) was last reported in a nuclear data conference at the International Conference on Nuclear Data for Science and Technology, ND-2004, in Santa Fe, New Mexico. Since that time the number and type of integral benchmarks have increased significantly. Included in the ICSBEP Handbook are criticality-alarm / shielding and fundamental physic benchmarks in addition to the traditional critical / subcritical benchmark data. Since ND 2004, a reactor physics counterpart to the ICSBEP, the International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. The IRPhEP is patterned after the ICSBEP, but focuses on other integral measurements, such as buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics measurements, reaction-rate and power distributions, nuclide compositions, and other miscellaneous-type measurements in addition to the critical configuration. The status of these two projects is discussed and selected benchmarks highlighted in this paper.

  4. Nuclear Data Sheets for A=22

    Energy Technology Data Exchange (ETDEWEB)

    Firestone, R. B.

    2005-10-18

    This evaluation of A=22 has been updated from previousevaluations published in 1998En04, 1990En08, and 1978En02. Coverageincludes properties of adopted levels and gamma rays, decay-scheme data(energies, intensities and placementof radiations), and cross referenceentries. The following tables continue the tradition of showing thesystematic relationships between levels in A=22. These assignments arebased on spectroscopic factors and energy differences whereDE-x=E{-x(+22Na) - E-x(+22Ne)-657.16 orDE-x=E-x(+22Mg)-E-x(+22Ne).

  5. Nuclear core activity reconstruction using heterogeneous instruments with data assimilation

    OpenAIRE

    Bouriquet Bertrand; Argaud Jean-Philippe; Erhard Patrick; Ponçot Angélique

    2015-01-01

    Evaluating the neutronic state (neutron flux, power…) of the whole nuclear core is a very important topic that has strong implication for nuclear core management and for security monitoring. The core state is evaluated using measurements and calculations. Usually, parts of the measurements are used, and only one kind of instrument is taken into account. However, the core state evaluation should be more accurate when more measurements are collected in the core. But using information from heter...

  6. NASIS data base management system - IBM 360/370 OS MVT implementation. 6: NASIS message file

    Science.gov (United States)

    1973-01-01

    The message file for the NASA Aerospace Safety Information System (NASIS) is discussed. The message file contains all the message and term explanations for the system. The data contained in the file can be broken down into three separate sections: (1) global terms, (2) local terms, and (3) system messages. The various terms are defined and their use within the system is explained.

  7. NASIS data base management system: IBM 360 TSS implementation. Volume 6: NASIS message file

    Science.gov (United States)

    1973-01-01

    The message file for the NASA Aerospace Safety Information System (NASIS) is discussed. The message file contains all the message and term explanations for the system. The data contained in the file can be broken down into three separate sections: (1) global terms, (2) local terms, and (3) system messages. The various terms are defined and their use within the system is explained.

  8. Evaluation of the nuclear cross section variance-covariance matrices issued from the nuclear optical model; Evaluation des matrices de variance-covariance des sections efficaces nucleaires issues du modele optique

    Energy Technology Data Exchange (ETDEWEB)

    Brassart, M. [Ecole Nationale Superieure Ingenieurs de Bourges, 18 - Bourges (France); Mounier, C. [CEA Saclay, Dir. de l' Energie Nucleaire DEN, Service d' Etudes des Reacteurs et de Modelisation Avancee, 91 - Gif sur Yvette (France); Dossantos-Uzarralde, P. [CEA Bruyeres le Chatel, 91 (France). Dept. de Physique Theorique et Appliquee

    2004-07-01

    Nuclear reaction models play an important role in today's nuclear data evaluations. There are, however, difficulties associated with evaluating data uncertainties, both while performing the experimental measurements as well as constructing them by nuclear models. In this general context, our interest is particularly targeted towards the study of the propagation uncertainties within nuclear models. In this report we discuss two distinct ways of calculating the nuclear cross section variance-covariance matrices and then show these can be applied to the nuclear spherical optical model. (authors)

  9. GEODOC: the GRID document file, record structure and data element description

    Energy Technology Data Exchange (ETDEWEB)

    Trippe, T.; White, V.; Henderson, F.; Phillips, S.

    1975-11-06

    The purpose of this report is to describe the information structure of the GEODOC file. GEODOC is a computer based file which contains the descriptive cataloging and indexing information for all documents processed by the National Geothermal Information Resource Group. This file (along with other GRID files) is managed by DBMS, the Berkeley Data Base Management System. Input for the system is prepared using the IRATE Text Editing System with its extended (12 bit) character set, or punched cards.

  10. Nuclear data review and compilation for ATW systems

    Energy Technology Data Exchange (ETDEWEB)

    Guzhovskii, B.; Gorelov, V.; Il`in, V.; Farafontov, G.; Grebennikov, A.

    1994-10-01

    In order to solve the problem of nuclear power waste transmutation in neutron flux it is necessary to know the characteristics of neutron interaction for a great number of nuclei in the energy range from 0 to hundreds of MeV. The authors distinguished the most important aspect of this problem that one of nuclear data for actinides, (from Th to Cm isotopes) They have given the overview of evaluations of characteristic of interaction between neutrons and these nuclei leading to transformation from target-nucleus to neighboring actinide-nucleus or fission fragments in the limited energy range from 0 to 14 MeV. The review was carried out by comparison of mentioned characteristics from the modern versions of ENDL-82, JENDL-3, ENDF/B-6 and BROND-2 neutron evaluated data among themselves and with recommended data of previous publications and, in some cases, with the measurement results. ENDL-82 and ENDF/B-6 versions were made in USA laboratories, JENDL-3 was made in the laboratories of Japan and BROND-2 version was made in the laboratories of former USSR. The comparison of nuclear data from various libraries was carried out by the most economic method permitting, nevertheless, fully judge of available uncertainties in the knowledge of competitive nuclear data which are important from the point of view of problem of transmutation in various energies neutron flux. The following characteristics were considered: (a) fission and capture cross-sections at thermal point (E{sub n}=0.0253 eV); (b) infinitely dilute resonance integrals of fission and capture designated by I{sub f} and I{sub {gamma}} (c) averaged on {sup 252}Cf spontaneous fission neutron spectrum cross-sections of fission, capture and the (n,2n) reactions; (d) cross-sections of fission and the (n,2n), (n,3n) reactions at the point En = 14 MeV; (e) fission and capture resonance integrals for a interval of sets with the increasing upper (E {sub max}) and lower (E {sub min}) limits of integral.

  11. Propagation of nuclear data uncertainties for fusion power measurements

    Directory of Open Access Journals (Sweden)

    Sjöstrand Henrik

    2017-01-01

    Full Text Available Neutron measurements using neutron activation systems are an essential part of the diagnostic system at large fusion machines such as JET and ITER. Nuclear data is used to infer the neutron yield. Consequently, high-quality nuclear data is essential for the proper determination of the neutron yield and fusion power. However, uncertainties due to nuclear data are not fully taken into account in uncertainty analysis for neutron yield calibrations using activation foils. This paper investigates the neutron yield uncertainty due to nuclear data using the so-called Total Monte Carlo Method. The work is performed using a detailed MCNP model of the JET fusion machine; the uncertainties due to the cross-sections and angular distributions in JET structural materials, as well as the activation cross-sections in the activation foils, are analysed. It is found that a significant contribution to the neutron yield uncertainty can come from uncertainties in the nuclear data.

  12. Propagation of nuclear data uncertainties for fusion power measurements

    Science.gov (United States)

    Sjöstrand, Henrik; Conroy, Sean; Helgesson, Petter; Hernandez, Solis Augusto; Koning, Arjan; Pomp, Stephan; Rochman, Dimitri

    2017-09-01

    Neutron measurements using neutron activation systems are an essential part of the diagnostic system at large fusion machines such as JET and ITER. Nuclear data is used to infer the neutron yield. Consequently, high-quality nuclear data is essential for the proper determination of the neutron yield and fusion power. However, uncertainties due to nuclear data are not fully taken into account in uncertainty analysis for neutron yield calibrations using activation foils. This paper investigates the neutron yield uncertainty due to nuclear data using the so-called Total Monte Carlo Method. The work is performed using a detailed MCNP model of the JET fusion machine; the uncertainties due to the cross-sections and angular distributions in JET structural materials, as well as the activation cross-sections in the activation foils, are analysed. It is found that a significant contribution to the neutron yield uncertainty can come from uncertainties in the nuclear data.

  13. Aerothermodynamic data base. Data file contents report, phase C

    Science.gov (United States)

    Lutz, G. R.

    1983-01-01

    Space shuttle aerothermodynamic data, collected from a continuing series of wind tunnel tests, are permanently stored with the Data Management Services (DMS) system. Information pertaining to current baseline configuration definition is also stored. Documentation of DMS processed data arranged sequentially and by space shuttle configuration is listed to provide an up-to-date record of all applicable aerothermodynamic data collected, processed, or summarized during the space shuttle program. Tables provide survey information to the various space shuttle managerial and technical levels.

  14. Cytological evaluation of thyroid lesions by nuclear morphology and nuclear morphometry

    OpenAIRE

    R Yashaswini; T N Suresh; Sagayaraj, A.

    2017-01-01

    Introduction: Fine needle aspiration (FNA) of the thyroid gland is an effective diagnostic method. The Bethesda system for reporting thyroid cytopathology classifies them into six categories and gives implied risk for malignancy and management protocol in each category. Though the system gives specific criteria, diagnostic dilemma still exists. Using nuclear morphometry, we can quantify the number of parameters, such as those related to nuclear size and shape. The evaluation of nuclear morpho...

  15. Bibliography of integral charged particle nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Burrows, T.W.; Burt, J.S.

    1977-03-01

    This bibliography is divided into three main sections covering experimental, theoretical, and review references. The review section also includes compilation and evaluation references. Each section contains two subsections. The main subsection contains all references satisfying the criteria noted above and the second subsection is devoted to isotope production. The main subsections are ordered by increasing Z and A of the incident particle, then by increasing Z and A of the target nucleus. Within this order, the entries are ordered by residual nucleus and quantity (e.g., sigma(E)). Finally, the entries are ordered by outgoing particles or processes. All entries which have the same target, reaction, and quantity are grouped under a common heading with the most recent reference first. As noted above the second subsection is devoted to isotope production and is limited in the information it carries. Only those references which contain data on a definite residual nucleus or group of nuclei (e.g., fission fragments) are included in these subsections. Entries within these second subsections are ordered by increasing Z and A of the isotope produced and then by quantity. All references containing data on the same isotope production and quantity are grouped together. All lines within a group are ordered by increasing Z and A of the target and then of the incident particle. The final ordering is by increasing minimum energy.

  16. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  17. Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core

    Science.gov (United States)

    Rochman, D.; Leray, O.; Hursin, M.; Ferroukhi, H.; Vasiliev, A.; Aures, A.; Bostelmann, F.; Zwermann, W.; Cabellos, O.; Diez, C. J.; Dyrda, J.; Garcia-Herranz, N.; Castro, E.; van der Marck, S.; Sjöstrand, H.; Hernandez, A.; Fleming, M.; Sublet, J.-Ch.; Fiorito, L.

    2017-01-01

    The impact of the current nuclear data library covariances such as in ENDF/B-VII.1, JEFF-3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work. The uncertainties due to nuclear data are calculated for existing PWR and BWR fuel assemblies (with burn-up up to 40 GWd/tHM, followed by 10 years of cooling time) and for a simplified PWR full core model (without burn-up) for quantities such as k∞, macroscopic cross sections, pin power or isotope inventory. In this work, the method of propagation of uncertainties is based on random sampling of nuclear data, either from covariance files or directly from basic parameters. Additionally, possible biases on calculated quantities are investigated such as the self-shielding treatment. Different calculation schemes are used, based on CASMO, SCALE, DRAGON, MCNP or FISPACT-II, thus simulating real-life assignments for technical-support organizations. The outcome of such a study is a comparison of uncertainties with two consequences. One: although this study is not expected to lead to similar results between the involved calculation schemes, it provides an insight on what can happen when calculating uncertainties and allows to give some perspectives on the range of validity on these uncertainties. Two: it allows to dress a picture of the state of the knowledge as of today, using existing nuclear data library covariances and current methods.

  18. FAMoS - an information service on the usage of data files in AliEn

    Science.gov (United States)

    Abramyan, A.; Betev, L.; Buncic, P.; Grigoras, C.; Grigoryan, A.; Manukyan, N.; Pedreira, M. M.; Saiz, P.

    2015-05-01

    The File Access Monitoring Service (FAMoS) leverages the information stored in the central AliEn file catalogue, which describes every file in a Unix-like directory structure, as well as metadata on file location and its replicas. In addition, it uses the access information provided by a set of API servers, used by all Grid clients to access the catalogue. The main functions of FAMoS are to sort the file accesses by logical groups, access time, user and storage element. The collected data identifies rarely used groups of files, as well as those with high popularity over different time periods. This information can be further used to optimize file distribution and replication factors, thus increasing the data processing efficiency. The paper describes the FAMoS structure and user interface and presents the results obtained in one year of service operation.

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

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.L.

    1988-12-01

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

  20. RPF: An Extensible, Cross-Platform, Binary File Format for Radiation Physics Data

    Energy Technology Data Exchange (ETDEWEB)

    Ham, C L

    2002-09-10

    Lawrence Livermore National Laboratory's Radiation Technology Group (RTG) uses a number of computer codes for simulation and analysis of radiation data. The number of incompatible data formats that these data presented themselves in have continued to multiply. In the 1980's a Common Data Format (CDF, see Appendix A) was devised for internal use by the RTG. This format represented a single gamma-ray spectrum as ASCII energy/count pairs preceded by an ASCII header. The ASCII representation of the data assured that it was compatible on any computing platform and this format is still in use. In the mid 1990's it became apparent that instrument systems of greater complexity would demand a file format of larger capacity to support systems then on the drawing board, including networks of sensors collecting time series of gamma-ray spectra. These systems were in the planning stage and defined data structures were not available. It became apparent that a new storage format for nuclear measurements data would be needed and it would have to be flexible and extensible to accommodate the requirements of systems of the future. As part of an LDRD, we began to investigate what others were doing, especially in the high-energy physics community, to deal with the large volumes of data being generated. Of particular interest was the very general Hierarchical Data Format (HDF), developed and maintained by the National Center for Supercomputing Applications (NCSA), that we ultimately used to develop the Radiation Physics Format (RPF). The HDF subroutine library provides users with the ability to customize a data file format based on standard calls to the HDF subroutine library. The RPF was developed and deployed on Sun and Hewlett-Packard workstations running their proprietary versions of UNIX.

  1. Inter-comparison of High Energy Files (neutron-induced, from 20 to 150 MeV)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young-Ouk; Fukahori, Tokio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    Recent new applications using accelerator-driven system require well-tested nuclear data when modeling the interaction of neutrons above 20 MeV. This work is aimed to review evaluation methods applied in currently available neutron high energy files above 20 to 150 MeV, to inter-compare their evaluated cross sections on some important isotopes, and to analyze resulting discrepancies. Through out these, integrities and consistencies of the high energy files are checked, applicability of physics models and evaluation methodologies are assessed, and some directions are derived to improve and expand current JENDL High Energy File. (author)

  2. ARM Data File Standards Version: 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Kehoe, Kenneth [University of Oklahoma; Beus, Sherman [Pacific Northwest National Laboratory; Cialella, Alice [Brookhaven National Laboratory; Collis, Scott [Argonne National Laboratory; Ermold, Brian [Pacific Northwest National Laboratory; Perez, Robin [State University of New York, Albany; Shamblin, Stefanie [Oak Ridge National Laboratory; Sivaraman, Chitra [Pacific Northwest National Laboratory; Jensen, Mike [Brookhaven National Laboratory; McCord, Raymond [Oak Ridge National Laboratory; McCoy, Renata [Sandia National Laboratories; Moore, Sean [Alliant Techsystems, Inc.; Monroe, Justin [University of Oklahoma; Perkins, Brad [Los Alamos National Laboratory; Shippert, Tim [Pacific Northwest National Laboratory

    2014-04-01

    The Atmospheric Radiation Measurement (ARM) Climate Research Facility performs routine in situ and remote-sensing observations to provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes. The result is a diverse data sets containing observational and derived data, currently accumulating at a rate of 30 TB of data and 150,000 different files per month (http://www.archive.arm.gov/stats/storage2.html). Continuing the current processing while scaling this to even larger sizes is extremely important to the ARM Facility and requires consistent metadata and data standards. The standards described in this document will enable development of automated analysis and discovery tools for the ever-growing volumes of data. It also will enable consistent analysis of the multiyear data, allow for development of automated monitoring and data health status tools, and facilitate development of future capabilities for delivering data on demand that can be tailored explicitly to user needs. This analysis ability will only be possible if the data follows a minimum set of standards. This document proposes a hierarchy that includes required and recommended standards.

  3. ARM Data File Standards Version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Palanisamy, Giri [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-05-01

    The U.S. Department of Energy (DOE)’s Atmospheric Radiation Measurement (ARM) Climate Research Facility performs routine in situ and remote-sensing observations to provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes. The result is a huge archive of diverse data sets containing observational and derived data, currently accumulating at a rate of 30 terabytes (TB) of data and 150,000 different files per month (http://www.archive.arm.gov/stats/). Continuing the current processing while scaling this to even larger sizes is extremely important to the ARM Facility and requires consistent metadata and data standards. The standards described in this document will enable development of automated analysis and discovery tools for the ever growing data volumes. It will enable consistent analysis of the multiyear data, allow for development of automated monitoring and data health status tools, and allow future capabilities of delivering data on demand that can be tailored explicitly for the user needs. This analysis ability will only be possible if the data follows a minimum set of standards. This document proposes a hierarchy of required and recommended standards.

  4. Nuclear Data for Safe Operation and Waste Transmutation: ANDES (Accurate Nuclear Data for nuclear Energy Sustainability); Datos nucleares para la operacion segura y la transmutacion de residuos: Andes (Datos Nucleares Precisos para la Sostenibilidad de la Energia Nuclear)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, E. M.

    2014-07-01

    Nuclear research within the 7th Framework Program (FP7 and FP7+2) of EURATOM has devoted a significant fraction of its efforts to the development of advanced nuclear fuel cycles and reactor concepts, mainly fast reactors, aiming to improve the long term sustainability by reduction of the final wastes, optimal use of natural resources and improvement of safety in the present and future nuclear installations. The new design need more accurate basic nuclear data for isotopes, like minor actinides, potentially playing an important role in the operation, fuel concept, safety or final wastes of those reactors and fuel cycles. Four projects, ANDES, ERINDA, EUFRAT and CHANDA, supported by EURATOM within the FP7 and FP7+2, have put together most of the European Nuclear Data community to respond efficiently and in a coordinated way to those needs. This paper summarizes the objectives, and main achievements of ANDES, the project responsible for most of the measurements and technical achievements that was coordinated by CIEMAT. Indeed, CIEMAT has coordinated the nuclear data R and D projects within EURATOM during the last 7 years (NUDATRA domain of EUROTRANS, and ANDES) and will continue this coordination in the CHANDA project till 2017. (Author)

  5. Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal

    National Research Council Canada - National Science Library

    Herrero J.J; Rochman D; Leray O; Vasiliev A; Pecchia M; Ferroukhi H; Caruso S

    2017-01-01

    .... In the context of criticality safety applying burn-up credit, k-eff eigenvalue calculations are affected by nuclear data uncertainty mainly in the burnup calculations simulating reactor operation...

  6. LASIP-III, a generalized processor for standard interface files. [For creating binary files from BCD input data and printing binary file data in BCD format (devised for fast reactor physics codes)

    Energy Technology Data Exchange (ETDEWEB)

    Bosler, G.E.; O' Dell, R.D.; Resnik, W.M.

    1976-03-01

    The LASIP-III code was developed for processing Version III standard interface data files which have been specified by the Committee on Computer Code Coordination. This processor performs two distinct tasks, namely, transforming free-field format, BCD data into well-defined binary files and providing for printing and punching data in the binary files. While LASIP-III is exported as a complete free-standing code package, techniques are described for easily separating the processor into two modules, viz., one for creating the binary files and one for printing the files. The two modules can be separated into free-standing codes or they can be incorporated into other codes. Also, the LASIP-III code can be easily expanded for processing additional files, and procedures are described for such an expansion. 2 figures, 8 tables.

  7. A Guidebook for Evaluating Organizations in the Nuclear Industry - an example of safety culture evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Oedewald, Pia; Pietikaeinen, Elina; Reiman, Teemu [VTT, Technical Research Centre of Finland, Espoo (Finland)

    2011-06-15

    Organizations in the nuclear industry need to maintain an overview on their vulnerabilities and strengths with respect to safety. Systematic periodical self assessments are necessary to achieve this overview. This guidebook provides suggestions and examples to assist power companies but also external evaluators and regulators in carrying out organizational evaluations. Organizational evaluation process is divided into five main steps. These are: 1) planning the evaluation framework and the practicalities of the evaluation process, 2) selecting data collection methods and conducting the data acquisition, 3) structuring and analysing the data, 4) interpreting the findings and 5) reporting the evaluation results with possible recommendations. The guidebook emphasises the importance of a solid background framework when dealing with multifaceted phenomena like organisational activities and system safety. The validity and credibility of the evaluation stem largely from the evaluation team's ability to crystallize what they mean by organization and safety when they conduct organisational safety evaluations - and thus, what are the criteria for the evaluation. Another important and often under-considered phase in organizational evaluation is interpretation of the findings. In this guidebook a safety culture evaluation in a Nordic nuclear power plant is presented as an example of organizational evaluation. With the help of the example, challenges of each step in the organizational evaluation process are described. Suggestions for dealing with them are presented. In the case example, the DISC (Design for Integrated Safety culture) model is used as the evaluation framework. The DISC model describes the criteria for a good safety culture and the organizational functions necessary to develop a good safety culture in the organization.

  8. Nuclear magnetic resonance data of C4H8S

    Science.gov (United States)

    Mikhova, B. M.

    This document is part of Part 6 `Organic Metalloid Compounds' of Subvolume D 'Chemical Shifts and Coupling Constants for Carbon-13' of Landolt-Börnstein III/35 'Nuclear Magnetic Resonance Data', Group III 'Condensed Matter'.

  9. Improving neutronics simulations and uncertainties via a selection of nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Rochman, D. [Paul Scherrer Institut, Laboratory for Reactor Physics Systems Behaviour, Villigen (Switzerland); Koning, A.J.; Marck, S.C. van der [Nuclear Research and Consultancy Group NRG, Petten (Netherlands)

    2015-12-15

    This work presents a novel approach to improve neutronics simulations, as in the case of criticality calculations, by simply combining the results of a limited set of random evaluations. Another outcome of this work is to lower uncertainties due to nuclear data by integrating the information from criticality benchmarks into the neutronics simulations scheme. Examples are presented for the {sup 239}Pu nuclear data and calculations of criticality benchmarks and a MOX fuel pincell. (orig.)

  10. Improving neutronics simulations and uncertainties via a selection of nuclear data

    Science.gov (United States)

    Rochman, D.; Koning, A. J.; van der Marck, S. C.

    2015-12-01

    This work presents a novel approach to improve neutronics simulations, as in the case of criticality calculations, by simply combining the results of a limited set of random evaluations. Another outcome of this work is to lower uncertainties due to nuclear data by integrating the information from criticality benchmarks into the neutronics simulations scheme. Examples are presented for the 239Pu nuclear data and calculations of criticality benchmarks and a MOX fuel pincell.

  11. Brief 74 Nuclear Engineering Enrollments and Degrees Survey, 2014 Data

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-15

    The 2014 survey includes degrees granted between September 1, 2013 and August 31, 2014, and enrollments for fall 2014. There are three academic programs new to this year's survey. Thirty-five academic programs reported having nuclear engineering programs during 2014, and data were provided by all thirty-five. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Two nuclear engineering programs have indicated that health physics option enrollments and degrees are also reported in the health physics enrollments and degrees survey.

  12. Brief 76 Nuclear Engineering Enrollments and Degrees Survey, 2015 Data

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2016-03-15

    The 2015 Nuclear Engineering Enrollments and Degrees Survey reports degrees granted between September 1, 2014 and August 31, 2015. Enrollment information refers to the fall term 2015. The enrollments and degrees data comprises students majoring in nuclear engineering or in an option program equivalent to a major. Thirty-five academic programs reported having nuclear engineering programs during 2015, and data was received from all thirty-five programs. The report includes enrollment information on undergraduate students and graduate students and information by degree level for post-graduation plans.

  13. Performance evaluation of fiber optic components in nuclear plant environments

    Energy Technology Data Exchange (ETDEWEB)

    Hastings, M.C.; Miller, D.W. [Ohio State Univ., Columbus, OH (United States); James, R.W. [Electric Power Research Institute, Palo Alto, CA (United States)

    1996-03-01

    Over the past several years, the Electric Power Research Institute (EPRI) has funded several projects to evaluate the performance of commercially available fiber optic cables, connective devices, light sources, and light detectors under environmental conditions representative of normal and abnormal nuclear power plant operating conditions. Future projects are planned to evaluate commercially available fiber optic sensors and to install and evaluate performance of instrument loops comprised of fiber optic components in operating nuclear power plant applications. The objective of this research is to assess the viability of fiber optic components for replacement and upgrade of nuclear power plant instrument systems. Fiber optic instrument channels offer many potential advantages: commercial availability of parts and technical support, small physical size and weight, immunity to electromagnetic interference, relatively low power requirements, and high bandwidth capabilities. As existing nuclear power plants continue to replace and upgrade I&C systems, fiber optics will offer a low-cost alternative technology which also provides additional information processing capabilities. Results to date indicate that fiber optics are a viable technology for many nuclear applications, both inside and outside of containments. This work is funded and manage& under the Operations & Maintenance Cost Control research target of EPRI`s Nuclear Power Group. The work is being performed by faculty and students in the Mechanical and Nuclear Engineering Departments and the staff of the Nuclear Reactor Laboratory of the Ohio State University.

  14. The NJOY nuclear data processing system Version 91

    Energy Technology Data Exchange (ETDEWEB)

    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.

  15. Impact of nuclear data on fast neutron therapy

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann Siantar, C.L.; Chandler, W.P.; Rathkopf, J.A.; Resler, D.A.; Cox, L.J.; Chadwick, M.B.; White, R.M.

    1994-05-12

    By combining a new, all-particle Monte Carlo radiation transport code, PEREGRINE, with the Lawrence Livermore National Laboratory (LLNL) nuclear data base, we have studied the importance of various neutron reactions on dose distributions in biological materials. Monte Carlo calculations have been performed for 5--20 MeV neutron pencil beams incident on biologically relevant materials arranged in several simple geometries. Results highlight the importance of nuclear data used for calculating dose distributions resulting from fast neutron therapy.

  16. Cytological evaluation of thyroid lesions by nuclear morphology and nuclear morphometry

    Directory of Open Access Journals (Sweden)

    R Yashaswini

    2017-01-01

    Full Text Available Introduction: Fine needle aspiration (FNA of the thyroid gland is an effective diagnostic method. The Bethesda system for reporting thyroid cytopathology classifies them into six categories and gives implied risk for malignancy and management protocol in each category. Though the system gives specific criteria, diagnostic dilemma still exists. Using nuclear morphometry, we can quantify the number of parameters, such as those related to nuclear size and shape. The evaluation of nuclear morphometry is not well established in thyroid cytology. Objective: To classify thyroid lesions on fine needle aspiration cytology (FNAC using Bethesda system and to evaluate the significance of nuclear parameters in improving the prediction of thyroid malignancy. Materials and Methods: In the present study, 120 FNAC cases of thyroid lesions with histological diagnosis were included. Computerized nuclear morphometry was done on 81 cases which had confirmed cytohistological correlation, using Aperio computer software. One hundred nuclei from each case were outlined and eight nuclear parameters were analyzed. Results: In the present study, thyroid lesions were common in female with M: F ratio of 1:5 and most commonly in 40–60 yrs. Under Bethesda system, 73 (60.83% were category II; 14 (11.6% were category III, 3 (2.5% were category IV, 8 (6.6% were category V, and 22 (18.3% were category VI, which were malignant on histopathological correlation. Sensitivity, specificity, and diagnostic accuracy of Bethesda reporting system are 62.5, 84.38, and 74.16%, respectively. Minimal nuclear diameter, maximal nuclear diameter, nuclear perimeter, and nuclear area were higher in malignant group compared to nonneoplastic and benign group. Conclusion: The Bethesda system is a useful standardized system of reporting thyroid cytopathology. It gives implied risk of malignancy. Nuclear morphometry by computerized image analysis can be utilized as an additional diagnostic tool.

  17. Cytological Evaluation of Thyroid Lesions by Nuclear Morphology and Nuclear Morphometry.

    Science.gov (United States)

    Yashaswini, R; Suresh, T N; Sagayaraj, A

    2017-01-01

    Fine needle aspiration (FNA) of the thyroid gland is an effective diagnostic method. The Bethesda system for reporting thyroid cytopathology classifies them into six categories and gives implied risk for malignancy and management protocol in each category. Though the system gives specific criteria, diagnostic dilemma still exists. Using nuclear morphometry, we can quantify the number of parameters, such as those related to nuclear size and shape. The evaluation of nuclear morphometry is not well established in thyroid cytology. To classify thyroid lesions on fine needle aspiration cytology (FNAC) using Bethesda system and to evaluate the significance of nuclear parameters in improving the prediction of thyroid malignancy. In the present study, 120 FNAC cases of thyroid lesions with histological diagnosis were included. Computerized nuclear morphometry was done on 81 cases which had confirmed cytohistological correlation, using Aperio computer software. One hundred nuclei from each case were outlined and eight nuclear parameters were analyzed. In the present study, thyroid lesions were common in female with M: F ratio of 1:5 and most commonly in 40-60 yrs. Under Bethesda system, 73 (60.83%) were category II; 14 (11.6%) were category III, 3 (2.5%) were category IV, 8 (6.6%) were category V, and 22 (18.3%) were category VI, which were malignant on histopathological correlation. Sensitivity, specificity, and diagnostic accuracy of Bethesda reporting system are 62.5, 84.38, and 74.16%, respectively. Minimal nuclear diameter, maximal nuclear diameter, nuclear perimeter, and nuclear area were higher in malignant group compared to nonneoplastic and benign group. The Bethesda system is a useful standardized system of reporting thyroid cytopathology. It gives implied risk of malignancy. Nuclear morphometry by computerized image analysis can be utilized as an additional diagnostic tool.

  18. Extracting the Data From the LCM vk4 Formatted Output File

    Energy Technology Data Exchange (ETDEWEB)

    Wendelberger, James G. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-01-29

    These are slides about extracting the data from the LCM vk4 formatted output file. The following is covered: vk4 file produced by Keyence VK Software, custom analysis, no off the shelf way to read the file, reading the binary data in a vk4 file, various offsets in decimal lines, finding the height image data, directly in MATLAB, binary output beginning of height image data, color image information, color image binary data, color image decimal and binary data, MATLAB code to read vk4 file (choose a file, read the file, compute offsets, read optical image, laser optical image, read and compute laser intensity image, read height image, timing, display height image, display laser intensity image, display RGB laser optical images, display RGB optical images, display beginning data and save images to workspace, gamma correction subroutine), reading intensity form the vk4 file, linear in the low range, linear in the high range, gamma correction for vk4 files, computing the gamma intensity correction, observations.

  19. Status of JENDL High Energy File. Evaluation method, tools, specification, release procedure, etc

    Energy Technology Data Exchange (ETDEWEB)

    Fukahori, Tokio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    The ENDF-6 format file should be kept as a standard distribution file and it is not difficult to convert into some other form for code`s libraries. From this point of view, status of JENDL High Energy File is introduced in this report as well as evaluation strategy, recommended specification, stored nuclides and quantities, a format structure, evaluation methods and tools, and release plan. (author)

  20. Analyzing endosonic root canal file oscillations: an in vitro evaluation.

    Science.gov (United States)

    Lea, Simon C; Walmsley, A Damien; Lumley, Philip J

    2010-05-01

    Passive ultrasonic irrigation may be used to improve bacterial reduction within the root canal. The technique relies on a small file being driven to oscillate freely within the canal and activating an irrigant solution through biophysical forces such as microstreaming. There is limited information regarding a file's oscillation patterns when operated while surrounded by fluid as is the case within a canal root. Files of different sizes (#10 and #30, 27 mm and 31 mm) were connected to an ultrasound generator via a 120 degrees file holder. Files were immersed in a water bath, and a laser vibrometer set up with measurement lines superimposed over the files. The laser vibrometer was scanned over the oscillating files. Measurements were repeated 10 times for each file/power setting used. File mode shapes are comprised of a series of nodes/antinodes, with thinner, longer files producing more antinodes. The maximum vibration occurred at the free end of the file. Increasing generator power had no significant effect on this maximum amplitude (p > 0.20). Maximum displacement amplitudes were 17 to 22 microm (#10 file, 27 mm), 15 to 21 microm (#10 file, 31 mm), 6 to 9 microm (#30 file, 27 mm), and 5 to 7 microm (#30, 31 mm) for all power settings. Antinodes occurring along the remaining file length were significantly larger at generator power 1 than at powers 2 through 5 (p < 0.03). At higher generator powers, energy delivered to the file is dissipated in unwanted vibration resulting in reduced vibration displacement amplitudes. This may reduce the occurrence of the biophysical forces necessary to maximize the technique's effectiveness. Copyright (c) 2010 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

  1. CIRFT Data Update and Data Analyses for Spent Nuclear Fuel Vibration Reliability Study

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wang, Hong [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2018-01-01

    The objective of this research is to collect experimental data on spent nuclear fuel (SNF) from pressurized water reactors (PWRs), including the H. B. Robinson Nuclear Power Station (HBR), Catawba Nuclear Station, North Anna Nuclear Power Station (NA), and the Limerick Nuclear Power Station (LMK) boiling water reactor (BWR). Data will be collected under simulated transportation environments using the cyclic integrated reversible-bending fatigue tester (CIRFT), an enabling hot-cell testing technology developed at Oak Ridge National Laboratory (ORNL). These data will be used to support ongoing SNF modeling activities and to address regulatory issues associated with SNF transport.

  2. Ultrafine flux spectrum calculation from the IAEA nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Jefferson Neves, E-mail: jeffersonnevespereira@gmail.com [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil); Silva, Paulo Henrique Pereira, E-mail: paulo.henrique1402@gmail.com [Universidade Federal do Ceara (UFC), Fortaleza, CE (Brazil); Vellozo, Sergio de Oliveira, E-mail: vellozo@ime.eb.br, E-mail: vellozo@cbpf.br [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The generation of multigroup cross sections from point data represents one of the basic problems in reactor physics analysis. Errors introduced in the processed data may lead to a significant uncertainty in the subsequent calculations. In order to estimate accurately few-group parameters such as total, fission or transport cross sections, precise evaluation of neutron spectrum is of great importance. For this work, the aim is to create an efficient and effective broad group nuclear data library from fundamental ultrafine cross sections set available from IAEA suitable for use in several kinds of calculation, for instance, reactor physics. The ultrafine energy group calculation is a simple and direct approach, in which neutron flux distribution is calculated with very fine energy groups. In the present work, the number of ultrafine groups is about 28000. Quite accurate multigroup cross section is obtained when evaluated with very detailed neutron spectrum. We start the calculation of flux spectrum on infinite system of uranium-235 in metallic form at room temperature. We used the Weisskopf evaporation model to determine all energy loss of a neutron inelastically scattered. According to this model the states of the compound nucleus, formed by the capture of the incident neutron, form a statistical assembly with a definite temperature, like a solid or liquid. The Okrent model, developed some decades after Weisskopf, was tested and showed a performance very similar to the first. The one and two energy group cross. (author)

  3. File-Based Data Flow in the CMS Filter Farm

    Energy Technology Data Exchange (ETDEWEB)

    Andre, J.M.; et al.

    2015-12-23

    During the LHC Long Shutdown 1, the CMS Data Acquisition system underwent a partial redesign to replace obsolete network equipment, use more homogeneous switching technologies, and prepare the ground for future upgrades of the detector front-ends. The software and hardware infrastructure to provide input, execute the High Level Trigger (HLT) algorithms and deal with output data transport and storage has also been redesigned to be completely file- based. This approach provides additional decoupling between the HLT algorithms and the input and output data flow. All the metadata needed for bookkeeping of the data flow and the HLT process lifetimes are also generated in the form of small “documents” using the JSON encoding, by either services in the flow of the HLT execution (for rates etc.) or watchdog processes. These “files” can remain memory-resident or be written to disk if they are to be used in another part of the system (e.g. for aggregation of output data). We discuss how this redesign improves the robustness and flexibility of the CMS DAQ and the performance of the system currently being commissioned for the LHC Run 2.

  4. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

  5. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-10-01

    This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

  6. A study on the use of the reactor basic experiments in the U-D2O lattices of the RB critical assembly for validation of modern nuclear data libraries

    Directory of Open Access Journals (Sweden)

    Pešić Milan P.

    2016-01-01

    Full Text Available Demand on the availability of well-defined reactor experiments for validation of computer codes for use in nuclear industry and nuclear technology is everlasting. Users must be confident of the results obtained by the proven computer codes and nuclear data libraries chosen in the models. The well-defined (mostly historical and evaluated reactor experiments (about 5000 in 2015 were collected continuously as the benchmarks within the frame of the OECD/NEA international projects ICSBEP (since 1995 and IRPhEP (since 2003. The Handbooks of the Projects are published in electronic forms (at the NEA web site of the OECD and at a DVD media every year. This study is aimed to (a examine and evaluate reactor basic experiments, carried out in the lattice of the natural uranium metal fuel in the heavy water of the RB critical assembly first core in 1958, and (b demonstrate their possibility for validation of modern nuclear data libraries. These RB reactor basic experiments include: (1 approach to criticality, (2 determination of the reactivity gradient at the D2O critical level, (3 measurement of the dependence of the D2O critical level on the D2O temperature, i. e. dependence of the reactivity with change in the D2O temperature; (4 the critical reactor geometrical parameter (buckling measurements, (5 the migration length measurements, (6 determination of the neutron multiplication factor in the infinite lattice, and (7 the safety rods reactivity measurements. Results of the experiments are compared to the results obtained using modern nuclear data libraries of the ACE type by applying the MCNP6.1, a well-known and proven computer code based on the Monte Carlo method. A short overview of these experiments (done at the RB assembly is shown. A brief description of the neutron ACE type nuclear data libraries (created in the LANL, based on the ENDF/B-VII.0 and ENDF/B-VII.1 files, or created in the OECD/NEA, based on the JEFF-3.2 evaluated nuclear data files

  7. MINING NUCLEAR TRANSIENT DATA THROUGH SYMBOLIC CONVERSION

    Energy Technology Data Exchange (ETDEWEB)

    Diego MAndelli; Tunc Aldemir; Alper Yilmaz; Curtis Smith

    2013-09-01

    Dynamic Probabilistic Risk Assessment (DPRA) methodologies generate enormous amounts of data for a very large number of simulations. The data contain temporal information of both the state variables of the simulator and the temporal status of specific systems/components. In order to measure system performances, limitations and resilience, such data need to be carefully analyzed with the objective of discovering the correlations between sequence/timing of events and system dynamics. A first approach toward discovering these correlations from data generated by DPRA methodologies has been performed by organizing scenarios into groups using classification or clustering based algorithms. The identification of the correlations between system dynamics and timing/sequencing of events is performed by observing the temporal distribution of these events in each group of scenarios. Instead of performing “a posteriori” analysis of these correlations, this paper shows how it is possible to identify the correlations implicitly by performing a symbolic conversion of both continuous (temporal profiles of simulator state variables) and discrete (status of systems and components) data. Symbolic conversion is performed for each simulation by properly quantizing both continuous and discrete data and then converting them as a series of symbols. After merging both series together, a temporal phrase is obtained. This phrase preserves duration, coincidence and sequence of both continuous and discrete data in a uniform and consistent manner. In this paper it is also shown that by using specific distance measures, it is still possible to post-process such symbolic data using clustering and classification techniques but in considerably less time since the memory needed to store the data is greatly reduced by the symbolic conversion.

  8. Archival and Dissemination of the U.S. and Canadian Experimental Nuclear Reaction Data (EXFOR Project)

    Science.gov (United States)

    Pritychenko, Boris; Hlavac, Stanislav; Schwerer, Otto; Zerkin, Viktor

    2017-09-01

    The Exchange Format (EXFOR) or experimental nuclear reaction database and the associated Web interface provide access to the wealth of low- and intermediate-energy nuclear reaction physics data. This resource includes numerical data sets and bibliographical information for more than 22,000 experiments since the beginning of nuclear science. Analysis of the experimental data sets, recovery and archiving will be discussed. Examples of the recent developments of the data renormalization, uploads and inverse reaction calculations for nuclear science and technology applications will be presented. The EXFOR database, updated monthly, provides an essential support for nuclear data evaluation, application development and research activities. It is publicly available at the National Nuclear Data Center website http://www.nndc.bnl.gov/exfor and the International Atomic Energy Agency mirror site http://www-nds.iaea.org/exfor. This work was sponsored in part by the Office of Nuclear Physics, Office of Science of the U.S. Department of Energy under Contract No. DE-AC02-98CH10886 with Brookha ven Science Associates, LLC.

  9. Photon and decay data libraries for ORIGEN2 code based on JENDL FP decay data file 2000

    CERN Document Server

    Katakura, J I

    2002-01-01

    Photon and decay data libraries for the ORIGEN2 code have been updated by using JENDL FP Decay Data File 2000 (JENDL/FPD-00). As for the decay data, half-lives, branching ratios and recoverable energy values have been replaced with those of the JENDL/FPD-00 file. The data of the photon library has been also replaced with those of the JENDL/FPD-00 file in which photon data of the nuclides without measured data are calculated with a theoretical method. Using the updated photon library, the calculation of photon spectrum at a short time after fission event is able to be made.

  10. Photon and decay data libraries for ORIGEN2 code based on JENDL FP decay data file 2000

    Energy Technology Data Exchange (ETDEWEB)

    Katakura, Jun-ichi; Yanagisawa, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    Photon and decay data libraries for the ORIGEN2 code have been updated by using JENDL FP Decay Data File 2000 (JENDL/FPD-00). As for the decay data, half-lives, branching ratios and recoverable energy values have been replaced with those of the JENDL/FPD-00 file. The data of the photon library has been also replaced with those of the JENDL/FPD-00 file in which photon data of the nuclides without measured data are calculated with a theoretical method. Using the updated photon library, the calculation of photon spectrum at a short time after fission event is able to be made. (author)

  11. Treatment of Nuclear Data Covariance Information in Sample Generation

    Energy Technology Data Exchange (ETDEWEB)

    Swiler, Laura Painton [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Adams, Brian M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wieselquist, William [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division

    2017-10-01

    This report summarizes a NEAMS (Nuclear Energy Advanced Modeling and Simulation) project focused on developing a sampling capability that can handle the challenges of generating samples from nuclear cross-section data. The covariance information between energy groups tends to be very ill-conditioned and thus poses a problem using traditional methods for generated correlated samples. This report outlines a method that addresses the sample generation from cross-section matrices.

  12. Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6 

    Energy Technology Data Exchange (ETDEWEB)

    P.L. Cloke

    2001-10-16

    The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities.

  13. User input verification and test driven development in the NJOY21 nuclear data processing code

    Energy Technology Data Exchange (ETDEWEB)

    Trainer, Amelia Jo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Conlin, Jeremy Lloyd [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McCartney, Austin Paul [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-08-21

    Before physically-meaningful data can be used in nuclear simulation codes, the data must be interpreted and manipulated by a nuclear data processing code so as to extract the relevant quantities (e.g. cross sections and angular distributions). Perhaps the most popular and widely-trusted of these processing codes is NJOY, which has been developed and improved over the course of 10 major releases since its creation at Los Alamos National Laboratory in the mid-1970’s. The current phase of NJOY development is the creation of NJOY21, which will be a vast improvement from its predecessor, NJOY2016. Designed to be fast, intuitive, accessible, and capable of handling both established and modern formats of nuclear data, NJOY21 will address many issues that many NJOY users face, while remaining functional for those who prefer the existing format. Although early in its development, NJOY21 is quickly providing input validation to check user input. By providing rapid and helpful responses to users while writing input files, NJOY21 will prove to be more intuitive and easy to use than any of its predecessors. Furthermore, during its development, NJOY21 is subject to regular testing, such that its test coverage must strictly increase with the addition of any production code. This thorough testing will allow developers and NJOY users to establish confidence in NJOY21 as it gains functionality. This document serves as a discussion regarding the current state input checking and testing practices of NJOY21.

  14. Descriptive data of JENDL-3.2

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Keiichi; Narita, Tsutomu [eds.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-02-01

    The second revision of JENDL-3 (JENDL-3.2) was released in 1994. The library contains evaluated neutron nuclear data for 340 nuclides which are needed for the design of fission and fusion reactors and for shielding calculation. This report presents a brief description of the evaluation method which is given in the File-1 part of JENDL-3.2. (author)

  15. Evaluation of metallic osseous implants with nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Wellman, H.N.; Schauwecker, D.S.; Capello, W.N.

    1988-04-01

    Nuclear medicine has proven to have a valuable role in the evaluation of osseous metallic implants, particularly with joint prostheses, but can assist with evaluation of other appliances as well. The nuclear arthrogram has become an invaluable adjunct to simultaneously performed radiographic contrast arthrography. This application has been best evaluated in what is one of the most common of orthopedic prosthesis problems, namely, loosening of total hip prostheses. Experience indicates that both sensitivity and specificity of loosening of the femoral component can be increased to over 90% through combined use of nuclear with radiographic contrast arthrography. Furthermore the combination of routine skeletal scintimaging with the nuclear arthrogram adds a significant dimension to precise localizing of the nuclear arthrographics agent In-111 chloride. Nuclear medicine also plays an important role in further evaluating the presence of infection associated with metallic implants with In-111 WBC preparations being superior to Ga-67 as the radiopharmaceutical tracer. Infection has been detected with a sensitivity of 73% and a specificity of 93% in our series using combined In-111 WBC and simultaneous skeletal imaging with conventional Tc-99m MDP. Acute infections are more readily identifiable than chronic in association with prostheses. 29 references.

  16. Evaluation at the medium energy region for Pb-208 and Bi-209

    Energy Technology Data Exchange (ETDEWEB)

    Fukahori, Tokio; Pearlstein, S.

    1991-01-01

    Medium energy nuclear data in the 1--1000 MeV range is necessary to accelerator applications which include spallation neutron sources for radioactive waste treatment and accelerator shielding design, medical applications which include isotopes production and radiation therapy, and space applications. For the design of fission and fusion reactors, the nuclear data file for neutrons below 20 MeV is available and well evaluated. Evaluated nuclear data for protons and data in the medium energy region, however, have not been prepared completely. Evaluation in the medium energy region was performed using the theoretical calculation code ALICE-P or experimental data. In this paper, the evaluation of neutron and proton induced nuclear data for Pb-208 and Bi-209 has been performed using ALICE-P, empirical calculations and new systematics for the fission cross section. The evaluated data are compiled for possible inclusion in the ENDF/B-VI High Energy File. 204 refs., 51 figs., 9 tabs.

  17. Decay data evaluation project (DDEP): Updated evaluations of the {sup 233}Th and {sup 241}Am decay characteristics

    Energy Technology Data Exchange (ETDEWEB)

    Chechev, Valery P., E-mail: chechev@khlopin.r [V.G. Khlopin Radium Institute, 28 Second Murinsky Ave., St. Petersburg 194021 (Russian Federation); Kuzmenko, Nikolay K. [V.G. Khlopin Radium Institute, 28 Second Murinsky Ave., St. Petersburg 194021 (Russian Federation)

    2010-07-15

    The results of new decay data evaluations are presented for {sup 233}Th ({beta}{sup -}) decay to nuclear levels in {sup 233}Pa and {sup 241}Am ({alpha}) decay to nuclear levels in {sup 237}Np. These evaluated data have been obtained within the Decay Data Evaluation Project using information published up to 2009.

  18. Instrumentation Requirements for the Engineering Evaluation of Nuclear-Electric Spacecraft

    Science.gov (United States)

    Apel, W. C.

    1961-01-01

    Spacecraft employing nuclear-electric propulsion are being proposed for missions to Venus and distances beyond. These spacecraft utilize a nuclear reactor to provide thermal energy to a turboalternator which generates electric power for an ion motor and the other spacecraft systems. This Report discusses the instrumentation and communications system needed to evaluate a nuclear-electric spacecraft in flight, along with the problems expected. A representative spacecraft design is presented, which leads to a discussion of the instrumentation needed to evaluate such a spacecraft. A basic communications system is considered for transmitting the spacecraft data to Earth. The instrumentation and communications system, as well as all electronic systems on a nuclear-electric spacecraft, will be operating in high temperature and nuclear-radiation environments. The problems caused by these environments are discussed, and possible solutions are offered.

  19. Review of nuclear physics experimental data for space radiation.

    Science.gov (United States)

    Norbury, John W; Miller, Jack

    2012-11-01

    The available nuclear fragmentation data relevant to space radiation studies are reviewed. It is found that there are serious gaps in the data. Helium data are missing in the intervals 280 MeV n-3 GeV n and >15 GeV n. Carbon data are missing >15 GeV n. Iron projectile data are missing at all energies except in the interval 280 MeV n-3 GeV n.

  20. Effect of Autoclave Cycles on Surface Characteristics of S-File Evaluated by Scanning Electron Microscopy

    OpenAIRE

    Razavian, Hamid; Iranmanesh, Pedram; Mojtahedi, Hamid; Nazeri, Rahman

    2015-01-01

    Introduction: Presence of surface defects in endodontic instruments can lead to unwanted complications such as instrument fracture and incomplete preparation of the canal. The current study was conducted to evaluate the effect of autoclave cycles on surface characteristics of S-File by scanning electron microscopy (SEM). Methods and Materials: In this experimental study, 17 brand new S-Files (#30) were used. The surface characteristics of the files were examined in four steps (without autocla...

  1. Generation of artificial FASTQ files to evaluate the performance of next-generation sequencing pipelines.

    Directory of Open Access Journals (Sweden)

    Matthew Frampton

    Full Text Available Pipelines for the analysis of Next-Generation Sequencing (NGS data are generally composed of a set of different publicly available software, configured together in order to map short reads of a genome and call variants. The fidelity of pipelines is variable. We have developed ArtificialFastqGenerator, which takes a reference genome sequence as input and outputs artificial paired-end FASTQ files containing Phred quality scores. Since these artificial FASTQs are derived from the reference genome, it provides a gold-standard for read-alignment and variant-calling, thereby enabling the performance of any NGS pipeline to be evaluated. The user can customise DNA template/read length, the modelling of coverage based on GC content, whether to use real Phred base quality scores taken from existing FASTQ files, and whether to simulate sequencing errors. Detailed coverage and error summary statistics are outputted. Here we describe ArtificialFastqGenerator and illustrate its implementation in evaluating a typical bespoke NGS analysis pipeline under different experimental conditions. ArtificialFastqGenerator was released in January 2012. Source code, example files and binaries are freely available under the terms of the GNU General Public License v3.0. from https://sourceforge.net/projects/artfastqgen/.

  2. Data File Standard for Flow Cytometry, Version FCS 3.1

    Energy Technology Data Exchange (ETDEWEB)

    Spidlen, Josef; Moore, Wayne; Parks, David; Goldberg, Michael; Bray, Chris; Gorombey, Peter; Hyun, Bill; Hubbard, Mark; Lange, Simon; Lefebvre, Ray; Leif, Robert; Novo, David; Ostruszka, Leo; Treister, Adam; Wood, James; Murphy, Robert F.; Roederer, Mario; Sudar, Damir; Zigon, Robert; Brinkman, Ryan R.; Brierre, Pierre

    2009-11-10

    The flow cytometry data file standard provides the specifications needed to completely describe flow cytometry data sets within the confines of the file containing the experimental data. In 1984, the first Flow Cytometry Standard format for data files was adopted as FCS 1.0. This standard was modified in 1990 as FCS 2.0 and again in 1997 as FCS 3.0. We report here on the next generation flow cytometry standard data file format. FCS 3.1 is a minor revision based on suggested improvements from the community. The unchanged goal of the standard is to provide a uniform file format that allows files created by one type of acquisition hardware and software to be analyzed by any other type. The FCS 3.1 standard retains the basic FCS file structure and most features of previous versions of the standard. Changes included in FCS 3.1 address potential ambiguities in the previous versions and provide a more robust standard. The major changes include simplified support for international characters and improved support for storing compensation. The major additions are support for preferred display scale, a standardized way of capturing the sample volume, information about originality of the data file, and support for plate and well identification in high throughput, plate based experiments. Please see the normative version of the FCS 3.1 specification in Supporting Information for this manuscript (or at http://www.isac-net.org/ in the Current standards section) for a complete list of changes.

  3. Design data and safety features of commerical nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Heddleson, F.A.

    1976-06-01

    Design data, safety features, and site characteristics are summarized for 34 nuclear power units in 17 power stations in the United States. Six pages of data are presented for each plant, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. This volume covers Light Water Reactors (LWRs) with dockets 50-508 through 50-549, four HTGRs--50-171, 50-267, 50-450/451, 50-463/464, the Atlantic Floating Station 50-477/478, and the Clinch River Breeder 50-537.

  4. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 14

    Energy Technology Data Exchange (ETDEWEB)

    Tam, P.S.

    1994-12-01

    Supplement No. 14 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with additional information submitted by the applicant since Supplement No. 13 was issued, and matters that the staff had under review when Supplement No. 13 was issued.

  5. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 12

    Energy Technology Data Exchange (ETDEWEB)

    Tam, P.S.

    1993-10-01

    Supplement No. 12 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued, and (2) matters that the staff had under review when Supplement No. 11 was issued.

  6. Decay Data Evaluation Project (DDEP): Evaluation of the main {sup 233}Pa decay characteristics

    Energy Technology Data Exchange (ETDEWEB)

    Chechev, Valery P. [V.G. Khlopin Radium Institute, 28 Second Murinsky Ave., St. Petersburg, 194021 (Russian Federation)]. E-mail: chechev@atom.nw.ru; Kuzmenko, Nikolay K. [V.G. Khlopin Radium Institute, 28 Second Murinsky Ave., St. Petersburg, 194021 (Russian Federation)

    2006-10-15

    The results of a decay data evaluation are presented for {sup 233}Pa ({beta} {sup -}) decay to nuclear levels in {sup 233}U. These evaluated data have been obtained within the Decay Data Evaluation Project using information published up to 2005.

  7. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim, Yun Jae; Choi, Jae Boong [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2002-03-15

    This project focuses on developing reliable life evaluation technology for nuclear power plant components, and is divided into two parts, development of a life evaluation system for nuclear pressure vessels and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered in this project: defect assessment method for steam generator tubes, development of fatigue monitoring system, assessment of corroded pipes, domestic round robin analysis for constructing P-T limit curve for RPV, development of probabilistic integrity assessment technique, effect of aging on strength of dissimilar welds, applicability of LBB to cast stainless steel, and development of probabilistic piping fracture mechanics.

  8. Estimation of covariances of {sup 16}O, {sup 23}Na, Fe, {sup 235}U, {sup 238}U and {sup 239}Pu neutron nuclear data in JENDL-3.2

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nakajima, Yutaka; Kawano, Toshihiko; Oh, Soo-Youl; Matsunobu, Hiroyuki; Murata, Toru

    1997-10-01

    Covariances of nuclear data have been estimated for 6 nuclides contained in JENDL-3.2. The nuclides considered are {sup 16}O, {sup 23}Na, Fe, {sup 235}U, {sup 238}U, and {sup 239}Pu, which are regarded as important for the nuclear design study of fast reactors. The physical quantities for which covariances are deduced are cross sections, resolved and unresolved resonance parameters, and the first order Legendre-polynomial coefficient for the angular distribution of elastically scattered neutrons. As for {sup 235}U, covariances were obtained also for the average number of neutrons emitted in fission. The covariances were estimated by using the same methodology that had been used in the JENDL-3.2 evaluation in order to keep a consistency between mean values and their covariances. The least-squares fitting code GMA was used in estimating covariances for reactions of which JENDL-3.2 cross sections had been evaluated by taking account of measurements. In nuclear model calculations, the covariances were calculated by the KALMAN system. The covariance data obtained were compiled in the ENDF-6 format, and will be put into the JENDL-3.2 Covariance File which is one of JENDL special purpose files. (author). 193 refs.

  9. Detailed requirements for a next generation nuclear data structure.

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2016-07-05

    This document attempts to compile the requirements for the top-levels of a hierarchical arrangement of nuclear data such as found in the ENDF format. This set of requirements will be used to guide the development of a new data structure to replace the legacy ENDF format.

  10. Nuclear chirality, a model and the data

    Science.gov (United States)

    Starosta, K.; Koike, T.

    2017-09-01

    In the last decade, the manifestation of chirality in atomic nuclei has become the subject of numerous experimental and theoretical studies. The common feature of current model calculations is that the chiral geometry of angular momentum coupling is extracted from expectation values of orientation operators, rather than being a starting point in construction of a model. However, using the particle-hole coupling model for triaxial odd-odd nuclei it is possible to construct a basis which contains right-handed, left-handed and planar states of angular momentum coupling. If this basis is used, the chirality is an explicit rather than an extracted feature as in any other models with non-chiral bases. The time-reversal symmetry, which relates the basis states of opposite handedness, can be used to reduce the dimension of matrices for diagonalization of the model Hamiltonian, proving the effectiveness of this approach. Moreover, the final model eigenstate wave functions show a concentration of amplitudes among a relatively small number (˜1%) of components compared to the full model space. In that sense, the ‘chiral’ basis provides a useful tool to examine model predictions providing direct insight into the structure of doublet states. In this work, similarities and differences between the rotational behaviour of an axial and triaxial body provide a starting point for derivation of the basis optimal for valence nucleon coupling to an axial and a triaxial core. The derived ‘chiral’ basis is optimal for coupling of a valence particle and hole to the triaxial core. Model predictions are presented and discussed. A comprehensive review of current experimental data on observed chiral band candidates is also provided.

  11. Ground-Based Global Navigation Satellite System Mixed Broadcast Ephemeris Data (daily files) from NASA CDDIS

    Data.gov (United States)

    National Aeronautics and Space Administration — This dataset consists of ground-based Global Navigation Satellite System (GNSS) Mixed Broadcast Ephemeris Data (daily files) from the NASA Crustal Dynamics Data...

  12. Development of nuclear reaction data retrieval system on Meme media

    Energy Technology Data Exchange (ETDEWEB)

    Ohbayasi, Yosihide; Masui, Hiroshi [Meme Media Lab., Hokkaido Univ., Sapporo (Japan); Aoyama, Shigeyoshi [Information Processing Center, Kitami Inst. of Tech., Hokkaido (Japan); Kato, Kiyoshi [Graduate School of Science, Hokkaido Univ., Sapporo (Japan); Chiba, Masaki [Division of Social Information, Sapporo Gakuin Univ., Ebetsu, Hokkaido (Japan)

    2000-03-01

    A newly designed retrieval system of charged particle nuclear reaction data is developed on Meme media architecture. We designed the network-based (client-server) retrieval system. The server system is constructed on a UNIX workstation with a relational database, and the client system is constructed on Microsoft Windows PC using an IntelligentPad software package. The IntelligentPad is currently available as developing Meme media. We will develop the system to realize effective utilization of nuclear reaction data: I. 'Re-production, Re-edit, Re-use', II. 'Circulation, Coordination and Evolution', III. 'Knowledge discovery'. (author)

  13. Evaluation of a new filing system's ability to maintain canal morphology.

    Science.gov (United States)

    Thompson, Matthew; Sidow, Stephanie J; Lindsey, Kimberly; Chuang, Augustine; McPherson, James C

    2014-06-01

    The manufacturer of the Hyflex CM endodontic files claims the files remain centered within the canal, and if unwound during treatment, they will regain their original shape after sterilization. The purpose of this study was to evaluate and compare the canal centering ability of the Hyflex CM and the ProFile ISO filing systems after repeated uses in simulated canals, followed by autoclaving. Sixty acrylic blocks with a canal curvature of 45° were stained with methylene blue, photographed, and divided into 2 groups, H (Hyflex CM) and P (ProFile ISO). The groups were further subdivided into 3 subgroups: H1, H2, H3; P1, P2, P3 (n = 10). Groups H1 and P1 were instrumented to 40 (.04) with the respective file system. Used files were autoclaved for 26 minutes at 126°C. After sterilization, the files were used to instrument groups H2 and P2. The same sterilization and instrumentation procedure was repeated for groups H3 and P3. Post-instrumentation digital images were taken and superimposed over the pre-instrumentation images. Changes in the location of the center of the canal at predetermined reference points were recorded and compared within subgroups and between filing systems. Statistical differences in intergroup and intragroup transportation measures were analyzed by using the Kruskal-Wallis analysis of variance of ranks with the Bonferroni post hoc test. There was a difference between Hyflex CM and ProFile ISO groups, although it was not statistically significant. Intragroup differences for both Hyflex CM and ProFile ISO groups were not significant (P Hyflex CM and ProFile ISO files equally maintained the original canal's morphology after 2 sterilization cycles. Published by Elsevier Inc.

  14. Nuclear data needs for non-intrusive inspection.

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D. L.; Michlich, B. J.

    2000-11-29

    Various nuclear-based techniques are being explored for use in non-intrusive inspection. Their development is motivated by the need to prevent the proliferation of nuclear weapons, to thwart trafficking in illicit narcotics, to stop the transport of explosives by terrorist organizations, to characterize nuclear waste, and to deal with various other societal concerns. Non-intrusive methods are sought in order to optimize inspection speed, to minimize damage to packages and containers, to satisfy environmental, health and safety requirements, to adhere to legal requirements, and to avoid inconveniencing the innocent. These inspection techniques can be grouped into two major categories: active and passive. They almost always require the use of highly penetrating radiation and therefore are generally limited to neutrons and gamma rays. Although x-rays are widely employed for these purposes, their use does not constitute nuclear technology and therefore is not discussed here. This paper examines briefly the basic concepts associated with nuclear inspection and investigates the related nuclear data needs. These needs are illustrated by considering four of the methods currently being developed and tested.

  15. EPPS16: nuclear parton distributions with LHC data

    Science.gov (United States)

    Eskola, Kari J.; Paakkinen, Petja; Paukkunen, Hannu; Salgado, Carlos A.

    2017-03-01

    We introduce a global analysis of collinearly factorized nuclear parton distribution functions (PDFs) including, for the first time, data constraints from LHC proton-lead collisions. In comparison to our previous analysis, EPS09, where data only from charged-lepton-nucleus deep inelastic scattering (DIS), Drell-Yan (DY) dilepton production in proton-nucleus collisions and inclusive pion production in deuteron-nucleus collisions were the input, we now increase the variety of data constraints to cover also neutrino-nucleus DIS and low-mass DY production in pion-nucleus collisions. The new LHC data significantly extend the kinematic reach of the data constraints. We now allow much more freedom for the flavor dependence of nuclear effects than in other currently available analyses. As a result, especially the uncertainty estimates are more objective flavor by flavor. The neutrino DIS plays a pivotal role in obtaining a mutually consistent behavior for both up and down valence quarks, and the LHC dijet data clearly constrain gluons at large momentum fraction. Mainly for insufficient statistics, the pion-nucleus DY and heavy-gauge-boson production in proton-lead collisions impose less visible constraints. The outcome - a new set of next-to-leading order nuclear PDFs called EPPS16 - is made available for applications in high-energy nuclear collisions.

  16. EPPS16: nuclear parton distributions with LHC data.

    Science.gov (United States)

    Eskola, Kari J; Paakkinen, Petja; Paukkunen, Hannu; Salgado, Carlos A

    2017-01-01

    We introduce a global analysis of collinearly factorized nuclear parton distribution functions (PDFs) including, for the first time, data constraints from LHC proton-lead collisions. In comparison to our previous analysis, EPS09, where data only from charged-lepton-nucleus deep inelastic scattering (DIS), Drell-Yan (DY) dilepton production in proton-nucleus collisions and inclusive pion production in deuteron-nucleus collisions were the input, we now increase the variety of data constraints to cover also neutrino-nucleus DIS and low-mass DY production in pion-nucleus collisions. The new LHC data significantly extend the kinematic reach of the data constraints. We now allow much more freedom for the flavor dependence of nuclear effects than in other currently available analyses. As a result, especially the uncertainty estimates are more objective flavor by flavor. The neutrino DIS plays a pivotal role in obtaining a mutually consistent behavior for both up and down valence quarks, and the LHC dijet data clearly constrain gluons at large momentum fraction. Mainly for insufficient statistics, the pion-nucleus DY and heavy-gauge-boson production in proton-lead collisions impose less visible constraints. The outcome - a new set of next-to-leading order nuclear PDFs called EPPS16 - is made available for applications in high-energy nuclear collisions.

  17. Upgrade and development of nuclear data production test facility

    Energy Technology Data Exchange (ETDEWEB)

    Namkung, Won; Ko, I. S.; Cho, M. H.; Lee, Y. S.; Kang, H. S. [Pohang Univ. of Science and Technology, Pohang (Korea, Republic of); Kim, G. N. [Kyungpook National Univ., Daegu (Korea, Republic of); Koh, S. K. [Univ. of Ulsan, Ulsan (Korea, Republic of); Ro, T. I. [Donga Univ., Busan (Korea, Republic of); Choi, G. U. [Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of)

    2005-04-15

    It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: upgrade the electron linac, collimators inside the TOF beam pipe, the development and installation of an automatic sample changer, the extension of the TOF beam line, and the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students.

  18. Upgrade and Development of Nuclear Data Production Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

    It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: (1) upgrade the electron linac, (2) collimators inside the TOF beam pipe, (3) the development and installation of an automatic sample changer, (4) the extension of the TOF beam line, and (5) the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students

  19. EPPS16: nuclear parton distributions with LHC data

    Energy Technology Data Exchange (ETDEWEB)

    Eskola, Kari J. [University of Jyvaskyla, Department of Physics, P.O. Box 35, University of Jyvaskyla (Finland); Helsinki Institute of Physics, P.O. Box 64, University of Helsinki (Finland); Paakkinen, Petja [University of Jyvaskyla, Department of Physics, P.O. Box 35, University of Jyvaskyla (Finland); Paukkunen, Hannu [University of Jyvaskyla, Department of Physics, P.O. Box 35, University of Jyvaskyla (Finland); Helsinki Institute of Physics, P.O. Box 64, University of Helsinki (Finland); Universidade de Santiago de Compostela, Instituto Galego de Fisica de Altas Enerxias (IGFAE), Galicia (Spain); Salgado, Carlos A. [Universidade de Santiago de Compostela, Instituto Galego de Fisica de Altas Enerxias (IGFAE), Galicia (Spain)

    2017-03-15

    We introduce a global analysis of collinearly factorized nuclear parton distribution functions (PDFs) including, for the first time, data constraints from LHC proton-lead collisions. In comparison to our previous analysis, EPS09, where data only from charged-lepton-nucleus deep inelastic scattering (DIS), Drell-Yan (DY) dilepton production in proton-nucleus collisions and inclusive pion production in deuteron-nucleus collisions were the input, we now increase the variety of data constraints to cover also neutrino-nucleus DIS and low-mass DY production in pion-nucleus collisions. The new LHC data significantly extend the kinematic reach of the data constraints. We now allow much more freedom for the flavor dependence of nuclear effects than in other currently available analyses. As a result, especially the uncertainty estimates are more objective flavor by flavor. The neutrino DIS plays a pivotal role in obtaining a mutually consistent behavior for both up and down valence quarks, and the LHC dijet data clearly constrain gluons at large momentum fraction. Mainly for insufficient statistics, the pion-nucleus DY and heavy-gauge-boson production in proton-lead collisions impose less visible constraints. The outcome - a new set of next-to-leading order nuclear PDFs called EPPS16 - is made available for applications in high-energy nuclear collisions. (orig.)

  20. A standard multidimensional, easy-access data file structure for Apple II computers.

    Science.gov (United States)

    Waterborg, J H; Harrington, R E

    1986-12-01

    A random access file structure was designed for Apple II microcomputers that allows data storage of more than 65,500 data values at 170 per Kbyte with a dynamic range of nearly 5 orders of magnitude. All or part of the data are easily accessible from BASIC under ProDOS operating conditions. The file structure accommodates single or multiple data sets in a single data file. Data values within a file with one set of data may interrelate by equal spacing along a second coordinate, such as time or space. Multiple data sets in a file can be independent, parallel or interdependent. Each interdependent data set defines the position of a data point along its coordinate in a two- or multidimensional registration system. The lowest and highest values of each data set are separately recorded to allow easy manipulation of even part of the data, e.g. for graphical presentation. The possibility of storing large numbers of data values in a single file facilitates high-resolution recording of events and simple mathematical manipulation.

  1. Cross-checking of Large Evaluated and Experimental Nuclear Reaction Databases

    Energy Technology Data Exchange (ETDEWEB)

    Zeydina, O. [Société de Calcul Mathématique, Paris (France); Koning, A.J. [Nuclear Research and Consultancy Group, Petten (Netherlands); Soppera, N. [OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux (France); Raffanel, D. [Société de Calcul Mathématique, Paris (France); Bossant, M. [OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux (France); Dupont, E., E-mail: data@oecd-nea.org [OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux (France); Beauzamy, B. [Société de Calcul Mathématique, Paris (France)

    2014-06-15

    Automated methods are presented for the verification of large experimental and evaluated nuclear reaction databases (e.g. EXFOR, JEFF, TENDL). These methods allow an assessment of the overall consistency of the data and detect aberrant values in both evaluated and experimental databases.

  2. Cross-checking of Large Evaluated and Experimental Nuclear Reaction Databases

    Science.gov (United States)

    Zeydina, O.; Koning, A. J.; Soppera, N.; Raffanel, D.; Bossant, M.; Dupont, E.; Beauzamy, B.

    2014-06-01

    Automated methods are presented for the verification of large experimental and evaluated nuclear reaction databases (e.g. EXFOR, JEFF, TENDL). These methods allow an assessment of the overall consistency of the data and detect aberrant values in both evaluated and experimental databases.

  3. Nuclear targets within the project of solving CHAllenges in Nuclear DAta

    Science.gov (United States)

    Sibbens, Goedele; Moens, André; Vanleeuw, David; Lewis, David; Aregbe, Yetunde

    2017-09-01

    In the frame of the European Commission funded integrated project CHANDA (solving CHAllenges in Nuclear DAta) the importance of nuclear target preparation for the accurateness and reliability of experimental nuclear data is set in a dedicated work package (WP3). The global aim of WP3 is the development of a network for nuclear target preparation and characterization, enabling to coordinate the target production corresponding to the experimental requirements. Therefore, a set of tasks within the work package needs to be followed. Primarily, an inventory of target related facilities and radioisotope providers was created. In the next step a priority list of target requests was made in agreement with the target user considering the technical specification, the scheduled experiments and the availability of the target laboratories. A set of target requests has been assigned to the Target Preparation laboratory of the European Commission - Joint Research Centre - Directorate G (EC-JRC.G.2) in Geel, Belgium. This contribution gives an overview of the nuclear targets that are produced within the CHANDA project. The equipment and techniques available for the preparation and characterization of uranium, plutonium and neptunium layers with an areal density ranging from 60 to 205 μg cm-2 will be emphasized.

  4. Microscopic evaluation of the nuclear dipole polarizability

    Energy Technology Data Exchange (ETDEWEB)

    Lipparini, E.; Orlandini, G.; Stringari, S.; Traini, M. (Trento Univ. (Italy). Dept. di Matematica e Fisica)

    1977-12-01

    The dipole polarizability sum rule has been evaluated by means of a restricted Hartree-Fock approach. The method leads to a simple and analytical expression for the dipole polarizability. Explicit calculations have been performed in /sup 16/O and /sup 40/Ca with different types of interaction.

  5. Review of Overall Safety Manual for space nuclear systems. An evaluation of a nuclear safety analysis methodology for plutonium-fueled space nuclear systems

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, J.; Inhaber, H.

    1984-02-01

    As part of its duties in connection with space missions involving nuclear power sources, the Office of Nuclear Safety (ONS) of the Office of Assistant Secretary for Environmental Protection, Safety, and Emergency Preparedness has been assigned the task of reviewing the Overall Safety Manual (OSM) (memo from B.J. Rock to J.R. Maher, December 1, 1982). The OSM, dated July 1981 and in four volumes, was prepared by NUS Corporation, Rockville, Maryland, for the US Department of Energy. The OSM provides many of the technical models and much of the data which are used by (1) space launch contractors in safety analysis reports and (2) the broader Interagency Nuclear Safety Review Panel (INSRP) safety evaluation reports. If fhs interaction between the OSM, contractors, and INSRP is to work effectively, the OSM must be accurate, comprehensive, understandable, and usable.

  6. Neutron-induced nuclear data for the MYRRHA fast spectrum facility

    Directory of Open Access Journals (Sweden)

    Romojaro Pablo

    2017-01-01

    Full Text Available The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions. On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.

  7. Determining the nuclear data uncertainty on MONK10 and WIMS10 criticality calculations

    Science.gov (United States)

    Ware, Tim; Dobson, Geoff; Hanlon, David; Hiles, Richard; Mason, Robert; Perry, Ray

    2017-09-01

    The ANSWERS Software Service is developing a number of techniques to better understand and quantify uncertainty on calculations of the neutron multiplication factor, k-effective, in nuclear fuel and other systems containing fissile material. The uncertainty on the calculated k-effective arises from a number of sources, including nuclear data uncertainties, manufacturing tolerances, modelling approximations and, for Monte Carlo simulation, stochastic uncertainty. For determining the uncertainties due to nuclear data, a set of application libraries have been generated for use with the MONK10 Monte Carlo and the WIMS10 deterministic criticality and reactor physics codes. This paper overviews the generation of these nuclear data libraries by Latin hypercube sampling of JEFF-3.1.2 evaluated data based upon a library of covariance data taken from JEFF, ENDF/B, JENDL and TENDL evaluations. Criticality calculations have been performed with MONK10 and WIMS10 using these sampled libraries for a number of benchmark models of fissile systems. Results are presented which show the uncertainty on k-effective for these systems arising from the uncertainty on the input nuclear data.

  8. Neutron-induced nuclear data for the MYRRHA fast spectrum facility

    Science.gov (United States)

    Romojaro, Pablo; Žerovnik, Gašper; Álvarez-Velarde, Francisco; Stankovskiy, Alexey; Kodeli, Ivan; Fiorito, Luca; Díez, Carlos Javier; Cabellos, Óscar; García-Herranz, Nuria; Heyse, Jan; Paradela, Carlos; Schillebeeckx, Peter; Eynde, Gert Van den

    2017-09-01

    The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven) and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta) Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions). On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.

  9. Determining the nuclear data uncertainty on MONK10 and WIMS10 criticality calculations

    Directory of Open Access Journals (Sweden)

    Ware Tim

    2017-01-01

    Full Text Available The ANSWERS Software Service is developing a number of techniques to better understand and quantify uncertainty on calculations of the neutron multiplication factor, k-effective, in nuclear fuel and other systems containing fissile material. The uncertainty on the calculated k-effective arises from a number of sources, including nuclear data uncertainties, manufacturing tolerances, modelling approximations and, for Monte Carlo simulation, stochastic uncertainty. For determining the uncertainties due to nuclear data, a set of application libraries have been generated for use with the MONK10 Monte Carlo and the WIMS10 deterministic criticality and reactor physics codes. This paper overviews the generation of these nuclear data libraries by Latin hypercube sampling of JEFF-3.1.2 evaluated data based upon a library of covariance data taken from JEFF, ENDF/B, JENDL and TENDL evaluations. Criticality calculations have been performed with MONK10 and WIMS10 using these sampled libraries for a number of benchmark models of fissile systems. Results are presented which show the uncertainty on k-effective for these systems arising from the uncertainty on the input nuclear data.

  10. Temperature Data Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, David

    2003-03-01

    Groundwater temperature is sensitive to the competing processes of heat flow from below the advective transport of heat by groundwater flow. Because groundwater temperature is sensitive to conductive and advective processes, groundwater temperature may be utilized as a tracer to further constrain the uncertainty of predictions of advective radionuclide transport models constructed for the Nevada Test Site (NTS). Since heat transport, geochemical, and hydrologic models for a given area must all be consistent, uncertainty can be reduced by devaluing the weight of those models that do not match estimated heat flow. The objective of this study was to identify the quantity and quality of available heat flow data at the NTS. One-hundred-forty-five temperature logs from 63 boreholes were examined. Thirteen were found to have temperature profiles suitable for the determination of heat flow values from one or more intervals within the boreholes. If sufficient spatially distributed heat flow values are obtained, a heat transport model coupled to a hydrologic model may be used to reduce the uncertainty of a nonisothermal hydrologic model of the NTS.

  11. The VENUS-7 benchmarks. Results from state-of-the-art transport codes and nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Zwermann, Winfried; Pautz, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Garching (Germany); Timm, Wolf [AREVA NP, Erlangen (Germany)

    2010-05-15

    For the validation of both nuclear data and computational methods, comparisons with experimental data are necessary. Most advantageous are assemblies where not only the multiplication factors or critical parameters were measured, but also additional quantities like reactivity differences or pin-wise fission rate distributions have been assessed. Currently there is a comprehensive activity to evaluate such measure-ments and incorporate them in the International Handbook of Evaluated Reactor Physics Benchmark Experiments. A large number of such experiments was performed at the VENUS zero power reactor at SCK/CEN in Belgium in the sixties and seventies. The VENUS-7 series was specified as an international benchmark within the OECD/NEA Working Party on Scientific Issues of Reactor Systems (WPRS), and results obtained with various codes and nuclear data evaluations were summarized. In the present paper, results of high-accuracy transport codes with full spatial resolution with up-to-date nuclear data libraries from the JEFF and ENDF/B evaluations are presented. The comparisons of the results, both code-to-code and with the measured data are augmented by uncertainty and sensitivity analyses with respect to nuclear data uncertainties. For the multiplication factors, these are performed with the TSUNAMI-3D code from the SCALE system. In addition, uncertainties in the reactivity differences are analyzed with the TSAR code which is available from the current SCALE-6 version. (orig.)

  12. Comparative Studies on UO2 Fueled HTTR Several Nuclear Data Libraries

    Science.gov (United States)

    Hidayati, Anni N.; Prastyo, Puguh A.; Waris, Abdul; Irwanto, Dwi

    2017-07-01

    HTTR (High Temperature Engineering Test Reactor) is one of Generation IV nuclear reactors that has been developed by JAERI (former name of JAEA, JAPAN). HTTR uses graphite moderator, helium gas coolant with UO2 fuel and outlet coolant temperature of 900°C or higher than that. Several studies regarding HTTR have been performed by employing JENDL 3.2 nuclear data libraries. In this paper, comparative evaluation of HTTR with several nuclear data libraries (JENDL 3.3, JENDL 4.0, and JEF 3.1) have been conducted.. The 3-D calculation was performed by using CITATION module of SRAC 2006 code. The result shows some differences between those nuclear data libraries result. K-eff or core effective multiplication factor results are about 1.17, 1,18 and 1,19 (JENDL 3.3, JENDL 4.0, and JEF 3.1) at Begin of Life, also at the End of Life (after two years operation) are 1.16, 1.17 and 1.17 for each nuclear data libraries. There are some different result of K-eff but for neutron spectra results, those nuclear data libraries show the same result.

  13. Image files of PCR data plotted on the FACS profiles - Plabrain DB | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data List Contact us Plab...earch . Data file File name: planaria_facs_profile.zip File URL: http://togodb.biosciencedbc.jp/togodb/view/plab...d License Update History of This Database Site Policy | Contact Us Image files of PCR data plotted on the FACS profiles - Plabrain DB | LSDB Archive ...

  14. Proceedings of the 1986 seminar on nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Asami, Tetsuo (eds.)

    1987-02-15

    The seminar focused on problems with nuclear data and reactor constants and their sensitivity analyses. The poster session concerned recent measurements of neutron cross sections and computer codes for theoretical calculations. Separate abstracts were prepared for 34 papers in these proceedings. (DWL)

  15. Supplementary data: Development of nuclear DNA markers for ...

    Indian Academy of Sciences (India)

    Supplementary data: Development of nuclear DNA markers for evolutionary studies in Plasmodium falciparum. Celia Thomas, Sneh Shalini, N. Raghavendra, Meenakshi Choudhary, Anju Verma, Hema Joshi,. A. P. Dash and Aparup Das. J. Genet. 86, 65–68. Primer sequences for amplification of putatively neutral ...

  16. Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal

    Science.gov (United States)

    Herrero, J. J.; Rochman, D.; Leray, O.; Vasiliev, A.; Pecchia, M.; Ferroukhi, H.; Caruso, S.

    2017-09-01

    In the design of a spent nuclear fuel disposal system, one necessary condition is to show that the configuration remains subcritical at time of emplacement but also during long periods covering up to 1,000,000 years. In the context of criticality safety applying burn-up credit, k-eff eigenvalue calculations are affected by nuclear data uncertainty mainly in the burnup calculations simulating reactor operation and in the criticality calculation for the disposal canister loaded with the spent fuel assemblies. The impact of nuclear data uncertainty should be included in the k-eff value estimation to enforce safety. Estimations of the uncertainty in the discharge compositions from the CASMO5 burn-up calculation phase are employed in the final MCNP6 criticality computations for the intact canister configuration; in between, SERPENT2 is employed to get the spent fuel composition along the decay periods. In this paper, nuclear data uncertainty was propagated by Monte Carlo sampling in the burn-up, decay and criticality calculation phases and representative values for fuel operated in a Swiss PWR plant will be presented as an estimation of its impact.

  17. Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal

    Directory of Open Access Journals (Sweden)

    Herrero J.J.

    2017-01-01

    Full Text Available In the design of a spent nuclear fuel disposal system, one necessary condition is to show that the configuration remains subcritical at time of emplacement but also during long periods covering up to 1,000,000 years. In the context of criticality safety applying burn-up credit, k-eff eigenvalue calculations are affected by nuclear data uncertainty mainly in the burnup calculations simulating reactor operation and in the criticality calculation for the disposal canister loaded with the spent fuel assemblies. The impact of nuclear data uncertainty should be included in the k-eff value estimation to enforce safety. Estimations of the uncertainty in the discharge compositions from the CASMO5 burn-up calculation phase are employed in the final MCNP6 criticality computations for the intact canister configuration; in between, SERPENT2 is employed to get the spent fuel composition along the decay periods. In this paper, nuclear data uncertainty was propagated by Monte Carlo sampling in the burn-up, decay and criticality calculation phases and representative values for fuel operated in a Swiss PWR plant will be presented as an estimation of its impact.

  18. PNNL Strategic Goods Testbed: A Data Library for Illicit Nuclear Trafficking

    Energy Technology Data Exchange (ETDEWEB)

    Webster, Jennifer B.; Erikson, Luke E.; Toomey, Christopher M.; Lewis, Valerie A.

    2014-05-12

    Pacific Northwest National Laboratory (PNNL) has put significant effort into nonproliferation activities as an institution, both in terms of the classical nuclear material focused approach and in the examination of other strategic goods necessary to implement a nuclear program. To assist in these efforts, several projects in the Analysis in Motion (AIM) and Signature Discovery (SDI) Initiatives at PNNL are developing machine learning methodology for human-computer interaction in real time environments to assist analysts in this domain. All of these technical projects require access to data – whether it is in terms of detector data, shipping records, financial information, company relations, or other communications. The first question that mathematical and computational researchers come up with when asked to build analyst assist or automated tools is “What does the data look like? ” They become frustrated when basic questions like this can not be easily answered and this can have the effect of pushing researchers away from the nuclear trafficking domain, especially in strategic commodity and export control areas where data sets can not easily be generated through standard experimental techniques. For small projects that are building a proof of concept for their methodology, obtaining this data can be arduous and expensive. To relieve the burden of data collection from these projects and grow a lab-wide capability, the Strategic Goods Testbed Team has taken over data collection and placed subscriptions and access to flat data files in a centralized location so that all projects can benefit from these items. We have collected shipping data in the form of PIERS records, judicial information about export control cases, NAC data on the nuclear fuel industry, and financial data from Dun and Bradstreet and our data sets are continuing to expand. With a single access agreement, researchers in data-mining and other fields can utilize all of the records that have been

  19. Converting Spreadsheet Files into Data Base Files Using AppleWorks V2.0 and the Apple IIGS Computer.

    Science.gov (United States)

    Schlenker, Richard M.

    This guide was developed as a "how to" training device for converting spreadsheet files into database files using AppleWorks version 2.0 on the Apple IIGS computer with two disk drives. Step-by-step instructions are provided for loading spreadsheet files, transferring spreadsheet files to the monitor, printing spreadsheet files, and…

  20. NIC (Nuclear Industry in China) exhibition. Press file; Exposition NIC (Nuclear Industry in China). Dossier de presse

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-27

    Framatome participated to the NIC exhibition which took place in Beijing (China) on March 1998. This press dossier was distributed to visitors. It presents in a first part the activities of the Framatome group in people`s republic of China (new constructions (Daya Bay, Ling Ao project), technological cooperation and contracts in the nuclear domain, technology transfers in the domain of nuclear fuels, activities and daughter companies in the domain of industrial equipments, Framatome Connectors International (FCI) daughter company in the domain of connectors engineering). Then, the general activities of Framatome in the nuclear, industrial equipment, and connectors engineering domains are summarized in the next 3 parts. (J.S.)

  1. Using AppleWorks V1.3 To Construct Data Base Files for the Apple IIe Computer. Second Edition.

    Science.gov (United States)

    Schlenker, Richard M.

    This step-by-step guide to using AppleWorks V1.3 to construct database files for the Apple IIe computer covers (1) program loading; (2) selecting the add files to the desktop option; (3) naming the file; (4) the blinking block cursor; (5) naming categories or fields; (6) moving to insert data; (7) inserting data; (8) changing database file…

  2. Emergy Evaluation of a Swedish Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kindberg, Anna

    2007-03-15

    Today it is common to evaluate and compare energy systems in terms of emission of greenhouse gases. However, energy systems should not only reduce their pollution but also give a large energy return. One method used to measure energy efficiency is emergy (embodied energy, energy memory) evaluation, which was developed by the system ecologist Howard T. Odum. Odum defines emergy as the available energy of one kind previously used up directly and indirectly to make a service or product. Both work of nature and work of human economy in generating products and services are calculated in terms of emergy. Work of nature takes the form of natural resources and work of human economy includes labour, services and products used to transform natural resources into something of value to the economy. The quotient between work of nature and work of human economy gives the emergy return on investment of the investigated product. With this in mind the present work is an attempt to make an emergy evaluation of a Swedish nuclear power plant to estimate its emergy return on investment. The emergy return on investment ratio of a Swedish nuclear power plant is calculated to approximately 11 in this diploma thesis. This means that for all emergy the Swedish economy has invested in the nuclear power plant it gets 11 times more emergy in return in the form of electricity generated by nuclear power. The method used in this work may facilitate future emergy evaluations of other energy systems.

  3. Evaluation and assessment of nuclear power plant seismic methodology

    Energy Technology Data Exchange (ETDEWEB)

    Bernreuter, D.; Tokarz, F.; Wight, L.; Smith, P.; Wells, J.; Barlow, R.

    1977-03-01

    The major emphasis of this study is to develop a methodology that can be used to assess the current methods used for assuring the seismic safety of nuclear power plants. The proposed methodology makes use of system-analysis techniques and Monte Carlo schemes. Also, in this study, we evaluate previous assessments of the current seismic-design methodology.

  4. Opinions on nuclear energy: Evaluations, beliefs, and attitudes.

    NARCIS (Netherlands)

    Meertens, R.W.; Stallen, P.J.

    1981-01-01

    Used the expectancy-value model of attitudes (M. Fishbein and I. Ajzen, 1975) to investigate the attitudes, evaluations, and beliefs concerning the peaceful use of nuclear energy in 252 Dutch social and natural scientists. The model received empirical support. A factor analysis revealed 2

  5. Chemometric Analysis of Nuclear Magnetic Resonance Spectroscopy Data

    Energy Technology Data Exchange (ETDEWEB)

    ALAM,TODD M.; ALAM,M. KATHLEEN

    2000-07-20

    Chemometric analysis of nuclear magnetic resonance (NMR) spectroscopy has increased dramatically in recent years. A variety of different chemometric techniques have been applied to a wide range of problems in food, agricultural, medical, process and industrial systems. This article gives a brief review of chemometric analysis of NMR spectral data, including a summary of the types of mixtures and experiments analyzed with chemometric techniques. Common experimental problems encountered during the chemometric analysis of NMR data are also discussed.

  6. Evaluation of nuclear magnetic resonance spectroscopy variability

    Energy Technology Data Exchange (ETDEWEB)

    Barreto, Felipe Rodrigues; Salmon, Carlos Ernesto Garrido, E-mail: garrido@ffclrp.usp.br [Universidade de Sao Paulo (FFCLRP/USP), Ribeirao Preto, SP (Brazil). Fac. de Filisofia, Ciencias e Letras; Otaduy, Maria Concepcion Garcia [Universidade de Sao Paulo (FAMUS/USP), Sao Paulo, SP (Brazil). Fac. de Medicina. Departamento de Radiologia

    2014-11-01

    Introduction: the intrinsically high sensitivity of Magnetic Resonance Spectroscopy (MRS) causes considerable variability in metabolite quantification. In this study, we evaluated the variability of MRS in two research centers using the same model of magnetic resonance image scanner. Methods: two metabolic phantoms were created to simulate magnetic resonance spectra from in vivo hippocampus. The phantoms were filled with the same basic solution containing the following metabolites: N-acetyl-aspartate, creatine, choline, glutamate, glutamine and inositol. Spectra were acquired over 15 months on 26 acquisition dates, resulting in a total of 130 spectra per center. Results: the phantoms did not undergo any physical changes during the 15-month period. Temporal analysis from both centers showed mean metabolic variations of 3.7% in acquisitions on the same day and of 8.7% over the 15-month period. Conclusion: The low deviations demonstrated here, combined with the high specificity of Magnetic Resonance Spectroscopy, confirm that it is feasible to use this technique in multicenter studies in neuroscience research. (author)

  7. Ground-Based Global Navigation Satellite System Combined Broadcast Ephemeris Data (hourly files) from NASA CDDIS

    Data.gov (United States)

    National Aeronautics and Space Administration — This dataset consists of ground-based Global Navigation Satellite System (GNSS) Combined Broadcast Ephemeris Data (hourly files of all distinct navigation messages...

  8. Ground-Based Global Navigation Satellite System Combined Broadcast Ephemeris Data (daily files) from NASA CDDIS

    Data.gov (United States)

    National Aeronautics and Space Administration — This dataset consists of ground-based Global Navigation Satellite System (GNSS) Combined Broadcast Ephemeris Data (daily files of all distinct navigation messages...

  9. Nuclear data banks generation by interpolation; Generacion de bancos de datos nucleares mediante interpolacion

    Energy Technology Data Exchange (ETDEWEB)

    Castillo M, J. A

    1999-07-01

    Nuclear Data Bank generation, is a process in which a great amount of resources is required, both computing and humans. If it is taken into account that at some times it is necessary to create a great amount of those, it is convenient to have a reliable tool that generates Data Banks with the lesser resources, in the least possible time and with a very good approximation. In this work are shown the results obtained during the development of INTPOLBI code, use to generate Nuclear Data Banks employing bicubic polynominal interpolation, taking as independent variables the uranium and gadolinia percents. Two proposal were worked, applying in both cases the finite element method, using one element with 16 nodes to carry out the interpolation. In the first proposals the canonic base was employed, to obtain the interpolating polynomial and later, the corresponding linear equation systems. In the solution of this systems the Gaussian elimination methods with partial pivot was applied. In the second case, the Newton base was used to obtain the mentioned system, resulting in a triangular inferior matrix, which structure, applying elemental operations, to obtain a blocks diagonal matrix, with special characteristics and easier to work with. For the validation tests, a comparison was made between the values obtained with INTPOLBI and INTERTEG (create at the Instituto de Investigaciones Electricas (MX) with the same purpose) codes, and Data Banks created through the conventional process, that is, with nuclear codes normally used. Finally, it is possible to conclude that the Nuclear Data Banks generated with INTPOLBI code constitute a very good approximation that, even though do not wholly replace conventional process, however are helpful in cases when it is necessary to create a great amount of Data Banks.

  10. Oscar — Using Byte Pairs to Find File Type and Camera Make of Data Fragments

    Science.gov (United States)

    Karresand, Martin; Shahmehri, Nahid

    Mapping out the contents of fragmented storage media is hard if the file system has been corrupted, especially as the current forensic tools rely on meta information to do their job. If it was possible to find all fragments belonging to a certain file type, it would also be possible to recover a lost file. Such a tool could for example be used in the hunt for child pornography. The Oscar method identifies the file type of data fragments based solely on statistics calculated from their structure. The method does not need any meta data to work. We have previously used the byte frequency distribution and the rate of change between consecutive bytes as basis for the statistics, as well as calculating the 2-gram frequency distribution to create a model of different file types. This paper present a variant of the 2-gram method, in that it uses a dynamic smoothing factor. In this way we take the amount of data used to create the centroid into consideration. A previous experiment on file type identification is extended with .mp3 files reaching a detection rate of 76% with a false positives rate of 0.4%. We also use the method to identify the camera make used to capture a .jpg picture from a fragment of the picture. The result shows that we can clearly separate a picture fragment coming from a Fuji or Olympus cameras from a fragment of a picture of the other camera makes used in our test.

  11. Development of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2004-02-15

    The objective of this research is to develop on efficient integrity evaluation technology and to investigate the applicability of the newly-developed technology such as internet-based cyber platform etc. to Nuclear Power Plant(NPP) components. The development of an efficient structural integrity evaluation system is necessary for safe operation of NPP as the increase of operating periods. Moreover, material test data as well as emerging structural integrity assessment technology are also needed for the evaluation of aged components. The following five topics are covered in this project: development of the wall-thinning evaluation program for nuclear piping; development of structural integrity evaluation criteria for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for major components of NPP; ingegration of internet-based cyber platform and integrity evaluation program for primary components of NPP; effects of aging on strength of dissimilar welds.

  12. Hazardous-waste Data Management System (HWDMS) facility location extract tape. Data files

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    The file contains data on hazardous-waste handlers, and/or generators, that are stored in the Hazardous Waste Data Base (HWDMS). The information is compiled from the notification of Hazardous Waste Activity, EPA Form 8700-1, and Forms 3510-3, Application for Hazardous Waste Permits. The data includes names and addresses as well as locational information for all notifying Treatment, Storage, and Disposal (TSD) Facilities, as well as for all notifying generators of at least 1000 KG/MO of non-active hazardous wastes or 1 KG/MO of acute hazardous wastes. EPA does not claim that HWDMS contains all the potential regulated hazardous-waste facilities that exist or will exist. Although the property in which you are interested is not currently listed in the data base, this is not a guarantee that a hazardous waste problem will not exist there.

  13. The IZA Evaluation Dataset Survey: A Scientific Use File

    NARCIS (Netherlands)

    P., Arni,; Caliendo, M.; Künn, Steffen; Zimmermann, K.F.

    2014-01-01

    This reference paper describes the sampling and contents of the IZA Evaluation Dataset Survey and outlines its vast potential for research in labor economics. The data have been part of a unique IZA project to connect administrative data from the German Federal Employment Agency with innovative

  14. The use of nuclear data in the field of nuclear fuel recycling

    Science.gov (United States)

    Martin, Julie-Fiona; Launay, Agnès; Grassi, Gabriele; Binet, Christophe; Lelandais, Jacques; Lecampion, Erick

    2017-09-01

    AREVA NC La Hague facility is the first step of the nuclear fuel recycling process implemented in France. The processing of the used fuel is governed by high standards of criticality-safety, and strong expectations on the quality of end-products. From the received used fuel assemblies, the plutonium and the uranium are extracted for further energy production purposes within the years following the reprocessing. Furthermore, the ultimate waste - fission products and minor actinides on the one hand, and hulls and end-pieces on the other hand - is adequately packaged for long term disposal. The used fuel is therefore separated into very different materials, and time scales which come into account may be longer than in some other nuclear fields of activity. Given the variety of the handled nuclear materials, as well as the time scales at stake, the importance given to some radionuclides, and hence to the associated nuclear data, can also be specific to the AREVA NC La Hague plant. A study has thus been led to identify a list of the most important radionuclides for the AREVA NC La Hague plant applications, relying on the running constraints of the facility, and the end-products expectations. The activities at the AREVA NC La Hague plant are presented, and the methodology to extract the most important radionuclides for the reprocessing process is detailed.

  15. The use of nuclear data in the field of nuclear fuel recycling

    Directory of Open Access Journals (Sweden)

    Martin Julie-Fiona

    2017-01-01

    Full Text Available AREVA NC La Hague facility is the first step of the nuclear fuel recycling process implemented in France. The processing of the used fuel is governed by high standards of criticality-safety, and strong expectations on the quality of end-products. From the received used fuel assemblies, the plutonium and the uranium are extracted for further energy production purposes within the years following the reprocessing. Furthermore, the ultimate waste – fission products and minor actinides on the one hand, and hulls and end-pieces on the other hand – is adequately packaged for long term disposal. The used fuel is therefore separated into very different materials, and time scales which come into account may be longer than in some other nuclear fields of activity. Given the variety of the handled nuclear materials, as well as the time scales at stake, the importance given to some radionuclides, and hence to the associated nuclear data, can also be specific to the AREVA NC La Hague plant. A study has thus been led to identify a list of the most important radionuclides for the AREVA NC La Hague plant applications, relying on the running constraints of the facility, and the end-products expectations. The activities at the AREVA NC La Hague plant are presented, and the methodology to extract the most important radionuclides for the reprocessing process is detailed.

  16. Analysis algorithm for digital data used in nuclear spectroscopy

    CERN Document Server

    AUTHOR|(CDS)2085950; Sin, Mihaela

    Data obtained from digital acquisition systems used in nuclear spectroscopy experiments must be converted by a dedicated algorithm in or- der to extract the physical quantities of interest. I will report here the de- velopment of an algorithm capable to read digital data, discriminate between random and true signals and convert the results into a format readable by a special data analysis program package used to interpret nuclear spectra and to create coincident matrices. The algorithm can be used in any nuclear spectroscopy experimental setup provided that digital acquisition modules are involved. In particular it was used to treat data obtained from the IS441 experiment at ISOLDE where the beta decay of 80Zn was investigated as part of ultra-fast timing studies of neutron rich Zn nuclei. The results obtained for the half-lives of 80Zn and 80Ga were in very good agreement with previous measurements. This fact proved unquestionably that the conversion algorithm works. Another remarkable result was the improve...

  17. Impact of nuclear data on sodium-cooled fast reactor calculations

    Directory of Open Access Journals (Sweden)

    Aures Alexander

    2016-01-01

    Full Text Available Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respect to nuclear data. Analysed quantities are the multiplication factor and nuclide densities as a function of burn-up and the Doppler and Na-void reactivity coefficients at begin of cycle. While ENDF/B-VII.0 / -VII.1 yield rather consistent results, larger discrepancies are observed between the JEFF libraries. While the newest evaluation, JEFF-3.2, agrees with the ENDF/B-VII libraries, the JEFF-3.1.2 library yields significant larger multiplication factors.

  18. Site selection and containment evaluation for LLNL nuclear events

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, C.W.

    1993-06-01

    During approximately the past decade, the site selection process at LLNL has evolved as the Test Program needs and resources have changed, containment practices have been modified, and the DOE and other regulatory agencies have become more restrictive. Throughout this period the Containment Program and the Field Operations Program at LLNL have managed a cooperative effort to improve site selection. The site selection process actually is three inter-related tasks, namely, selection of a stockpile hole for a specific nuclear test, selection of a drill site for a stockpile hole, and selection of a new drill site for a specific test. Each proposed site is carefully reviewed for known or projected geologic structure and medium properties, nearby holes, containment experience in the region, likelihood of drilling problems, programmatic need for a given depth of hole, and scheduling of Test Program events and resources. By using our data bank, our general knowledge of the Nevada Test Site (NTS) geology, and other information sources, as well as our background in drilling large diameter holes at the NTS, we have been able to optimize our use of NTS real estate and programmatic resources. The containment evaluation of a site is facilitated by considering the location before the hole is drilled. Discuss imposed restraints and our criteria and guidelines for site selection and assignment of events to specific holes, along with the factors that influence selection of a Working Point (WP) depth. Since siting and containment evaluation are strongly related, most major factors related to the containment evaluation process will also be reviewed.

  19. Evaluation of Apache Hadoop for parallel data analysis with ROOT

    Science.gov (United States)

    Lehrack, S.; Duckeck, G.; Ebke, J.

    2014-06-01

    The Apache Hadoop software is a Java based framework for distributed processing of large data sets across clusters of computers, using the Hadoop file system (HDFS) for data storage and backup and MapReduce as a processing platform. Hadoop is primarily designed for processing large textual data sets which can be processed in arbitrary chunks, and must be adapted to the use case of processing binary data files which cannot be split automatically. However, Hadoop offers attractive features in terms of fault tolerance, task supervision and control, multi-user functionality and job management. For this reason, we evaluated Apache Hadoop as an alternative approach to PROOF for ROOT data analysis. Two alternatives in distributing analysis data were discussed: either the data was stored in HDFS and processed with MapReduce, or the data was accessed via a standard Grid storage system (dCache Tier-2) and MapReduce was used only as execution back-end. The focus in the measurements were on the one hand to safely store analysis data on HDFS with reasonable data rates and on the other hand to process data fast and reliably with MapReduce. In the evaluation of the HDFS, read/write data rates from local Hadoop cluster have been measured and compared to standard data rates from the local NFS installation. In the evaluation of MapReduce, realistic ROOT analyses have been used and event rates have been compared to PROOF.

  20. Integral test of JENDL fusion file

    Energy Technology Data Exchange (ETDEWEB)

    Maekawa, Fujio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    Integral test of JENDL Fusion File (J-FF) is performed through analyses of available benchmark experiments. As a result, good agreement between the calculated results with J-FF and the measured data is observed as a whole. Thus, J-FF is qualified to be used for nuclear design of fusion reactors. Owing to the high quality evaluation of J-FF, cross section data in J-FF for many nuclides are recommended to be assigned as data in FENDL/E-2.0 in the IAEA Consultants` Meeting held at Karlsruhe, Germany, 24-28 June, 1996. (author)